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Analysis on hydrogen risk mitigation in severe accidents for Pressurized Heavy Water Reactor

机译:加压重水反应堆重大事故中降低氢气风险的分析。

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摘要

Hydrogen source term and hydrogen mitigation under severe accidents is evaluated for most nuclear power plants (NPPS) after Fukushima Daiichi accident. Two units of Pressurized Heavy Water Reactor (PHWR) are under operating in China, and hydrogen risk control should be evaluated in detail for the existing design. The distinguish feature of PHWR, compared with PWR, is the horizontal reactor core surrounded by moderator in calandria vessel (CV), which may influence the hydrogen source term. Based on integral system analysis code of PHWR, the plant model including primary heat transfer system (PHTS), calandria, end shield system, reactor cavity and containment has been developed. Two severe accident sequences have been selected to study hydrogen generation characteristic and the effectiveness of hydrogen mitigation with igniters. The one is Station Blackout (SBO) which represents high-pressure core melt accident, and the other is Large Break Loss of Coolant Accident (LLOCA) at reactor outlet header (ROH) which represents low-pressure core melt accident. Results show that under severe accident sequences, core oxidation of zirconium-steam reaction will produce hydrogen with deterioration of core cooling and the water in CV and reactor cavity can inhibits hydrogen generation for a relatively long time. However, as the water dries out, creep failure happens on CV. As a result, molten core falls into cavity and molten core concrete interaction (MCCI) occurs, releasing a large mass of hydrogen. When hydrogen igniters fail, volume fraction of hydrogen in the containment is more than 15% while equivalent amount of hydrogen generate from a 100% fuel clad-coolant reaction. As a result, hydrogen risk lies in the deflagration-detonation transition area. When igniters start at the beginning of large hydrogen generation, hydrogen mixtures ignite at low concentration in the compartments and the combustion mode locates at the edge of flammable area. However, the power supply to igniters should be ensured. (C) 2014 Elsevier Ltd. All rights reserved.
机译:福岛第一核电站事故发生后,大多数核电厂(NPPS)都会评估严重事故下的氢源期限和氢缓解措施。中国有两台加压重水反应堆(PHWR)在运行,对于现有设计,应详细评估氢风险控制。与压水堆相比,PHWR的显着特征是在排管容器(CV)中被缓和剂包围的卧式反应堆堆芯可能会影响氢源项。根据PHWR的整体系统分析代码,开发了包括一次传热系统(PHTS),加热炉,端罩系统,反应堆腔和安全壳在内的工厂模型。选择了两个严重的事故序列来研究氢气的产生特性和点火器缓解氢气的效果。一个是代表高压堆芯融化事故的电站停电(SBO),另一个是代表低压堆芯融化事故的反应堆出口集管(ROH)处的冷却液事故大破坏损失(LLOCA)。结果表明,在严重事故序列下,锆-蒸汽反应堆芯氧化会产生氢气,并使堆芯冷却性能降低,而恒压腔和反应器腔中的水可以在较长时间内抑制氢气的产生。但是,随着水的干燥,CV会发生蠕变破坏。结果,熔融岩心落入型腔,发生熔融岩心混凝土相互作用(MCCI),释放出大量的氢。当氢气点火器发生故障时,安全壳中氢气的体积分数将超过15%,而100%的复合燃料冷却剂反应会产生等量的氢气。结果,在爆燃-爆震过渡区域中存在氢气风险。当大量氢气产生开始时点火器开始工作时,氢气混合物在车厢中以低浓度点火,并且燃烧模式位于易燃区域的边缘。但是,应确保为点火器供电。 (C)2014 Elsevier Ltd.保留所有权利。

著录项

  • 来源
    《Progress in Nuclear Energy》 |2015年第4期|128-135|共8页
  • 作者

    Tong Lili; Zou Jie; Cao Xuewu;

  • 作者单位

    Shanghai Jiao Tong Univ, Sch Mech Engn, Shanghai 200240, Peoples R China;

    Shanghai Jiao Tong Univ, Sch Mech Engn, Shanghai 200240, Peoples R China;

    Shanghai Jiao Tong Univ, Sch Mech Engn, Shanghai 200240, Peoples R China;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    PHWR; Hydrogen source term; SBO; LLOCA; Igniters;

    机译:PHWR;氢源术语;SBO;LLOCA;点火器;

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