首页|先进压水堆核电厂LOCA叠加ATWS事故分析及敏感性研究

先进压水堆核电厂LOCA叠加ATWS事故分析及敏感性研究

扫码查看
为了分析核电厂发生冷却剂丧失事故(LOCA)叠加未能紧急停堆预期运行瞬态(ATWS)事故后的瞬态响应,研究不同事故情景下的缓解路径,本文以国产先进压水堆核电厂为研究对象,利用系统分析程序建立了核电厂模型,研究了该事故下核电厂的瞬态特性,并开展了敏感性分析,得出如下结论:对于极限小破口工况,则至少需要 1 个稳压器安全阀和 1 列应急给水系统有效,才能避免事故早期一回路超压;对于相对较大的小破口工况,至少需要 1 列应急给水、1 列中压安注系统和 1 列应急硼注入系统有效才能缓解事故;对于中破口工况,若破口尺寸相对较小,则需要 1 列应急给水、1 列中压安注系统、1 个安注箱、1 列低压安注系统和 1 列应急硼注入系统来缓解事故;若破口尺寸较大,则只需要 1 列中压安注系统、1 个安注箱、1 列低压安注系统有效就可以缓解事故.
Accident Analysis and Sensitivity Study of LOCA Superimposed ATWS in Advanced PWR Nuclear Power Plant
In order to analyze the transient response of nuclear power plant after the LOCA superimposed anticipated transients without scram,and study the accident mitigation path under different accident scenarios,this paper takes domestic advanced PWR nuclear power plant as the case of study,establishes the nuclear power plant model by using system analysis code,and studies the transient characteristics of the power plant under the accident condition.The sensitivity analysis is carried out,and the conclusion is as follows.For the extreme small break condition,at least one pressurizer safety valve and one emergency water supply system should be effective to avoid the primary overpressure in the early stage of the accident.For relatively large small break conditions,at least one emergency water supply system,one medium pressure safety injection system and one emergency boron injection system should be effective to alleviate the accident.For the medium break condition,if the size of the break is relatively small,it is necessary to have one emergency water supply system,one medium pressure safety injection system,one accumulator,one low pressure safety injection system and one emergency boron injection system to alleviate the accident.If the size of the break is large,only one medium pressure safety injection system,one accumulator,and one low pressure safety injection system are required to alleviate the accident.

LOCAAnticipated transients without scramAccident analysis

王业辉、潘昕怿、张盼

展开 >

生态环境部核与辐射安全中心,北京 100082

冷却剂丧失事故 未能紧急停堆预期运行瞬态 事故分析

2024

核科学与工程
中国核学会

核科学与工程

CSTPCD北大核心
影响因子:0.586
ISSN:0258-0918
年,卷(期):2024.44(5)