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Characteristics of debris in the lower head of a BWR in different severe accident scenarios

机译:不同严重事故情况下压水堆下部头部的碎屑特征

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摘要

Nordic boiling water reactors (BWRs) adopt ex-vessel debris cooling to terminate severe accident progression. Core melt released from the vessel into a deep pool of water is expected to fragment and form a coolable debris bed. Characteristics of corium melt ejection from the vessel determine conditions for molten fuel-coolant interactions (FCI) and debris bed formation. Non-coolable debris bed or steam explosion can threaten containment integrity. Vessel failure and melt ejection mode are determined by the in vessel accident progression. Characteristics (such as mass, composition, thermal properties, timing of relocation, and decay heat) of the debris bed formed in the process of core relocation into the vessel lower plenum define conditions for the debris reheating, remelting, melt-vessel structure interactions, vessel failure and melt release. Thus core degradation and relocation are important sources of uncertainty for the success of the ex-vessel accident mitigation strategy.
机译:北欧沸水反应堆(BWR)采用前容器碎片冷却来终止严重的事故发展。从容器释放到深水池中的岩心熔体预计会碎裂并形成可冷却的碎屑床。从容器中喷出的皮质熔体的特性决定了熔融燃料-冷却剂相互作用(FCI)和碎屑床形成的条件。不可冷却的碎屑床或蒸汽爆炸会威胁到安全壳的完整性。容器故障和熔体喷射方式取决于容器内事故的进展。在堆芯重定位到容器下部气室的过程中形成的碎屑床的特性(例如质量,成分,热性质,重定位的时间和衰减热)定义了碎片重热,重熔,熔体-容器结构相互作用的条件,容器故障和熔体释放。因此,堆芯退化和重新安置是船外事故缓解策略成功与否的重要不确定因素。

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  • 来源
    《Nuclear Engineering and Design》 |2016年第8期|359-370|共12页
  • 作者单位

    Royal Inst Technol, Div Nucl Power Safety, Roslagstullsbacken 21, S-10691 Stockholm, Sweden;

    Royal Inst Technol, Div Nucl Power Safety, Roslagstullsbacken 21, S-10691 Stockholm, Sweden;

    Royal Inst Technol, Div Nucl Power Safety, Roslagstullsbacken 21, S-10691 Stockholm, Sweden;

    Royal Inst Technol, Div Nucl Power Safety, Roslagstullsbacken 21, S-10691 Stockholm, Sweden;

    Royal Inst Technol, Div Nucl Power Safety, Roslagstullsbacken 21, S-10691 Stockholm, Sweden;

    Royal Inst Technol, Div Nucl Power Safety, Roslagstullsbacken 21, S-10691 Stockholm, Sweden;

    Royal Inst Technol, Div Nucl Power Safety, Roslagstullsbacken 21, S-10691 Stockholm, Sweden;

    Royal Inst Technol, Div Nucl Power Safety, Roslagstullsbacken 21, S-10691 Stockholm, Sweden;

  • 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
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