FHR在全厂断电事故下对RVACS散热能力的要求

赵晶; 王凯; 焦小伟; 何兆忠; 陈堃

doi:10.11889/j.0253-3219.2017.hjs.40.090603

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FHR在全厂断电事故下对RVACS散热能力的要求

核能科学与工程 | 更新时间：2021-05-19

- FHR在全厂断电事故下对RVACS散热能力的要求
- The requirement to the reactor vessel auxiliary cooling system of fluoride salt-cooled high-temperature reactors during station blackout
- 核技术 2017年40卷第9期文章编号：090603
- 作者机构：
  
  1.中国科学院上海应用物理研究所嘉定园区上海 201800
  2.中国科学院大学北京 100049
- 作者简介：
  
  [ "赵晶, 女, 1994年出生, 2014年毕业于兰州大学, 现为硕士研究生, 研究领域为核反应堆安全分析", "ZHAO Jing, female, born in 1994, graduated from Lanzhou University in 2014, master student, focusing on nuclear reactor safety analysis" ]
  陈堃, E-mail:chenkun@sinap.ac.cn CHEN Kun, E-mail:chenkun@sinap.ac.cn
- 基金信息：
  
  中国科学院战略性先导科技专项项目(XDA02050100)
- DOI：10.11889/j.0253-3219.2017.hjs.40.090603
  中图分类号： TL364
- 收稿日期：2017-04-20，
  
  修回日期：2017-06-09，
  
  纸质出版日期：2017-09
- 稿件说明：
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赵晶, 王凯, 焦小伟, 等. FHR在全厂断电事故下对RVACS散热能力的要求[J]. 核技术, 2017,40(9):090603

Jing ZHAO, Kai WANG, Xiaowei JIAO, et al. The requirement to the reactor vessel auxiliary cooling system of fluoride salt-cooled high-temperature reactors during station blackout[J]. Nuclear techniques, 2017, 40(9): 090603
赵晶, 王凯, 焦小伟, 等. FHR在全厂断电事故下对RVACS散热能力的要求[J]. 核技术, 2017,40(9):090603 DOI： 10.11889/j.0253-3219.2017.hjs.40.090603.

Jing ZHAO, Kai WANG, Xiaowei JIAO, et al. The requirement to the reactor vessel auxiliary cooling system of fluoride salt-cooled high-temperature reactors during station blackout[J]. Nuclear techniques, 2017, 40(9): 090603 DOI： 10.11889/j.0253-3219.2017.hjs.40.090603.

摘要

氟盐冷却高温堆（Fluoride salt-cooled High-temperature Reactor，FHR）是一种采用包覆颗粒燃料、高温熔融氟盐冷却剂的先进反应堆。部分FHR概念采用了反应堆容器辅助冷却系统（Reactor Vessel Auxiliary Cooling System，RVACS）导出事故下的堆芯余热。RVACS通过导热、对流换热、辐射换热等非能动过程，在事故发生时将堆芯余热排出至大气中。本文采用中国科学院上海应用物理研究所设计的10 MW FHR作为基准，利用RELAP5-MS程序，对其在全厂断电事故下的瞬态过程进行了模拟，验证了RVACS的余热导出能力。本文进一步研究了高反应堆功率情况下的全厂断电事故的瞬态过程，探讨了不同反应堆功率的FHR对RVACS散热能力的要求。

Abstract

Background:

Reactor vessel auxiliary cooling system (RVACS) is a passive residual heat removal system applied to thorium molten salt reactor-solid fuel (TMSR-SF1). There are difficulties to use it to high-power reactor with its multifunction reactor vessel. To maximize vessel integrity

vessel should be minimized.

Purpose:

This study aims to verify the heat-discharge capability of the RVACS under station blackout accident (SBO).

Methods:

With a 10-MW fluoride salt-cooled high-temperature reactor (FHR) designed by Shanghai Institute of Applied Physics of Chinese Academy of Sciences as the baseline design

the RELAP5-MS code was adopted to simulate the transients during a SBO.

Results:

A scope of RVACS power for heat dissipation of FHR under SBO is given by this study.

Conclusion:

The heat-discharge capability of the RVACS was verified.

关键词

Keywords

references

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