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严重事故下非能动安全壳冷却系统行为研究

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非能动安全壳冷却系统(PCCS)可以在事故下有效导出安全壳内的热量,并维持安全壳压力和温度,从而保障安全壳的完整性.PCCS启动后会对安全壳流动与分层产生影响,同时不断升高的PCCS水箱温度和持续变化的安全壳热工水力状态也将改变PCCS的带热功率,最终形成一个安全壳热工水力与PCCS运行状态耦合的现象.本文采用一体化严重事故分析程序ASTEC搭建了具有PCCS的三代压水堆核电厂模型.研究结果显示在冷管段双端剪切大破口的工况中,在无PCCS的情况下安全壳压力会在3 天左右到达0.7 MPa,而在有PCCS的情况下安全壳压力可以保持在0.3 MPa.与此同时,PCCS的功率随着PCCS水箱温度的升高而降低,并在水箱饱和时达到最低谷.此后,PCCS功率将随着安全壳温度压力的上升而再次上升.在此过程中,根据PCCS带热功率与安全壳压力分布关系,可将PCCS的带热功率阶段分为高功率阶段、低功率阶段以及饱和阶段.PCCS带热功率阶段的转换主要与PCCS水箱温度相关,增大水箱水装量可在一定程度上延缓低功率阶段以及饱和阶段到达的时间.
Study of the Passive Containment Cooling System Behavior in Severe Accident
The passive containment cooling system(PCCS)can effectively remove the heat in the containment and maintain the pressure and temperature in case of accident,thus ensuring the containment integrity.PCCS can introduce the gaseous flow and stratification of containment.At the same time,the increasing temperature of PCCS water tank and the different state of containment will also change the heat transfer power of PCCS.In this paper,the integrated severe accident analysis code ASTEC(Accident Source Term Evaluation Code)is used to establish a Gen Ⅲ PWR model with PCCS,and the simulation result of PCCS is compared with unit experiment:In large break loss of coolant accident,the containment pressure reaches 0.7 MPa in 3 days without PCCS,while that is 0.3 MPa with PCCS.Meanwhile,PCCS heat transfer power decreases with the increasing temperature of PCCS water tank,and reaches the lowest point when the water tank is saturated.PCCS power rises again with the increasing containment temperature.In the whole process,PCCS heat transfer power can be divided into high power stage,low power stage and saturation stage.The stage conversion mainly depends on the water temperature of the PCCS tank.Increasing the water capacity can delay the arrival of the low power stage and the saturation stage.

PCCSContainment thermo-hydraulicsASTEC

欧平文、屈波

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中广核研究院有限公司,广东 深圳 518000

PCCS 安全壳热工水力 ASTEC

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)