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核电厂SGTR规程优化研究 被引量:1

Optimization Research of SGTR Procedure for Nuclear Power Plant
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摘要 核电厂通过应急运行规程(EOP)来缓解蒸汽发生器传热管破裂(SGTR)事故,SGTR事故分析结果显示,在缓解过程中操纵员开启稳压器卸压阀进行反应堆冷却剂系统(RCS)降压后,安全注射(简称“安注”)流量大幅增加,导致稳压器水位大幅增加,可能存在潜在的危险。本文目的是为了更好地缓解SGTR事故,使事故缓解过程中稳压器水位不致上升过高,确保核电厂安全。通过对EOP缓解步骤进行优化,提前切除一列安注,并对优化后的EOP缓解事故过程进行分析计算,最终结果显示稳压器最高水位下降,减少了稳压器水位过高的风险,为后续核电厂规程的改进提供了依据。 Nuclear power plant mitigates SGTR accident by emergency operating procedure(EOP).SGTR analysis results show that after the operator opens the pressurizer relief valve to decrease reactor coolant system pressure in the process of accident mitigation,the safety injection flow increases quickly causing the pressurizer level increasing substantially,there may be a potential danger.The purpose of this paper is to better mitigate the SGTR accident,so that the pressurizer level will not rise too high during the accident mitigation process to keep the nuclear power plant safe.By optimizing the EOP mitigation steps,cutting off a row of safety injection in advance,and analyzing and calculating the accident mitigation process of the optimized EOP,the final results show that the maximum level of the pressurizer decreases,which reduces the risk of excessive level of the pressurizer,which provides a basis for the follow-up improvement of the nuclear power plant procedure.
作者 刘立欣 王喆 Liu Lixin;Wang Zhe(Shanghai Nuclear Engineering Research&Design Institute,Shanghai,200233,China)
出处 《核动力工程》 EI CAS CSCD 北大核心 2022年第4期126-130,共5页 Nuclear Power Engineering
关键词 蒸汽发生器传热管破裂(SGTR) 应急运行规程(EOP)优化 稳压器水位 安注系统 Steam generator tube rupture(SGTR) Emergency operating procedure optimization Pressurizer level Safety injection system
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  • 1CAP1000初步安全分析报告[R].上海:上海核工程研究设计院,2013.
  • 2CARLIN E L. AP1000 analysis methodology summary for events using the LOFTRAN code family[R]. USA: Westinghouse Electric Compa- ny LLC, 2001.
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  • 5柯晓.CAP1000核电厂全功率范围SGTR事故研究[J].原子能科学技术,2014,48(6):1031-1037. 被引量:8

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