机组断然处置措施课件.ppt

1、台電公司核能電廠因應福島事故台電公司核能電廠因應福島事故之斷然處置措施說明與介紹之斷然處置措施說明與介紹王琅琛王琅琛20132013年年1 1月月2323日日2簡報內容簡報內容一一.前言前言二二.緣起緣起三三.斷然處置措施斷然處置措施四四.分析結果分析結果五五.結論結論23一一.前言前言1.1.9/9 9/9 台電首次於大型國際會議台電首次於大型國際會議(NUTHOS-9)(NUTHOS-9)發表斷然發表斷然處置措施處置措施2.2.9/199/19兩岸交流研討會兩岸交流研討會台電公司向大陸介紹斷然台電公司向大陸介紹斷然處置措施處置措施3.3.大陸學者李冠興院士認為台電斷然處置措施實際上大陸學者

2、李冠興院士認為台電斷然處置措施實際上是一套保證及時注水的決策程序，值得研究學習。是一套保證及時注水的決策程序，值得研究學習。大陸大陸核安全與放射性汙染防治核安全與放射性汙染防治“十二五十二五”規劃及規劃及20202020年遠景目標年遠景目標將斷然處置納入研究建立目標將斷然處置納入研究建立目標4.4.台電斷然處置措施已發表於國際期刊台電斷然處置措施已發表於國際期刊Nuclear Nuclear Engineering and Design 253(2012)259-268Engineering and Design 253(2012)259-26835678二二.緣起緣起 u福島事故福島事故-加

3、長型的電廠全黑事故加長型的電廠全黑事故長時間喪失長時間喪失ECCSECCS設計資源設計資源運轉參數已不可信運轉參數已不可信僅剩非正常爐心注水系統僅剩非正常爐心注水系統(特性特性-注水壓低注水壓低)移動式電源移動式電源/消防車消防車廠用水廠用水/生水生水/海水海水89Key lesson learned3/11 2:46 PMEarthquake Happened(loss of offsite power,start IC/RCIC)3/11 3:3841 PMTsunami attack(loss of AC/DC power)After 3 or 4 daysRCIC/HPCI faile

4、dDelayed venting,depressurizationFinallyCore DegradationHydrogen Explosion To avoid core damage:Short term:Reactor water makeup by non-AC power(IC/RCIC/HPCI)10Key lesson learned3/11 2:46 PMEarthquake Happened(loss of offsite power,start IC/RCIC)3/11 3:3841 PMTsunami attack(loss of AC/DC power)After

5、3 or 4 daysRCIC/HPCI failedDelayed venting,depressurizationFinallyCore DegradationHydrogen Explosion To avoid core damage:Short term:Reactor water makeup by non-AC power(IC/RCIC/HPCI)Require workable/effective SAM11Workable SAMG(severe accident management guideline)3/11 2:46 PMEarthquake Happened(lo

6、ss of offsite power,start IC/RCIC)3/11 3:3841 PMTsunami attack(loss of AC/DC power)After 3 or 4 daysRCIC/HPCI failedDelayed venting,depressurizationFinallyCore DegradationHydrogen Explosion To avoid core damage:Short term:Reactor water makeup by non-AC power(IC/RCIC/HPCI)Require workable/effective S

7、AMWhile trying to restore AC/DC power&heat sink,Also:Depressurize by SRV Activate low pressure injection system Containment venting(avoid over-pressure failure)12Require workable/effective SAMWhile trying to restore AC/DC power&heat sink,Also:Depressurize by SRV Activate low pressure injection syste

8、m Containment venting(avoid over-pressure failure)Our DIVing procedure:l Lineup within 1 hourl Start DIVing:Depressurize by SRV Activate low pressure injection system Containment venting(keep containment in a low pressure)131415三三.斷然處置措施斷然處置措施u“Ultimate Response Guidelines(URG)”.u正常正常設計設計爐心注水系統功能恢復前

9、之應變措施爐心注水系統功能恢復前之應變措施u機組斷然處置措施機組斷然處置措施-DIVing procedure:D:Depressurization緊急洩壓緊急洩壓I:Cooling Water Injection灌灌水水V:Containment Venting圍阻體通氣圍阻體通氣ing:Simultaneously同時進行同時進行15機組斷然處置措施(各廠已建立程序書並完成演練)1616Assumptions for Analysis0秒 發生地震發生地震 喪失廠外電源，RCIC啟動10分 海嘯進來海嘯進來 電廠全黑，控制性降壓開始1小時 RCIC假設失效(Start DIVing)啟動啟

10、動緊急洩壓，洩壓至低壓水可注入之壓力後，開始注水數小時後 持續操作持續操作EOP，維持釋壓閥開啟以利持續注水(使PCT維持低溫)1718uDIVingDIVing高壓轉低壓高壓轉低壓(HI(HI TO TO LO)LO)過程過程 燃料尖峰護套溫度燃料尖峰護套溫度 1500 1500 F F無爐心熔毀無爐心熔毀無氫氣產生無氫氣產生無須進行疏散無須進行疏散u維持電廠完整性確保大眾安全維持電廠完整性確保大眾安全成功準則成功準則181919四四.分析結果分析結果(核一廠核一廠)19壓力與注水流量變化圖(C)0123Time(hr)020040060080010001200Pressure(psia)C

11、ontrolledDe-press.DIVing StartADS De-press.Raw Water800 GPMRaw Water250 GPM0123Time(hr)020040060080010001200Flow Rate(gpm)20壓力與水位變化圖(C)0123Time(hr)020040060080010001200Pressure(psia)ControlledDe-press.DIVing StartADS De-press.Raw Water800 GPMRaw Water250 GPMTAFBAF0123-200-1000100200300Level(in)21水位與

12、PCT變化圖(C)0123Time(hr)040080012001600Cladding Temperature(F)1500FDIVing StartADS De-press.Raw Water800 GPMRaw Water250 GPMRCIC 0123-200-1000100200300Level(in)TAFBAF22PCT vs.Raw Water Flow300350400450500Flow(gpm)60080010001200140016001800Cladding Temperature(F)1500 F370 gpmRaw Water FlowPCT()450 gpm80

13、9.20 400 gpm1404.01 350 gpm1550.35 2324 Effect of RCIC Available Time PCT vs.Raw Water Flow200300400500Flow(gpm)40060080010001200140016001800Cladding Temperature(F)1HR4HR8HRRaw Water FlowPCT()4HR 8HR 400 gpm756.909-350 gpm1250.52 587.33300 gpm1566.75 1323.1 250 gpmExceed 1520.4 255 gpm310 gpm370 gpm

14、8 hr4 hr1 hr01234Time(hr)040080012001600Cladding Temperature(F)400gpm200gpm150gpm130gpm100gpm25Diff.Raw Water Flow Rate after PCT vs.PCTChinshan Raw Water Pool Capability:250 gpm1500 F2626四四.分析結果分析結果(核二廠核二廠)26壓力與注水流量變化圖(K)270123Time(hr)020040060080010001200Pressure(psia)ControlledDe-press.DIVing Sta

15、rtADS De-press.Raw Water800 GPMRaw Water350 GPM0123Time(hr)020040060080010001200Flow Rate(gpm)壓力與水位變化圖(K)280123Time(hr)020040060080010001200Pressure(psia)ControlledDe-press.DIVing StartADS De-press.Raw Water800 GPMRaw Water350 GPMTAFBAF0123-200-1000100200300Level(in)水位與PCT變化圖(K)290123Time(hr)0400800

16、12001600Cladding Temperature(F)1500FDIVing StartADS De-press.Raw Water800 GPMRaw Water350 GPMRCIC TAFBAF0123-200-1000100200300Level(in)550600650700750800850Flow(gpm)100012001400160018002000Cladding Temperature(F)PCT vs.Raw Water Flow1500 F645 gpmRaw Water FlowPCT()8001055.297501092.67 7001201.256501

17、466.906001803.02 3031 Effect of RCIC Available Time PCT vs.Raw Water Flow400500600700800900Flow(gpm)600800100012001400160018002000Cladding Temperature(F)1HR4HR8HRRaw Water FlowPCT()4HR 8HR 600920.387 761.9285501356.97-5001760.151322.93450exceed1642.97645 gpm530 gpm475 gpm8 hr4 hr1 hr3232四四.分析結果分析結果(

18、核四廠核四廠)3233Raw Water2400 gpmControlled De-press.DIVing StartADS De-press.Raw Water800 gpm0123Time(hr)06001200180024003000Flow Rate(gpm)025050075010001250Pressure(psia)壓力與注水流量變化圖(L)34壓力與水位變化圖(L)Raw Water2400 gpmRaw Water800 gpmControlled De-press.DIVing StartADS De-press.BAFTAF0123Time(hr)-500-250025

19、0500750Level(cm)025050075010001250Pressure(psia)35水位與PCT變化圖(L)DIVing StartADS De-press.RCICRaw Water2400 gpmRaw Water800 gpm1500FTAFBAF0123Time(hr)-500-2500250500750Level(cm)040080012001600Cladding Temperature(F)36Analysis ConditionRequired MinimumReactor Injection Flow Rate(gpm)Base Case19744 Hours

20、 RCIC Available Time14838 Hours RCIC Available Time1335Raw Water Injection at Reactor Upper Plenum8013737四四.分析結果分析結果(核三廠核三廠)370246810Time after Event(hr)0246810Steam Generator Pressure(MPa)RW Injection Capacity=600 gpmSteam Generator-1Steam Generator-2Steam Generator-3msdiv-rw-5-3-p_SG-3.grf60 psia蒸

21、汽產生器壓力蒸汽產生器壓力3839蒸汽產生器水位蒸汽產生器水位0246810Time after Event(hr)020406080100SG Narrow Range Water Level(%)SG-1 Water Level for RWI Capacity=600 gpmNRWLWRWLmsdiv-rw-5-3-SGWL-1.grfNormal NRWL3940一次側自然循環流量一次側自然循環流量0246810Time after Event(hr)050001000015000Core Inlet Flow(kg/s)RW Injection Capacity=600 gpmCor

22、e Inlet Flowmsdiv-rw-5-3-mf017.grf4.36%of initial flow4041RCP 軸封洩漏分析軸封洩漏分析Emptiness of Accumulator by RCP Seal Leakage 05101520Time after Event(hr)010203040Liquid Volume in Accumulator(m3)RW Injection with Seal LOCALiquid Volume in ACC-1msdiv-rw-7-3a-acvliq-1.grfleak begin4142RCP RCP 軸封洩漏分析軸封洩漏分析Des

23、cending of Reactor Water Level by RCP Seal Leakage 05101520Time after Event(hr)051015Reactor Vessel Water Level(m)RW Injection with Seal LOCAReactor Vessel Water Levelmsdiv-rw-7-3a-cv008.grfTAFBAF4243RCP RCP 軸封洩漏分析軸封洩漏分析Termination of RCS Natural Circulation Flow by RCP Seal Leakage 05101520Time aft

24、er Event(hr)050001000015000Core Inlet Flow(kg/s)RW Injection with Seal LOCACore Inlet Flowmsdiv-rw-7-3a-mf017.grf4344RCP RCP 軸封洩漏分析軸封洩漏分析Effect of Accumulator Isolation on Reactor Water Level Descending 05101520Time after Event(hr)051015Reactor Vessel Water Level(m)RW Injection with Seal LOCAWith AC

25、C InjectionNo ACC Injectionmsdiv-rw-7-3a-cv008-1.grfTAFBAFleak begin4445RCP RCP 軸封洩漏分析軸封洩漏分析Effect of Accumulator Isolation on PCT Ascending 05101520Time after Event(hr)0500100015002000Fuel Cladding Temperature(K)RW Injection with Seal LOCAWith ACC InjectionNo ACC Injectionmsdiv-rw-7-3a-pct16-1.grf1

26、500 oF45五五.結論結論n應付福島此類加長型的電廠全黑事故，應付福島此類加長型的電廠全黑事故，機組斷然處置措施主要操作為機組斷然處置措施主要操作為:(1)啟動啟動DIVing動作之前，爐心或蒸汽產生器動作之前，爐心或蒸汽產生器設法先行適度降壓設法先行適度降壓。(2)啟動啟動DIVing動作時，動作時，緊急緊急洩壓將已列置妥洩壓將已列置妥當之非正常爐心注水當之非正常爐心注水(消防水消防水)迅速灌入爐心迅速灌入爐心或蒸汽產生器同時執行或蒸汽產生器同時執行圍阻體通圍阻體通氣至氣至大氣大氣，避免圍阻體避免圍阻體內內壓過高造成水無法壓過高造成水無法灌入灌入。(3)DIVing動作順利完成後，動作順

27、利完成後，EOP後續之操後續之操作應避免爐心或蒸汽產生器壓力再次上升而作應避免爐心或蒸汽產生器壓力再次上升而阻礙消防水持續灌入。阻礙消防水持續灌入。46五五.結論結論(續續)n台電公司各運轉中台電公司各運轉中核能電廠已依核能電廠已依機組斷機組斷然處置措施之理念，精進現有操作程序然處置措施之理念，精進現有操作程序書及完成人員訓練，並利用夜間實地模擬書及完成人員訓練，並利用夜間實地模擬全黑測試及在多次緊急計畫演習中演練，全黑測試及在多次緊急計畫演習中演練，證實一旦證實一旦核能電廠核能電廠遭遇超過預期的複合式遭遇超過預期的複合式災害，災害，機組斷然處置措施仍然可以確機組斷然處置措施仍然可以確保核能安

28、全，不會讓輻射有外洩的機會。保核能安全，不會讓輻射有外洩的機會。n另因應日本福島事故，台電公司也比照國另因應日本福島事故，台電公司也比照國際作法進行核安總體檢，以深度防禦觀念際作法進行核安總體檢，以深度防禦觀念，執行各項強化措施，提升各電廠的防災，執行各項強化措施，提升各電廠的防災能力。能力。4748Thanks for your attention謝謝注意謝謝注意洩洩注逸洩洩注逸洩洩注溢洩洩注溢48內容(緊急洩壓緊急洩壓)n核一廠4260-3600=660 secondsn核二廠4200-3600=600 secondsn核四廠 4644-3600=1044 seconds4950PCT與注

29、水流量關係圖與注水流量關係圖Base Case:1974 gpm(緊急洩壓開啟緊急洩壓開啟 8 只只 SRVs;生水注入降流區生水注入降流區)SRVx16 Case:1497 gpm(緊急洩壓開啟緊急洩壓開啟 16 只只 SRVs;生水注入降流區生水注入降流區)600800100012001400160018002000220024002600Raw Water Flow(gpm)50080011001400170020002300260029003200Peak Cladding Temperature(F)Base CaseSRVx16 Case1497gpm1974gpm2200F1800F1500F