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Detailed evaluation of coolant injection into the reactor vessel with RCS depressurization for high pressure sequences

机译:使用RCS降压对高压序列向反应堆容器中注入冷却剂的详细评估

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摘要

A coolant injection into the reactor vessel with depressurization of the reactor coolant system (RCS) has been evaluated as part of the evaluation for a strategy of the severe accident management guidance (SAMG). Two high pressure sequences of a small break loss of coolant accident (LOCA) without safety injection (SI) and a total loss of feedwater (LOFW) accident in Optimized Power Reactor (OPR)1000 have been analyzed by using the SCDAP/RELAP5 computer code. The SCDAP/RELAP5 results have shown that only one train operation of a high pressure safety injection at 30,000 s with indirect RCS depressurization by using one condenser dump valve (CDV) at 6 min after implementation of the SAMG prevents reactor vessel failure for the small break LOCA without SI. In this case, only one train operation of the low pressure safety injection (LPSI) without the high pressure safety injection (HPSI) does not prevent reactor vessel failure. Only one train operation of the HPSI at 20,208 s with direct RCS depressurization by using two SDS valves at 40 min after an initial opening of the safety relief valve (SRV) prevents reactor vessel failure for the total LOFW.
机译:作为对严重事故管理指南(SAMG)的评估策略的一部分,已经评估了随着反应堆冷却剂系统(RCS)减压而注入反应堆容器的冷却剂。通过使用SCDAP / RELAP5计算机代码分析了两个高压序列,即在没有安全注入(SI)的情况下发生了少量冷却剂破裂损失事故(LOCA),而在优化动力堆(OPR)1000中发生了给水总量损失(LOFW)事故。 。 SCDAP / RELAP5结果表明,在实施SAMG的6分钟后,仅使用一个冷凝器卸压阀(CDV)在30,000 s进行一次高压RCS间接降压的一次列车运行即可防止反应堆容器因小断裂而失效没有SI的LOCA。在这种情况下,只有低压安全注入(LPSI)的一次列车运行而没有高压安全注入(HPSI)的运行不能防止反应堆容器故障。在安全溢流阀(SRV)初次打开后的40分钟,仅使用两个SDS阀就可在20,208 s时对HPSI进行一次直接RCS降压的列车运行,从而防止了整个LOFW的反应堆容器故障。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2009年第11期|2484-2490|共7页
  • 作者单位

    Korea Atomic Energy Research Institute, 1045 Daedeok-daero, Yuseong-Gu, Daejeon 305-353, Republic of Korea;

    Korea Atomic Energy Research Institute, 1045 Daedeok-daero, Yuseong-Gu, Daejeon 305-353, Republic of Korea;

    Korea Atomic Energy Research Institute, 1045 Daedeok-daero, Yuseong-Gu, Daejeon 305-353, Republic of Korea;

    Korea Atomic Energy Research Institute, 1045 Daedeok-daero, Yuseong-Gu, Daejeon 305-353, Republic of Korea;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
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