Radiation dose analysis of the cover gas purge system failure incident of 2 MW TMSR-LF1

Changqi CHEN; Xiaobin XIA; Jun CAI; Zhihong ZHANG; Changyuan LI

doi:10.11889/j.0253-3219.2018.hjs.41.050604

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Radiation dose analysis of the cover gas purge system failure incident of 2 MW TMSR-LF1

NUCLEAR ENERGY SCIENCE AND ENGINEERING | 更新时间：2021-05-19

- Radiation dose analysis of the cover gas purge system failure incident of 2 MW TMSR-LF1
- NUCLEAR TECHNIQUES Vol. 41, Issue 5, Article number: 050604(2018)
- 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：
- 基金信息：
  
  Strategic Priority Research Program of Chinese Academy of Sciences
- DOI：10.11889/j.0253-3219.2018.hjs.41.050604
  CLC： TL75
- Received：20 December 2017，
  
  Revised：29 January 2018，
  
  Published：10 May 2018
- 稿件说明：
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Changqi CHEN, Xiaobin XIA, Jun CAI, et al. Radiation dose analysis of the cover gas purge system failure incident of 2 MW TMSR-LF1[J]. Nuclear techniques, 2018, 41(5): 050604
DOI：

Changqi CHEN, Xiaobin XIA, Jun CAI, et al. Radiation dose analysis of the cover gas purge system failure incident of 2 MW TMSR-LF1[J]. Nuclear techniques, 2018, 41(5): 050604 DOI： 10.11889/j.0253-3219.2018.hjs.41.050604.

摘要

覆盖气净化系统失效事件是2 MW液态燃料钍基熔盐实验堆（Thorium Molten Salt experimental Reactor-Liquid Fueled，TMSR-LF1）可能导致放射性释放的典型假想事件之一。本文根据事件的释放模式和源项，在保守假设的情况下，使用ARCON96计算事件发生后厂房各边界处的大气弥散因子，估算事件发生后假设的烟囱下风向各厂房边界处的工作人员的个人有效剂量，然后分析事件发生后反应堆厂房内的可居留性。经过计算可以得出，覆盖气净化系统失效事件发生后，产生的有效剂量主要来源于浸没外照射途径。厂房边界处最大24 h全身累积剂量为3.04 mSv，低于国家核安全导则规定的场区应急行动水平，事件发生后TMSR-LF1将进入厂房应急状态，无需场外应急。

Abstract

Background

The cover gas purge system failure incident is one of the typical incidents of 2 MW liquid-fueled thorium molten salt experimental reactor-liquid fueled (TMSR-LF1)

which could result in radiation releasing.

Purpose

This paper attempts to analyze the habitability for operations in the powerhouse under the cover gas removal system failure incidental condition

and provide data for nuclear emergency for TMSR-LF1.

Methods

Based on source items and emission pattern

we did conservative evaluations of atmospheric dispersion factors of powerhouse boundaries by using ARCON96 and 24 h individual effective dose for occupational workers locate at powerhouse boundaries.

Results

For this incident

the highest 24 h individual cumulative dose is 3.04 mSv and it appears on the powerhouse boundary nearest to the reactor core.

Conclusion

Compared the results with the national standards

it is not up to site-area emergency action level so that the reactor would enter in alert emergency classification.

关键词

Keywords

references

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