CMRR堆内高温高压辐照考验回路典型事故分析

胡泊; 郭斯茂; 王冠博; 钱达志; 郭玉川; 余恒

doi:doi:10.11884/hplpb201931.190023

强激光与粒子束, 2019, 31 (9): 096001, 网络出版: 2019-10-12

CMRR堆内高温高压辐照考验回路典型事故分析

Simulation of typical accidents in fuel test loop of CMRR

论文大纲

胡泊郭斯茂王冠博钱达志郭玉川余恒

作者单位

中国工程物理研究院核物理与化学研究所, 四川绵阳 621900

高温高压辐照考验回路失水事故失流事故中国绵阳研究堆 fuel test loop loss-of-coolant accident loss-of-flow accident China’s Mianyang Research Reactor

摘要

基于中国绵阳研究堆（CMRR）高温高压辐照考验回路初步设计方案，就回路失水事故（LOCA）及失流事故（LOFA）两类典型事故进行分析。结果表明：回路在冷管段及热管段失水事故下包壳热点温度最高为880.6 ℃及367.6 ℃，均远低于1204 ℃；全部失流事故下最小偏离泡核沸腾比（MDNBR）大于1.5，不会发生偏离泡核沸腾；卡轴事故中包壳最高温度为734.1 ℃，低于1482 ℃。上述结果均满足验收准则，符合安全法规要求。

Abstract

In order to reflect the behavior of the nuclear materials in the operating reactor veritably and roundly, and to supply reliable data for the safety review of the nuclear materials, the most effective solution is building a fuel test loop (FTL) based on the real pressurized water reactor in the research reactor. To ensure the safety of the fuel test loop and the research reactor, it is necessary to analyze the safety of the fuel test loop during accident transient. This article simulates and analyzes two typical kinds of accidents-small break loss-of-coolant accidents (LOCA) and loss-of-flow accidents (LOFA)-based on the origin design of the fuel test loop in China’s Mianyang Research Reactor (CMRR). The peak cladding temperature in cold leg SBLOCA and hot leg small break LOCA is 880.6 ℃ and 367.6 ℃ respectively, which is under the critical value (1204 ℃). During the total LOFA, the MDNBR is greater than 1.5, which means there is no departure from nucleate boiling. In the clamp shaft accident, the cladding temperature is 734.1 ℃，which is less than 1482 ℃. The results obtained are consistent with the safety criteria.

参考文献

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胡泊, 郭斯茂, 王冠博, 钱达志, 郭玉川, 余恒. CMRR堆内高温高压辐照考验回路典型事故分析[J]. 强激光与粒子束, 2019, 31(9): 096001. Hu Bo, Guo Simao, Wang Guanbo, Qian Dazhi, Guo Yuchuan, Yu Heng. Simulation of typical accidents in fuel test loop of CMRR[J]. High Power Laser and Particle Beams, 2019, 31(9): 096001.

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