10MW固态燃料熔盐实验堆安全分析关键技术初步研究

左嘉旭; 高新力; 李朝君; 宋维; 王昆鹏; 刘巧凤; 靖剑平; 张春明

doi:10.11889/j.0253-3219.2017.hjs.40.040601

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10MW固态燃料熔盐实验堆安全分析关键技术初步研究

核能科学与工程 | 更新时间：2021-05-19

- 10MW固态燃料熔盐实验堆安全分析关键技术初步研究
- Preliminaryresearch of safety analysis for 10-MW thorium-basedmolten salt reactor-solid fuel
- 核技术 2017年40卷第4期文章编号：040601
- 作者机构：
  
  环境保护部核与辐射安全中心北京 100082
- 作者简介：
  
  [ "左嘉旭, 男, 1980年出生, 2008年于中国科学院上海应用物理研究所获博士学位, 研究领域为反应堆概率安全分析及可靠性技术", "ZUO Jiaxu, male, born in 1980, graduated from Shanghai Institute of Applied Physics, Chinese Academy of Sciences with a doctoral degree in 2008, focusing on the reactor safety analysis and probabilistic risk assessment" ]
  靖剑平, E-mail:jingjianping@163.com JING Jianping, E-mail:jingjianping@163.com
- 基金信息：
  
  中国科学院战略性先导科技专项(XDA02050500);国家自然科学基金(11505076)
- DOI：10.11889/j.0253-3219.2017.hjs.40.040601
  中图分类号： TL99
- 收稿日期：2016-11-11，
  
  修回日期：2016-12-20，
  
  纸质出版日期：2017-04-10
- 稿件说明：
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左嘉旭, 高新力, 李朝君, 等. 10MW固态燃料熔盐实验堆安全分析关键技术初步研究[J]. 核技术, 2017,40(4):040601

Jiaxu ZUO, Xinli GAO, Chaojun LI, et al. Preliminaryresearch of safety analysis for 10-MW thorium-basedmolten salt reactor-solid fuel[J]. Nuclear techniques, 2017, 40(4): 040601
左嘉旭, 高新力, 李朝君, 等. 10MW固态燃料熔盐实验堆安全分析关键技术初步研究[J]. 核技术, 2017,40(4):040601 DOI： 10.11889/j.0253-3219.2017.hjs.40.040601.

Jiaxu ZUO, Xinli GAO, Chaojun LI, et al. Preliminaryresearch of safety analysis for 10-MW thorium-basedmolten salt reactor-solid fuel[J]. Nuclear techniques, 2017, 40(4): 040601 DOI： 10.11889/j.0253-3219.2017.hjs.40.040601.

摘要

钍基熔盐反应堆（ThoriumMolten Salt Reactor，TMSR）项目是中国科学院科技先导项目之一。基于10 MW热功率熔盐反应堆-固体燃料（ThoriumMolten Salt Reactor-Solid Fuel，TMSR-SF）的设计，对TMSR的关键技术安全分析进行了初步研究。TMSR-SF与现有反应堆之间的差异对核安全审查提出挑战，TMSR-SF审查方法的研究将准备其安全审查的技术和要求。固态燃料熔盐实验堆安全分析关键技术初步研究包含4个方面：堆芯核设计关键安全限值、事故序列及验收准则、源项及其审评方法和验收准则、概率安全评价方法和始发事件。首先对其它类型反应堆的安全审查方法进行了研究，对其关键参数和重要规定做了概述，并借鉴了高温气体冷堆和钠冷却快堆的审评要求和方法；然后使用蒙特卡罗和其他方法、模型来计算TMSR-SF的关键参数。应用逻辑图方法讨论概率风险评价（Probabilistic Risk Assessment，PRA）方法和始发事件清单。在本研究中，计算了核心核设计安全限值，研究和讨论事故列表和分类，讨论了TMSR-SF的PRA框架和始发事件清单，该研究将支持TMSR-SF的安全审查和安全设计。

Abstract

Background

ThoriumMolten Salt Reactor (TMSR) project is one of the Strategic Priority Programprojects of Chinese Academy of Sciences. Based on the design of 10-MWThermal Molten Salt Reactor-Solid Fuel (TMSR-SF)

the preliminary study on safety analysis of TMSR about the key technology are done.

Purpose

This study aims to prepare the technology and requirements for TMSR-SF safety review

and show the guidance and support to the design.

Methods

The study includesfour areas: core nuclear design safety limits

accident analysis and acceptance criteria

the source term and the review methods and acceptance criteria

probabilistic riskassessment (PRA) methods and initiating events.The safety review methods of other type reactors have been studied and compared. The key parameters and important regulations have been summary. From review and summary of the high temperature gas coolant reactor and sodium cooled fast reactor

based on the logic diagram methods

the PRA framework of TMSR-SF and initiating events list are discussed. The Monte Carlo and other methods and models are used to calculate the key core nuclear design safety parameters limits of TMSR-SF. The accident list and classification are studied and discussed from computational fluid dynamics (CFD) calculation.

Results

The core design of TMSR-SF has sufficient negative reactivity coefficientsunder operating conditions.The temperature limit could reference high temperature gas cooled reactor and could be set to 1495 ·C. The shutdown margin should not be less than 0.2 for TMSR-SF.

Conclusions

The preliminary accident type and accident event list of design basis have been setup

and the initialingevents listhas been discussed.The study will support the safety review and safety design of TMSR-SF.

关键词

Keywords

references

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