严重事故下大功率先进压水堆IVR-ERVC有效性分析
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摘要
通过压力容器外部冷却(ERVC)以实现堆内熔融物滞留(IVR)作为反应堆严重事故缓解管理的一项重要举措一直以来广泛受到关注和研究。本文使用严重事故分析程序MELCOR,从瞬态角度对大型先进压水堆进行了IVR-ERVC相关研究。过程中重点关注了堆芯熔毁和重新定位,熔池形成、生长及其传热过程,并且对压力容器外部流动传热进行了分析。MELCOR计算所得下封头热流密度分布的瞬态结果与临界热流密度(CHF)比较和分析表明,1700 MWe大功率压水堆发生严重事故后在IVRERVC条件下能够保证压力容器的完整性,即,IVR-ERVC能够有效带出下封头熔融物的衰变热量,缓解严重事故后果。
As a key severe accident management strategy for light water reactors(LWRs),in-vessel retention(IVR) through external reactor vessel cooling(ERVC)has been the focus of relevant studies for decades.This paper addressed the IVR-ERVC issues from a transient perspective using the severe accident code MELCOR for largesize advanced passive nuclear power plant.Current analysis was mainly focused on the transients in severe accident including core degradation and relocation,molten pool formation,growth and heat transfer within,together with external flow and heat transfer analysis.MELCOR calculations for lower head heat flux were then compared with critical heat flux(CHF) of lower head to assess the effectiveness of IVR-ERVC.The results suggest that lower head heat flux is well below the CHF value.Thus,the IVR-ERVC strategy is considered to be physically effective.
As a key severe accident management strategy for light water reactors(LWRs),in-vessel retention(IVR) through external reactor vessel cooling(ERVC)has been the focus of relevant studies for decades.This paper addressed the IVR-ERVC issues from a transient perspective using the severe accident code MELCOR for largesize advanced passive nuclear power plant.Current analysis was mainly focused on the transients in severe accident including core degradation and relocation,molten pool formation,growth and heat transfer within,together with external flow and heat transfer analysis.MELCOR calculations for lower head heat flux were then compared with critical heat flux(CHF) of lower head to assess the effectiveness of IVR-ERVC.The results suggest that lower head heat flux is well below the CHF value.Thus,the IVR-ERVC strategy is considered to be physically effective.
引文
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[2]Esmaili.H..Khatib-Rahbar,M..Analysis of likelihood of lower head failure and ex-vessel fuel coolant interaction energetics for AP1000[J].Nuclear Engineering and Design 235,1583-1605,2005
[3]Gauntt,R.O.,et al..MELCOR computer code manuals Vol.1:Primer and Users'Guide[CP].Sandia National Laboratories,Albuquerque,NM 87185-0739,2005.
[4]Gauntt.R.O.,et al..MELCOR computer code manuals Vol.2:Reference Manuals[CP].Sandia National Laboratories,Albuquerque,NM 87185-0739,2005.
[5]Knudson.D.L.,Rempe,J.L.,et al..Late-phase melt conditions affecting the potential for in-vessel retention in high power reactors[J].Nuclear Engineering and Design 230,133-150,2004.
[6]Rempe,J.L.,et al..Potential for AP600 in-vessel retention through ex-vessel flooding[R].1NEEL/EXT-97-00779,2004,1997.
[7]Rempe,J.L.,Suh,K.Y.,Cheung,F.B.,Kim,S.B..InVessel Retention Strategy for High Power Reactors[R].INEEEL/EXT-04-025621,2008.
[8]Theofanous,T.G.,et al..In-vessel coolability and retention of a core melt[R],DOE/ID-10460,Revised October,1996a.
[9]Theofanous,T.G.,et al..The first results from the ACOPO experiment[C].In:Proceedings of the Topical Meeting on Probabilistic Safety Assessment(PSA'96),Park Soty,Utah,,1996b.
[10]Theofanous,T.G.,et al..The first results from the ACOPO experiment[J].Nuclear Engineering and Design 169,49-57.1997.