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首页> 外文期刊>International Journal of Heat and Mass Transfer >Effects of failure location and pressure on the core voiding under SGTR accident in a LBE-cooled fast reactor
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Effects of failure location and pressure on the core voiding under SGTR accident in a LBE-cooled fast reactor

机译：LBE冷却快堆中SGTR事故下失效位置和压力​​对堆芯空隙的影响

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摘要

The multiphase flow phenomenon of the interaction between lead-bismuth eutectic and water is a safety concern for the design of lead-based fast reactor. In order to investigate the steam transport characteristics under a postulated Steam Generator Tube Rupture (SGTR) accident in a lead-based reactor, numerical simulation of lead-bismuth eutectic-water/steam multiphase flow in a reactor pool was performed and the effects of failure location and pressure of secondary loop on steam volume fraction in reactor core was evaluated. Under the present theoretical analysis, the results showed that the maximum steam volume fraction in the core occurred for the condition of cooling tube failure located at the outlet of SG which is closest to the pump duct and the accident consequence might be the most serious. The maximum steam volume fraction in reactor core increased with the increasing of the pressure of secondary loop. The analysis results will provide reference for the safety design and engineering guidance of lead-cooled fast reactor. (C) 2019 Elsevier Ltd. All rights reserved.
机译：铅铋共晶与水相互作用的多相流现象是铅基快堆设计的安全考虑。为了研究铅基反应堆在假定的蒸汽发生管破裂（SGTR）事故下的蒸汽传输特性，对反应堆池中铅-铋共晶水/蒸汽多相流的数值模拟以及失效的影响评价了二次回路的位置和压力​​对反应堆堆芯中蒸汽体积分数的影响。根据目前的理论分析，结果表明，在SG出口最靠近泵管的冷却管故障的情况下，堆芯中的最大蒸汽体积分数发生了，事故后果可能最严重。反应堆堆芯中的最大蒸汽体积分数随二次回路压力的增加而增加。分析结果可为铅冷快堆的安全设计和工程指导提供参考。 （C）2019 Elsevier Ltd.保留所有权利。

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  • 来源
  • 作者

    Zhang Chaodong; Sa Rongyuan; Zhou Danna; Zhang Guangyu; Wang Lei;

  • 作者单位

    Chinese Acad Sci, Inst Nucl Energy Safety Technol, Key Lab Neutron & Radiat Safety, Hefei 230031, Anhui, Peoples R China;

    Chinese Acad Sci, Inst Nucl Energy Safety Technol, Key Lab Neutron & Radiat Safety, Hefei 230031, Anhui, Peoples R China;

    Chinese Acad Sci, Inst Nucl Energy Safety Technol, Key Lab Neutron & Radiat Safety, Hefei 230031, Anhui, Peoples R China;

    Chinese Acad Sci, Inst Nucl Energy Safety Technol, Key Lab Neutron & Radiat Safety, Hefei 230031, Anhui, Peoples R China;

    Chinese Acad Sci, Inst Nucl Energy Safety Technol, Key Lab Neutron & Radiat Safety, Hefei 230031, Anhui, 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

    Lead-cooled fast reactor; SGTR; Multiphase flow; Steam transport; Core voiding;

    机译：铅冷却快速反应堆;SGTR;多相流动;蒸汽运输;核心排尿;

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