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1. 19 4 2 Operational Data sistere tpe atn dad pa a id TRUE ERN DEN ERE XT RAE 21 4 2 1 Production Data Electricity 21 4 2 2 Production Data Lifetime Electricity Supplied 22 4 2 3 Production Data Reactor 24 ADA Performance Midi caters wed on neca dehet obuia e mia toa 25 4 2 5 Trends Performance Indicators eese 21 4 2 6 Trends Operated erac veto 29 4 3 Worldwide Statistics Tables ico rbv dto RIO edad tud 31 4 3 1 Reactor Overview and Nuclear Share Table 1 31 4 3 2 Operational Reactors by Type 2 32 4 3 3 Reactors Under Construction by Type Table 3 33 4 3 4 Reactor Years of Operation Table 4 34 4 3 5 History of Operating Reactors Table 5 35 4 3 6 History of Electricity Production Table 6 36 4 3 7 Historical Development Table 7 serene 37 4 3 8 Construction Time Span Table 8 aote eec eee rte eines 38 4 3 9 Construction Starts 9 uses etre tania 38 4 3 10 Connections to the Grid Table 10
2. calculations are based on all monthly performance data available in PRIS until the end of selected year The basic selection criteria monthly data from commercial date 50 data completeness condition 15 day borderline check are the same as for the regular Performance Indicator report described earlier in this document Reactor specification information is based on the Reactor table of the PRIS database and several reference tables Status Country Region Type Site SiteLocation and ClimaticZone RUP is reconstructed from monthly production data in AnnualElectricityReconstruction and corresponds to the RUP at the end of the reporting year If the reactor is shutdown it is the RUP before the permanent shutdown that is used If the reactor is in long term shutdown the last known RUP before the long term shutdown is used 5 3 Outages The detailed outage records captured in PRIS allow users to analyse energy losses and downtime caused by power reductions and reactor shutdowns All outage reports in PRISTA are based on the PRIS outage coding system For the purpose of PRIS coding outages are defined as any status of a reactor unit when its actual output power is lower than the reference unit power for a period of time By this definition outages include both power reductions and unit shutdowns These are referred to as partial and full outages respectively 5 3 1 Full Outage Statistics Per Outage This report p
3. 2 2 2 0 39 4 3 11 Scheduled Connections to the Grid Table 11 40 4 3 12 Planned Reactors Table 12 uu esee trt 40 4 3 13 Reactors under Construction Table 13 41 4 3 14 Operational Reactors Table 14 42 4 3 15 Reactors in Long Term Shutdown Table 15 44 4 3 16 Reactors in Permanent Shutdown Table 16 44 4 3 17 Decommissioning Process decommissioned Table 17 45 4 3 18 Performance Indicators Table 19 46 4 3 19 Pull Outage Statistics Table 47 4 3 20 Direct Causes of Full Outages Annual Table 20 49 4 3 21 Direct Causes of Full Outages Total Table 21 50 4 3 22 Countries Summary Table 22 etie deii oci P 51 4 3 23 Reactor Type Summary Table 23 Dv ettet 22 4 3 24 Operator Summary Table 24 bye stie Qe 53 4 3 25 Supplier Summary Table 25 55 4 4 Decommissioning ei 56 4 4 1 Decommissioned Reactors 56 4 4 2 Reasons Tor SBtdOWIE So uoce t dee UN 58 4 4 3 DECOMMISSIONING SIEate SIGS ads ie virgi du aget 59
4. Information for this report is extracted from the Reactor table as well as the decommissioning tables in PRIS 4 3 18 Performance Indicators Table 18 This report presents average performance indicators by reactor category for the three year period up to the reporting year The performance indicators included are Energy availability factor EAF Planned Capability Loss Factor PCL Unit Capability Factor UCF Forced Loss Rate FLR Operating Factor OF Load Factor LF 46 Performance factors by reactor category 2008 to 2010 Reactor Reactors reporting to IAEA PRIS see note category Number of Units Availability Factor Planned Cap Loss Factor Capacity Factor UCF Forced Loss Rate Operating Factor Load Factor LF EAF PCL FLR OF PWR 269 83 30 11 30 84 40 3 00 84 60 82 60 PWR 600 MWe 47 84 30 13 90 84 60 1 50 85 10 82 90 PWR gt 600 MWe 222 83 20 11 00 84 30 3 10 84 60 82 60 BWR 94 74 70 18 00 75 20 6 00 76 30 74 20 BWR lt 600 MWe 12 68 00 25 20 68 30 6 80 71 60 68 10 BWR gt 600 MWe 82 75 00 17 60 75 60 6 00 76 90 74 50 PHWR 46 75 70 14 20 80 50 5 20 76 60 75 00 PHWR lt 600 MWe 26 58 40 19 30 71 40 10 90 69 70 56 80 PHWR gt 600 MWe 20 84 80 11 50 85 30 2 50 85 10 84 60 LWGR 16 78 50 18 10 78 80 2 30 77 20 78 30 LWGR lt 600 MWe 4 72 00 27 00 72 00 0 20 69 00 32 80 LWGR gt 600 MWe 12 78 50 18 00 78 80 2 30 80 00 78 50 GCR 18 61 40 13 00 61 60 19 00 68 90 61 50
5. 466 VVER V 466 PRE KONVOI BN20 CNP 600 CNP 600 CPR1000 CPR1000 CPR 1000 CPR 1000 CPR 1000 CPR 1000 CPR 1000 AP 1000 AP 1000 CPR 1000 CPR 1000 CPR 1000 CPR 1000 CPR1000 CPR1000 CPR1000 CPR1000 CPR1000 CNP 600 FIG 4 23 Table 13 Report Capacity MW Thermal Gross 2160 745 3000 1000 3000 1000 3765 1350 65 25 1930 650 1930 650 2905 1087 2905 1087 2905 1087 2905 1087 2905 1087 2905 1087 2905 1087 3750 1250 3750 1250 2905 1080 2905 1080 2905 1080 2905 1080 2905 1080 2905 1087 2905 1080 2905 1080 2905 1080 1930 650 Operator Net 692 NASA 953 KOZNPP 953 KOZNPP 1245 ELETRONU 20 CIAE 610 HNPC 610 HNPC 1000 GFNPC 1000 GFNPC 1000 QNPC 1000 QNPC 1000 1000 1000 1000 SNPC 1000 SNPC 1000 LHNPC 1000 LHNPC 1000 LHNPC 1000 LHNPC 1000 LDNPC 1000 NDNPC 1000 NDNPC 1000 NDNPC 1000 NDNPC 610 NPQJVC NSSS Supplier SIEMENS ASE ASE KWU IZ DFEC DFEC DFEC DFEC DFEC DFEC DFEC DFEC DFEC DFEC DFEC DFEC DFEC DFEC DFEC DFEC DFEC DFEC Construction start 1981 7 1987 1 1987 3 2010 6 2000 5 2010 4 2010 11 2010 7 2010 12 2008 12 2009 7 2008 11 2009 6 2010 12 2009 9 2010 6 2007 8 2008 3 2009 3 2009 8 2006 6 2008 2 2008 11 2010 1 2010 9 2007 1 First Criticality 2010 7 2011 2 2011 12 Grid Connection 2012 7 2011 7 2011 5 2012 3 When generated for the current year the report includes al
6. CHINA CN 78 SANMEN 3 PWR AP 1000 3750 1250 1000 SMNPC WHIMHI CHINA CN 79 SANMEN 4 PWR AP 1000 3750 1250 1000 SMNPC WHIMHI CHINA CN 70 SANMING 1 FBR BN800 800 FSNPC FIG 4 22 Table 12 Report Condition report includes all reactors that are currently in planned status Net electrical capacity is the design net electrical capacity from the Reactor table or if unavailable the latest net electrical capacity from the Reactor table 4 3 13 Reactors under Construction Table 13 This report lists all reactors that are were under construction in the reporting year 41 Reactors under construction Latest in 2010 Country Code ARGENTINA AR 3 BULGARIA BG 7 BULGARIA BG 8 BRAZIL BR 3 CHINA CN 84 CHINA CN 51 CHINA CN 52 CHINA CN 55 CHINA CN 56 CHINA CN 28 CHINA CN 29 CHINA CN 30 CHINA CN 31 CHINA 47 CN 24 25 CN 20 CHINA CN 21 CHINA CN 22 CHINA CN 23 CHINA CN 13 CHINA 36 CN 37 CN 38 39 15 Condition Reactor Name ATUCHA 2 BELENE 1 BELENE 2 ANGRA 3 CEFR 1 2 FANGCHENGGA NG1 FANGCHENGGA NG2 FANGJIASHAN 1 FANGJIASHAN 2 FUQING 1 FUQING 2 FUQING 3 HAIYANG 1 HAIYANG 2 HONGYANHE 1 HONGYANHE 2 HONGYANHE 3 HONGYANHE 4 LINGAO 4 NINGDE 1 NINGDE 2 NINGDE 3 NINGDE 4 QINSHAN 2 4 Type Model PHWR KWU
7. Fax 1 800 865 3450 Email customercare bernan com Web site http Awww bernan com Renouf Publishing Company Ltd 1 5369 Canotek Rd Ottawa Ontario K1J 9J3 Telephone 613 745 2665 Fax 613 745 7660 Email order dept renoufbooks com Web site http www renoufbooks com CHINA IAEA Publications in Chinese China Nuclear Energy Industry Corporation Translation Section P O Box 2103 Beijing CZECH REPUBLIC Suweco CZ S R O Klecakova 347 180 21 Praha 9 Telephone 420 26603 5364 Fax 420 28482 1646 Email nakup suweco cz Web site http www suweco cz FINLAND Akateeminen Kirjakauppa PO BOX 128 Keskuskatu 1 00101 Helsinki Telephone 358 9 121 41 Fax 358 9 121 4450 Email akatilaus akateeminen com Web site http www akateeminen com FRANCE Form Edit 5 rue Janssen P O Box 25 F 75921 Paris Cedex 19 Telephone 33 1 42 01 49 49 Fax 33 1 42 01 90 90 Email formedit formedit fr Web site http www formedit fr Lavoisier SAS 145 rue de Provigny 94236 Cachan Cedex Telephone 33 1 47 40 67 02 Fax 33 1 47 40 67 02 Email romuald verrier lavoisier fr Web site http www lavoisier fr GERMANY UNO Verlag Vertriebs und Verlags GmbH Am Hofgarten 10 D 53113 Bonn Telephone 49 228 94 90 20 Fax 49 228 94 90 20 or 49 228 94 90 222 Email bestellung uno verlag de Web site http www uno verlag de HUNGARY Librotrade Ltd Book Import P O Box 126 H 1656 Budap
8. in five year intervals up to the reporting year Nuclear electricity production and share from 1980 to 2010 Nuclear production TW e h of reactors connected to the Grid Latest in each year Country 1980 1985 1990 1995 2000 2005 2009 2010 TWee h 2 TW e h 2 Of TW e h TW e h 2 2 Of TW e h 0 TW e h 2 of 2 Total Total Total Total Total Total Total Total ARGENTINA 2480 NA 525 117 672 198 657 118 574 73 637 69 758 70 669 59 ARMENIA 0 00 NA 0 00 NA 000 NA 000 184 330 250 427 229 450 229 394 BELGIUM 1186 2925 598 4059 601 3930 556 4581 568 4534 556 4496 516 4573 512 BRAZIL 000 NA 347 16 206 10 233 10 5 59 1 9 920 25 1222 29 1390 31 BULGARIA 571 NA 1217 316 13 51 357 1622 464 1679 450 17 38 441 1422 359 14 24 331 3802 5947 127 6987 148 9398 173 6912 118 86 83 145 85 13 148 8550 161 CHINA 000 NA 0 00 NA 000 NA 12 13 12 16 02 12 5033 20 65 71 19 70 96 18 CZECH REP 000 NA 199 NA 1177 NA 1223 200 1271 187 23258 305 25 66 338 26 44 333 FINLAND 668 NA 17 98 382 1813 350 1813 299 2158 322 2236 329 2260 329 21 89 284 FRANCE 57 31 NA 21328 648 29761 745 35871 761 39539 764 43118 785 39175 782 41009 741 GERMANY 41440 11959 312 13937 331 14613 296 16066 306 15461 266 12772 229 13301 226 HUNGARY 000 NA 610 236 1288 514 1320 423 1335 406 1302 372 1430 430 14 66 421 INDIA 277 387 22 529 22 6 99 19 1423 34 15 73 28 14 75 22 204818 28 ITALY 241 NA 6 46 3
9. 2011 To 2011 Changes during the specified year range Construction Starts Show Reactor Details Yes Summaries Site Year No of reactors RUP MWe TOTALS 1 315 EJ CHASNUPP 1 315 E 2011 1 315 a a a a i a a a Latest gt 150 gt unit Type Model Current 7 Operator Reactor Const gt Grid Comm 2 Shutdown RUP Code Status Supplier Date Date Date Date MWe PK CHASNUPP 3 CNP 300 Under PAEC CZEC 2011 05 28 2016 09 01 2016 12 01 315 Construction FIG 4 2 Example of the Status Change Report Concept The report provides the number of reactors and total net electrical capacity of all reactors within the selected type of status change in the reporting period The report can be generated for historical periods up to and including the current year By default the report is generated for the current year If the user only enters a from year and leaves the to year of the reporting period blank the report is generated for one year i e the from year Only one type of status change can be selected by the user construction starts grid connections permanent shutdowns long term shutdowns and restarts after a long term shutdown Up to three levels of grouping Region Country Site Type and Year can be applied to the result set A reactor can only appear in exactly one group The Show Reactor Details option returns specification data about individual reactors in addition to summary level resul
10. 34 00 34 01 34 02 34 03 34 04 34 05 34 06 34 07 34 08 34 09 34 10 34 99 Turbine and auxiliaries Turbine Moisture separator and reheater Turbine control valves and stop valves Main condenser including vacuum system Turbine by pass valves Turbine auxiliaries lubricating oil gland steam steam extraction Turbine control and protection system None of the above systems Feedwater and Main Steam System Main steam piping and valves Main steam safety and relief valves Feedwater system including feedwater tank piping pumps and heaters Condensate system including condensate pumps piping and heaters Condensate treatment system None of the above systems Circulating Water System Circulating water system pumps and piping ducts excluding heat sink system Cooling towers heat sink system Emergency ultimate heat sink system None of the above systems Miscellaneous Systems Compressed air essential and non essential high pressure and low pressure Gas storage supply and cleanup systems nitrogen hydrogen carbon dioxide etc Service water process water supply system including water treatment Demineralized water supply system including water treatment Auxiliary steam supply system including boilers and pressure control equipment Non nuclear area ventilation including main control room Chilled water supply system Chemical additive injection and makeup systems Non nuclear equipment ventin
11. 44 1438748844 Email orders earthprint com Web site http www earthprint com UNITED NATIONS Dept 1004 Room DC2 0853 First Avenue at 46th Street New York N Y 10017 USA UN Telephone 800 253 9646 or 212 963 8302 Fax 212 963 3489 Email publications un org Web site http www un org UNITED STATES OF AMERICA Bernan Associates 4501 Forbes Blvd Suite 200 Lanham MD 20706 4346 Telephone 1 800 865 3457 Fax 1 800 865 3450 Email customercare bernan com Web site http www bernan com Renouf Publishing Company Ltd 812 Proctor Ave Ogdensburg NY 13669 Telephone 888 551 7470 toll free e Fax 888 568 8546 toll free Email order dept renoufbooks com Web site http www renoufbooks com Orders and requests for information may also be addressed directly to Marketing and Sales Unit International Atomic Energy Agency Vienna International Centre PO Box 100 1400 Vienna Austria Telephone 43 1 2600 22529 or 22530 Fax 43 1 2600 29302 Email sales publications iaea org Web site http www iaea org books 1 0 1 L2 INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA kd i LA EXE LU re B oo lt gt 4
12. District Heating Desalination Summaries NEA Application Type Number of Reactors RUP MWe Total Heat Electrical of NEA with NEA GCal equivalent of heat GWh TOTALS 75 52387 7247140 04 2491 77 0 01 Desalination 12 8611 151174 01 77 15 0 00 ISO Code Unit Type Model District Heating Process Desalination Total Heat of NEA Heating Thermal PPH Thermal PDI Thermal Electrical Water Total Heat Electrical energy GCal energy GCal energy GCal energy for production PPH equivalent of Reverse m3 PDI heat GWh Osmosis GWh IN MADRAS 1 PHWR Horizontal 9950 70 0 00 0 00 9950 70 3 46 0 19 Pres IN MADRAS 2 PHWR Horizontal 0 00 0 00 0 00 0 00 0 00 0 Pres JP GENKAI 3 PWR M 400p 26170 00 0 00 367835 00 26170 00 9 11 0 09 JP GENKAI 4 PWR M 4 loop 1906 00 0 00 25742 00 1906 00 0 66 0 01 JP IKATA 1 PWR M 2 loop 0 00 0 00 333362 00 8667 41 8 67 0 18 JP IKATA 2 PWR M 2 1o0p 0 00 0 JP IKATA 3 PWR M 3400p 0 00 0 00 267300 00 6949 80 6 95 0 09 JP OHI 1 PWR W 4 loop 0 00 0 00 1072387 00 27882 06 27 88 0 28 JP OHI 2 PWR W 4 loop 0 00 0 JP TAKAHAMA 3 PWR M 3400p 0 00 0 00 480340 00 12488 84 12 49 0 17 JP 4 PWR M 3400p 0 00 0 FIG 5 11 Example of the NEA Energy Report Concept The report is a summary of the three non electrical application types process heating district heating and desalination For report totals and summaries it returns the number and net electrical capacity of re
13. FBR 2 70 40 27 70 70 50 1 60 61 70 70 70 TOTAL 445 80 20 13 20 81 30 410 81 00 79 60 FIG 4 28 Table 18 Report Condition When the report is generated for the current calendar year it includes all reactors that are currently in operational status When generated for a past year the report includes all reactors that are in commercial operation for at least one day during the three year reporting period The following criteria are applied e The reactor is currently in operational long term shutdown or permanent shutdown status e The reporting year is gt the reactor s commercial date e The shutdown date is gt the first year of the three year reporting period e The reactor is not in long term shutdown in December of the reporting year Reactors are divided into categories according to their reactor type PWR BWR PHWR LWGR GCR and FBR and their capacity lt 600 MWe gt 600 MWe and all of them To split reactors into categories according to their net electrical capacity the capacity in the last year of the reporting period is used In absence of the relevant value the latest capacity from the Reactor table is used Performance indicators are calculated from monthly production data Only months that a reactor was in commercial operation are considered i e months from the reactor s commercial date to its shutdown date excluding periods of long term shutdown and applying the 15 day condition Th
14. GERMANY 19 DE 4 AVR JUELICH AVR HTGR 46 15 13 AVR 1961 8 1967 12 1969 5 1988 12 FIG 4 26 Table 16 Report Condition The report lists all reactors in shutdown status that shut down in or before the reporting year Net Capacity is understood to be the net electrical capacity in the last month the reactor was operational i e the month preceding the permanent shutdown date Data Selection All information except for net electrical capacity MW is selected from the Reactor table Net electrical capacity before the permanent shutdown is selected from the Monthly Production table if a record for the month before the shutdown is available Otherwise the latest net electrical capacity recorded in the Reactor table is used 4 3 17 Decommissioning Process decommissioned Table 17 This report provides information on all reactors that are in the decommissioning process or that have been already decommissioned For each reactor the following results are grouped by country shutdown date shutdown reason decommissioning strategy current decommissioning phase current fuel management phase decommissioning licensee and decommissioning license termination The table is complete with a legend of decommissioning process terms 45 Reactors Decommissioning process Decommissioned Country Reactor Shutdown Shutdown Decom Current decom Current fuel Decom License Totals Ref no Unit reason strategy phase ma
15. and cancelled construction if the date of cancellation suspension shut down date is past the reporting year Capacity is the design net electrical capacity Data Selection All information in this report is selected from the Reactor table 4 3 4 Reactor Years of Operation Table 4 This report provides an overview by country of the reactors contributing to operating experience in operation in long term shutdown and in permanent shutdown up to the end of a reported year The report includes the total operating experience in years and months per country 34 Reactor Years of Operating Experience up to end of 2010 Country In Operation Long Term Shutdown Permanently Shutdown All rene and Shutdown Operating Experience leactors Number Net Capacity Number Net Capacity Number Net Capacity Number Net Capacity Years Months MW e 2 935 2 935 64 7 ARMENIA 1 375 1 376 2 751 36 8 BELGIUM 7 5926 1 10 8 5936 240 7 BRAZIL 2 1884 2 1884 39 3 BULGARIA 2 1906 4 1632 6 3538 149 5 CANADA 18 12569 4 2726 3 478 25 15773 600 2 CHINA 13 10058 13 10058 111 2 6 3678 6 3678 116 10 4 2716 4 2716 127 4 FRANCE 58 63130 12 3789 70 66919 1758 4 GERMANY 17 20490 19 5879 36 26369 768 5 HUNGARY 4 1889 4 1889 102 2 INDIA 19 4189 19 4189 337 3 ITALY 4 1423 4 1423 81 0 JAPAN 54 46821 1 246 5 1618 60 48685 1494 8 KAZAKHSTA
16. report calculates the total energy and time lost for planned and unplanned full outages during the reporting year In addition it presents the percentage distribution of energy and time lost due to the different outage causes report considers reactors that are in operation in the reporting period according to the following rules e The reactor unit is connected to the grid within or before the reporting year e Ifthe reactor is shut down it was shut down within or after the reporting year report considers outages starting from the month of a reactor s commercial date These may include outages that occur in the days of trial operations preceding the actual commercial date The report does not filter outages on the long term shutdown date restart date or permanent shutdown date If an error is made and outages have been entered for long term shutdowns or after a reactor s permanent shutdown they would be taken into account Data Selection Outage information duration energy loss cause is selected from the Outages table and the Cause table Reactor table is used for filtering purposes 49 4 3 21 Direct Causes of Full Outages Total Table 21 This report examines the direct causes of planned and unplanned full outages from 2009 to the current reporting year Energy loss GWh and operating hours lost are calculated for each outage cause in absolute numbers as well as a percentage Direct
17. statistical values per Reactor Year Full Outage Statistics Per Reactor Year Reactor Group All Reactors Filters Year From 2008 To 2010 Show Reactor Details Yes Summaries Type Outage Type 1st Character Duration hours No of Reactor Frequency Sum Average Max Min outages Years reactor year TOTALS 3232 1312 5 2 46 2180766 68 1661 54 8784 0 BWR 536 278 17 1 93 579660 08 2083 86 8784 0 P Planned 264 278 17 0 95 471146 71 1693 76 8784 0 U Unplanned 252 278 17 0 91 100164 7 360 09 8784 0 X External 20 278 17 0 07 8348 67 30 01 3426 0 FBR 25 5 08 4 92 16572 3260 07 6105 761 14 5 08 2 75 15409 303128 6068 761 180 Unit Type RUP No of Reactor Frequency Duration hours Code MWe outages Years per reactor year Sum Average Max Min FR PHENIX FBR 130 8 2 08 3 84 9185 4408 8 6068 761 RU BELOYARSKY 3 FBR 560 6 3 2 6224 2074 67 2219 1981 BN 600 U Unplanned 9 5 08 1 77 1036 203 8 999 0 X External 2 5 08 0 39 127 24 98 127 0 GCR 112 54 2 07 14501425 2685 45 8784 0 LWGR 105 47 223 94456 5 2009 71 8760 70 FIG 5 6 Example of the Full Outage Statistics per Year Report 67 Concept The report provides an analysis of full outages i e outages for a reactor unit that was disconnected from the grid The report includes number of outages number of reactor years and frequency of outages per reactor year Statistics include sum average per reactor year maximum per reactor year m
18. the period from the reactor s commercial date to its permanent shutdown date excluding periods of long term shutdown The 15 day condition is applied to decide whether borderline months i e the months of the commercial date the long term shutdown date the restart date and the permanent shutdown date should be included in the calculation The borderline month is included when the reactor was in commercial operation at least 15 days in the month For instance when Commercial date is 25 April the data for April are not included in the calculation Reactors that were not operational for at least one month during the reporting period are automatically excluded from the report In early years there were gaps in production data A criterion to determine whether data are sufficient for selection and PI result calculation is the so called 50 criterion Data are considered sufficient if there are monthly production records for at least half of the required months during which a reactor was operational in the reporting period When the PI report includes reactors with less than 100 completeness a column Data Completeness is displayed showing percentage of available data PI results related to insufficient data are displayed in red as not qualified and are not included in calculation of aggregated values 2 4 2 Methods Used for Group Statistics Report statistics are aggregated for a chosen group of reacto
19. year and leaves the to year of the reporting period blank the report is generated for one year i e the from year The user has to select one reactor status as a filter Only reactors that were in the chosen status for at least one year during the reporting period are included in the report The default selection is the status Operational For reactors under construction there are two options e Under construction current amp completed projects includes all reactors that were under construction in the base year excluding projects that were eventually suspended or cancelled e Under construction incl Cancelled Suspended includes all projects that were under construction in the base year regardless of whether they were eventually completed or not Up to three levels of grouping Region Climatic Zone Country Location Site Type and Age may be applied to the result set A reactor can only appear in one group in the result set The user has the choice of three summary options e Number of reactors the bar chart illustrates the total number of reactors in the chosen status for each year in the reporting period Summary level information in the data table includes the number of reactors for each group for each year e Net electrical capacity the bar chart illustrates the total net electrical capacity of reactor units MWe in the chosen status for each year in the reporting period Summary level information
20. 2 1120 101 17 05 NINE MILE BWR BWR 2 Mark 1 621 97 32 POINT 1 05 NINE MILE BWR BWR 5 Mark 2 1143 89 34 POINT 2 05 PERRY 1 BWR BWR 6 Mark 3 1240 97 77 FBR 76 62 76 62 76 62 76 62 1 LWGR 83 34 84 27 94 30 69 98 12 30 4 PHWR 82 43 81 06 93 80 52 67 13 65 17 PWR 86 58 88 94 94 56 56 74 11 80 42 Inland near a river location 82 48 85 20 92 05 0 00 21 64 181 Seacoast location 76 32 84 05 91 37 0 00 23 27 188 FIG 5 12 Example of the LHL Report Concept The report provides the LFH as weighted average median best quartile minimum value and standard deviation for a chosen reactor group report includes all commercially operated reactors whether they have non electrical applications or not For reactors without NEA LFH is equivalent to LF 79 The only mandatory parameter for the report is the reporting period from and year The report may be generated for historical periods up to and including the previous year By default the previous year is selected as a reporting period Up to three levels of grouping Region Climatic Zone Country Location Site Type Age and Year can be applied to the result set If age and or year are selected any given reactor may be listed in several summary groups The Show Reactor Details option provides the reactor level LFH values in addition to summary level results Detailed information about each reactor also includes basic specification information i e name type
21. 376 BELGIUM 1 10 BULGARIA 4 1632 CANADA 3 478 HWLWR 1 250 ISO Code Unit Type Model License Const Date Grid Date Shutdown Info update RUP MWe More holder Date date Details CA GENTILLY 1 HWLWR BLWR AECL 1966 09 01 1971 04 05 1977 06 01 2009 01 12 250 D B B amp PHWR 2 228 FRANCE 12 3789 GERMANY 27 14301 ITALY 4 1423 JAPAN 9 3577 KAZAKHSTAN 1 52 LITHUANIA 2 2370 NETHERLANDS 1 55 RUSSIA 5 786 SLOVAKIA 3 909 SPAIN 2 621 FIG 4 36 Decommissioned Reactor Report Concept The report provides information about all reactors that were in permanent shutdown in a given year The report has one mandatory parameter the base year for which the report is being generated By default the current year is chosen as the base year Optionally an age filter can be applied to reactors in operation in long term shutdown or in permanent shutdown so that only reactors that are a certain age in the base year are considered Age is calculated from the year of the first grid connection to the year of the permanent shutdown Up to three levels of grouping Region Climatic Zone Country Location Site Type and Age can be selected A reactor can only appear in exactly one group in the result set The Show Reactor Details option returns specification data about individual reactors in addition to summary level results Detailed information about each reactor includes basic design information i e type model RUP etc key milestone
22. 5 5 ces inis aT tec aote 61 5 1 Specification Data iie eati blc dive actes 61 5 1 1 Specifications Reports Reactor 61 5 2 reani E a S 63 5 2 1 Performance Indicators Histogram 63 5 2 2 Performance Indicators Lifetime Indicators 22 422 64 5 3 nrc 65 5 3 1 Full Outage Statistics Per Outage sss 65 5 3 2 Outages Full Outage Statistics Per 67 5 3 3 Outages Combined Outage 69 5 3 4 Outages Operating Period between Full 72 5 3 5 Outages Outage Details seins 73 5 4 Non Electrical Application NEA Data sese 75 5 4 1 Specification Reactors with 0 0 22 0 0 000 75 5 4 2 Production Energy Utilized 77 5 4 3 Production Load Factor Including Heat LFH 79 MAP BASED REPORTS ots aea men ean 82 REFERENCES 5e qe eee ette tese 85 GLOSSARY iacente dte uve
23. 8 000 NA 0 00 NA 0 00 NA 000 NA 0 00 NA 0 00 NA JAPAN 79 11 14537 227 18719 271 27551 334 30624 338 28050 293 26305 292 28025 292 KAZAKHSTAN 0 00 NA 0 00 NA 000 NA 008 01 0 00 NA 000 NA 0 00 NA 0 00 NA KOREA REP 326 1236 232 5026 491 60 21 361 10354 407 13759 447 14112 348 14189 322 FIG 4 16 Table 6 Report 36 Condition and Data Selection The report uses the same formulas and conditions for nuclear share that are used in Table 1 The energy production and nuclear energy share values in particular years are thus equivalent to Table 1 for those years 4 3 7 Historical Development Table 7 This report presents the number of construction starts grid connections and operational reactors for each year since 1954 Annual statistics excluding unfinished constructions 1954 to 2010 Year Construction Starts Connections to the Grid Reactors in operation Units MW e Units MW e Units MW e 1954 1 60 1 5 1 5 1955 8 260 0 1 5 1956 5 577 1 35 2 65 1957 1836 3 119 5 209 1958 6 476 1 35 6 269 1959 7 976 5 176 11 548 1960 11 1010 4 438 15 1087 1961 7 1531 1 15 16 1104 1962 8 1379 9 955 25 2223 1963 5 1722 9 500 33 2677 1964 9 2866 8 1022 40 3686 1965 9 3291 8 1879 48 5910 1966 15 7052 8 1530 55 7539 FIG 4 17 Table 7 Report Condition Construction starts are counted in the year of a reactor s construction date Grid connections are counted in the year of a reactor s grid date Operational reactors are counte
24. TOTALS 121 117830 CHINA 42 34786 INDIA 2 1400 EJ IRAN ISLAMIC REPUBLIC OF 3 2160 JAPAN 10 7568 KOREA REPUBLIC OF 2 2680 PAKISTAN 1 315 EJ RUSSIAN FEDERATION 37 38963 UNITED STATES OF AMERICA 22 27958 VIET NAM 2 2000 FIG 4 3 Example of the Planned Reactor Report Concept report can only be generated for the current year The report calculates the total net electrical capacity and the number of the reactors included in the report Upto three levels of grouping Region Climatic Zone Country Location Site and Type may be applied to the result set A reactor can only appear in exactly one group in the result set 18 The Show Reactor Details option returns specification data about individual reactors in addition to summary level results Detailed information about each reactor includes basic design information e g type model operator RUP etc as well as key milestone dates construction date commercial date shutdown date Condition Design net capacity is used as RUP Data Selection Reactor detail information is selected from the Reactor table The report uses the same selection criteria as the Year End Reactor Status report The base date uses all reactors in planned status up to 31 December of the current year 4 1 4 History Year end Reactor Status Trends This report displays the historical evolution of either the number of reactors in a selected status
25. X Operational Data Performance Indicators Select Outages Select Non Electrical Application NEA Data 7 Specification Select X Production Select FIG 5 1 Advanced Reports Selection 5 1 Specification Data 5 1 1 Specifications Reports Reactor Specification The content of this report is about reactor specification information and is highly customisable The user chooses up to 20 parameters related to reactor basic information and design characteristics which will be displayed as columns in the report 61 Reactor Specification Reactor Group All Reactors Data Columns Basic Information Unit Name Status Country Type Model Design Characteristics Reactor vessel shape Fuel material Average discharge bumup MWd t Refuelling type No of reactors TOTALS 1024 Unit Name Status Country Type Model Reactor vessel Fuel material Average Refuelling type shape discharge burnup IMWdit AGESTA Permanent SWEDEN PHWR 002 8500 ON line Shutdown AKADEMIK Under RUSSIA PWR KLT 40S Floating Cylindrical Other 68700 OFF line LOMONOSOV 1 Hemispherical End AKADEMIK RUSSIA PWR KLT 40S Floating Cylindrical Other 68700 OFF ine LOMONOSOV2 Construction Hemispherical End AKKUYU Suspended Plan TURKEY PWR ALLENS CREEK 1 Cancelled Plan UNITED STATES BWR Cylindrical OFF line OF AMERICA Hemispherical End ALLENS 2 Cancelled Plan UNITED STATES BWR Cylindrical OFF line OF AME
26. are two options e Under construction current and completed projects includes all reactors that were under construction in the base year excluding projects that were eventually suspended or cancelled e Under construction including cancelled suspended includes all projects that were under construction in the base year regardless of whether they were eventually completed or not Optionally an age filter can be applied to reactors in operation in long term shutdown or in permanent shutdown so that only reactors that were of a certain age in the base year are considered Up to three levels of grouping Region Country Location Site Type and Age can be applied to the result set A reactor can only appear in exactly one group in the result set The Show Reactor Details option returns specification data about individual reactors in addition to summary level results Detailed information about each reactor includes basic design information e g type model RUP etc as well as links to the Basic Information Design Characteristics and Schematics reports Condition For historical years the report reflects reactor status and reference unit power RUP at the end of the base year In the current year the latest situation is reflected Reactors that were in a given status during the year but changed status before the end of that year are not included in the report For reactors under construction the design net electrical ca
27. before or within the reporting year The reactor is not shutdown by December of the reporting year The reactor is not in long term shutdown by December of the reporting year e Long term shutdown 51 The reactor is currently operational in long term shutdown or in permanent shutdown The reactor unit is connected to the grid before or during the reporting year The reactor is not permanently shutdown in the reporting year The reactor is in long term shutdown by December of the reporting year Permanent shutdown Data Selection The reactor is in operational long term shutdown or permanent shutdown status The reactor is shutdown before or during the current reporting year The reactor unit is connected to the grid before or during the reporting year dates used to determine the historical status of a reactor in the reporting year are selected from the Reactor and Long term Shutdown Details tables Country information is selected from the Country table 4 3 23 Reactor Type Summary Table 23 For each reactor type this report provides the number of reactors under construction in operation in long term shutdown and in permanent shutdown at the end of the reporting year Reactor Types Abbreviations and Summaries Latest in 2010 Type Code BWR LWGR PHWR SGHWR WORLDWIDE Type Under construction Operational Long term shutdown Shutdown Boiling Light Water Cooled and 4 92 0 23 Moder
28. being used became obsolete 2 The process was no longer profitable lic req 3 There were changes in licensing requirements incident 4 After an operating incident technol 5 Other technological reasons please mention them below econom 6 Other economical reasons please mention them below public 7 Public Acceptance Political Reasons component fail 8 After major component failure or deterioration Others undefd Others Please specify below Select other only when none of the listed criteria matches the shutdown reason FIG 4 37 Reasons for Shutdown Report 58 Concept The report provides a breakdown of shutdown reactors by reasons of their shutdown The report has no mandatory parameters It always reflects the latest information available If it is generated without reactor details the report shows a simple bar chart with the number of reactors for each shutdown reason If it is generated with reactor details the report also lists the reactors concerned by each shutdown reason with the country name and permanent shutdown date Condition The report includes reactors that are in permanent shutdown status with decommissioning information included in the report If no shutdown reason has been provided for a reactor the reactor is not considered in the report More than one shutdown reason can apply to any particular reactor Data Selection Reactor detailed information is selected from the Reactor and Country tabl
29. descriptions are truncated after 200 characters Outage filters are applied at the combined outage level If a user elects to filter by outage type cause or system component the filter is applied to the respective attribute of the combined outage not of each of the fragments For example a report filtered to only include full outages might include partial outage fragments provided that these fragments belong to a combined outage of type full Similarly duration and energy loss of combined outages take into account the duration and energy loss of all fragments not only of those meeting the combined outage filter criteria Data Selection Outage information is extracted from the outage records table in the PRIS database primarily from the Outages Combined table If the view fragments option is selected the Outages table is also queried 5 4 Non Electrical Application NEA Data The electricity production data in PRIS are complemented by information on energy provided by nuclear power plants to non electrical applications such as district heating process heat supply or desalination The following reports generate information related to non electrical applications NEA 5 4 1 Specification Reactors with NEA This report provides an overview of reactors with non electrical applications in a selected status of their life cycle from construction through operation to permanent shutdown 75 Overvie
30. from the ratio of to REG reference electricity generation Data Selection Reactor detail information is from reactor and site tables of the PRIS database NEA information is from the NEA tables in PRIS WaAnnualProductionHeat WAnnualProduction Water is selected from the AnnualProduction table is reconstructed from monthly production data to reflect RUP revisions The closest available match from the AnnualElectricityReconstruction table is used for that purpose 5 4 3 Production Load Factor Including Heat LFH This performance indicator report provides statistics for a modified Load Factor LF LFH takes into account the energy used for non electrical applications besides electricity production for a reporting period spanning one or several consecutive calendar years Load Factor Including Heat LFH Reactor Group All Reactors Filters Year From 2010 To 2010 Show Reactor Details Yes Summaries Location Type Weighted Median Best Minimum Standard No of Average Quartile Deviation Operated Reactors TOTALS 80 62 84 88 92 09 0 00 21 34 441 Inland near a lake location 86 26 88 54 94 03 52 67 12 09 72 BWR 92 10 93 16 97 66 79 92 7 10 8 ISO Code Unit Type Model RUP MWe LF NEA 05 CLINTON 1 BWR BWR 6 Mark 3 1065 92 31 us FERMI BWR BWR 4 Mark 1 1106 79 92 05 FITZPATRICK BWR BWR 4 Mark 1 855 84 94 05 LASALLE 1 BWR BWR 5 Mark 2 1118 94 01 05 LASALLE 2 BWR BWR 5 Mark
31. in the data table includes the total net electrical capacity of reactor units for each group for each year e Number of reactors and net electrical capacity the bar chart illustrates the total number of reactors in the chosen status for each year in the reporting period Summary level information in the data table includes the number of reactors and the total net electrical capacity for each group for each year The Show Reactor Details option includes reactor level information in addition to summary level results Detailed information includes the name and net electrical capacity of each reactor unit in the reporting period Condition A maximum of 20 years can be specified for the reporting period The report reflects reactor status and Reference Unit Power RUP at the end of each year for historical years For the current year it reflects the latest situation Data is only provided for those years in which a reactor was in the selected status at the end of the year For all other years in the report reactor level information is left blank and the reactor is not counted in yearly totals When age is selected in summaries the current age of the reactor is applied in the report Data Selection 20 Reactor detail information is from Reactor and Site tables of the PRIS database For operational reactors RUP is selected from monthly production data to reflect RUP revisions The closest available match from the Annual Electricity Rec
32. model and RUP in the relevant reporting year Condition LFH is defined as the ratio of EG EEH to REG expressed as a percentage where EG is for electricity generated EEH for electrical equivalent of heat and REG for reference energy generation Electricity generation EG and reference energy generation REG are calculated from monthly production data The electrical equivalent of heat EEH is calculated from annual production data LFH is thus a combination of both monthly and annual production records The report reflects the performance indicator value and Reference Unit Power RUP at the end of a selected year or year range In the case of the current year it reflects the latest situation Reactors that were not operational for at least one month during the reporting period because they were in long term shutdown are automatically excluded from the report Reference Unit Power RUP refers to the net electrical capacity at the end of the final year of the reporting period unless grouping by year is selected In the current year RUP reflects the latest situation Age in summaries refers to a reactor s age at the end of the reporting period Exception when age and year are selected as summary criteria in combination age is calculated separately for each year in the reporting period For periods years for which data collection is not completed or data is missing an additional data completeness indicator in per cent is displayed I
33. of generated report into the following formats Acrobat PDF Web Archive HTML Excel XLS Select one of the three options from the drop down menu and select Export The report is transferred into the desired format and opened in the desired application The report can be saved in this format and customized further in Excel REACTOR GROUPS STANDARD REPORTS ADVANCED REPORTS MAP Year end Reactor Status 100 Find Next select a format z Select formal Acn F fil Reactor Status Operational reactors Reactor Group All Reactors Filters Base Year 2011 Show Reactor Details es Summaries Location No of reactors RUP MWe TOTALS 440 374093 8 Inland near a lake location 72 66355 8 Inland near a river location 182 153920 Seacoast location 186 153818 FIG 2 4 Report EXPORT function 2 4 General Rules and Methods Used Reports Report specific conditions are described in each particular report guidelines This section refers to general conditions allied mainly to the performance indicator PI reports 2 4 1 Criteria for Data Selection for PI Reports Except for the scram rates UA7 and US7 and LFH which includes annual non electrical applications data the performance indicators are calculated from monthly records The records are filtered to only include those months during which a reactor was in commercial operation 1
34. or their total net electrical capacity Yearly totals are displayed as a bar chart and as a data table Year end Reactor Status trends Operational reactors Reactor Group All Reactors Filters Year From 2003 To 2012 Show Reactor Details Yes Totals Number of reactors Summaries Region Number of reactors Number of reactors 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 TOTALS 437 438 441 435 439 438 437 441 435 435 Africa 2 2 2 2 2 2 2 2 2 2 America Latin 6 6 6 6 6 6 6 6 6 6 Unit RUP MW RUP MW RUP MW RUP MW RUP MW RUP MW RUP MW RUP MW RUP MW RUP MW ANGRA 1 626 626 626 626 520 401 609 609 600 eo ANGRA 2 1275 1275 1275 1275 1275 1275 1275 1275 1275 1275 ATUCHA 1 335 335 335 335 335 335 335 335 335 335 EMBALSE 600 600 600 600 600 600 600 600 600 LAGUNA VERDE 1 680 680 680 6s0 680 60 650 650 650 650 LAGUNA VERDE 2 680 680 680 680 620 eso 650 650 650 650 America Northern 119 120 121 121 122 122 122 122 122 122 Asia Far East 85 87 90 91 92 91 94 93 93 Asia Middle East and 16 16 17 18 19 19 20 21 24 24 South Europe Central and 68 70 70 67 68 67 66 67 68 68 Eastern Europe Western 141 137 135 130 130 130 130 129 120 120 FIG 4 4 Example of the Year end Reactor Status Trend Change Report 19 Concept The report can be generated for historical periods up to and including the current year By default the report is generated for the current year If the user enters a from
35. particular year Age in Summaries relates to each particular year Data Selection Reactor detail information is from reactor and site tables of the PRIS database RUP is calculated from monthly production data to reflect RUP revisions The closest available match from the Annual Electricity Reconstruction table is used 30 4 3 Worldwide Statistics Tables The 25 reports tables in the Worldwide Statistics section provide a global overview of nuclear power They are equivalent to the tables published in the IAEA annual publication Nuclear Power Reactors in the World RDS 2 The last number of the following subchapters corresponds to the number of the table in RDS 2 Concept The reports are applied to all reactors worldwide As a consequence reactor group selection is not available The only report criterion is base year for the report By default the previous year is selected Three reports scheduled connections to the grid planned reactors and decommissioning process decommissioned do not require a base year selection Condition The reports query all reactors in the world 4 3 1 Reactor Overview and Nuclear Share Table 1 This report provides an overview by country of the reactors under construction in operation and in long term shutdown in a given year In addition it includes information about the total nuclear energy production TW h and the nuclear energy share o
36. qae hea 87 ABBREVIATIONS s acutis dictae eh leh aN Le M EU MM od atten 9 ANNEX CODES USED IN PRIS OUTAGE REPORTS sse 93 CONTRIBUTORS TO DRAFTING AND REVIEW doloe 99 1 INTRODUCTION 1 1 Power Reactor Information System PRIS PRIS is a comprehensive data source for nuclear power reactors in the world It includes specification and performance history data on operating reactors as well as reactors under construction or reactors being decommissioned Ref 1 One of the most important purposes of the PRIS database is to provide data and tools for nuclear power plant NPP overview performance analyses as well as trending and benchmarking reactor units worldwide To achieve this goal various statistical functions and reports have been included in PRIS The reactor specification data consist of basic information location operator owner suppliers milestone dates and design technical characteristics The performance data include energy production and loss data as well as outage and operational function information Due to detailed classification of energy losses and comprehensive outage coding system Ref 2 a set of internationally accepted performance indicators Ref 1 are calculated from the PRIS performance data The indicators can be used for benchmarking international comparison or analyses of nuclear power availability safety and reliability from reactor specific national or worldwide pers
37. reporting period are automatically excluded from the report The 15 day condition is applied to decide whether borderline months the months of the commercial date the long term shutdown date the restart date and the permanent shutdown date should be included in the calculation periods years that data collection is not completed or data is missing an additional data completeness indicator in percent is displayed It is calculated as a ratio of number of months that data is available to the number of months a reactor was operational The data completeness indicator helps the user interpret the reliability accuracy of the performance indicator values On the summary and report total levels only reactors that have data completeness gt 50 are considered qualified reactors The qualified reactors column indicates how many reactors out of the operational reactors were considered for summary totals calculation Reference Unit Power RUP refers to the net electrical capacity at the end of the final year of the reporting period unless grouping by year is selected In the current year RUP reflects the latest situation Age in the summaries refers to a reactor s age at the end of the reporting period except when age and year are both selected In this case age is calculated separately for each year in the reporting period Data Selection Reactor detail information is selected from the Reactor
38. several groups of the result set No filters are available as the report search duration between any consequent full outages regardless type cause system codes 72 The Show Reactor Details option returns operating period data for individual reactors in addition to summary level results Total median mean and maximum operating periods as well as the standard deviations are displayed Condition As a general rule the operating period between two full outages is calculated as the time difference in days between the start date of a full outage and the end date of the previous full outage n 1 The end date of the previous full outage is calculated as the start date of that outage plus its duration In the case of combined outages containing full outage fragments as well as partial outage fragments the full outage start date is calculated as the start date of the first full outage fragment in the combined outage The full outage end date is calculated as the end date of the last full outage fragment in the combined outage plus its duration Hence the operating period between two combined full outages may be longer than the simple time difference between the start and end dates of these outages If a reactor is in long term shutdown between two full outages the restart date is used for calculating the operating period instead of the end date of the previous outage For the first full outage during a reactor s op
39. shutdown light water cooled graphite moderated reactor megawatt megawatt hour non electrical application nuclear power plant nuclear steam supply system 91 PHWR PEL PI PRIS PRISTA PUF PWR RUP SGHWR TW h 7 UCL US7 UUF WANO WEDAS XEL XUF 92 operation factor pressurized heavy water reactor planned energy loss performance indicator power reactor information system PRIS Statistics planned unavailability factor pressurized water reactor reference energy generation reference unit power steam generating heavy water reactor terawatt hour unplanned automatic scram rate unit capability factor unplanned capability loss factor unplanned energy loss Unplanned scram rate unplanned unavailability factor World Association of Nuclear Operators web enabled data acquisition system externally caused energy loss external unavailability factor ANNEX CODES USED IN PRIS OUTAGE REPORTS The outage coding system clearly refers to statistical objectives and not to an event approach with detailed description and root cause analyses It constitutes a first level tool for plant performance analyses and benchmarking Detailed definitions of outage codes is in IAEA TECDOC 1393 1 Outage type The outage type is a three character code The third character is for unplanned outages only Code_1 description P Planned outage due to causes under the plant management co
40. those belonging to this group When a summary is not exclusive such as in the case of outage codes a reactor can have multiple outages corresponding to various codes the total reactor years will equal that of the broader exclusive group In other words the total reactor years will be the sum of all reactors from the broader superior summary Reactors and summaries without any occurrence of the selected outages are not displayed but are included in a reactor year calculation When generating the report for several years and grouping by year the results on the year group level will be equivalent to generating the report separately for each year numbers and subgroups below the year group only refer to the respective year numbers above the year group level refer to the whole reporting period Outage frequency is the number of outages for a reactor for a given summary group or for all reactors in the report divided by number of reactor years 71 Data Selection Outage information is extracted from the combined outage records table in the PRIS database 5 3 4 Outages Operating Period between Full Outages This report provides statistics on the duration of continuous operation of power reactors between two full outages disconnections from the grid Operating Period Between Full Outages Reactor Group All Reactors Filters Year From 2007 To 2010 Show Reactor Details Yes Summaries Country Type
41. 1300 2 1300 NETHERLANDS 1 482 1 482 PAKISTAN 1 300 1 125 2 425 ROMANIA 2 1300 2 1300 RUSSIA 16 11914 15 10219 1 560 32 22693 SLOVAKIA 4 1816 4 1816 SLOVENIA 1 666 1 666 SOUTH AFRICA 2 1800 2 1800 SPAIN 6 6004 2 1510 8 7514 SWEDEN 3 2799 7 6504 10 9303 SWITZERLAND 3 1700 2 1538 5 3238 TAIWAN CN 2 1841 4 3141 6 4982 UK 1 1188 18 8949 19 10137 FIG 4 12 Table 2 Report Condition When generated for the current year the report only considers reactors that are currently in the status operational When generated for a year in the past the report considers reactors that have been operational at the end of the reporting year by applying the following conditions e The reactor is currently in the status operational long term shutdown or permanent shutdown ts grid date is in or before the reporting year e Its permanent shutdown date is past the reporting year t was not in long term shutdown in December of the reporting year Capacity is calculated as follows e Capacity in the year of the report by default e Latest net electrical capacity if the capacity in the year of the report is not available Ordesign net electrical capacity Data Selection Reactor basic information including country and type are selected from the Reactor table RUP is selected from the Annual Production table if available or from the Reactor table 4 3 3 Reactors Under Construction by Type Table 3
42. 2 SPAIN 8 7567 SWEDEN 10 9298 BWR 7 6503 150 Code Unit Current Sta Model Operator Reactor Suppli Const Date Grid Date RUP MWe More De SE FORSMARK 1 Operational BWR BWR 75 FKA ABBATOM 1973 06 01 1980 06 06 978 B D S SE FORSMARK 2 Operational BWR BWR 75 FKA ABBATOM 1975 01 01 1981 01 26 990 Bj D S SE FORSMARK 3 Operational BWR BWR 3000 ABBATOM 1979 01 01 1985 03 05 1170 B 018 SE OSKARSHAMN 1 Operational BWR ABBBWR OKG ABBATOM 1966 08 01 1971 08 19 473 Bj D S SE OSKARSHAMN Z Operational BWR OKG 1969 09 01 1974 10 02 638 Bj D S SE OSKARSHAMN 3 Operational BWR BWR 75 OKG ABBATOM 1980 05 01 1985 03 03 1400 D S SE RINGHALS 1 Operational BWR BWR RAB ABBATOM 1969 02 01 1974 10 14 854 Bj D S PWR 3 2795 SWITZERLAND 5 3263 UNITED KINGDOM 18 9920 FIG 4 1 Example of the Year end Reactor Status Report 15 Concept The report provides information about all reactors in a given status in a year selected by the user The report has two mandatory parameters the base year for which the report shall be generated and one or more reactor status to be considered The report can be generated for the current year and for historical years By default the current year is selected as a base year The user must select at least one reactor status to be included in the report By default the status operational is selected For reactors under construction there
43. 25221 7 97 25065 7 02 TOTALS 818689 100 00 1027875 100 00 316432 100 00 356865 100 00 FIG 4 31 Table 21 Report Condition The report only considers planned and unplanned full outages outages codes PF and UF The report calculates the total energy and time lost for planned and unplanned full outages during the two year reporting period In addition it presents the percentage distribution of energy and time lost due to the different outage causes The report is year based Outages are included if they start in the reporting period The report considers reactor units in operation in long term shutdown and permanent shutdown that were connected to the grid on or before the reporting year The report considers outages starting from the year of a reactor s commercial date This may include outages that occurred in the months of trial operation preceding the actual commercial date The report does not filter outages on long term shutdown date restart date or permanent shutdown date Data Selection 50 Outage information duration energy loss cause is selected from the Outages table and the Cause table The Reactor table is used for filtering purposes 4 3 22 Countries Summary Table 22 For each country this report provides the number of reactors under construction in operation in long term shutdown and in permanent shutdown at the end of the reporting year Countries Abbreviations and Summaries Latest in 2010 Iso C
44. 3 66 24 68 15 86 3 93 4 124 GERMANY 9 68 F 100 6 103 HUNGARY 2 112 2 90 INDIA 1 152 2 154 1 152 3 120 4 122 1 64 3 74 ITALY 1 101 JAPAN 11 61 10 46 8 49 10 46 3 42 4 47 1 53 KOREA REP 1 63 4 65 4 62 2 61 5 59 4 54 LITHUANIA 1 80 1 116 MEXICO 1 151 1 210 PAKISTAN 1 83 ROMANIA 1 169 1 161 RUSSIA 6 74 9 73 4 72 1 109 2 233 SLOVAKIA 2 89 2 99 2 119 SLOVENIA 1 80 SOUTH AFRICA 2 102 SPAIN 5 112 2 96 SWEDEN 3 85 4 74 SWITZERLAND 1 63 1 125 TAIWAN CN 2 64 4 72 FIG 4 18 Table 8 Report Condition The construction time span for each reactor is calculated as the difference in months between a reactor s construction date and its grid date excluding periods during which construction was suspended The months of the construction start and grid connection are included in the time span as are the months of the construction suspension and restart where applicable Each reactor is counted in the time interval when it was connected to the grid grid date Data Selection All data required for the report is selected from the Reactor and Long term Shutdown Details tables 4 3 9 Construction Starts Table 9 This report lists all reactors that began construction in a selected reporting year 38 Construction starts during 2010 Construction Country Code BRAZIL 3 CHINA CN 51 CHINA CN 52 CHINA CN 55 CHINA CN 56 CHINA CN 47 CHINA CN 25 CHINA CN 38 CHINA CN 39 CHINA CN 35 CHINA CN 43 INDIA
45. Annual Table 20 This report examines the direct causes of planned and unplanned full outages in a selected reporting year Energy loss GWh and operating hours lost are calculated for each outage cause in absolute numbers and percentages Direct causes of full outages Latest in 2010 Planned Full Outages Unplanned Full Outages Direct Outage Cause Energy Lost Time Lost Energy Lost Time Lost GW e h Hours GW e h Hours Plant equipment problenyfailure 118668 74 58 138785 74 02 Refueling without a maintenance 17861 457 17587 3 64 Inspection maintenance or repair combined with refuelling 287995 73 74 331197 68 50 Inspection maintenance or repair without refuelling 24962 6 39 44658 924 Testing of plant systems or components 485 0 12 7084 147 124 0 08 249 0 13 Major back fitting refurbishment or upgrading activities with 12741 3 26 27444 5 68 refuelling Major back fitting refurbishment or upgrading activities without 45740 11 71 46770 9 67 refuelling Nuclear regulatory requirements 19895 12 50 25401 13 55 Human factor related 6649 418 8646 4 61 1523 0 96 2397 1 28 Fuel management limitation including high flux tilt stretch out or 1807 1 14 1804 0 96 coast down operation Others 790 0 20 8762 1 81 10444 6 56 10215 5 45 TOTAL 390574 100 00 483502 100 00 159110 100 00 187497 100 00 FIG 4 30 Table 20 Report Condition The report only considers planned and unplanned full outages outages codes PF UF
46. COMPUTER MANUAL SERIES No 22 PRIS STATISTICS Power Reactor Information System Statistical Reports User s Manual 5 IAEA nternational Atomic Energy Agency PRIS STATISTICS POWER REACTOR INFORMATION SYSTEM STATISTICAL REPORTS USER S MANUAL The following States are Members of the International Atomic Energy Agency AFGHANISTAN ALBANIA ALGERIA ANGOLA ARGENTINA ARMENIA AUSTRALIA AUSTRIA AZERBAIJAN BAHRAIN BANGLADESH BELARUS BELGIUM BELIZE BENIN BOLIVIA BOSNIA AND HERZEGOVINA BOTSWANA BRAZIL BULGARIA BURKINA FASO BURUNDI CAMBODIA CAMEROON CANADA CENTRAL AFRICAN REPUBLIC CHAD CHILE CHINA COLOMBIA CONGO COSTA RICA COTE D IVOIRE CROATIA CUBA CYPRUS CZECH REPUBLIC DEMOCRATIC REPUBLIC OF THE CONGO DENMARK DOMINICA DOMINICAN REPUBLIC ECUADOR EGYPT EL SALVADOR ERITREA ESTONIA ETHIOPIA FIJI FINLAND FRANCE GABON GEORGIA GERMANY GHANA GREECE GUATEMALA HAITI HOLY SEE HONDURAS HUNGARY ICELAND INDIA INDONESIA IRAN ISLAMIC REPUBLIC OF IRAQ IRELAND ISRAEL ITALY JAMAICA JAPAN JORDAN KAZAKHSTAN KENYA KOREA REPUBLIC OF KUWAIT KYRGYZSTAN LAO PEOPLE S DEMOCRATIC REPUBLIC LATVIA LEBANON LESOTHO LIBERIA LIBYA LIECHTENSTEIN LITHUANIA LUXEMBOURG MADAGASCAR MALAWI MALAYSIA MALI MALTA MARSHALL ISLANDS MAURITANIA MAURITIUS MEXICO MONACO MONGOLIA MONTENEGRO MOROCCO MOZAMBIQUE MYANMAR NAMIBIA NEPAL NETHERLANDS NEW ZEALAND NICARAGUA NIGER NIGERIA NORWAY OMA
47. CTRAB ACECOWEN 1971 9 1975 8 1975 12 81 9 827 BELGIUM BE 5 DOEL 3 PWR WE Hoops 3054 1056 1006 ELECTRAB FRAMACEC 1975 1 1982 6 1982 10 86 1 875 BELGIUM 7 DOEL 4 PWR WE Hoops 2988 1090 1038 ELECTRAB 1978 12 1985 4 1985 7 83 8 845 BELGIUM 3 TIHANGE 1 PWR Framatome 3 lo 2873 1009 962 ELECTRAB 1970 6 1975 3 1975 10 84 864 BELGIUM 6 2 PWR WE Hoops 3064 1055 1008 ELECTRAB FRAMACEC 1976 4 1982 10 1983 6 87 9 88 9 BELGIUM 8 TIHANGE 3 PWR WE 34oops 3000 1094 1046 ELECTRAB ACECOWEN 1978 11 1985 6 1985 9 87 4 89 BRAZIL BR 1 ANGRA 1 PWR 2 WE 1882 640 609 ELETRONU WH 1971 5 1982 4 1985 1 543 61 1 BRAZIL BR2 ANGRA 2 PWR PRE KONVOI 3764 1350 1275 ELETRONU KWU 1976 1 2000 7 2001 2 83 9 85 6 BULGARIA BG 5 KOZLODUY 5 PWR VVER V 320 3000 1000 953 KOZNPP AEE 1980 7 1987 11 1988 12 657 68 6 BULGARIA BG 6 KOZLODUY 6 PWR WER V 320 3000 1000 953 KOZNPP AEE 1982 4 1991 8 1993 12 729 754 CANADA CA 10 BRUCE 3 PHWR CANDU 750A 2832 805 730 BRUCEPOW 1972 7 1977 12 1978 2 73 738 CANADA 11 BRUCE4 PHWR CANDU 750A 2832 805 730 BRUCEPOW 1972 9 1978 12 1979 1 72 729 CANADA CA 18 BRUCE 5 PHWR CANDU 750B 2832 872 817 BRUCEPOW OH AECL 1978 6 1984 12 1985 3 844 85 CANADA CA 19 BRUCE PHWR CANDU 7508 2690 891 817 BRUCEPOW OH AECL 1978 1 1984 6 1984 9 808 815 CANADA CA 20 BRUCE 7 PHWR CANDU 750B 2832 872 817 BRUCEPOW OH AECL 1979 5 1986 2 1986 4 847 85 6 CANADA CA 21 BRUCE 8 PHWR CANDU 750B 2690 845 782 BRUC
48. E 0 3 0 0 AVR ARBEITSGEMEINSCHAFT 0 0 0 1 VERSUCHSREAKTOR GMBH Axpo AG Keerkraftwerk Berrau 0 2 0 0 CH 5312 BRITISH ENERGY 0 15 0 0 BHAVINI Bharatiya Nabhileya Vidyut Nigam Limited 1 0 0 0 BKAB Barseback Kraft 0 0 0 3 BKW BKW ENERGIE AG 0 1 0 0 BRUCEPOW BRUCE POWER 0 6 2 0 BV GKN BV GEMEENSCHAPPELIJKE 0 0 0 t KERNENERGIECENTRALE NEDERLAND BV GKN CEAEDF Commissarat Atomque 80 0 0 0 t France 20 CENSCK CENTRE D ETUDE DE LENERGE 0 0 0 NUCLEAIRE STUOIECENTRUM VOOR KERNENERGIE CEZ CZECH POWER COMPANY CEZ as 0 6 0 0 FIG 4 34 Table 24 Report Condition When generated for the current year the report counts reactors according to their current status When generated for a year in the past the following rules are applied 54 Operational The reactor is currently in any status planned under construction operational long term shutdown or permanent shutdown The reactor unit is connected to the grid before or during the reporting year The reactor is not shutdown by December of the reporting year The reactor is not in long term shutdown by December of the reporting year Under construction The reactor is currently under construction operational in long term shutdown or permanently shut down Construction for the reactor has started before or during the reporting year The reactor unit is not connected to the grid by December of the reporting ye
49. ECDOC 1393 IAEA Vienna 2004 88 outage duration The total clock hours of the outage measured from the beginning of the reference period or the outage whichever comes last to the end of the reference period or the outage whichever comes first outage extension The outage extension is defined as an unplanned portion of a planned outage causing prolongation of the planned outage partial outage An outage is considered partial if the actual unit output power is lower than its reference value but the reactor unit is still connected to the grid permanent shutdown date The date when the plant is officially declared by the owner to be taken out of commercial operation and shut down permanently planned outage An outage is considered planned if it was scheduled at least four weeks in advance power reactor A nuclear reactor is a device to initiate and control a sustained nuclear chain reaction In a power reactor the energy released is used as heat to make steam to generate electricity PRIS statistics PRISTA A web based reporting application used by registered users to produce reports and statistics from PRIS reactor age Number of years the reactor was in operation from its first grid connection to a referred date reactor model The reactor model identifies a specific reactor design series e g Magnox AGR or VVER V 213 Konvoi EPR BWR 6 within a particular reactor type GCR or PWR respectively Al
50. EPOW OH AECL 1979 8 1987 3 1987 5 82 9 841 CANADA CA 22 DARLINGTON 1 PHWR 850 2776 934 878 OPG OH AECL 1982 4 1990 12 1992 11 84 5 85 5 CANADA 22 DARLINGTON 2 PHWR CANDU 850 2776 934 878 OPG OH AECL 1981 9 1990 1 1990 10 774 784 CANADA CA 24 DARLINGTON 3 PHWR 850 2776 934 878 OPG OH AECL 1984 9 1992 12 1993 2 85 7 86 6 CANADA CA 25 DARLINGTON 4 PHWR 850 2776 934 878 OPG OH AECL 1985 7 1993 4 1993 6 85 1 85 8 CANADA 12 GENTILLY 2 PHWR 6 2156 675 635 HQ AECL 1974 4 1982 12 1983 10 80 2 82 1 CANADA 4 PICKERING 1 PHWR CANDU 500A 1744 542 515 OPG OH AECL 1966 6 1971 4 1971 7 65 8 65 9 CANADA 7 4 PHWR CANDU 500A 1744 542 515 OPG OH AECL 1968 5 1973 5 1973 6 65 7 66 CANADA 13 PICKERING 5 PHWR CANDU 5008 1744 540 516 OPG OH AECL 1974 11 1982 12 1983 5 737 742 FIG 4 24 Table 14 Report Condition When generated for the current calendar year the report includes all reactors that are currently in operational status When generated in a past year the report includes all reactors that were in commercial operation for at least one day during the year concerned The following criteria are applied e The reactor is currently in operational long term shutdown or permanent shutdown status e The reporting year is between the reactor s commercial date inclusive and shutdown date exclusive e The reactor is not in long term shutdown in December
51. H 1957 11 1962 10 1962 10 1987 6 BULGARIA 4 BG 1 KOZLODUY 1 PWR 1375 440 408 KOZNPP AEE 1970 4 1974 7 1974 10 2002 12 2 KOZLODUY 2 PWR 1375 440 408 KOZNPP AEE 1970 4 1975 8 1975 11 2002 12 BG 3 KOZLODUY 3 PWR 1375 440 408 KOZNPP AEE 1973 10 1980 12 1981 1 2006 12 BG KOZLODUY 4 PWR 1375 440 408 KOZNPP AEE 1973 10 1982 5 1982 6 2006 12 CANADA 3 2 DOUGLAS POINT PHWR 704 218 206 OH AECL 1960 2 1967 1 1968 9 1984 5 3 GENTILLY 1 HWLWR 792 266 250 HQ AECL 1966 9 1971 4 1972 5 1977 6 CA 1 ROLPHTON NPD PHWR 92 25 22 CGE 1958 1 1962 6 1962 10 1987 8 FRANCE 12 FR 9 BUGEY 1 GCR 1954 555 540 EDF FRAM 1965 12 1972 4 1972 7 1994 5 FR 2 CHINON A1 GCR 300 80 70 EDF LEVIVIER 1957 2 1963 6 1964 2 1973 4 FR 3 CHINON A2 GCR 800 230 180 EDF LEVIVIER 1959 8 1965 2 1965 2 1985 6 FRA CHINON A3 GCR 1170 480 360 EDF GTM 1961 3 1966 8 1966 8 1990 6 FR 5 CHOOZ A ARDENNES PWR 1040 320 305 SENA 1962 1 1967 4 1967 4 1991 10 FR4 EL 4 MONTS D ARREE HWGCR 250 75 70 EDF GAAA 1962 7 1967 7 1968 6 19857 FR 1B G 2 MARCOULE GCR 260 43 39 COGEMA SACM 1955 3 1959 4 1959 4 1980 2 FR 1 G 3 MARCOULE GCR 260 43 40 COGEMA SACM 1956 3 1960 4 1960 4 1984 6 FR 10 PHENIX FBR 345 142 130 CEA EDF CNCLNEY 1968 11 1973 12 1974 7 2010 2 FR 7 ST LAURENT A1 GCR 1650 500 390 EDF FRAM 1963 10 1969 3 1969 6 1990 4 FR 8 ST LAURENT A2 GCR 1475 530 465 EDF FRAM 1966 1 1971 8 1971 11 1992 5 FR 24 SUPER PHENIX FBR 3000 1242 1200 EDF ASPALDO 1976 12 1986 1 1986 12 1998 12
52. IN 30 INDIA IN 31 JAPAN JP 66 RUSSIA RU 164 RUSSIA RU amp 4 WORLDWID E Condition Reactor Name ANGRA 3 CHANGJIANG 1 CHANGJIANG 2 FANGCHENGGA NG 1 FANGCHENGGA NG2 FUQING 3 HAIYANG 2 NINGDE 3 NINGDE 4 TAISHAN 2 YANGJIANG 3 KAKRAPAR 3 KAKRAPAR 4 OHMA LENINGRAD 2 2 ROSTOV 4 Construction starts 16 Type Model Capacity MW Thermal Gross PWR PRE 3765 1350 KONVOI PWR CNP 600 1930 650 PWR CNP 600 1930 650 PWR CPR1000 2905 1087 PWR CPR1000 2905 1087 PWR CPR 1000 2905 1087 PWR AP 1000 3750 1250 PWR CPR1000 2905 1080 PWR CPR1000 2905 1080 PWR EPR 1700 4500 1750 PWR CPR1000 2905 1087 PHWR PHWR 700 2166 700 PHWR PHWR 700 2166 700 BWR ABWR 3926 1383 PWR VVER V 3200 1170 491 PWR VVER V 3000 1070 320 Total Net Capacity Operator Net 1245 ELETRONU 610 HNPC 610 HNPC 1000 GFNPC 1000 GFNPC 1000 FQNP 1000 SNPC 1000 NDNPC 1000 1700 1000 YJNPC 630 NPCIL 630 NPCIL 1325 1085 REA 1011 REA 15846 MW FIG 4 19 Table 9 Report NSSS Supplier KWU DFEC DFEC DFEC DFEC ROSATOM ROSATOM start 2010 6 2010 4 2010 11 2010 7 2010 12 2010 12 2010 6 2010 1 2010 9 2010 4 2010 11 2010 11 2010 11 2010 5 2010 4 2010 6 Grid Connection 2015 3 2015 9 Commercial Operation 2018 12 2015 12 2015 7 2015 6 2015 12 2014 11 reactor is included in the report if it is currently under construction operation
53. MONOSOV 2 5 AKKUYU aao Climatic Zone 4 Review amp Save helps to check the results of the chosen selections and filters It also gives the opportunity to exclude particular reactors from the group When the list of reactors satisfies all expectations it can be saved with a specific name Group Name and explanation notes placed in the Group Description field Note A group could be either Dynamic or Static The dynamic group is updated automatically when any of filtering parameter is changed in PRIS The static group which allows exclusion of individual reactors from the group does not reflect any later changes in filtering parameters Nevertheless the static group can be refreshed manually using the Refresh button REACTOR GROUPS STANDARD REPORTS ADVANCED REPORTS Basic Faes Design Piters Review amp Save 9 Go to Standard Reports 3 Go to Advanced Reports 90 Name PHWR in Ontario Casada Group Descriptions operational PENR in Ontario Canada Defaut Opname State Save Group lt _ k Group Group Group Founs 20 records in this Group Refresh a Include Region gt Country Unit Reteconce Unit Power MWe Status Group Amenca Notem CANADA BRUCE 1 PHWR 772 Operational America Nother CANADA BRUCE 2 PHAR 734 Operational Amenca Northem CANADA BRUCE 3 PHWR 730 Operational Amena Northen CANADA BRUCE 4 PHAR 730 Operationa
54. Manual of PRIS Statistics in a new window The report specific guidelines can be opened by clicking on the icon 22 Reactor group User can select one of the predefined group of reactors See 3 Reactor Groups Also 1 View Reactors will confirm the group selected or choose L Create New Reactor Group directly from this parametrization page If any group is assigned as a default group it is predefined for the report If not the standard choice reactors is predefined Summaries In most reports it is possible to summarise results into sub levels Summaries should be selected from the left box and transferred to the right box When any of the summaries are selected the report provides results for the group and for specific reactors if this choice is available ser Manual m STATISTICS WEDA A 1 oru REACTOR GROUPS STANDARD REPORTS ADVANCED REPORTS Reactor Status Change Reactor Group Reactors Summaries Region Year Criteria From Year 2000 Changes during the specified year range Construction starts Shutdowns Restarts after LTS Show reactor details M Show reactor details FIG 2 2 Selection of Summaries Up to three Summaries can be selected This enables aggregation of data in the report in sections one summary level sub sections two and three summary levels The rank of the parameters selected will define the level of sectioning The up
55. N PAKISTAN PALAU PANAMA PAPUA NEW GUINEA PARAGUAY PERU PHILIPPINES POLAND PORTUGAL QATAR REPUBLIC OF MOLDOVA ROMANIA RUSSIAN FEDERATION RWANDA SAUDI ARABIA SENEGAL SERBIA SEYCHELLES SIERRA LEONE SINGAPORE SLOVAKIA SLOVENIA SOUTH AFRICA SPAIN SRI LANKA SUDAN SWAZILAND SWEDEN SWITZERLAND SYRIAN ARAB REPUBLIC TAJIKISTAN THAILAND THE FORMER YUGOSLAV REPUBLIC OF MACEDONIA TOGO TRINIDAD AND TOBAGO TUNISIA TURKEY UGANDA UKRAINE UNITED ARAB EMIRATES UNITED KINGDOM OF GREAT BRITAIN AND NORTHERN IRELAND UNITED REPUBLIC OF TANZANIA UNITED STATES OF AMERICA URUGUAY UZBEKISTAN VENEZUELA VIETNAM YEMEN ZAMBIA ZIMBABWE The Agency s Statute was approved on 23 October 1956 by the Conference on the Statute of the IAEA held at United Nations Headquarters New York it entered into force on 29 July 1957 The Headquarters of the Agency are situated in Vienna Its principal objective is to accelerate and enlarge the contribution of atomic energy to peace health and prosperity throughout the world COMPUTER MANUAL SERIES No 22 PRIS STATISTICS POWER REACTOR INFORMATION SYSTEM STATISTICAL REPORTS USER S MANUAL INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA 2013 IAEA scientific and technical publications protected by the terms of the Universal Copyright Convention as adopted in 1952 Berne and as revised in 1972 Paris The copyright has s
56. N 1 52 1 52 25 10 KOREA REP 21 18698 21 18698 360 1 LITHUANIA 2 2370 2 2370 43 6 MEXICO 2 1300 2 1300 37 11 NETHERLANDS 1 482 1 55 2 537 66 0 PAKISTAN 2 425 2 425 49 10 ROMANIA 2 1300 2 1300 17 11 RUSSIA 32 22693 5 786 37 23479 1026 5 SLOVAKIA 4 1816 3 909 7 2725 136 7 SLOVENIA 1 666 1 666 29 3 SOUTH AFRICA 2 1800 2 1800 52 3 SPAIN 8 7514 2 621 10 8135 277 6 FIG 4 14 Table 4 Report Condition The number and capacity of operational reactors and reactors in long term shutdown are calculated following the same rules as Table 1 Reactor Overview and Nuclear Share The rules applied for selecting reactors in permanent shutdown are e When generated for the current year the report considers only reactors that are currently in status shutdown e When generated for a year in the past the report considers reactors that are currently in status permanent shutdown and their shutdown date is in or before the reporting year The basic rule for calculating the operating experience in months per reactor is to count the number of months that a reactor was operational for at least one day i e from its grid date to its permanent shutdown date excluding periods of long term shutdown The operating experience includes the months of the grid date long term shutdown and restart date and the permanent shutdown date Data Selection Operating experience is calculated from the dates in the Reactor table and does not re
57. N 23 14918 33 23612 41 30867 50 39625 52 43245 55 47593 54 46821 54 46821 KAZAKHSTAN 1 135 1 135 1 135 1 50 KOREA REP 1 564 5 3692 9 7220 11 9115 16 12990 20 16810 20 17705 21 18698 LITHUANIA 1 1380 2 2760 2 2370 2 2370 1 1185 MEXICO 1 640 2 1256 2 1290 2 1360 2 1300 2 1300 NETHERLANDS 2 498 2 508 2 539 2 510 1 449 1 450 1 487 1 482 PAKISTAN 1 125 1 137 1 125 1 125 2 425 2 425 2 425 2 425 ROMANIA 1 655 1 655 2 1300 2 1300 RUSSIA 20 8596 28 15841 29 18898 30 19848 30 19848 31 21743 31 21743 32 22693 SLOVAKIA 2 780 4 1632 4 1632 4 1632 6 2440 6 2442 4 1762 4 1816 SLOVENIA 1 632 1 620 1 620 1 676 1 656 1 666 1 666 SOUTH AFRICA 1840 2 1840 2 1840 2 1840 2 1800 2 1800 2 1800 SPAIN 3 1073 8 5608 9 7099 9 7097 9 7468 9 7591 8 7450 8 7514 SWEDEN 8 5510 12 9455 12 9826 12 10043 11 9412 10 8905 10 9036 10 9303 SWITZERLAND 4 1940 5 2881 5 2942 5 3056 5 3170 5 3220 5 3238 5 3238 FIG 4 15 Table 5 Report Condition and Data Selection The number of reactors and the capacity of operational reactors are calculated in the same way as Table 1 The report is thus equivalent to the operational reactors column in Table 1 as if the report for Table 1 were generated for each particular year in Table 5 4 3 6 History of Electricity Production Table 6 This report displays the history of annual nuclear energy production and nuclear energy share per country for the past 30 years It provides a snapshot of energy production TWh and nuclear energy share
58. OWEN ACEC COCKERILL 0 4 0 0 WESTINGHOUSE ACLF ACECOWEN CREUSOT LOIRE 0 1 0 0 FRAMATOME AECL ATOMIC ENERGY OF CANADA LTD 0 9 0 2 ATOMIC ENERGY OF CANADA Ltda 0 1 0 0 DEPARTMENT ATOMIC ENERGY INDIA AECL DHI ATOMIC ENERGY OF CANADA LTD DOOSAN 0 3 0 0 HEAVY INDUSTRY amp CONSTRUCTION AEE ATOMENERGOEXPORT 0 8 0 6 AEG ALLGEMEINE ELEKTRICITAETS 0 0 0 1 GESELLSCHAFT AEG GE ALLGEMEINE ELECTRICITAETS 0 0 0 1 GESELLSCHAFT GENERAL ELECTRIC COMPANY US AEG KWU ALLGEMEINE ELEKTRICITAETS 0 0 0 2 GESELLSCHAFT KRAFTWERK UNION AG AMNIGETS ANSALDO MECCANICO NUCLEARE SPA 0 0 0 1 GENERAL ELECTRIC TECHNICAL SERVICES co ATOMIC POWER CONSTRUCTION LTD 0 2 0 2 AREVA AREVA 27 29 rue Le Peletier 75433 Paris cedex 4 0 0 0 09 URL www areva com ASE ATOMSTROYEXPORT 5 0 0 0 ASEASTAL ASEA ATOM STAL LAVAL 0 2 0 1 ASPALDO ASPALDO 0 0 0 1 ATOMENERGOEXPORT 0 0 0 6 Baw BABCOCK amp WILCOX CO 0 T 0 3 BBK BROWN BOVERI KRUPP REAKTORBAU GMBH 0 0 0 1 FIG 4 35 Table 25 Report Condition When generated for the current year the report counts reactors according to their current status When generated for a past year the following rules are applied 55 Operational The reactor is currently operational in long term shutdown or permanently shut down The reactor unit is connected to the grid before by the reporting year end The reactor is not shutdown by December of t
59. PORTS This chapter provides detailed information about the individual PRIS Statistics reports Each report is introduced via a high level description explaining the purpose of the report Second the concept behind each report is explained in detail and the parameters to be provided by the user are described Third the conditions applied to the PRIS data for calculating the statistics presented in the report are explained The condition section is relevant to advanced users who want to know how certain numbers are calculated Moreover understanding these conditions allows the user to understand differences between reports Finally the data sources for each report are outlined The structure of this chapter follows the menu structure in PRISTA 4 1 Specification Data 4 1 1 Status Report Year End Reactor Status This report provides an overview of reactors in a selected life cycle status from construction through operation to permanent shutdown Year end Reactor Status Operational reactors Reactor Group All Reactors Filters Base Year 2011 Show Reactor Details Yes Summaries Region Country Type No of reactors RUP MWe TOTALS 433 366442 Africa 2 1800 America Latin 6 4119 America Northern 122 113809 Asia Far East 92 78860 Asia Middle East and South 24 6031 Europe Central and Eastern 67 47452 Europe Western 120 114371 BELGIUM 7 5927 FINLAND 4 2716 FRANCE 58 63130 GERMANY 9 12068 NETHERLANDS ij 48
60. RICA Hemispherical End ALMARAZ 1 Operational SPAIN PWR WE 3 loops Cylindrical 002 58000 OFF line Hemispherical End ALMARAZ 2 Operational SPAIN PWR WE 3 loops Cylindrical 002 45000 OFF line Hemispherical End ANGRA 1 Operational BRAZIL PWR 2 loop WE Cylindrical 002 33000 OFF line Hemispherical End ANGRA 2 Operational BRAZIL PWR PRE KONVOI Cylindrical 002 35000 OFF line Hemispherical End ANGRA 3 Under BRAZIL PWR PRE KONVOI Cylindrical Uo2 34000 OFF ine Construction Hemispherical End APS 1 OBNINSK Permanent RUSSIA LWGR AM 1 uU ON line Shutdown ARKANSAS ONE Operational UNITED STATES PWR B amp W L loop Cylindrical u02 35000 OFF ine 1 OF AMERICA DRYAMB Hemispherical End Concept FIG 5 2 Example of the Reactor Specification Report A selected set of specification information is displayed for a selected reactor group A minimum of one and maximum of 20 items can be selected for basic information and design characteristics The report always contains the latest information available in the PRIS database Up to three summary levels Region Country Site and Type can be selected by the user The summaries only contain the number of reactors for each group Condition The report includes all reactors from a selected group and reflects various reactor specifications sorted by the chosen summary The report does not filter by reactor status It includes reactors that are filtered out by most other PRISTA reports e g cancelled const
61. The complex information is included in the multiple summary levels it supports Up to three summary levels enable the user to generate insightful statistics 1 by country reactor type or year The only mandatory parameter for the report is the reporting period from and to year The report may be generated for historical periods up to and including the previous year By default the previous year is selected as a reporting period Up to three levels of grouping Region Climatic Zone Country Location Site Type Age and Year can be applied to the result set If age and or year are selected any given reactor may be listed in several summary groups The Show Reactor Details option provides reactor level performance indicator values in addition to summary level results Detailed information about each reactor also includes basic specification information i e name type model and RUP in the relevant reporting year Condition Except for the scram rates UA7 and US7 and Load Factor including Heat LFH that are calculated from annual production data the performance indicator values are calculated from monthly production records Monthly production records are filtered to include only months that a reactor was operational i e the period from the reactor s commercial date to its permanent shutdown date excluding periods of long term shutdown Reactors that were not operational for at least one month during the
62. This report provides an overview of the number of reactors under construction and their total net electrical capacity by country and by reactor type 33 Net Electrical Power of reactors under construction Latest in 2010 Country PWR BWR PHWR LWGR FBR Totals No MW e No MWe No MW e No MW e ARGENTINA 1 692 1 692 BRAZIL 1 1245 1 1245 BULGARIA 2 1906 2 1906 CHINA 28 28230 1 20 29 28250 FINLAND 1 1600 1 1600 FRANCE 1 1600 1 1600 INDIA 2 1834 3 1462 1 470 6 3766 IRAN ISL REP 1 915 1 915 JAPAN r 2650 2 2650 KOREA REP 5 5560 5 5560 PAKISTAN 1 300 1 300 RUSSIA 9 7434 1 915 1 804 11 9153 SLOVAKIA 2 782 2 782 TAIWAN CN 2 2600 2 2600 UKRAINE 2 1900 2 1900 USA 1 1165 1 1165 WORLDWIDE 56 54471 4 5250 4 2154 1 915 3 1294 68 64084 FIG 4 13 Table 3 Report Condition When generated for the current year the report considers only reactors that are currently in the status under construction When generated for a year in the past the report determines whether a reactor was under construction in the reporting year by considering the reactor s current status its construction date and its grid date It includes reactors e In the status under construction operational long term shutdown and permanent shutdown if the reporting year is between the year of the construction date and the year of the grid date e In the status suspended construction
63. Total Mean Median Max days Std dev Duration days days days days TOTALS 505668 39 116 14 61 06 731 00 136 54 ARGENTINA 2561 88 71 16 40 48 291 95 82 37 ARMENIA 1242 54 112 96 133 30 291 20 109 78 BELGIUM 9551 51 106 13 68 21 492 94 117 14 BRAZIL 2478 76 65 23 46 25 245 07 67 95 BULGARIA 2418 29 201 52 268 79 342 04 124 54 CANADA 20486 53 97 09 54 90 687 24 115 41 CHINA 14574 12 191 76 163 34 528 62 159 14 CZECH REPUBLIC 7407 43 94 97 40 80 348 16 114 44 FINLAND 5738 06 185 10 186 28 366 23 154 11 BWR 3004 44 136 57 96 69 366 23 145 54 PWR 2733 62 303 74 337 21 363 11 105 56 ISO Code Unit Total Duration Mean days Median days Max days Std dev days days LOVIISA 1 1356 06 271 21 328 45 359 03 138 52 FI LOVIISA 2 1377 56 344 39 340 18 363 11 12 85 FRANCE 67546 23 58 94 31 02 434 27 72 73 GERMANY 19379 72 151 40 137 69 520 42 133 88 HUNGARY 5000 69 178 60 169 79 344 43 103 32 FIG 5 8 Example of the Combined Outage Report Concept The only mandatory parameter for the report is the reporting period from and to year By default the previous year is selected as the reporting period Up to three levels of grouping Region Country Type Current Age and Year can be applied to the result set Aggregated summaries contain the total duration of operation between breaks mean median maximum and standard deviation of duration days of continuous operation When grouping by year each reactor may appear in
64. actors with NEA total heat production GCal the electrical equivalent of heat GWh and the percentage of energy used for NEA The report has two mandatory parameters e The base year for which the report shall be generated By default the previous year is selected e The non electrical application types to be included process heating district heating and or desalination By default all three application types are included Up to three levels of grouping NEA Application Type Region Climatic Zone Country Location Site Type and Age can be applied to the result set A reactor can only appear in exactly one group in the result set The Show Reactor Details option returns specification data about individual reactors in addition to summary level results Detailed information about each reactor includes basic design information e g type model RUP etc as well as detailed information about NEA energy generation Condition The report reflects the Reference Unit Power RUP at the end of a selected year In the case of current year it reflects the latest situation Total heat is reported also as Electrical Equivalent of Heat EEH using either entered data or calculation by a formula implemented in PRIS The report only includes reactors that were operational in the reporting year When age is used as a summary criterion it means the age of a reactor at the end of the selected year 78 Percentage of NEA is calculated
65. al in long term shutdown or in permanent shutdown and if its construction start date falls within the reporting year Net electrical capacity is the design net electrical capacity 4 3 10 Connections to the Grid Table 10 This report lists all reactor units that were connected to the grid in a given reporting year 10 Connections to the Grid during 2010 First Critically Grid Country Code CHINA CN 12 CN 14 INDIA IN 20 KOREA REP KR 21 RUSSIA RU 62 WORLDWID E Condition Reactor Type Name LINGAO 3 PWR QINSHAN 2 3 PWR RAJASTHAN 6 PHWR SHIN KORI 1 PWR ROSTOV 2 PWR Grid connections 5 Model Capacity MW Thermal Gross CPR1000 2905 1080 CNP600 1930 650 Horizontal 801 220 Pre OPR 1000 2825 1048 VVER V 3200 1000 3201 Total Net Capacity Operator NSSS Net 1000 LDNPC DFEC 610 NPQJVC CNNC 202 NPCIL NPCIL 1001 950 3763 MW FIG 4 20 Table 10 Report Construction Supplier start 2005 12 2006 3 2003 1 DHICKOPC 2006 6 ROSATOM 1983 5 2010 6 2010 7 2010 1 2010 7 2010 1 Connection 2010 7 2010 8 2010 3 2010 8 2010 3 A reactor is included in the report if it is currently operational in long term shutdown or in permanent shutdown and its grid date falls within the reporting year Net electrical capacity is the design net electrical capacity 39 4 3 11 Scheduled Connections to the Grid Table 11 This report lists all reactor units that are sche
66. and could lead to misleading statistics calculations Aggregated summaries contain the number of operational reactors number of reactor years number of outages outage frequency sum of outage duration hours and energy loss GWh The reports can be summarized by categories of standard reports and by outage codes Summary by outage codes is not disjunctive for reactors as standard ones one reactor can have any number of outage codes therefore calculation of reactor years differs from standard summaries see Conditions Outage codes can be chosen as filters Ist code for the outage type P Planned U Unplanned and X External losses e 2nd code to outage character F Full or P Partial outage e 3rd code for unplanned outage details 1 deferred shutdown 2 immediate shutdown 3 outage extension 4 automatic scram 5 manual scram e Cause code for a direct cause of an outage A Plant Equipment problem failure Refuelling without a maintenance Inspection maintenance or repair combined with refuelling D Inspection maintenance or repair without refuelling Testing of plant systems or components F Major back fitting refurbishment or upgrading activities with refuelling Major back fitting refurbishment or upgrading activities without refuelling H Nuclear Regulatory Requirements J Grid limitation failure or grid unavailability K Load Following frequency co
67. ar Long term shutdown The reactor is currently operational in long term shutdown or in permanent shutdown The reactor unit is connected to the grid before or during the reporting year The reactor is not permanently shutdown in the reporting year The reactor is in long term shutdown by December of the reporting year Permanent shutdown The reactor is now in operational long term shutdown or permanent shutdown status The permanent shutdown date is during the current year and before the reporting year end grid connection date is during the current year or before the reporting year end Data Selection The dates used to determine the historical status of a reactor in the reporting year are selected from the Reactor and Long term Shutdown Details tables Reactor operator information is selected from the Operator table 4 3 25 Supplier Summary Table 25 For each reactor supplier this report provides the number of reactors under construction in operation in long term shutdown and in permanent shutdown at the end of the reporting year Note NSSS stands for the Nuclear Steam Supply System NSSS Suppliers Abbreviations and Summaries Latest in 2010 Supplier Code Full Name Under construction Operational Long term shutdown Shutdown AIFIW ASSOCIATION ACEC FRAMATOME 0 0 0 1 WESTINGHOUSE ABBATOM ABBATOM formerly ASEA ATOM 0 0 2 ALLIS CHALMERS 0 0 0 ACEC
68. as been modified 4 3 12 Planned Reactors Table 12 This report lists all reactors that are in planned status in the reporting year It can only be generated for the current calendar year 40 Reactors planned for construction Latest in 2011 Country Reactor Type Model Capacity MW Operator NSSS Expected Code Name Thermal Gross Net Supplier construction start CHINA CN 42 BAMAOSHAN PWR CRP 1000 1080 900 CHINA CN 53 CHANGJIANG 3 PWR 1930 650 610 CHINA CN 54 CHANGJIANG 4 PWR 1930 650 610 CHINA CN 57 FANGCHENGGANG 3 PWR 1000 CHINA CN 58 FANGCHENGGANG 4 PWR 1000 CHINA 59 FANGCHENGGANG 5 PWR 1000 CHINA CN 60 FANGCHENGGANG 6 PWR 1000 CHINA CN 48 FUQING 4 PWR CPR 1000 2905 1087 1000 DFEC CHINA CN 49 FUQING 5 PWR CPR 1000 2905 1087 1000 DFEC CHINA 50 FUQING 6 PWR CPR 1000 2905 1087 1000 DFEC CHINA 76 HAIYANG 3 PWR AP 1000 3750 1250 1000 SNPC WH CHINA CN 77 HAIYANG 4 PWR AP 1000 3750 1250 1000 SNPC WH CHINA CN 26 HONGSHIDING 1 PWR 0 CN 27 HONGSHIDING 2 PWR 0 HONGYANH DFEC CHINA CN 80 HONGYANHE 5 PWR CPR 1000 2905 1080 1000 LHNPC DFEC CHINA CN 81 HONGYANHE 6 PWR CPR 1000 2905 1080 1000 LHNPC DFEC CHINA CN 65 JIYANG 1 PWR 1000 CHINA CN 66 JIYANG 2 PWR 1000 CHINA 67 JIYANG 3 PWR 1000 CHINA 68 JIYANG 4 PWR 1000 CHINA CN 61 PENGZE 1 PWR 1250 CHINA CN 62 PENGZE 2 PWR 1250 CHINA 63 2 3 PWR 1250 CHINA CN 64 PENGZE 4 PWR 1250
69. ated Reactor Fast Breeder Reactor 3 1 1 7 Gas Cooled Graphite Moderated Reactor 0 18 0 34 High Temperature Gas Cooled Graphite 0 0 0 4 Moderated Reactor Heavy Water Moderated Gas Cooled 0 0 0 4 Heavy Water Moderated Boiling Light Water Cooled Reactor Light Water Cooled Graphite Moderated Reactor Pressurized Heavy Water Moderated and Cooled Reactor Pressurized Light Water Moderated and Cooled Reactor Steam Generating Heavy Water Reactor Others Boo FIG 4 33 Table 23 Report Condition When generated for the current year the report counts reactors according to their current status When generated for a past year the following rules are applied 52 Under construction The reactor is currently in main status planned under construction operational long term shutdown or permanent shutdown Construction for the reactor has started before or during the reporting year The reactor unit is not connected to the grid by December of the reporting year Operational The reactor is currently in any main status planned under construction operational long term shutdown or permanent shutdown The reactor unit is connected to the grid before or during the reporting year The reactor is not shutdown by December of the reporting year The reactor is not in long term shutdown by December of the reporting year e Long term shutdown The reactor is currently operational i
70. bined outages only full outage fragments are considered for the calculation of energy loss and duration If the same combined outage also has partial outage fragments their duration and energy loss are disregarded is RUP of the reactor unit at the end of the reporting period 66 Age in summaries refers to the current age of reactor independently of the reporting period chosen For combined outages outage related summary criteria consider the outage type system and cause of the combined outage When selecting an outage related criteria or the year for grouping any given reactor may appear in several summary groups Only full outages that started while a reactor was operational i e between a reactor s grid date and shutdown date excluding long term shutdowns are considered Data Selection Outage information is extracted from the Outage records in the PRIS database Primarily the OutagesCombined table is used 5 3 2 Outages Full Outage Statistics Per Reactor Year This report deals with all full outages that relate to the reporting period It includes combined outages that may have started prior to the reporting period and may extend beyond the reporting period However duration and energy loss are only calculated from those full outage fragments that lie within the reporting period Unlike the Full Outage Statistics Per Outage report this report is time based and calculates
71. but that data collection is still incomplete RUP of individual reactor units is the RUP at the end of the reporting period When the report is grouped by age instead of year the age of each reactor is calculated from the end of the reporting period When the report is grouped by age and year in combination the age of each reactor is calculated for each reporting year Therefore reactors are likely to appear in several age year groups Data Selection Reactor detail information is from the Reactor and Site tables of the PRIS database The calculation of electricity supplied is based on monthly production records between a reactor s grid date and its shutdown date excluding periods of long term shutdown Reactors that were not operational during at least one month during the reporting period are excluded from the report When calculating summaries i e when grouping is selected the electricity supplied by all reactor unit s within a group is considered independently of the data completeness Data completeness for each group is calculated on a monthly basis and not as an average of the reactor level values 4 2 2 Production Data Lifetime Electricity Supplied This report calculates the lifetime electricity supplied in Terawatt Hours for all reactor units that were operational in the reporting year Lifetime electricity supplied is defined as the total amount of electricity supplied by a reactor unit from its first grid connection to
72. causes of full outages 2009 to 2010 Planned Full Outages Unplanned Full Outages Direct Outage Cause Energy Lost Time Lost Energy Lost Time Lost GWie h Hours GW e h Hours Plant equipment problenvfailure 234804 74 20 262560 73 57 Refueling without a maintenance 31050 3 79 32383 3 15 86 0 03 144 0 04 Inspection maintenance or repair combined with refuelling 573338 70 03 675087 65 68 4291 1 36 7313 2 05 Inspection maintenance or repair without refuelling 47274 577 85197 8 29 Testing of plant systems or components 1377 0 17 12928 1 26 171 0 05 412 0 12 Mair back fitting refurbishment or upgrading activities with 53983 6 59 89841 8 74 1681 0 53 2064 0 58 refuelling Major back fitting refurbishment or upgrading activities without 110330 13 48 120925 11 76 refuelling Nuclear regulatory requirements 35196 11 12 41184 11 54 Human factor related 8075 2 55 9958 2 79 Environmental conditions lack of cooling water due to dry weather 1057 0 33 1001 0 28 cooling water temperature limits flood storm lightning etc Fire 2123 0 67 3462 0 97 External restrictions on supply and services lack of funds due to 381 0 05 1909 0 19 1920 0 61 1898 0 53 delayed payments from customers disputes in fuel industries fuel rationing labour strike outside the plant spare part delivery problems etc Fuel management limitation including high flux tilt stretch out or 166 0 02 843 0 08 1807 0 57 1804 0 51 coast down operation Others 790 0 10 8762 0 85
73. ctor related Governmental requirements or court decisions Environmental conditions flood storm lightning lack of cooling water due to dry weather cooling water temperature limits etc Fire External restrictions on supply and services lack of funds due to delayed payments from customers disputes in fuel industries fuel rationing labour strike outside the plant spare part delivery problems etc Fuel management limitation including high flux tilt stretch out or coast down operation Heat supply on site to support next unit or desalination and off site distribution Security and access control and other preventive shutdown due to external threats Others Codes of plant systems and components involved Nuclear Systems 11 00 11 01 11 02 11 03 11 04 11 05 11 06 11 99 12 00 12 01 12 02 12 03 12 04 12 05 12 06 12 07 12 99 13 00 13 01 13 02 13 03 13 04 Reactor and Accessories Reactor vessel and main shielding including penetrations and nozzles Reactor core including fuel assemblies Reactor internals including steam separators dryers BWR graphite pressure tubes Auxiliary shielding and heat insulation Moderator and auxiliaries PHWR Annulus gas system PHWR RBMK None of the above systems Reactor I amp C Systems Control and safety rods including drives and special power supply Neutron monitoring in core and ex core Reactor instrumentation except neutron Reactor control
74. d Moreover only the duration and energy loss of fragments of type full are considered A reactor year is the equivalent of 12 months when the reactor is in commercial operation As reactor years are calculated with month precision it is possible that the number of reactor years is lower than the number of years in the reporting period because the reactor started commercial operation during the reporting period or because it was shut down or because of a long term shutdown Aggregated reactor years are calculated from the number of months each reactor in the report was in commercial operational during the reporting period Calculation of reactor years in summaries depends on their exclusivity A summary is exclusive if each reactor belongs to only one summary group such as country reactor type or site If a summary is exclusive the total reactor years is a sum of those belonging to this group When a summary is not exclusive such as in the case of outage codes a reactor can have multiple outages corresponding to various codes the total reactor years will equal that of the broader exclusive group In other words the total reactor years will be the sum of all reactors from the broader superior summary Reactors and summaries without any occurrence of selected outages are not displayed but are included in a reactor year calculation and contribute by a zero value to statistics for duration and energy loss When generating the report for
75. d in any year from the year of their grid date to the year preceding their shutdown date excluding years of long term shutdown see Table 1 for more details The capacity for reactor units with construction starts and connection to the grid is the design net capacity The capacity column for operational reactor units is the total net electrical capacity of all units that were operational in a given year Data Selection If available RUP for operational reactor units is selected from the Annual Electricity Reconstruction table Alternatively the latest net electrical capacity from the Reactor table is used 37 4 3 8 Construction Time Span Table 8 This report provides a historical overview of the number of reactor units connected to the grid during the past 35 years in five year periods For each country and five year period the number of reactor units connected to the grid is given together with the median construction time span for the reactors in months Number of new reactors connected to the grid and median construction time span Country 1976 to 1980 1981 to 1985 1986 to 1990 1991 to 1995 1996 to 2000 2001 to 2005 2006 to 2010 No Months No Months No Months No Months No Months No Months No Months ARGENTINA 1 109 ARMENIA 2 73 BELGIUM 4 80 BRAZIL 1 132 1 176 BULGARIA 1 87 1 104 1 89 1 113 CANADA 4 69 98 5 101 2 97 3 73 6 60 2 80 CZECH REP 1 74 3 93 1 167 1 191 FINLAND 4 63 FRANCE 1
76. dates as well as links to the Basic Information Design Characteristics Decommissioning Details and Schematics reports Condition report reflects the permanently shutdown reactors at the end of the reporting year To be included the report the reactor s shutdown date needs to be before the end of the base year RUP is the last known net electrical capacity of a reactor unit before its permanent shutdown 57 Data Selection Reactor detail information 15 selected from the Reactor Type Reactor Decommissioning tables of the PRIS database The selection criteria for this report are the same as for the Year end Reactor Status report 4 4 2 Reasons for Shutdown This report provides shutdown reactors by reason for their shutdown The following are a list of reasons for shutdown The technology or process used became obsolete process was no longer profitable Changes in licensing requirements After an operating incident Other technological reasons Other economic reasons Public acceptance political reasons After a major component failure or deterioration Other Reasons for shutdown Reactor Group All Reactors Number of reactors by shutdown reasons 50 Number of reactors obsol lic req technol public Others unprofit incident econom component fail Reasons for shutdown Reason Reason D Description obsol unprofit 1 The technology or process
77. duled to be connected to the grid in the current calendar year Scheduled connection to the Grid during 2011 Country Reactor Type Model Capacity MW Operator NSSS Construction First Grid Date Supplier start Criticality Code Name Thermal Gross Net CHINA CN 84 CEFR FBR BN20 65 25 20 CIAE 2 2000 5 2010 7 2011 7 CN 13 LINGAO4 PWR CPR1000 2905 1080 1000 LDNPC DFEC 2006 6 2011 2 2011 5 INDIA IN 16 KAIGA 4 PHWR Heals 800 220 202 NPCIL NPCIL 2002 5 2010 11 2011 1 INDIA IN 25 KUDANKULAM 1 PWR VVER V 412 3000 1000 917 NPCIL 2002 3 2011 11 2011 12 IRANJSL REP 1 BUSHEHR 1 PWR VVER V 446 3000 1000 915 NPPDCO ASE 1975 5 2011 5 2011 9 JAPAN JP 65 SHIMANE 3 BWR ABWR 3926 1373 1325 CHUGOKU HITACHI 2007 10 2011 12 PAKISTAN PK 3 CHASNUPP 2 PWR PWR 999 325 300 PAEC CNNC 2005 12 2011 2 2011 3 RUSSIA RU 37 4 PWR VVER V 320 3200 1000 950 REA ROSATOM 1986 8 2011 10 2011 11 TAIWAN TW 7 LUNGMEN 1 BWR ABWR 3926 1350 1300 TPC GE 1999 3 2011 10 2011 11 WORLDWIDE Scheduled grid connections 9 Total Net Capacity 6929 MW FIG 4 21 Table 11 Report Condition report can only be generated for the current year no historical information available The report includes all reactors with a planned grid date or in absence of a grid date commercial date in the current year Net electrical capacity is the design net electrical capacity from the Reactor table or the latest net electrical capacity if the design h
78. e mater vo Original dewys net ekoctiicar power Mae Pelosi frequency Latent roterorce une pomer mer 317 Arrage didaga turup VUA 7o Aires come denas ser Core d 5 Murer of sehe Ser baden 6240 Murra of ccn sementi me Morrie of extemal cool Net Pales Contant pe Opening cootant puerro 2 Reach outlet temperature C Row af the rated poser Dh 42000 Type 450 venka Number of paragr per RCS vop 4 Cortanmart tree Net Secondary miena Mumia ol har berns ervan alors 1 intimus Turtere oen opara ibat aleam MPul an E 2922 2003 2004 2005 200 Ld 2009 200 3010 Poducbon GAN 490200 5922114 500251 510943 672349 6710389 559697 682670 469949 1567038 7 tS 70 9 628 72 7434 vn 25 ny Par ps E 226 2224 7 54 1922 0 22 1458 2425 001 ma nm sau 7 wu ve nue o 207 235 ono 245 am 240 074 60 1 1 on 7140 87 10 n sa 925 9 7904 9 14 ss on vmi 7662 na 9519 75 9539 LIS DI Energy Availability Trends Causes of grid disconnection in the last 5 years astnouton of cutage durasan FIG 4 7 Example of the Dashboard Report Concept The report can be generated for any reactor group or for all reactors However it is rec
79. e Annual Production table RUP is calculated following the same logic as the Year end Reactor Status report 23 4 2 3 Production Data Reactor Dashboards This report is highly informative combining specification and production data about a particular reactor on a single page The following data are included in the dashboard Unit picture right upper corner Basic information e Reactor type and model e Latest thermal gross and net electrical power RUP MW e e Design net electrical capacity in MW e e Key lifecycle dates construction date grid connection commercial date Design Characteristics selected characteristics Operating History Performance indicators for 10 years and lifetime Energy Availability Trends for the reactor in relation to the world median and top quartile chart Causes of grid disconnection in the past 5 years pie chart distribution of causes by full outage duration CA 18 BRUCE 5 CANADA Siansa Operational Operator BRUCEPOW BRUCE POWER BRUCEPOW BRUCE POWER Recher Sopote OMAECL ONTARIO MYORO ATOMIC ENERGY OF CANADA LTD A Tartans CGE CANADIAN GENERAL ELECTRIC Basic Information Design Characteristics Type PNR Pimax sistens Mofes CANDY 7508 Roat venies navora Latent Turnis power 2832 Reactor vowel height jm 5561 Latent cien cad pose 872 M
80. e performance indicator values are weighted averages weighted by reactor unit capacity and the number of months in operation during the reporting period for each reactor 4 3 19 Full Outage Statistics Table 19 This report provides statistics about full outages i e outages causing reactor units to be disconnected from the grid The distribution percentage of planned unplanned and external full outages is provided per reactor category along with the total number of full outage hours per operating experience year 47 Full Outage Statistics Latest in 2010 Reactor Type Number of Full Outage Hours per Planned Unplanned External Units Operating Experience Year Outages Outages Outages PWR 268 1302 73 00 24 10 2 90 PWR lt 600 MWe 46 1167 89 20 9 20 1 60 PWR gt 600 MWe 222 1331 70 00 26 80 3 20 BWR 92 1892 66 80 31 50 1 70 BWR lt 600 MWe 11 2052 54 90 45 00 0 10 BWR gt 600 MWe 81 1871 68 60 29 50 1 90 PHWR 46 1956 78 40 21 40 0 20 PHWR lt 600 MWe 26 2410 78 20 21 60 0 20 PHWR gt 600 20 1366 78 90 20 80 0 30 MWe LWGR 15 2063 88 70 7 70 3 60 LWGR lt 600 MWe 4 3155 91 80 0 80 7 40 LWGR gt 600 11 1665 86 50 12 40 1 10 MWe GCR 18 2146 29 60 69 30 1 10 FBR 1 2219 100 00 0 00 0 00 ALL REACTORS 440 1557 70 50 27 40 2 10 FIG 4 29 Table 19 Report Condition When generated for the current calendar year the report includes all reactors that are currently in operational status When generated in a pas
81. e previous year Ifthe user only enters a from year and leaves the to year of the reporting period blank the report is generated for one year i e the from year Up to three levels of grouping Region Climatic Zone Country Location Site Type Age and Year may be applied to the result set When grouping by year or age a reactor may appear in several all groups of the result set Show Reactor Details option includes reactor level information in addition to summary level results Detailed information includes the name type model and net 21 electrical capacity of each reactor unit in addition to the electricity supplied throughout the reporting period Condition Only reactors that were operational for at least one month during the reporting period are included in the report Electricity supplied is calculated for the period between the reactor s grid connection including trial operation and its permanent shutdown excluding periods of long term shutdown When data are not complete for a reporting period a Data Completeness indicator by percentage is shown The percentage value is calculated as the number of months for which data is available in relation to the number of months during which a given reactor was operational during the reporting period Therefore completeness of less than 100 indicates that the total electricity supplied during the reporting period is likely to be higher
82. e source for statistical reports based on PRIS data 1 3 PRIS Data Model Annual Reactor Unit Specification Country Data Total nuclear Owners production Site Data Operators Total production Contractors Nuclear share Design Parameters Key Dates Schematics Milestones Annual Operating Monthly Monthly Experience Data Production Data Unavailability Data Decommissioning Outages Data Reference power Lifetime generation Scrams amp criticalhours Annual highlights Operating Cycle Data Start Time Duration coni Project Status Type Cause System il Description and Mode Milestones Scram Details Electricity production Plannedenergy loss On linehours Forced energy loss NEA production Outage extension loss heat water Externally caused loss FIG 1 1 PRIS data structure Annual electricity production data is collected from each country with operating NPPs to evaluate the nuclear share of countries total electricity production Reactor specific data consists of reactor specification and production data Specification information is updated whenever there is a change in any of the parameters At a minimum data providers should verify the specification data annually Monthly production data refers to the plant availability data model see Fig 1 2 Electricity production and plant unavailability related energy loss are reported in the monthly records Energy losses are als
83. enova L Stowisek J CONTRIBUTORS TO DRAFTING AND REVIEW International Atomic Energy Agency Kr ko Nuclear Power Plant Slovenia Temelin Nuclear Power Plant Czech Republic Electrabel S A Belgium Mochovce Nuclear Power Plant Slovakia VNIIAES Russian Federation International Atomic Energy Agency Department of Energy United States of America EDF DOAAT OSGE France UNESA Spain Forsmark Nuclear Power Plant Sweden Nuclear Power Corp of India Ltd India International Atomic Energy Agency Bruce Power Canada Energoatom Ukraine International Atomic Energy Agency Consultants Meeting Vienna Austria 4 6 May 2011 Vienna Austria 18 20 April 2012 99 SYIAEA No 22 NA International Atomic Energy Agency Where to order IAEA publications In the following countries IAEA publications may be purchased from the sources listed below or from major local booksellers Payment may be made in local currency or with UNESCO coupons AUSTRALIA DA Information Services 648 Whitehorse Road MITCHAM 3132 Telephone 61 3 9210 7777 Fax 61 3 9210 7788 Email service dadirect com au Web site http www dadirect com au BELGIUM Jean de Lannoy avenue du Roi 202 B 1190 Brussels Telephone 32 2 538 43 08 Fax 32 2 538 08 41 Email jean de lannoy infoboard be Web site http www jean de lannoy be CANADA Bernan Associates 4501 Forbes Blvd Suite 200 Lanham MD 20706 4346 USA Telephone 1 800 865 3457
84. ent structures Fire protection system None of the above systems Reactor Cooling Systems Reactor coolant pumps blowers and drives Reactor coolant piping including associated valves Reactor coolant safety and relief valves including relief tank Reactor coolant pressure control system Main steam piping and isolation valves BWR None of the above systems Steam generation systems Steam generator PWR boiler PHWR AGR steam drum vessel RBMK BWR Steam generator blowdown system Steam drum level control system RBMK BWR None of the above systems Safety I amp C Systems excluding reactor I amp C Engineered safeguard feature actuation system Fire detection system Containment isolation function Main steam feedwater isolation function Main steam pressure emergency control system turbine bypass and steam dump valve control Failed fuel detection system DN monitoring system for PHWR RCS integrity monitoring system RBMK None of the above systems 95 96 Fuel Refuelling Systems 21 00 21 01 21 02 21 03 21 99 Fuel Handling and Storage Facilities On power refuelling machine Fuel transfer system Storage facilities including treatment plant and final loading and cask handling facilities None of the above systems Secondary Plant Systems 31 00 31 01 31 02 31 03 31 04 31 05 31 06 31 07 31 99 32 00 32 01 32 02 32 03 32 04 32 05 32 99 33 00 33 01 33 02 33 03 33 99
85. erational life the operating period is calculated as the time difference between the full outage start date and the grid date of the reactor If the calculated operating period between two full outages is longer than 365 days additional data consistency checks are applied To avoid misleading statistics because of missing data the operating period is only counted if Annual production data has been reported for the year concerned Outage data has been reported for the year concerned or the time difference between online hours and total hours is less than two hours Operating periods of less than 24 hours are excluded from the report Data Selection Outage information is extracted from the outage records table in the PRIS database As calculating the operating period preceding each full outage is time consuming the data 1s prepared in a reporting table Combined Outage Info on a nightly basis 5 3 5 Outages Outage Details This report provides detailed information about all outages that occurred in the reporting period allowing the user to filter by reactor group as well as by outage related criteria the report provides a powerful analysis tool on PRIS outage data 73 Outage Details Reactor Group Europe Filters Year From 2011 To 2011 View Fragments Yes Show Reactor Details Yes Summaries Outage Type 1st Character Criteria Cause J Grid limitation failure or grid unavailability K Load following f
86. es of the PRIS database Decommissioning details are selected from the Reactor Shut Down Reason and Shut Down Reason tables 4 4 3 Decommissioning Strategies This report provides shutdown reactors by decommissioning strategy The following are a list of decommissioning strategies Deferred dismantling including partial dismantling and placing remaining radiological areas into safe enclosure Deferred dismantling placing all radiological areas into safe enclosure Immediate dismantling and removal of all radioactive materials In situ disposal involving encapsulation of radioactive materials and subsequent restriction of access Other 59 Decommissioning strategies Reactor Group All Reactors Number of reactors by decommissioning strategy 50 40 2 o 30 8 20 E 2 z 10 0 Dd PD SE Dd SE Imdte dism in situ disp Other Current decommissioning strategy 5 Descriot Dd PD SE Deferred dismantling including partial dismantling and placing remanining radiological areas into safe enclosure Dd SE Deferred dismantling placing all radiological areas into safe enclosure Imdte dism Immediate dismantling and removal of all radioactive materials in situ disp In situ disposal involving encapsulation of radioactive materials and subsequent restriction of access Other Other please specify below FIG 4 38 Decommissioning Strategies Report Concept The report provides a breakdown of shutdown reactors by decom
87. est Telephone 36 1 257 7777 Fax 36 1 257 7472 Email books librotrade hu INDIA Allied Publishers Group 1st Floor Dubash House 15 J N Heredia Marg Ballard Estate Mumbai 400 001 Telephone 91 22 22617926 27 Fax 91 22 22617928 Email alliedp vsnl com Web site http www alliedpublishers com Bookwell 2 72 Nirankari Colony Delhi 110009 Telephone 91 11 23268786 91 11 23257264 Fax 91 11 23281315 Email bookwell vsnl net ITALY Libreria Scientifica Dott Lucio di Biasio AEIOU Via Coronelli 6 20146 Milan Telephone 39 02 48 95 45 52 or 48 95 45 62 Fax 39 02 48 95 45 48 Email info libreriaaeiou eu Website www libreriaaeiou eu JAPAN Maruzen Company Ltd 1 9 18 Kaigan Minato ku Tokyo 105 0022 Telephone 81 3 6367 6079 Fax 81 3 6367 6207 Email journal maruzen co jp Web site http www maruzen co jp REPUBLIC OF KOREA KINS Inc Information Business Dept Samho Bldg 2nd Floor 275 1 Yang Jae dong SeoCho G Seoul 137 130 Telephone 02 589 1740 Fax 02 589 1746 Web site http www kins re kr NETHERLANDS De Lindeboom Internationale Publicaties B V M A de Ruyterstraat 20A NL 7482 BZ Haaksbergen Telephone 31 0 53 5740004 Fax 31 0 53 5729296 Email books delindeboom com Web site http www delindeboom com Martinus Nijhoff International Koraalrood 50 P O Box 1853 2700 CZ Zoetermeer Telephone 31 793 684 400 Fax 31 793 615 698 Email info nijho
88. est Quartile A comprehensive list of filters is used for outage related reports STATISTICS 5 int Settings oru storia REACTOR GROUPS STANDARD REPORTS ADVANCED REPORTS MAP ou in STATISTICS STANDARD REPORTS Performance Indicators erformance Indicators Reactor Gioup All Reactors v View Reactors Summaries Note A minimum of 1 and maximum of 3 Summaries can be selected for the report Region Climatic Zone Hi Location Site v 99 oo Criteria From Year 2000 To Year 2010 Performance Indicators Energy Availability Factor EAF Statistics Weighted Average E Show reactor details FIG 2 3 Example of report criteria filters parameters and selections The Worldwide Statistics reports have a very simplified criteria Those reports do not work with reactors groups applied to all reactors summaries and filters The only parameter that should be specified is a year Tables offer data with comprehensive information relative to the selected report type for a defined year for all worldwide reactors These tables are compatible with the tables in the annual publication Nuclear Power Reactors in the World 2 3 Report Functions All reports provide ZOOM FIND PRINT and EXPORT functions ZOOM function allows display control of the generated report PRINT function provides a user friendly printout of a report EXPORT function allows exporting
89. f each country Reactors Overview and Nuclear Electricity Share Reactor Status and Electricity Production latest in 2010 Country Reactors in Operation Long Term Shutdown Reactors Reactors Under Construction Nucelar Electricity Supplied Number of Units Total Capacity MW e Number of Units Total Capacity MWie Number of Units Total Capacity MW e TW e h of Total ARGENTINA 2 935 1 692 6 69 591 ARMENIA 1 375 229 3942 BELGIUM L 5926 45 73 51 16 BRAZIL 2 1884 1 1245 13 90 3 06 BULGARIA 2 1906 2 1906 14 24 33 13 CANADA 18 12569 4 2726 85 50 1507 CHINA 13 10058 29 28250 70 96 1 82 CZECH REP 6 3678 26 44 3327 FINLAND 4 2716 1 1600 21 89 28 43 FRANCE 58 63130 1 1600 410 09 74 12 GERMANY 17 20490 133 01 22 62 HUNGARY 4 1889 14 66 42 10 INDIA 19 4189 6 3766 20 48 2 85 IRAN ISL REP 1 915 NA NA JAPAN 54 46821 1 246 2 2650 280 25 2921 KOREA REP 21 18698 5 5560 141 89 3218 MEXICO 2 1300 5 59 3 59 NETHERLANDS 1 482 375 3 38 PAKISTAN 2 425 1 300 256 260 ROMANIA 2 1300 10 70 19 48 RUSSIA 32 22693 11 9153 159 41 17 09 SLOVAKIA 2 1816 2 782 1354 51 80 SLOVENIA 1 666 538 3730 SOUTH AFRICA 2 1800 12 90 5 18 SPAIN 8 7514 59 26 20 09 SWEDEN 10 9303 55 73 38 13 SWITZERLAND 5 3238 25 34 38 01 TAIWAN CN 6 4982 2 2600 39 89 19 30 FIG 4 11 Table 1 Report Condition The nuclear energy production for each country is calculated from monthly production data It includes data for all months of a reactor s operation from grid connection to shutdown e
90. f three summary options e Number of reactors the bar chart illustrates the total number of operational reactors for each year in the reporting period Summary level information in the data table includes the number of reactors for each group for each year e Net electrical capacity the bar chart illustrates the total net electrical capacity of operational reactor units MWe for each year in the reporting period Summary level information in the data table includes the total net electrical capacity of reactor units for each group for each year e Number of reactors and net electrical capacity the bar chart illustrates the total number of operational reactors for each year in the reporting period Summary level information in the data table includes the number of reactors and the total net electrical capacity for each group for each year The Show Reactor Details option includes reactor level information in addition to summary level results Detailed information includes the name and net electrical capacity of each reactor for each year in the reporting period Condition The difference between status year end report for operational reactors and operated reactor reports should be well understood Operational reactors in the year end status report are those reactors that were in operation at the end of the year Operated reactors in this report are reactors that were in operation at any time during the year As a result t
91. ff nl e Web site http www nijhoff nl Swets and Zeitlinger b v Box 830 2160 SZ Lisse Telephone 31 252 435 111 Fax 31 252 415 888 Email infoho swets nl Web site http www swets nl NEW ZEALAND DA Information Services 648 Whitehorse Road MITCHAM 3132 Australia Telephone 61 3 9210 7777 Fax 61 3 9210 7788 Email service dadirect com au Web site http www dadirect com au SLOVENIA Cankarjeva Zalozba d d Kopitarjeva 2 SI 1512 Ljubljana Telephone 386 1 432 31 44 Fax 386 1 230 14 35 Email import books cankarjeva z si Web site http www cankarjeva z si uvoz SPAIN D az de Santos S A c Juan Bravo 3A E 28006 Madrid Telephone 34 91 781 94 80 Fax 34 91 575 55 63 Email compras diazdesantos es carmela diazdesantos es barcelona diazdesantos es julilo diazdesantos es Web site http www diazdesantos es UNITED KINGDOM The Stationery Office Ltd International Sales Agency PO Box 29 Norwich NR3 1 GN Telephone orders 44 870 600 5552 enquiries 44 207 873 8372 Fax 44 207 873 8203 Email orders book orders tso co uk enquiries book enquiries tso co uk Web site http www tso co uk On line orders DELTA Int Book Wholesalers Ltd 39 Alexandra Road Addlestone Surrey KT15 2PQ Email info profbooks com Web site http www profbooks com Books on the Environment Earthprint Ltd Box 119 Stevenage SG1 4TP Telephone 44 1438748111 Fax
92. g and drainage system Communication system None of the above systems 35 00 35 01 35 02 35 03 35 04 35 05 35 99 All other I amp C Systems Plant process monitoring systems excluding process computer Leak monitoring systems Alarm annunciation system Plant radiation monitoring system Plant process control systems None of the above systems Electrical Systems 41 00 41 01 41 02 41 03 41 04 41 05 41 99 42 00 42 01 42 02 42 03 42 04 42 05 42 06 42 07 42 99 Main Generator Systems Generator and exciter including generator output breaker Sealing oil system Rotor cooling gas system Stator cooling water system Main generator control and protection system None of the above systems Electrical Power Supply Systems Main transformers Unit self consumption transformers station auxiliary house reserve etc Vital AC and DC plant power supply systems medium and low voltage Non vital AC plant power supply system medium and low voltage Emergency power generation system e g emergency diesel generator and auxiliaries Power supply system logics including load shed logic emergency bus transfer logic load sequencer logic breaker trip logic etc Plant switchyard equipment None of the above systems 97 Antweiler Bach Bila N Eloye P Frtusova S Gelman S G George R Gospodarczyk M Hamon S Iba ez M Johansson N G Kumar A Mandula J Riggin L Sem
93. he chosen performance indicator and the selected summary criteria The report has three mandatory parameters e The base year for the report By default the previous year is selected PI values will include all data up to and including the selected year The lifetime performance indicator EAF LF etc to be calculated e A filter to indicate whether the report includes reactors that are operational at the end of the reporting year This filter is selected by default Up to three levels of grouping Region Climatic Zone Country Location Site Type and Age can be applied to the result set A reactor will only appear in a single summary group age is meant to be the reactor s age at the end of the reporting year The Show Reactor Details option provides reactor level performance indicator values in addition to summary level results Reactor level details include the country name type model and status of the reactor unit as well as its net electrical capacity RUP at the end of the reporting year Condition Lifetime indicators are based on available monthly production data in PRIS from the start of the commercial operation of a reactor Reactors are only included in the report if monthly production data is available for at least 50 of the months that a reactor is operational excluding long term shutdowns RUP is the net electrical capacity of a reactor unit at the end of the reporting year Data Selection
94. he reporting year The reactor is not in long term shutdown by December of the reporting year end e Under construction The reactor is currently under construction operational in long term shutdown or permanently shut down Construction for the reactor has started before the reporting year end C hereactor is not operational by the December of the reporting year end e Long term shutdown The reactor is in long term shutdown for at least the entire month of December in the reporting year Permanent shutdown reactor is now in operational or permanent shutdown status The permanent shutdown date is on or before the reporting year end Data Selection dates used to determine the historical status of a reactor in the reporting year are selected from the Reactor and Long term Shutdown Details tables Reactor supplier information is selected from the Contractor table 4 4 Decommissioning Reports The reports in this section provide information about reactors that have been permanently shutdown and are currently being decommissioned 4 4 1 Decommissioned Reactors List This report lists all reactors that were in permanent shutdown and currently being decommissioned in a year selected by the user 56 Decommissioned Reactors List Reactor Group All Reactors Filters Base Year 2012 Show Reactor Details Yes Summaries Country Type No of reactors RUP MWe TOTALS 138 48392 ARMENIA 1
95. he world This user s manual was prepared to facilitate the use of the PRIS Statistics application and to provide guidelines and detailed information for each report in the application Statistical reports support analyses of nuclear power development and strategies and the evaluation of nuclear power plant performance The PRIS database can be used for comprehensive trend analyses and benchmarking against best performers and industrial standards This user s manual was developed by IAEA staff members and external experts with the support of two consultancy meetings The IAEA wishes to express its gratitude to L Riggin Canada and to the others who contributed to the drafting and reviewing of this manual The IAEA officer responsible for this publication was J Mandula of the Division of Nuclear Power EDITORIAL NOTE This publication has not been edited by the editorial staff of the IAEA It does not address questions of responsibility legal or otherwise for acts or omissions on the part of any person The use of particular designations of countries or territories does not imply any judgement by the publisher the IAEA as to the legal status of such countries or territories of their authorities and institutions or of the delimitation of their boundaries The mention of names of specific companies or products whether or not indicated as registered does not imply any intention to infringe proprietary rights nor should it be cons
96. his report also considers reactors that were operated but were shutdown permanently or long term during the year For some years there is a difference in reactor numbers in Electricity Supplied and Performance Indicator reports because electricity supplied is reported from the Grid Date first connection of the reactor unit to the grid while PI reports are calculated for commercial operation from the Commercial Date In some cases a reactor unit was connected to the grid and supplied electricity in the reported year but started commercial operation in a following year or later Therefore the reactor is included in operated reactors but not in PI reports of that year A maximum of 20 years can be specified for the reporting period The report reflects individual reactor units and their RUP at the end of a selected year In a case of current year it reflects the latest situation Reactors in long term shutdown are not queried in the report Results in this report can differ from status year end reports which reflect situation at the end of a year Reactors shut down permanently or into long term shutdown during a year are counted in the operated reactor reports but not in year end reports reactor is considered in operation from the Grid Date Number of reactors in this report can differ from the PI report which includes only reactors in commercial operation RUP relates to the end of each
97. ich can be done either manually or automatically thermal capacity The Reference thermal power of the plant expressed in MW th The reactor thermal power is the net heat transferred from the fuel to the coolant trial operation In PRIS a reactor is in trial operation from its first grid connection to the date when it is officially declared in commercial operation Commercial Operation Date unavailability A status when the plant is not able to operate at its reference power This condition which may be under or beyond plant management control should only reflect lack of availability of the plant itself regardless of energy demand transmission grid condition or political situation in the country web enabled data acquisition system WEDAS Web based application used by PRIS data providers for on line data entry to the PRIS database 90 AGR BWR CF DI EAF EEH EG EUF FBR FLR Gcal GCR GW GW h HTGR HWGCR LF LFH LTS LWGR MW MW h NEA NPP NSSS ABBREVIATIONS advanced gas cooled reactor boiling water reactor capacity factor data insufficient energy availability factor The electrical equivalent of heat electricity generated energy unavailability factor Fastbreeder reactor Forced loss rate Gigacalorie Gas cooled reactor Gigawatt Gigawatt hour high temperature gas cooled graphite moderated reactor heavy water moderated gas cooled reactor load factor load factor including heat Long term
98. ince been extended by the World Intellectual Property Organization Geneva to include electronic and virtual intellectual property Permission to use whole or parts of texts contained in IAEA publications in printed or electronic form must be obtained and is usually subject to royalty agreements Proposals for non commercial reproductions and translations are welcomed and considered on a case by case basis COPYRIGHT NOTICE Enquiries should be addressed to the IAEA Publishing Section at Marketing and Sales Unit Publishing Section International Atomic Energy Agency Vienna International Centre PO Box 100 1400 Vienna Austria fax 43 1 2600 29302 tel 4 43 1 2600 22417 email sales publications iaea org http www iaea org books For further information on this publication please contact Nuclear Power Engineering Section International Atomic Energy Agency Vienna International Centre PO Box 100 1400 Vienna Austria Email Official Mail iaea org PRIS STATISTICS POWER REACTOR INFORMATION SYSTEM STATISTICAL REPORTS USER S MANUAL IAEA VIENNA 2013 IAEA CMS 22 IAEA 2013 Printed by the IAEA in Austria March 2013 FOREWORD The IAEA developed the Power Reactor Information System PRIS Statistics application to assist PRIS end users with generating statistical reports from PRIS data Statistical reports provide an overview of the status specification and performance results of every nuclear power reactor in t
99. inimum per reactor year and standard deviation per reactor year for both duration hours and energy losses GWh The required criterion is a chosen year or year range The earliest year to query is 2004 as for the previous years the outage records are not combined by logical links Using the report for years before 2004 might lead to incorrect calculation of outage frequencies The report can be summarized by the categories of standard reports country site etc and by outage codes While summaries by standard categories such as country are disjunctive summaries by outage codes are not In other words a reactor can have outages of several types in any reporting period and can appear in several subgroups This has a major impact on how reactor years are calculated on the summary level The Show Reactor Details option provides reactor level performance outage statistics in addition to summary level results Condition 68 The report deals with combined outages where more outage records fragments belonging to the same event are combined by logic links into one outage Combined outages are considered if at least one outage fragment starts in the reporting period Fragments linked to combined outages contribute to the outage count number of outages as one outage For the calculation of duration and energy loss statistics only those fragments of a combined outage that start and end within the reporting period are considere
100. its permanent shutdown excluding periods of long term shutdown 22 Lifetime Electricity Supplied Reactor Group All Reactors Filters Base Year 2010 Show Reactor Details Yes No of reactors Annual Total energy lifetime supplied energy GWh TWh TOTALS 441 2628928 34 61303 53 Annual 2 Lifetime 2 More ISO Unit 2 Model Operator Reactor Const Grid 2 Commercial RUP electricity electricity Details Code Supplier Date Date Date MWe supplied supplied GWh AM ARMENIA 2 PWR VVER V 270 FAEA 1975 07 01 1980 01 05 1980 05 03 375 2286 54 5339 0 58 1 PHWR PHWRKWU NASA SEMENS 1968 06 01 1974 03 19 1974 06 24 335 2782 75 75 14 B D S AR EMBALSE PHWR CANDU 6 NASA AECL 1974 04 01 1983 04 25 1984 01 20 600 3908 69 121 18 0 5 BE DOEL 1 PWR WE 2 loops ELECTRAB ACECOWEN 1969 07 01 1974 08 28 1975 02 15 433 3401 38 106 83 B 0 8 DOEL 2 PWR WE 2 loops ELECTRAB ACECOWEN 1971 09 01 1975 08 21 1975 12 01 433 3411 40 10226 B D S RUE Aa EF SER an FIG 4 6 Example of the Lifetime Electricity Supplied Report Concept The report has only one mandatory parameter the base year for which the report is generated The report can be generated for the current year and for historical years By default the current year is selected Up to three levels of grouping Region Climatic Zone Cou
101. l E America Nontem CANADA BRUCE S PMWR B17 Operational Arnenca Northen CANADA BRUCE 6 PHWR B17 Operational Amenca Notem CANADA BRUCE 7 817 Operational 13 The system allows to select one group as a default group The default group is the preselected choice in report interface setting To assign the group as a default check the Default Group box The system allows using the selected reactor group without its saving When the list of reactors is agreed it is possible to go directly to standard or advanced reports and generate them for the unsaved group 5 Ifthe grouping saved successfully it will receive a checkmark If no checkmark is received more information is needed for the grouping meee STATISTICS REACTOR GROUPS STANDARD REPORTS ADVANCED REPORTS 9 Reactor Group information saved successfully 6 Go back to Reactor Groups to view the new group created For each group there are two reports available Reactor locations shows all reactors from the group on a map View Reactors provides sorting ability for the lists of reactors from the group including icons for dashboard for operational reactors only basic information design characteristics and schematics Using Reactor Groups is essential for plant performance analyses and benchmarking Selection of relevant reactors into a group assures that reports compare pertinent information 14 4 STANDARD RE
102. l Reactors Filters Year From 2006 To 2011 Show Reactor Details No Totals Number of reactors and net electrical capacity Summaries Type v 5 E e 5 i Number and net capacity MW of reactors operated in a year r 2006 2007 r 2008 r 2009 r 2010 id 2011 TOTALS 443 371816 439 371645 439 371903 440 373211 442 375397 448 378919 BWR 93 83855 94 84959 94 84833 94 84869 92 84062 92 83502 2 690 2 690 2 690 2 690 2 690 2 580 GCR 22 10639 18 9034 18 8909 18 8949 18 8949 18 8949 LWGR 16 11404 16 11404 16 11404 16 11404 15 10219 15 10219 PHWR 42 21531 44 22384 44 22441 45 22638 46 22840 47 23160 PWR 268 243697 265 243174 265 243626 265 244661 269 248637 274 252509 FIG 4 10 Example of the Operated Reactor Trend Report Concept report contains all reactors that were operated for at least one day in one of the years of the reporting period report be generated for historical periods up to and including the current year default the report is generated for the current year Ifthe user only enters a from year and leaves the year of the reporting period blank the report is generated for one year 1 e the from year 29 Up to three levels of grouping Region Climatic Zone Country Location Site Type and Age may be applied to the result set A reactor can only appear in exactly one group in the result set The user has the choice o
103. l hours this applies to scram rate factors When operating time of individual reactors is different the time in operation is an additional weight in the PRIS weighted average Calculation of the median centred value is done on individual PI results using a standard statistical function The quartile is also calculated using individual PI results Contrary to the median there are different methods for quartile calculation In PRIS the Minitab method is used The same method is used by WANO MS Excel on the other hand uses a Freund and Perles method This can cause minor differences when the best quartile is recalculated for exportation to Excel Maximum and minimum values are simply selections from individual PI results 1 3 REACTOR GROUPS Managing reactor groups allows users to build groups of reactors which suit reporting needs The system allows a user to create an unlimited number of predefined groups which are assigned only to the user who created the group When a group is created it can be used for any report in the system For instance to group all reactors that are in a specific country or all reactors with the same design characteristics the following will aid in creation of these groupings 1 Select Reactor Groups REACTOR GROUPS STANDARD REPORTS ADVANCED REPORTS MAP Standard Repo Specification Data Status Reports gf History Stet Operational Data Prod
104. l models of the same reactor type usually have the same basic design characteristics moderator and coolant type and form reactor status One of power reactor stages during its lifecycle Planned Under construction In operational In long term shutdown Permanently shut down reactor type Classification of power reactors by coolant and moderator material reactor year A reactor year is the equivalent of 12 months when the reactor is in commercial operation 89 reference energy generation REG Reference energy generation MWh or GWh for the period is the net electricity output that would be produced if a reactor unit is operated at its rated power output for the entire period reference unit power RUP The reference unit power expressed in units of megawatt electrical is the maximum electrical power that could be maintained continuously throughout a prolonged period of operation under reference ambient conditions The power value is measured at the unit outlet terminals i e after deducting the power taken by unit auxiliaries and the losses in the transformers that are considered integral parts of the unit The reference unit power is expected to remain constant unless following design changes or a new permanent authorization the management decides to amend the original value scram The reactor scram is defined as a reactor emergency shutdown achieved by rapid insertion of negative reactivity into the reactor core wh
105. l reactors that are currently in under construction status any year in the past the report includes reactors in status under construction operational long term shutdown and permanent shutdown for which construction started in or before the reporting year and were not yet connected to the grid in the reporting year Net electrical capacity MW is the design net electrical capacity from the Reactor table or if unavailable the latest net electrical capacity from the Reactor table Data Selection data for this report is selected from the Reactor table 4 3 14 Operational Reactors Table 14 This report lists all reactors that are in operation in the reporting year with basic design information as well as performance indicators EAF UCF for the past decade 42 Reactors operation Latest in 2010 Country Reactor Type Model Capacity MW Operator NSSS Const Grid Comm EAF UCF Code Name Thermal Gross Net Supplier Start Connectio Operation 2000 2010 2000 2010 n ARGENTINA AR 1 ATUCHA 1 PHWR PHWRKWU 1179 357 335 NASA SIEMENS 1968 6 1974 3 1974 6 727 739 ARGENTINA AR 2 EMBALSE PHWR CANDU 6 2015 648 600 NASA AECL 1974 4 1983 4 1984 1 86 7 871 ARMENIA AM 19 ARMENIA 2 PWR VVER V 270 1375 408 375 ANPPJSC FAEA 1975 7 1980 1 1980 5 65 67 BELGIUM 2 DOEL 1 PWR WE 2 loops 1311 454 433 ELECTRAB ACECOWEN 1969 7 1974 8 1975 2 85 2 86 1 BELGIUM 4 DOEL 2 PWR WE 2 loops 1311 454 433 ELE
106. l times one per year of the reporting period Parentheses convention for intervals x y is intervals for PI gt x and PI lt y Data Selection Reactor information is from the Reactor table and several reference tables of the PRIS database Country Region Type Site Climatic Zone and Site Location Unlike for the Performance Indicator reports PI values are calculated from the Annual Production data table RUP is the latest net electrical capacity from the Reactor table 5 2 2 Performance Indicators Lifetime Indicators This report generates statistics of reactors lifetime performance indicators up to the end of a given year Lifetime Forced Loss Rate FLR Reactor Group Reactors Filters Lifetime values up to year 2010 Show Reactor Details No Show Operational Reactor Yes Summaries Climatic Zone Type Weighted Median Best Minimum Standard No of Average Quartile Deviation Reactors TOTALS 6 48 4 75 2 29 63 03 7 09 440 Mild Temperate zone 6 43 4 68 2 25 63 03 6 80 416 Sub Arctic zone 3 04 2 56 1 11 3 34 1 01 8 Subtropical zone 14 70 12 02 6 41 47 05 11 47 14 Tropical zone 5 53 5 42 4 51 6 33 1 29 2 FIG 5 4 Example of the Lifetime PI Report Concept 64 The report provides aggregated summaries of a selected lifetime of performance indicators The report provides several statistical values weighted average median best quartile minimum standard deviation and number of reactors for t
107. ly on production data 4 3 5 History of Operating Reactors Table 5 This report displays the number of operating reactor units and their net electrical capacity per country for the past 30 years It provides a snapshot view of reactor count and capacity in five year intervals in addition to data for the reporting year and the previous year 35 Operating Reactors and Net Electrical Power 1980 to 2010 Number of Units and Net Capacity MW e Connected to the Grid Latest in each year Country 1980 1985 1990 1995 2000 2005 2009 2010 No MW e No MWe No MW e No MWe No MW e No MW e No MW e No MWe ARGENTINA 1 335 2 935 r 935 2 935 2 978 2 935 2 935 2 935 ARMENIA 2 816 2 816 1 376 1 376 1 376 1 375 1 375 BELGIUM 4 1670 8 5464 7 5501 7 5631 T 5712 x 5801 x 5902 rf 5926 BRAZIL 1 626 1 626 1 626 2 1976 2 1901 2 1884 2 1884 BULGARIA 3 1224 4 1632 5 2585 6 3538 6 3760 4 2722 2 1906 2 1906 CANADA 10 5172 16 9741 20 13993 21 14902 14 9998 18 12584 18 12569 18 12569 CHINA 3 2188 3 2188 9 6587 11 8438 13 10058 CZECH REP 1 391 4 1632 4 1782 5 2611 6 3373 6 3678 6 3678 FINLAND 4 2208 4 2300 4 2310 4 2310 4 2656 4 2676 4 2696 4 2716 FRANCE 22 14388 43 37478 56 55808 56 58573 59 63080 59 63260 59 63260 58 63130 GERMANY 19 10323 24 18110 21 21250 19 20972 19 21283 17 20339 17 20480 17 20490 HUNGARY 2 825 4 1710 4 1729 4 1729 4 1755 4 1889 4 1889 INDIA 4 832 6 1143 7 1324 10 1746 14 2508 15 2993 18 3987 19 4189 ITALY 4 1112 3 1273 JAPA
108. missioning strategy The report has no mandatory parameters It reflects the latest information available If it is generated without reactor details the report shows a simple bar chart with the number of reactors for each decommissioning strategy If it is generated with reactor details the report lists the reactors concerned by each decommissioning strategy with their country name and permanent shutdown date Condition The report includes reactors that are in permanent shutdown status and includes decommissioning information that has been entered If no decommissioning strategy has been specified for a reactor the reactor is not considered by the report Only one decommissioning strategy can be assigned to any given reactor Data Selection 60 Reactor detail information is selected from the Reactor and Country tables of the PRIS database Decommissioning details are selected from the Reactor Decom and Decom Strategy tables 5 ADVANCED REPORTS Advanced reports allow the extraction of customized data sets and more specific information to support plant performance analyses The reports are divided into three sections Specification data Operational data Non electrical application data WEDAS Account Settings Forum Tutorial REACTOR GROUPS STANDARD REPORTS ADVANCED REPORTS MAP ou are in STATISTICS ADVANCED REPORTS dvanced Reports Specification Data 7 Specification Reports Select
109. n long term shutdown or in permanent shutdown The reactor unit is connected to the grid before or during the reporting year The reactor is not permanently shutdown in the reporting year The reactor is in long term shutdown by December of the reporting year e Permanent shutdown Data Selection The reactor is now in operational long term shutdown or permanent shutdown status The reactor is shutdown before or during the reporting year The reactor unit is connected to the grid before or during the reporting year dates used to determine the historical status of a reactor in the reporting year are selected from the Reactor and Long term Shutdown Details tables Reactor type information description is selected from the Type table 4 3 24 Operator Summary Table 24 For each reactor operator this report provides the number of reactors under construction in operation in long term shutdown and in permanent shutdown at the end of the reporting year 53 Operators Abbreviations and Summaries Latest in 2010 Operator Code Fut Name Under construction Operational Long term shutdown Shutdown AECINPPO Atomic Energy Commission and Nebraska 0 0 0 1 Public Power District AEP American Power Company inc 0 2 0 0 AmeceniUt AMEREN UE Union Company 0 1 0 9 ASOCIACION NUCLEAR ASCO 0 3 0 0 VANDELLOS ALE ENDESA ID ANPPJSC Joint Stock Company Armenian NPP 0 1 0 1 APS ARIZONA PUBLIC SERVIC
110. nagemt phase licensee terminated ARMENIA 1 AM 18 ARMENIA 1 1989 2 Others Other ANPPJSC BELGIUM 1 BE 1 BR 3 1987 6 25 Imdte dism 49 4 CEN SCK BULGARIA 4 BG 1 KOZLODUY 1 2002 12 7 Others Dd PD SE 67 3 6 7 E 03492 2036 BG 2 KOZLODUY 2 2002 12 T Others Dd PD SE 6 7 3 6 7 03493 2036 BG 3 KOZLODUY 3 2006 12 7 Others Dd PD SE 2 6 7 00174 2036 BG 4 KOZLODUY 4 2006 12 T Others Dd PD SE 27 0008 2036 CANADA 3 CA 1 ROLPHTON NPD 1987 8 2 Dd PD SE 8 AECL 2 DOUGLAS POINT 1984 5 2 Dd SE 8 7 AECL 3 GENTILLY 1 1977 6 2 Dd PD SE 8 7 AECL FRANCE 10 FR 10 PHENIX 2010 2 Others Imdte dism gt FR 2 CHINON A1 1973 4 12 Imdte dism EDF FR 24 SUPER PHENIX 1998 12 Others Imdte dism 6 36 NERSA FR 3 CHINON A2 1985 6 12 Imdte dism EDF 2025 FR 4 CHINON A3 1990 6 12 Imdte dism EDF FR 5 CHOOZ A ARDENNES 1991 10 Others Imdte dism 49 SENA 2019 FR 6 EL 4 MONTS D ARREE 1985 7 12 Imdte dism 9 EDF 2015 FR 7 ST LAURENT A1 1990 4 12 Imdte dism EDF 2027 FR 8 ST LAURENT A2 1992 5 12 Imdte dism EDF 2025 FR 9 BUGEY 1 1994 5 1 2 Imdte dism 9 EDF 2020 GERMANY 11 DE 10 STADE KKS 2003 11 2 Imdte dism 346 E ON 2014 DE 3 ee eae KRB 1977 1 68 Imdte dism KGG DE 4 AVR JUELICH AVR 1988 12 Imdte dism 349 FIG 4 27 Table 17 Report Condition report includes reactor units that have been shutdown or before the reporting year and have decommissioning information published Data Selection
111. nced Reports includes the report options for more detail and specific reports including outage based reports For detailed information on each report go to the 5 Advanced Reports section of the manual provides a tool for visualising where power reactor sites are in the world using Google map features 2 1 Access to the Application To get on line access to PRIS Statistics the Subscription Form http pris iaea org PRIS Downloads PPC INF pdf must be completed and sent to the IAEA through the national authorities of its Member States Government organizations and NPP operators can send the application directly to the IAEA or to the PRIS administrator PrisAdmin iaea org The access authorization is completed by the user receiving an ID and password from the IAEA PRIS Statistics application has four levels of access rights 1 Basic level 2 Non nuclear organization level 3 Nuclear industry level 4 Governmental organizations and NPP owners and operators Statistical reports and details within the reports depend on the assigned level Basic level users can see Standard Reports with aggregated values and without plant specific results Users from non nuclear organizations have all rights at the basic level plus they have Trend Reports available to them Users from nuclear organizations can see plant specific results and have access to Advanced Reports except outage related reports Users from governmental
112. nd energy loss MWh Aggregated summaries contain the number of outages for each group their total duration and their total energy loss The report can only be summarized by outage related criteria outage type Ist 2nd and 3rd character outage cause and outage system The report supports the following optional filters Outage 1st character planned P unplanned U and external X outages e Outage Type 2nd character full F and partial P outages e Outage Type 3rd character deferred shutdown 1 immediate shutdown 2 outage extension 3 manual scram 4 and automatic scram 5 e Outage Cause one several or all outage causes Outage System Component one several or all outage components The View Fragments checkbox allows the user to display the complete structure of combined outages i e all fragments The report supports two outage selection mode e Outage related to the reporting period includes combined outages that may have started before the reporting period but continued into the reporting period e Outage starting in the reporting period The Show outage details checkbox allows the user to display individual outage records If this checkbox is unchecked only summary level information and report level totals are displayed Condition The report cannot be generated for reactor groups containing less than three reactors or reactors from less than two different countries Outage
113. nected from the grid Statistics include sum average per outage maximum per outage minimum outage and standard deviation per outage for both duration hours and energy losses GWh The report can be generated for a historical period up to and including the current year By default the previous year is selected as a reporting period Up to three levels of grouping can be applied to the result set In addition to standard grouping criteria Region Country Type Current Age Year the report support outage related grouping criteria Outage Type Ist 2nd and 3rd character Outage Cause Outage System The Show Reactor Details option provides reactor level performance outage statistics in addition to summary level results Condition This report deals with combined outages where several outage records fragments belonging to the same event are logically linked into a single combined outage For the purposes of the report combined outages are always counted as one outage no matter how many fragments they contain This report only considers full outages that started in the reporting period Combined outages are considered if the start date of the first outage fragment is within the reporting period Duration and energy loss statistics are calculated from the duration and energy loss values of the entire combined outage even if the outage lasted beyond the end of the reporting period For com
114. ntrol U Unplanned outage due to causes under the plant management control X Outage due to causes beyond the plant management control external Code_2 description F Full outage P Partial outage Code_3 description 1 2 3 4 5 Controlled shutdown or load reduction that could be deferred but had to be performed earlier than four weeks after the cause occurred or before the next refuelling outage whatever comes first Controlled shutdown or load reduction that had to be performed in the next 24 hours after the cause occurred Extension of planned outage Reactor scram automatic Reactor scram manual 2 Outage direct cause codes A B C D E F G H Plant equipment failure Refuelling without maintenance Inspection maintenance or repair combined with refuelling Inspection maintenance or repair without refuelling Testing of plant systems or components Major back fitting refurbishment or upgrading activities with refuelling Major back fitting refurbishment or upgrading activities without refuelling Nuclear regulatory requirements 2 INTERNATIONAL ATOMIC ENERGY AGENCY International Outage Coding System for Nuclear Power Plants IAEA TECDOC 1393 IAEA Vienna 2004 93 3 94 7 L M N P R S T U Z Grid failure or grid unavailability Load following frequency control reserve shutdown due to reduced energy demand Human fa
115. ntrol reserve shutdown due to reduced energy demands L Human Factor Related M Governmental requirements or court decisions N Environmental Conditions lack of cooling water due to dry conditions cooling water temperature limits P Fire R External restrictions on supply and services lack of funds due to delayed payments from customers S Fuel management limitation including high flux tilt stretch out or coast down operation Heat supply on site to support next unit or desalination and off site distribution U Security and access control and other preventative shutdown due to external threads Z Other System Component code there is a comprehensive list of components to choose from see Ref 2 report supports two outage selection modes Outages related to the reporting period includes combined outages that may have started before the reporting period but continued into the reporting period Outages starting in the reporting period The Show outage details checkbox allows the user to display individual outage records If this checkbox is unchecked only summary level information and report level totals are displayed Condition For All outages related to the reporting period the report considers all combined and non combined outages for at least one fragment start in the reporting period Duration and energy loss is calculated from only those fragmen
116. ntry Location Site Type and Age can be applied to the result set A reactor can only appear in one group of the result set The Show Reactor Details option returns specification data about individual reactors in addition to summary level results Detailed information about each reactor includes basic design information e g type model RUP etc as well as links to the Basic Information Design Characteristics and Schematics reports Condition For each reactor as well as for group and report level totals the report calculates the amount of electricity supplied in the reporting year annual electricity supplied For each reactor included in the report as well as for group and report level totals the report calculates the total amount of electricity supplied during the reactor s lifetime up to the end of the reporting year lifetime electricity supplied If data collection for the reporting year is incomplete DI data insufficient is displayed instead of the annual electricity production value The rule applied to determine whether data is sufficient is the 50 criterion Data is considered sufficient if there are monthly production records for at least half of the months during which a reactor was operational during the reporting year RUP for individual reactor units is the RUP at the end of the base year Data Selection Lifetime and annual electricity supplied are selected from th
117. o be calculated Up to three levels of grouping Region Climatic Zone Country Location Site Type Year and Age can be applied to the result set The Show Reactor Details option provides reactor level performance indicator values in addition to summary level results Reactor level details are the name and type of the reactor unit its RUP as well as the PI value for the year reporting period Condition Histogram intervals are adjustable in the report Intervals are defined by interval width initial value and end value 1 e 10 intervals from 10 to 90 The total number of intervals in the report is limited to 20 Performance indicators are calculated using the same formulae as in the PI report In contrast to the general Performance Indicator report however PI values are calculated from a reactor s grid connection date and include trial operation Also the 15 day borderline condition does not apply report does not check for data completeness If annual production data for a reactor is available it is used to calculate the PI value without considering if the data is complete 63 When grouping by age or year a given reactor can appear in several groups of the result set The performance indicator values on the reactor level are to be interpreted as value for the year rather than for the whole reporting period This also changes the meaning of report level totals as a single reactor is counted severa
118. o be used for calculation weighted average median best quartile Up to three levels of grouping Region Climatic Zone Country Location Site Type and Age can be applied to the result set When grouping by age is selected a given reactor will appear in different age groups for each reporting year The Show Reactor Details option provides reactor level performance indicator values in addition to summary level results Condition 28 A maximum of 20 years can be specified for the reporting period Performance indicator values are calculated in the same manner as for the corresponding Performance Indicator report Only reactors with at least 50 data completeness are taken into account The number of reactors in the PI Trend report is akin to the number of qualified reactors in the PI report This number be lower than the number of reactors that were operational during a reporting year Grouping by age refers to a reactor s age at the end of each reporting year Data Selection Refer to the Performance Indicator report for more information about data selection 4 2 6 Trends Operated Reactors This report illustrates the number of operated reactors and or their total net electrical capacity over a selected period In contrast to the Year end Reactor Status Trends report the Operated Reactors report considers all reactors that were operational for at least one day during a reporting year Reactor Group Al
119. o reported in the outage records using an outage coding system Available energy that is not supplied to the grid due to grid limitation is not reported in the monthly records but recorded in the outage records Reference Energy Generation Unavailable Energy Under plant management control Capability Planned Unplanned losses FIG 1 2 Availability data model Each Member State with nuclear power plants is responsible for submitting authorized data into PRIS using WEDAS There is one PRIS Liaison Officer for each country Each NPP operating utility can nominate one data provider who 18 responsible for reporting the plant specific data The Liaison Officer supervises the data inputs within the country In addition there are many accuracy checks within WEDAS that verify the accuracy of the data provided by the Nuclear Power Plants 1 4 PRIS Outputs PRIS allows the user to have access to statistical reports and gives the user the ability to analyse data using all nuclear reactor units in the world whether they are under construction operational or have been permanently shut down The most called upon data includes Reactor status overview Reactor status changes Historical development of nuclear power Nuclear Power Plant analyses using well defined and internationally accepted performance indicators ndustrial standards quartiles median average Trend analy
120. ode Country Under construction Operational Long term shutdown Shutdown AM ARMENIA 0 1 0 1 AR ARGENTINA 1 2 0 0 BELGIUM 0 7 0 1 BG BULGARIA 2 2 0 4 BR BRAZIL 1 2 0 0 CANADA 0 18 4 3 SWITZERLAND 0 5 0 1 29 13 0 0 cz CZECH REPUBLIC 0 6 0 0 DE GERMANY 0 17 0 19 ES SPAIN 0 8 0 2 FI FINLAND 1 4 0 0 FR FRANCE 1 58 0 12 GB UNITED KINGDOM 0 19 0 26 HUNGARY 0 4 0 0 IN INDIA 6 19 0 0 IR IRAN ISLAMIC REPUBLIC 1 0 0 0 IT ITALY 0 0 0 4 JP JAPAN 2 54 1 5 KR KOREA REPUBLIC OF 5 21 0 0 KZ KAZAKHSTAN 0 0 0 1 LT LITHUANIA REPUBLIC OF 0 0 0 2 0 2 0 0 NL NETHERLANDS 0 1 0 1 PAKISTAN 1 2 0 0 RO ROMANIA 0 2 0 0 RU RUSSIAN FEDERATION 11 32 0 5 SE SWEDEN 0 10 0 3 Si SLOVENIA 0 1 0 0 FIG 4 32 Table 22 Report Condition When generated for the current year the report counts reactors according to their current status When generated for a year in the past the following rules are applied e Under construction he reactor is currently in any status planned under construction operational long term shutdown or permanent shutdown Construction for the reactor has started before or during the reporting year The reactor unit was not connected to the grid in December of the reporting year Operational reactor is currently in any status planned under construction operational long term shutdown or permanent shutdown The reactor unit is connected to the grid
121. oduces electricity nuclear share Percentage share by country of electricity generation mix for nuclear power The ratio of the nuclear electricity production to the total electricity production from all sources in a country nuclear steam supply system NSSS The NSSS consists of a nuclear reactor and all of the components necessary to produce high pressure steam which is used to turn the turbine for the electrical generator on line hours Total clock hours in the reporting period during which the unit was operated with at least one main generator connected to the grid operational reactor In PRIS a reactor is considered as operational or operation from its first grid connection to permanent shutdown During the status long term shutdown a reactor is excluded from operational reactors outage For the purpose of PRIS coding the outage is defined as any status of a reactor unit when its actual output power is lower than the reference unit power for a period of time By this definition the outage includes both power reduction and unit shutdown outage cause In PRIS only direct outage causes are coded The direct cause is defined as an immediate action or condition that has directly resulted in the outage outage coding system The set of internationally accepted codes used for outage records in PRIS 1 INTERNATIONAL ATOMIC ENERGY AGENCY International Outage Coding System for Nuclear Power Plants IAEA T
122. of the reporting year Net electrical capacity is the reactor unit s capacity in the reporting year calculated from monthly production data Performance indicators are calculated from monthly production data for a selected number of years Only operational excluding long term shutdowns months are considered The 15 day condition for borderline months is applied Data Selection All reactor related columns are selected from the Reactor table except for net electrical capacity Net electrical capacity is selected from Annual Electricity Reconstruction if no value is available the latest net electrical capacity from the Reactor table is used Performance indicator values rely on data in the Monthly Production table 43 4 3 15 Reactors Long Term Shutdown Table 15 This report lists all reactors that are in long term shutdown at the end of the reporting year Long term shutdown reactors Latest in 2010 Country Code CANADA CA 8 CANADA CA 9 CANADA 5 CANADA CA 6 JAPAN JP 31 WORLDWID E Condition This report includes all reactors that are in long term shutdown LTS at the end of the Reactor Name BRUCE 1 BRUCE 2 PICKERING 2 PICKERING 3 MONJU reporting year The report includes reactors in operational long term shutdown and permanent shutdown status LTS date is in or before the reporting year and LTS restart date is not Type PHWR PHWR PHWR PHWR FBR Long term shutdown
123. ommended to select a small reactor group in order to avoid long processing time 24 report provides a one page summary of PRIS information about each reactor the selected group The report is only applicable to operational reactors Condition The report includes all reactors in the selected group that were operational up until the current year The latest available data are used for the dashboard statistics Data Selection Reactor dashboard information is from reactor specification data design characteristics monthly production data outage data and other information extracted from the PRIS database 4 2 4 Performance Indicators The Performance Indicator PI reports series comprises 13 reports Energy Availability Factor EAF Energy Unavailability Factor EUF Planned Unavailability Factor PUF Unplanned Unavailability Factor UUF External Unavailability Factor XUF Unit Capability Factor UCF Unplanned Capability Loss Factor UCL Forced Loss Rate FLR Load Factor LF Operating Factor OF Unplanned Automatic Scram Rate UA7 Unplanned Scram Rate US7 Load Factor including Heat LFH Non electrical applications data For a selected group of reactors the report calculates the relevant performance indicator for a period of one or several consecutive calendar years Detailed definitions of the performance indicators are p
124. onstruction table is used for that purpose For reactors under construction including cancelled and suspended projects design net electrical capacity from the Reactor table is used For reactors in long term shutdown the last net electrical capacity before the shutdown is used for all reporting years For permanently shut down reactors the last net capacity before the shutdown is used as RUP for all reporting years 4 2 Operational Data 4 2 1 Production Data Electricity Supplied This report calculates the total amount of electricity supplied to the grid 1n gigawatt hours by all reactor units that were operational during the reporting period Electricity Supplied 100 X Find Next Select a format Export 2 9 Electricity Supplied Reactor Group All Reactors Filters Year From 2010 2010 Show Reactor Details Yes Summaries Country No of Sum Reactors GWh TOTALS 442 2629946 40 ARGENTINA 2 6691 44 ARMENIA 1 2286 54 BELGIUM 7 45728 49 BRAZIL 2 13898 76 BULGARIA 2 14236 37 CANADA 18 85501 09 CHINA 13 70962 15 FIG 4 5 Example of the Electricity Supplied Report Concept The report provides the sum of electricity supplied net generation for all reactor units that were operational during the reporting period chosen by the user report can be generated for historical periods up to and including the current year By default the report is generated for th
125. organizations and utilities that operate or own NPPs have all reports available to them including maps 2 2 Guidelines on How to Generate Reports Selecting a report in any category brings up to the parametrisation page where the user can define choices filters and parameters REACTOR GROUPS STANDARD REPORTS ADVANCED REPORTS MAP Year end Reactor Status trends eae in Summaries refers to the Current Age of a Reactor Reactor Group All Reactors 2 View Reactors Create New Reactor Group Summaries Region Climatic Zone Country Location Y A Criteria From Year 2012 To Year 2012 Reactor Status Under construction current amp completed projects Under construction incl Cancelled Suspended Operational Long Term Shutdown Permanent Shutdown FIG 2 1 Example of a report interface If necessary additional information or instruction will appear between the title of the report and the parameterisation page The icon W appears at the top left hand corner of the margin It is important that the user read this message as it will give the relevant information before starting the parametrization of the required report In some reports there is a warning message to provide important information before running the report To get more detailed guidelines for the report it is possible to use the function on the top right hand corner of the margin This function provides the entire User
126. pacity is used as RUP For reactors in long term shutdown RUP is the net electrical capacity in the month preceding the long term shutdown For reactors in permanent shutdown RUP is the last known net electrical capacity at the point in time the reactor was shut down Data Selection 16 Reactor detail information is selected from the Reactor table of the PRIS database For reactors that have reached the operational status RUP is selected from monthly production data to reflect RUP revisions The closest available match from the Annual Electricity Reconstruction table is used For planned reactors and reactors under construction including cancelled and suspended projects design net electrical capacity from the Reactor table is used When age is used as a filter or summary criterion it means the age of a reactor at the end of selected year As PRIS does not store historical status information about reactors the status of a reactor in a given year is determined from its current status as well as milestone dates available in the Reactor table 4 1 2 Status Reports Reactor Status Change Report This report provides an overview of reactors status changes during a given year The status changes considered by the report are construction starts grid connections permanent shutdowns long term shutdowns and restarts after a long term shutdown Reactor Status Change Reactor Group All Reactors Filters Year From
127. pectives These analyses can be utilized evaluating the nuclear power competitive advantages compared with other power sources The reporting system PRIS Statistics is a web based oriented on line application which makes PRIS globally available The user friendly interface provides the opportunity to easily generate both global and plant specific reports and graphs on nuclear energy status performance and trends The status and performance reports help nuclear power plants with safety performance analysis and nuclear industry with analysis of global trends and strategic planning 1 2 History of PRIS PRIS was established in 1970 The database was computerized in 1981 with the first reporting system PRIS PC and on line statistical reports generation introduced in 1993 In 2003 the first version of a web based application for statistical outputs was incorporated into the Web based Data Acquisition System WEDAS The first version had basic functions of reactor grouping and included six statistical reports Interest in PRIS outputs has considerably increased in recent years As a result it has become evident that further development of the PRIS Statistics would be necessary to reach the database s full potential Therefore activities to improve the current PRIS Statistics were resumed in 2007 These activities resulted in an enhanced version PRIS Statistics which is now used as the main statistical tool of the PRIS database and a referenc
128. per parameter will be the highest section level To select a summary click on the parameter and on the button If several summaries are selected rank can still be organized by clicking on the e move up or move down buttons Criteria Most of reports are annual reports therefore annual period specification is required When the report reflects the end of a particular year the base year should be specified If the desired report is within a period it should be specified by From To Years The system allows the user to fill only the From Year and leave the Year blank assuming that the report covers for only one year The Show Reactor Details checkbox if available provides the possibility to enable or disable reactor specific data within the summaries breakdown Ifthe box is not checked the report returns the aggregated data in accordance with the summaries chosen without the reactor details The Planned Reactor report does not work with a year range as the report only provides a list of reactors currently registered in PRIS as planned Other filters and selections Other criteria specific to the selected report can be offered Specifically Trends in the Operational Data category offers the possibility to generate a histogram for a chosen performance indicator as shown below EAF as the example with a choice of comparative statistics within a reactor group Median Weighted Average or B
129. r Details Yes Summaries Climatic Zone Outage Cause No of Reactors Reactor No of Frequency per Duration Energy Loss Years Outages reactor year Hours GWh TOTALS 445 1312 49 14108 11 82 6309350 86 2005937 94 Mild Temperate zone 421 1240 49 13331 10 75 5760805 51 1937554 91 Sub Arctic zone 8 24 00 212 8 83 224984 70 14856 35 Outage Cause A 8 24 00 14 0 58 586 10 76 77 180 Code Unit Type Reactor Years No of Frequency per Duration Hours Energy Loss outages reactor year GWh RU BILIBINO 2 LWGR 3 00 4 1 33 219 10 1 24 RU BILIBINO 3 LWGR 3 00 3 0 33 11 00 0 06 RU BILIBINO 4 LWGR 3 00 1 0 33 44 00 0 12 RU KOLA 2 PWR 3 00 3 0 33 210 00 43 36 RU KOLA 3 PWR 3 00 6 2 00 86 00 30 43 RU KOLA 4 PWR 3 00 1 0 33 16 00 1 56 Outage Cause C 8 24 00 24 1 00 38896 30 6185 78 Outage Cause D 8 24 00 12 0 50 4603 00 926 48 Outage Cause E 8 24 00 6 0 25 6347 00 66 34 Outage Cause J 8 24 00 138 5 75 169303 30 7490 67 FIG 5 7 Example of the Operating Period Report 69 Concept 70 The report provides an analysis of combined outages in PRIS Compared to Full Outage Statistics this report also deals with partial outage derates The report may be generated for historical periods up to and including the current year By default the previous year is selected as a reporting period For the time being the earliest year is 2004 for the reporting period This is because outage records are not combined by logical links prior to 2004
130. rbine supplier can be expand by selecting the adjacent symbols for more detailed information 100 X Find Next Selecta format Export a BE 7 DOEL 4 BELGIUM Basic Information Type PWR Pressurized Light Water Moderated and Cooled Reactor Model WE 3 loops Status Operational BSite DOEL Operator ELECTRAB BlOwner EBES Reactor Supplier ACECOWEN Turbine Supplier AA BB AC Capacity Latest Thermal Power 2988 MWth Latest Gross Electrical Power 1090 MWe Original Design Net Electrical Power 1000 MWe Latest Reference Unit Power net 1039 MWe History YYYY MM DD Construction Date 1978 12 01 Criticality Date 1985 03 31 Grid Date 1985 04 08 Commercial Date 1985 07 01 Permanent Shutdown Date FIG 6 3 Reactor selection 83 1 2 3 REFERENCES INTERNATIONAL ATOMIC ENERGY AGENCY The Power Reactor Information System PRIS and its Extension to Non electrical Applications Decommissioning and Delayed Projects Information IAEA Technical Reports Series No 428 IAEA Vienna 2005 INTERNATIONAL ATOMIC ENERGY AGENCY International Outage Coding System for Nuclear Power Plants IAEA TECDOC 1393 IAEA Vienna 2004 INTERNATIONAL ATOMIC ENERGY AGENCY Nuclear Power Plant Design Characteristics IAEA TECDOC 1544 IAEA Vienna 2007 85 GLOSSARY available capacity Maximum net capacity at a given moment at which the reactor unit is able or is authorized to be opera
131. rds is the total energy that was not supplied to the grid due to the outage full outage An outage is considered full when the reactor unit is disconnected from the grid grid connection date The date when the plant is first connected to the electrical grid for the supply of power After this date the plant is considered in operation gross capacity Reference gross electrical power of the plant expressed in MW e The maximum electrical power that could be maintained continuously throughout a prolonged period of operation under reference ambient conditions The gross electrical power is measured at the output terminals of the turbine generator 87 Long term shutdown LTS Reactor is considered in long term shutdown status if it has been shut down for an extended period usually several years without any firm recovery schedule at the beginning but there is the intention of re starting the unit eventually non electrical application NEA Some power reactor units produce a portion of their output energy in the form of heat steam for non electrical applications desalination district heating and industrial heat This energy is also reported into PRIS nuclear power plant NPP A nuclear power plant is a thermal power station in which the heat source is one or more nuclear reactors As in a conventional thermal power station the heat is used to generate steam which drives a steam turbine connected to a generator which pr
132. reactors 5 in the reporting year Net electrical capacity is the net electrical capacity in the month before the long term shutdown date Data Selection Net electrical capacity before the LTS is selected from the Monthly Production table if a Model Capacity MW Thermal Gross CANDU 791 2832 824 CANDU 791 2832 824 CANDU 500A 1744 542 CANDU 500A 1744 542 Not specified 714 280 Total Net Capacity Operator Net 848 BRUCEPOW 848 BRUCEPOW 515 OPG 515 OPG 246 JAEA 2972 MW NSSS Supplier OH AECL OH AECL OH AECL OH AECL FIG 4 25 Table 15 Report record for the month before the LTS is available capacity recorded in the Reactor table is used 4 3 16 Reactors in Permanent Shutdown Table 16 This report lists all reactors that are in permanent shutdown at the end of the reporting year The results are grouped by country 44 Construction start 1971 6 1970 12 1966 9 1967 12 1986 5 Grid connection 1977 1 1976 9 1971 10 1972 5 1995 8 Commercial operation 1977 9 1977 9 1971 12 1972 6 Otherwise the latest net electrical Reactors Permanent Shutdown Latest in 2010 Country Reactor Type Capacity MW Operator NSSS Construction Grid Commercial Shutdown Totals Ref no Unit Thermal Gross Net Supplier start connection operation ARMENIA 1 AM 18 ARMENIA 1 PWR 1375 408 376 ANPPJSC FAEA 1969 7 1976 12 1977 10 1989 2 BELGIUM 1 BE 1 BR 3 PWR 41 12 10 CEN SCK W
133. report reconstructed from historical data or the latest net electrical capacity if the report is generated for the current year Reactors in Long term Shutdown Capacity in the month before the long term shutdown reconstructed from monthly production data The latest net electrical capacity is used if the capacity immediately before the shutdown is not available Data Selection Depending on reactor status RUP is selected from the Annual Electricity Reconstruction Monthly Production or Reactor table see above Energy production and nuclear energy share are calculated from data in the Country Annual table 4 3 2 Operational Reactors by Type Table 2 This report provides an overview of the number of operational reactor units and their total net electrical capacity by country and by reactor type 32 and Net Electrical Power of Reactors connected to the Grid Latest in 2010 Country PWR BWR GCR PHWR LWGR FBR Totals No No No No No No ARGENTINA 2 935 2 935 ARMENIA 1 375 1 375 BELGIUM 7 5926 7 5926 BRAZIL 2 1884 2 1884 BULGARIA 2 1906 2 1906 CANADA 18 12569 18 12569 CHINA 11 8758 2 1300 13 10058 CZECH REP 6 3678 6 3678 FINLAND 2 976 2 1740 4 2716 FRANCE 58 63130 58 63130 GERMANY 11 14033 6 6457 17 20490 HUNGARY 4 1889 4 1889 INDIA 2 300 17 3889 19 4189 JAPAN 24 19284 30 27537 54 46821 KOREA REP 17 15976 4 2722 21 18698 MEXICO 2
134. requency control reserve shutdown due to reduced energy demand Type 2nd Character F All outages related to the reporting period Yes Number of outages Duration Energy Loss Hours MWh TOTALS 2 105 00 59620 00 X External 2 105 00 59620 00 StartDate Cause System Component Operational Description Duration Hours Energy Loss mode MWh 2011 02 25 2 J 42 07 Power operation Decline to cold shutdown reactor 10 00 5628 00 at the request of the Swedish National Grid SVK for the repair of measuring transformers 400kV 2011 02 25 XF J 42 07 Power operation Decline to cold shutdown reactor 40 00 34160 00 at the request of the Swedish National Grid SVK for the repair of measuring transformers 400kV FIG 5 9 Example of the Outage Details Report Concept 74 The report provides access to raw outage data stored in PRIS It is based on combined outages as well as non combined outages As outage data is considered sensitive the data is hidden and presented to the user by stripping off country and reactor information Moreover the report can be only be generated for all reactors or for a reactor group containing at least three reactors from two different countries The report can be generated for historical periods up to and including the current year By default the previous year is selected as a reporting period Individual outage records contain the complete outage code description duration hours a
135. rovided in the PRIS Ref 1 25 Energy Availability Factor Reactor Group PHWR Canada Filters Year From 2010 To 2010 Show Reactor Details Yes Summaries Country Year Type Weighted Median Best Minimum Standard No of Average Quartile Deviation Operated Reactors TOTALS 77 60 78 84 94 01 0 00 23 29 18 CANADA 77 60 78 84 94 01 0 00 23 29 18 2010 77 60 78 84 94 01 0 00 23 29 18 PHWR 77 60 78 84 94 01 0 00 23 29 18 ISO Code Unit Type Model RUP MWe EAF CA BRUCE 3 PHWR CANDU 750A 730 68 44 CA BRUCE 4 PHWR CANDU 750A 730 94 11 CA BRUCE 5 PHWR CANDU 7508 817 93 97 BRUCE 6 PHWR CANDU 7505 817 76 54 BRUCE 7 PHWR CANDU 7505 817 93 68 BRUCE 8 PHWR CANDU 7508 782 98 58 DARLINGTON 1 PHWR CANDU 850 878 94 48 DARLINGTON 2 PHWR CANDU 850 878 81 14 DARLINGTON 3 PHWR CANDU 850 878 97 47 DARLINGTON 4 PHWR CANDU 850 878 73 26 GENTILLY 2 PHWR CANDU 6 635 62 75 CA PICKERING 1 PHWR CANDU 500A 515 52 73 PICKERING4 PHWR CANDU 5004 515 71 13 CA PICKERING S PHWR CANDU 5008 516 83 73 PICKERING 6 PHWR CANDU 5008 516 85 83 PICKERING 7 PHWR CANDU 5008 516 64 78 PICKERINGS PHWR CANDU 5008 516 68 16 POINT PHWR CANDU 6 635 0 00 LEPREAU FIG 4 8 Example of the Performance Indicator Report Concept 26 The report provides performance indicator values as weighted average median best quartile minimum value and standard deviation for a chosen reactor group
136. rovides statistical information about full outages i e outages that have caused a reactor shutdown Unlike the Full Outage Statistics Per Reactor Year this report only considers outages that started in the reporting period For calculating outage duration and energy loss statistics total average max min etc the duration and energy loss of the whole combined outage are taken into account even if the outage ends after the end of the reporting period The report is event based as all statistics are calculated outage 65 Full Outage Statistics Per Outage Reactor Group All Reactors Filters Year From 2010 To 2010 Show Reactor Details Yes Summaries Outage Cause Outage Cause Outage Cause Outage Cause Outage Cause Outage Cause Outage Cause Outage Cause Outage Cause Outage Cause Outage Cause Outage Cause rxXcrommoou No of outages 1068 535 27 TOTALS 35 Sum 559484 71 97019 32 24424 30 345581 76 48085 67 8799 41 7554 00 88 70 5806 43 2855 37 3308 65 1648 54 Duration hours Average 524 181 Max 10968 00 10968 00 1888 00 6322 00 4447 00 6295 00 7008 00 88 70 5318 00 378 15 1175 00 190 35 Std dev 905 589 347 890 735 1207 4569 0 1981 116 393 51 FIG 5 5 Example of Full Outage Statistics Report Concept The report provides an analysis of full outages i e outages when a reactor unit was discon
137. rs or all reactors and for selected summary levels Aggregated statistics include only results from qualified reactors Qualified reactors are those reactors which performance data meets 50 criterion When the number of qualified reactors is less than the number of operated reactors an extra column with number of qualified reactors is shown in PI reports PRISTA reports contain the following statistics Weighted average Median Best quartile Maximum minimum Standard deviation 10 weighted average in PRIS is not calculated from individual PI results but as a group value Raw data from individual reactors are summarized and then the calculating formula is applied For example Load Factor for individual reactor 1 is defined as EG i REG i LF i x 100 Where 1 is electricity generated for the period and 1 is reference energy generated for the period capacity multiplied by hours in the period of an individual i reactor The weighted average in PRIS is calculated as LEG i LE y REGO x 100 When all reactors from reported groups are operated during the entire selected period the PRIS weighted average is equivalent to Weighted average of individual PI results where weight is a reactor capacity this applies to performance indicators where REG is used as a denominator Weighted average of individual PI results where weight is a number of critica
138. ruction suspended construction cancelled plan suspended plan planned Data Selection 62 Basic reactor information is selected from the Reactor table of the PRIS database the Long term Shutdown Details table as well as several reference tables Country Region Type Status Site Climatic Zone Site Location Operator and Contractor Design Characteristics information is selected from the Template Char and Reactor Char tables 5 2 Operational Data 5 2 1 Performance Indicators Histogram This report provides an alternative view on reactor performance indicators by visualising the distribution of performance indicator values across a reactors group in percentage intervals The data is provided as a histogram chart as well as a data table Histogram Energy Availability Factor EAF Reactor Group PHWR Canada Filters Year From 2010 To 2010 Show Reactor Details Yes 5 Number of reactors lt 30 35 401 45 50 55 60 96 65 701 75 801 85 901 gt 95 30 351 40 451 50 551 60 551 70 751 80 851 90 95 PI Interval FIG 5 3 Example of the PI Histogram Report Concept report reflects the number of reactors and sum of RUP at each performance indicator percentage interval has two mandatory parameters The reporting period from year to year The default selection is the previous year The performance indicator EAF LF etc t
139. s Pins display the location of all sites from around the world on a map via Google 1 Using a dropdown menu as shown in Fig 6 1 the user can first filter on the status of reactors to be displayed on the map The map can then be set to display reactors that are classified operational under construction planned long term shutdown permanent shutdown suspended construction or cancelled construction Although the default setting displays only operational reactors the user may also view all statuses at once STATISTICS REACTOR GROUPS STANDARD REPORTS ADVANCED REPORTS MAP You are in STATISTICS MAP Worldwide sites Status Operational Operationa Under Construction Planned Long term Shutdown 5 3 Permanent Shutdown Suspended Constr Cancelled Constr ALL FIG 6 1 Status selection 2 Selecting a site on the map will display site specific information Fig 6 2 including a picture and the type capacity and current status of units within that site STATISTICS REACTOR GROUPS STANDARD REPORTS ADVANCED REPORTS MAP Worldwide sites Suus SEER gt Capacity MWe Current Status 433 Operational 433 Operational 1006 Operational 1039 Operational FIG 6 2 Site selection 82 3 Finally selecting specific reactor will display reactor specific information as seen in Fig 6 3 The criteria highlighted in blue such as the site operator owner reactor supplier and tu
140. ses Process of reactor decommissioning PRIS outputs are available in annual publications on the PRIS public web site and to registered users through on line applications The annual publication Nuclear Power Reactors the World has been published since 1981 and provides an overview of power reactors by country status and history The publication Operating Experience with Nuclear Power Stations in Member States has been published since 1971 and consists of comprehensive information about operational performance for each individual reactor unit Registered users have on line access to PRIS through the web based application PRIS Statistics supporting statistical data reporting The PRIS web site www iaea org pris provides information and statistical reports to the public 2 PRIS STATISTICS APPLICATION The PRIS reporting system called PRIS Statistics or PRISTA is available for registered users on the web address http prisweb 1aea org PRIS Statistics have four main tabs Reactor Grouping allows the user to create and save their own groups of nuclear power reactors based on a preference for data analyses For detailed information on creating reactor groups go to the 3 Reactor Groups section of the manual Standard Reports default includes the report options for general reports For detailed information on each report go to the 4 Standard Reports section of the manual Adva
141. several years and grouping by year the results on the year group level will be equivalent to generating the report separately for each year All numbers and subgroups below the year group only refer to the respective year numbers above the year group level refer to the whole reporting period Outage frequency is the number of outages for a reactor for a given summary group or for all reactors in the report per reactor year Data Selection Outage information is extracted from the outage records table in the PRIS database 5 3 3 Outages Combined Outage Statistics An outage can be entered into PRIS in more than one outage record Outage records that belong to the same outage are called outage fragments Outage fragments of the same outage are combined by links into one logical record Among the reasons for outage fragmenting is monthly reporting different phases of an outage shutting down full outage ramp up unplanned extension of planned outages etc Using combined statistics is critical for the calculation of meaningful statistics like outage frequency This report provides statistics on combined outage statistics In contrast to the full outage statistics this report includes also partial outage records de rates Statistics are calculated per reactor year Combined Outage Statistics Reactor Group All Reactors Filters Year From 2008 To 2010 All outages related to the reporting period Yes Show Reacto
142. system Reactor protection system Process computer Reactor recirculation control BWR None of the above systems Reactor Auxiliary Systems Primary coolant treatment and clean up system Chemical and volume control system Residual heat removal system including heat exchangers Component cooling system 13 05 13 06 13 07 13 08 13 09 13 10 13 11 13 12 13 13 13 99 14 00 14 01 14 02 14 03 14 04 14 05 14 06 14 07 14 08 14 99 15 00 15 01 15 02 15 03 15 04 15 05 15 99 16 00 16 01 16 02 16 03 16 99 17 00 17 01 17 02 17 03 17 04 17 05 17 06 17 07 17 99 Gaseous liquid and solid radwaste treatment systems Nuclear building ventilation and containment inerting system Nuclear equipment venting and drainage system including room floor drainage Borated or refuelling water storage system injection and storage system GCR Sodium heating system FBR Primary pump oil system including RCP or make up pump oil D20 leakage collection and dryer system PHWR Essential auxiliary systems GCR None of the above systems Safety Systems Emergency core cooling systems including accumulators and core spray system High pressure safety injection and emergency poisoning system Auxiliary and emergency feedwater system Containment spray system active Containment pressure suppression system passive Containment isolation system isolation valves doors locks and penetrations Containm
143. t is calculated as a ratio of number of years that NEG data is available to the number of years that a reactor was operational The data completeness indicator helps the user interpret the reliability accuracy of the performance indicator values On the summary and report total levels only reactors where the data completeness is gt 50 are considered qualified reactors The qualified reactors column indicates how many reactors out of the operational reactors were considered for summary totals calculation Data Selection 80 Monthly production data is filtered to only include the months that a reactor is operational i e the period from the reactor s commercial date to its permanent shutdown date excluding periods of long term shutdown Please refer to the performance indicator report for all conditions that apply The 15 day condition is applied to decide whether borderline months i e the months of the commercial date the long term shutdown date the restart date and the permanent shutdown date should be included in the calculation Reactor detail information is selected from the Reactor table RUP is taken from the monthly production tables For historical years without production data RUP is reconstructed by closest available production data or by information in the Reactor table 81 6 MAP BASED REPORTS The mapping feature enables the user to select and obtain information regarding specific sites and reactor
144. t year the report includes all reactors that are in commercial operation in the reporting year according to the following criteria e The reactor is currently in operational long term shutdown or permanent shutdown status e The reactor started commercial operation before or in the reporting year e Ifthe reactor is currently shutdown the year of the shutdown is past the reporting year e The reactor was not in long term shutdown in December of the reporting year Reactors are split into categories following the same criteria as in Table 18 The full outage hours per operating experience year are calculated as the ratio of full outage hours of all reactors in a category to the number of reactors in that category The exact number of months each reactor was operational during the reporting year is not taken into account The report considers all full outages that started in the reporting year Note This may include outages during a reactor s trial period or during a long term shutdown All full outages that coded anything but planned P or unplanned U are considered to be external Data Selection All outage data is selected from the Outages table The outage type code is used for outage breakdown 48 The Annual Electricity Reconstruction and or Reactor tables are used to determine the net electrical capacity of reactors that are used for reactor classification 4 3 20 Direct Causes of Full Outages
145. table RUP is taken from the monthly production tables For historical years without production data RUP is reconstructed by closest available production data or by information in the reactor table 4 2 5 Trends Performance Indicators This report illustrates the historical evolution of performance indicator values over the years Performance indicator values for each year in the reporting period selected by the user are calculated and displayed as a bar chart with the data table 27 Unplanned Capability Loss Factor UCL trends year Reactor Group All Reactors Filters Year From 2008 To 2010 Statistics Weighted Average Show Reactor Details Yes Summaries Location 6 UCL 1 2008 208 2010 Year Number of Reactors amp UCL Weighted Average per year 2008 r 2009 r 2010 TOTALS 439 5 29 438 5 45 441 5 68 Inland near a lake location T3 3 51 73 4 71 72 324 Inland near a river location 179 5 54 178 55 181 5 04 Seacoast location 187 5 03 187 5 73 188 7 38 FIG 4 9 Example of the Performance Indicator Trend Report Concept This report provides the evolution of performance indicator values for a chosen group of reactors The report has three mandatory parameters e The reporting period from year to year period of up to 20 years can be selected The default selection is the previous year The performance indicator EAF LF etc to be calculated The statistical value t
146. ted at a continuous rating under the prevailing conditions assuming unlimited transmission facilities It is a capacity available for the grid commercial operation In PRIS a commercial operation of a reactor is from its Commercial Operation Date A period from the first grid connection to the Commercial Date is called trial operation Performance Indicators in PRIS reports are calculated for commercial operation Electricity production is calculated from the first grid connection commercial operation start The date when the plant is handed over by the contractors to the owner and declared officially in commercial operation construction start date The date when first major placing of concrete usually for the base mat of the reactor building is done From this date the reactor is considered to be under construction electricity supplied Net electrical energy produced during the reference period as measured at the unit outlet terminals i e after deducting the electrical energy taken by unit auxiliaries and the losses in transformers that are considered integral parts of the unit Also called as Net Energy Generated Measured in MW h energy loss EL Energy which could have been produced during the reference period by the unavailable capacity It is categorized into three types PEL planned energy loss UEL unplanned energy loss XEL energy loss due to causes external to the plant Energy loss related to the outage reco
147. truction in the base year no matter whether they were completed or not Optionally an age filter can be applied to reactors in operation in long term shutdown or in permanent shutdown so that only reactors that were of a certain age in the base year are considered Up to three levels of grouping NEA Application Type Region Climatic Zone Country Location Site Type and Age can be applied to the result set A reactor can only appear in exactly one group in the result set The Show Reactor Details option returns specification data about individual reactors in addition to summary level results Detailed information about each reactor includes basic design information e g type model RUP etc as well as information about the NEA types supported by a particular reactor process heating district heating and or desalination 76 Condition For historical years the report reflects reactor status and Reference Unit Power RUP at the end of the base year In the case of the current year the latest situation is reflected Reactors that were in a given status during the year but have changed status before the end of that year are not included in the report For reactors under construction the design net capacity is used as RUP Fora reactor in long term shutdown the RUP is the net capacity when it was shutdown Fora reactor in a status of permanent shutdown the RUP is its latest net capacity when it was sh
148. trued as an endorsement or recommendation on the part of the IAEA CONTENTS INTRODUC EION 5555 ad nda ee eae eens 1 1 1 Power Reactor Information System 5 1 152 History OE PRIS esistente em oaa t Eta CO alts 1 1 3 PRIS Data Model taper dne Mas certe naw De aq 2 1 4 PRIS M 3 PRIS STATISTICS APPLICA TION iiic epa ve edant 5 2 1 Access to the Application teet etna ere Ria eigen e Re tees 5 2 2 Guidelines on How to Generate Reports ssssssssseeeeeeeenneene 5 2 3 Report FunctonDg ses Feo e eei t Ue T e a RAS 9 2 4 General Rules and Methods Used in 10 2 4 1 Criteria for Data Selection for PI Reports sess 10 2 4 2 Methods Used for Group Statistics us oae ducens sees duc eaae 10 REACTOR GROUPS senti op eei ea RA ds 12 SLANDARDPREPOBSS II CI PERI M DE MEIUE 15 4 1 Speciheation Data usos ed ade dte 15 4 1 1 Status Report Year End Reactor Status 15 4 1 2 Status Reports Reactor Status Change 17 4 1 3 Status Report Planned 200 0 18 4 1 4 History Year end Reactor Status
149. ts Detailed information about each reactor includes basic design information e g type model RUP etc as well as links to the Basic Information Design Characteristics and Schematics reports Condition The Reference Unit Power RUP is calculated in the following way 17 e For construction starts and grid connections design net electrical capacity is used If the design capacity is unavailable 0 the latest net electrical capacity from the Reactor table is used e For permanent shutdowns the latest net electrical capacity from the reactor table is used If the latest capacity is unavailable 0 the design net electrical capacity is used e For long term shutdowns and restarts the last known net electrical capacity before the long term shutdown from the Annual Electricity Reconstruction table is used Data Selection Reactor detail information is from the Reactor table of the PRIS database report determines the date of a status change based on Thereactor s current status e The relevant dates in the Reactor table construction date grid date shutdown date e Information on long term shutdowns Long term Shutdown Details table 4 1 3 Status Report Planned Reactors This report lists all reactors that are currently reported as planned for construction Planned Reactors Reactor Group All Reactors Filters Show Reactor Details Yes Summaries Country No of reactors RUP MWe
150. ts that are within the reporting period Fragments linked into a combined outage contribute to the outage number as one outage For Only outages starting in the reporting period only outages that start in the reporting period are considered Combined outages are only considered if the start date of the first fragment is in the reporting period Duration and energy loss is calculated from the values for the entire combined outage even if the outage lasted beyond the reporting period The aggregated number of reactors is the total number of reactors that were operated at least partially in the reporting period A reactor year is the equivalent of 12 months when the reactor is in commercial operation Reactor years are calculated from the number of months each reactor in the report was operational during the reporting period The aggregated number of reactor years is the sum of years during which these reactors where operational in the reporting period The number of reactor years might be different from total number of reactors number of years in the reporting period as certain reactors included in the report may not have been operational during all years included in the reporting period Calculation of reactor years in summaries depends on their exclusivity A summary is exclusive if each reactor belongs to only one summary group such as country reactor type or site If a summary is exclusive the total reactor years is a sum of
151. uction data gf Performance Indicators Sect 0 5 C Trends Set gf Worldwide Statistics C Tables Select Decommissioning Data Trends Decommissioning Reports Select 2 Select Add New Group STANDARD REPORTS ADVANCED REPORTS MAP You are in STATISTICS User Manual Reactor Groups 9 Name Description Reactor View Reactors No of Default Group Group Delete locations Reactors Type ALL PHWR All including India Pakistan gt 25 Dynamic x Bruce B Unit 5 6 7 8 a 1 4 Static x Bruce Power Bruce Power Units 1 2 3 4 5 6 7 8 e gt 8 Dynamic x FUKUSHIMA DAIICHI 2 operational 4 permanent shutdown amp 2 cancelled plan amp 8 Dynamic x North American Operational 122 Static x PHWR Canada Ontario Quebec NB Q m 25 Yes Dynamic x PHWR in Ontario Canada Operational PHWRs in Ontario Canada 18 Static Add New Group 3 Select the required parameters for the desired grouping There are 2 tabs Basic Filters Design Filters for selection criteria Fill in all the information that is required for the grouping For more details about Design Characteristics see Ref 3 12 BEACTOR GROUPS STANDARD REPORTS ADVANCED REPORTS New group Basic Fitters Design Fiters Review amp Save je negat Information So AGESTA BRUCE AKKUYU Joaruncron AKTAU PICKERING ALLENS CREEK Ac Reactor Unit AGESTA e AKADEMIK LOMONOSOV 1 o AKADEMIK LO
152. utdown Data Selection Reactor detail information is from Reactor table of the PRIS database reactors that have reached the operational stage RUP is reconstructed from monthly production data to reflect RUP revisions The closest available match from the Annual Electricity Reconstruction table is used for that purpose For planned reactors and reactors under construction including cancelled and suspended projects design net electrical capacity from the Reactor table is used When age is used as a filter or summary criterion it means the age of a reactor at the end of selected year PRIS does not store historical status information about reactors the status of a reactor in a given year is reconstructed from its current status as well as milestone dates available in the Reactor table NEA Information whether a given reactor produces energy for a specific NEA application type is selected for the NEA unit table 5 4 2 Production Energy Utilized for NEA This report provides detailed information about nuclear energy used for non electrical applications For the reporting year selected it provides the amount of energy utilized for process heating district heating and desalination as well as the electrical equivalent of heat T Energy produced from Non Electrical Applications Reactor Group All Reactors Filters Base Year 2010 Show Reactor Details Yes NEA Application type Process Heating
153. w of reactors with Non Electrical Applications Operational reactors Reactor Group All Reactors Filters Base Year 2011 Show Reactor Details Yes Summaries Country NEA Application Type Number of Reactors RUP MWe with NEA TOTALS 75 52387 BULGARIA 2 1906 CZECH REPUBLIC 2 1926 HUNGARY 3 1419 INDIA 6 1091 JAPAN 9 8076 PAKISTAN 1 125 ROMANIA 2 1300 RUSSIA 30 20793 District Heating 29 19843 Process Heating 26 20749 SLOVAKIA 2 944 SWITZERLAND 3 1700 UKRAINE 15 13107 FIG 5 10 Example of the Non Electrical Application Report Concept The report has the same concept as the Year end Status report However it only includes reactors that have non electrical applications The report has two mandatory parameters the base year for which the report shall be generated and one or more reactor status to be considered The report can be generated for the current year and for historical years By default the current year is chosen as a base year user must select at least one reactor status to be included in the report By default the status operational is selected For reactors under construction there two options e Under construction current amp completed projects includes all reactors that were under construction in the base year excluding projects that were eventually suspended or cancelled e Under construction incl Cancelled Suspended includes all projects that were under cons
154. xcluding periods of long term shutdown 31 The nuclear energy share is calculated as a percentage of nuclear energy production total production and is based on country annual data Reactor data is calculated as follows depending on a reactor s status Reactors under Construction When generated for the current year the report considers only reactors that are currently under construction When generated for a past year the report determines whether a reactor was under construction in the reporting year by considering its current status construction date and grid date Note The report does not consider reactors in current status cancelled construction or suspended construction even if they might have been under construction in the reporting year Operational Reactors When generated for the current year the report considers only reactors that are currently operational When generated for a year in the past the report considers reactors that have been operational at the end of the reporting year Reactors in Long term Shutdown A reactor is considered to be in long term shutdown if the long term shutdown started before December of the reporting year and did not end before January of the following year Net electrical capacity is calculated as follows for different reactor status Reactors under Construction The design net electrical capacity is used Operational Reactors Capacity in the year of the

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