首页|华龙一号主泵卡轴事故工况瞬态过渡过程数值分析

华龙一号主泵卡轴事故工况瞬态过渡过程数值分析

Numerical Analysis of Transient Process of HPR1000 Reactor Coolant Pump Shaft Jamming Accident Condition

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为揭示核主泵卡轴事故工况管路瞬变机制,通过匹配核主泵和反应堆一回路系统管路阻力特性的关系,建立三环路反应堆冷却剂系统的简化水体模型.基于计算流体动力学(CFD)方法,再现了卡轴事故工况下系统内部的实际瞬态流动过程及其参数实时变化规律,构建了卡轴工况下反应堆冷却剂系统事故安全评估方法,对卡轴事故工况下系统主管路压力、过渡段弯头壁面载荷、三种典型曲率半径传热管压力的瞬态变化情况进行分析.研究表明:在卡轴事故过程中,事故环路中流量在下降至0m3/h后反向增加,发生倒流现象;事故环路与其他环路的压力和壁面载荷在发生卡轴事故后均会发生剧烈变化后稳定,且事故环路变化程度更大;不同曲率半径传热管压力振荡规律基本一致,且沿各传热管进口至出口方向,监测点的压力峰值逐渐递增.
In order to reveal the pipeline transient mechanism under the shaft jamming accident condition of the reactor coolant pump(RCP),a simplified fluid domain model of the coolant system of the three-loop reactor was established by matching the relationship between the resistance characteristics of the reactor coolant pump and the pipeline of the primary system.Based on the computational fluid dynamics(CFD)method,the actual transient flow process and the real-time change rule of parameters in the reactor coolant system under shaft jamming accident condition were reproduced,and the accident safety evaluation method of reactor coolant system under shaft jamming accident condition was established.The transient changes of main pipeline pressure,wall load of transition bend and pressure of three typical heat transfer tubes with radius of curvature were analyzed under shaft jamming accident condition.The results show that:in the process of the shaft jamming accident,the flow in the accident loop decreases to 0 m3/h and then increases in reverse,and reverse flow occurs.The pressure and wall load of the accident loop and other loops will change dramatically after the shaft jamming accident,and the change degree of the accident loop is greater.The pressure oscillation law of the heat transfer tubes with different curvature radii is basically the same,and the peak pressure of the monitoring point increases gradually along the direction from the inlet to the outlet of each heat transfer tube.

Reactor coolant pumpShaft jamming accidentPipeline transient mechanismReactor coolant systemNumerical analysis

潘军、黎义斌、瞿泽晖、郭艳磊、杨从新、王秀勇

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兰州理工大学能源与动力工程学院,兰州,730050

兰州理工大学特种泵阀及流控系统教育部重点实验室,兰州,730050

核主泵 卡轴事故 管路瞬变机制 反应堆冷却剂系统 数值分析

甘肃省教育厅"双一流"重点项目国防基础科研项目

JCKY2019427D001

2024

核动力工程
中国核动力研究设计院

核动力工程

CSTPCD北大核心
影响因子:0.3
ISSN:0258-0926
年,卷(期):2024.45(1)
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