期刊论文

中文

核科学与工程

0258-0918

2022

42

2

398-407

10.3969/j.issn.0258-0918.2022.02.022

核反应堆系统设计技术重点实验室基金资助项目(HT-KFKT-10-2018001)。

本校为其他机构

基于RELAP5/MOD3.4分析软件建立了1 000 MW核电机组一回路模型，在发生多根蒸汽发生器传热管道双端断裂事故（SGTR）瞬态下对发生事故后30 min内无人为操作的5种不同断裂工况进行了主要参数对比分析，并且对蒸汽发生器（SG）发生满溢时间进行了敏感性分析。研究表明：传热管断裂根数不同，各参数变化趋势相似；断裂根数越多，破口初始流量越大，触发系统动作越早；破口面积、主泵运作、主给水关闭时间、辅助给水投入时间和投入量都会影响SG满溢时间。对CPR1000机组发生多根SGTR事故对比分析和事故后各设备动作对SG满溢时间影响的研究有实际设计和运行参考价值。

Based on the RELAP5/MOD3.4 analysis software, a primary circuit model of a 1 000 MW nuclear power plant was established. In the event of a SGTR transient of multiple steam generator heat transfer tubes, there were five different fracture conditions for which no human operation was performed within 30 minutes after the SGTR accident happened. The comparative analysis of the main parameters was carried out, and the sensitivity analysis was performed on the overfill time of SG. Results show that the trend of each parameter is similar for heat transfer tubes with different numbers of fractures. Th...