A PSA Case Study: Promoting the Reliability of the CRSS on the CMRR Through the ATWS Mitigation System

Heng Yu, Guangze Wang, Da-zhi Qian, Yuchuan Guo, B. Hu
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Abstract

An increasing number of PSA programs concerning research reactors have been launched across the world. As with many other reactors, the CMRR (China Mianyang Research Reactor), a typical pool-type research reactor, regards the control rod shutdown system (CRSS) as its primary shutdown system which enables the reactor subcritical by dropping control rods into the core after a specific initiating event is detected. As a result, the CRSS is an essential ingredient of engineered safety features. It is necessary to enhance the reliability of the CRSS, ensuring the reactor can be successfully shut down when the ATWS — the anticipated transients without scram occurs. Therefore, additional facilities should be designed to cope with the extremely severe circumstance. Accordingly, the purpose of this paper is to evaluate the promotion of the CMRR’s safety degree and the reliability of its CRSS from the PSA’s perspective with an ATWS mitigation system installed. Results indicate that, by introducing the ATWS mitigation system, the failure probability of the CRSS can decrease from 1.52e−05 per demand to 3.35e−06 per demand, while the aggregate CDF (core damage frequency) induced by all IE (initiating event) groups, is able to decrease to a relatively low value 1.17e−05/y from its previous value 3.11e−06/y. It is apparent that the reliability of the CRSS as well as the safety degree of the overall reactor can be enhanced effectively by adding the ATWS mitigation system to the elementary design of the normal CRSS.
PSA案例研究:通过ATWS缓解系统提高CMRR上CRSS的可靠性
越来越多的关于研究堆的PSA项目在世界范围内启动。与许多其他反应堆一样,中国绵阳研究堆(CMRR)是一个典型的池式研究堆,将控制棒关闭系统(CRSS)作为其主要关闭系统,该系统在检测到特定的启动事件后,通过将控制棒放入堆芯,使反应堆处于亚临界状态。因此,CRSS是工程安全特性的基本组成部分。有必要提高CRSS的可靠性,以确保在ATWS(预期的瞬态无停堆)发生时反应堆能够成功关闭。因此,应该设计额外的设施来应对极端恶劣的情况。因此,本文的目的是从PSA的角度来评估安装ATWS缓解系统后CMRR安全程度的提升及其CRSS的可靠性。结果表明,引入ATWS缓解系统后,CRSS的失效概率可从1.52e−05 /次需求降低到3.35e−06 /次需求,而所有IE组引起的堆芯损伤频率(CDF)可从之前的3.11e−06/y降低到较低的1.17e−05/y。结果表明,在常规CRSS的初步设计中加入ATWS减缓系统,可以有效地提高CRSS的可靠性和整个反应堆的安全程度。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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