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EPR缓解SGTR事故的设计特点 被引量:6

Design features for mitigating SGTR of EPR
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摘要 蒸汽发生器传热管破裂(SGTR)事故可能造成安全壳旁通,是一个特殊而重要的设计基准事故。本文归纳了EPR缓解SGTR事故的主要设计特点:(1)中压安注(MHSI)泵关闭扬程低于主蒸汽安全阀(MSSV)开启整定值,避免MSSV开启;(2)大气旁排系统(VDA)通过降低其整定值自动启动部分冷却,使一回路快速冷却、降压;(3)蒸汽发生器排污系统(APG)增加转移管线,有助于以排污和蒸汽排放组合方式最终冷却、降压。这些EPR设计特点可供CPR1000核电厂系统设计改进参考。 Steam generator tube rupture(SGTR) accident may bypass the containment,and is a special and important design basis accident.This paper summarizes the main design features for mitigating SGTR of EPR nuclear power plant:(1) The shutoff head of Medium Head Safety Injection(MHSI) pump is lower than the setpoint of Main Steam Safety Valve(MSSV),which avoid the opening of MSSV;(2) The atmosphere discharge system(VDA) automatically initiates partial cooldown by lowering its setpoint,which cooldown and depressurize the primary side quickly;(3) Two transfer lines between two adjacent steam generators are added in steam generator blowdown system(APG),which facilitate the final cooldown and depressurization by the combination of blowdown and steam dump.These EPR unique design features can provide some reference for CPR1000 nuclear power plant system design modification.
作者 郑华
出处 《核科学与工程》 CSCD 北大核心 2010年第1期15-18,共4页 Nuclear Science and Engineering
关键词 欧洲压水堆 蒸汽发生器传热管破裂 部分冷却 EPR steam generator tube rupture partial cooldown
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参考文献4

  • 1European utility requirements for LWR nuclear power plants[S].2001.
  • 2Guangdong Taishan Nuclear Power Company,Ltd.Taishan Nuclear Power Station Unit 1& 2 Preliminary Safety Analysis Report[R].2008.
  • 3HAF·Y0005.法国900 MWe压水堆核电站系统设计和建造规则(RCC-P)[S].1991.
  • 4Design and construction rules for system design of 900MWe PWR nuclear power plants (RCC-P)[S].1995.

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