固态熔盐堆全厂断电ATWS事故工况下的堆芯安全探讨

焦小伟; 王 凯; 何兆忠; 陈 堃

doi:10.11889/j.0253-3219.2015.hjs.38.020604

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固态熔盐堆全厂断电ATWS事故工况下的堆芯安全探讨

核能科学与工程 | 更新时间：2021-03-03

- 固态熔盐堆全厂断电ATWS事故工况下的堆芯安全探讨
- Core safety discussion under station blackout ATWS accident of solid fuel molten salt reactor
- 核技术 2015年38卷第2期文章编号：020604
- 作者机构：
  
  中国科学院上海应用物理研究所嘉定园区,上海,201800
- 作者简介：
  
  [ "作者简介:焦小伟，男，1989年出生，2013年于中国科学技术大学获硕士学位，主要从事反应堆事故分析" ]
  [ "通讯作者: 何兆忠，E-mail: hezhaozhong@sinap.ac.cn E-mail:hezhaozhong@sinap.ac.cn" ]
- 基金信息：
  
  中国科学院战略性先导科技专项项目(No.XDA02050100)资助()
- DOI：10.11889/j.0253-3219.2015.hjs.38.020604
  中图分类号：
- 纸质出版日期：2015-02-02
- 稿件说明：
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焦小伟, 王凯, 何兆忠, 等. 固态熔盐堆全厂断电ATWS事故工况下的堆芯安全探讨[J]. 核技术, 2015,38(2):020604

JIAO Xiaowei, WANG Kai, HE Zhaozhong, et al. Core safety discussion under station blackout ATWS accident of solid fuel molten salt reactor[J]. Nuclear techniques, 2015, 38(2): 020604
焦小伟, 王凯, 何兆忠, 等. 固态熔盐堆全厂断电ATWS事故工况下的堆芯安全探讨[J]. 核技术, 2015,38(2):020604 DOI： 10.11889/j.0253-3219.2015.hjs.38.020604.

JIAO Xiaowei, WANG Kai, HE Zhaozhong, et al. Core safety discussion under station blackout ATWS accident of solid fuel molten salt reactor[J]. Nuclear techniques, 2015, 38(2): 020604 DOI： 10.11889/j.0253-3219.2015.hjs.38.020604.

摘要

利用修改后的适用于固态熔盐堆的RELAP5/MOD4.0系统分析程序，对固态熔盐堆全厂断电ATWS (Anticipated Transient Without Scram)事故进行了分析。主回路系统进行了合理简化建模，模拟系统在全厂断电ATWS事故时非能动余热排出系统有效与否两种情况下的瞬态响应过程。分析结果表明：非能动余热排出系统在全厂断电ATWS事故初期作用不明显，但长期作用较明显，投入使用后最终将使堆芯温度和主冷却剂温度达到稳定；对于固态熔盐堆来说，即使非能动余热排出系统失效，燃料元件温度上升也很缓慢，给人员干预采取必要措施提供了超过20天的宽限时间。分析结果表明了固态熔盐堆在应对极端事件时具有高的安全性。

Abstract

Background: For solid fuel molten salt reactor

the Station Blackout Anticipated Transient Without Scram (SBO-ATWS) is an accident with very low probability

but the consequences are more serious compared with other design basis accidents. The decay heat may not be removed timely and the core safety will be challenged. Purpose: The aim is to study the core safety features under SBO-ATWS accident. Methods: The transient characteristic of simplified system for solid fuel molten salt reactor under SBO-ATWS accident was calculated by using RELAP5/MOD4.0 code which was modified to suit to solid molten salt reactor. Two scenarios (valid or not) of Passive Residual Heat Removal System (PRHR) were simulated. Results: The calculation results show that the effect of PRHR in early accident is not obvious

but the long-term effect is disctinct. The PRHR will ultimately make the core temperature and coolant temperature to reach a stable state even if it is failure.The fuel element temperature rises very slowly in the circumstance of SBO-ATWS which provides more than 20 day’s grace period for human intervention and taking necessary measures. Conclusion: The results show that the solid fuel molten salt reactor has high safety in response to SBO-ATWS. Abstract

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