The requirement to the reactor vessel auxiliary cooling system of fluoride salt-cooled high-temperature reactors during station blackout

Jing ZHAO; Kai WANG; Xiaowei JIAO; Zhaozhong HE; Kun CHEN

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

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The requirement to the reactor vessel auxiliary cooling system of fluoride salt-cooled high-temperature reactors during station blackout

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

- The requirement to the reactor vessel auxiliary cooling system of fluoride salt-cooled high-temperature reactors during station blackout
- NUCLEAR TECHNIQUES Vol. 40, Issue 9, Article number: 090603(2017)
- 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：
  
  the Strategic Priority Research Program of Chinese Academy of Sciences
- DOI：10.11889/j.0253-3219.2017.hjs.40.090603
  CLC： TL364
- Received：20 April 2017，
  
  Revised：09 June 2017，
  
  Published：2017-09
- 稿件说明：
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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：

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

Forsberg C W, Hu L W, Peterson P F, et al. Fluoride-salt-cooled high-temperature reactors (FHRs) for power and process heat[R]. MIT-ANP-TR-157, Cambridge, MA:Massachusetts Institute of Technology, 2014.

J Serp , M Allibert , O Beneš , . The molten salt reactor (MSR) in generation Ⅳ:overview and perspectives . Progress in Nuclear Energy , 2014 . 77 308 - 319 . DOI: 10.1016/j.pnucene.2014.02.014 http://doi.org/10.1016/j.pnucene.2014.02.014 .

C W Forsberg , P F Peterson , P S Pickard . Molten-salt-cooled advanced high-temperature reactor for production of hydrogen and electricity . Nuclear Technology , 2003 . 144 ( 3 ): 289 - 302 . DOI: 10.13182/NT03-1 http://doi.org/10.13182/NT03-1 .

Ingersoll D T. Status of physics and safety analyses for the liquid-salt-cooled very high-temperature reactor (LS-VHTR)[R]. ORNL/TM-2005/218, Oak Ridge, Tennessee:Oak Ridge National Laboratory, 2005. https://digital.library.unt.edu/ark:/67531/metadc875665/m2/1/high_res_d/885991.pdf

J Žáková . Analysis of an advanced graphite moderated and molten salt cooled high temperature reactor , : Sweden Kungliga Tekniska Högskolan , 2006 .

Holcomb D E, Peretz F J, Qualls A L. Advanced high temperature reactor systems and economic analysis[R]. ORNL/TM-2011/364, Oak Ridge, Tennessee:Oak Ridge National Laboratory, 2011.

沈苏 , 苏宏 . 高温气冷堆的特点及发展概况 . 东方电气评论 , 2004 . 18 ( 1 ): 50 - 54 . DOI: 10.13661/j.cnki.issn1001-9006.2004.01.013 http://doi.org/10.13661/j.cnki.issn1001-9006.2004.01.013 .

Su SHEN , Hong SU . Status of high temperature gas-cooled reactor . Dongfang Electric Review , 2004 . 18 ( 1 ): 50 - 54 . DOI: 10.13661/j.cnki.issn1001-9006.2004.01.013 http://doi.org/10.13661/j.cnki.issn1001-9006.2004.01.013 .

Forsberg C W. Alternative passive decay-heat systems for the advanced high-temperature reactor[C]. International Congress on the Advances in Nuclear Power Plants (ICAPP'06) Embedded Topical in the 2006 American Nuclear Society Annual Meeting, 2006, 8(3):4-8.

H Rouch , O Geoffroy , P Rubiolo , . Preliminary thermal-hydraulic core design of the molten salt fast reactor (MSFR) . Annals of Nuclear Energy , 2014 . 64 449 - 456 . DOI: 10.1016/j.anucene.2013.09.012 http://doi.org/10.1016/j.anucene.2013.09.012 .

TMSR-SF1反应堆系统工程技术部. 10 MW固态钍基熔盐实验堆概念设计报告[R]. 上海: 中国科学院上海应用物理研究所, 2014.

TMSR-SF1 Department of Reactor System Engineering Technology. Conceptual design of 10-MW solid thorium molten salt reactor experiment reactor[R]. Shanghai:Shanghai Institute of Applied Physics, Chinese Academy of Sciences, 2014.

Wang K, He Z Z, Chen K. Application of RELAP5/MOD4.0 code in a fluoride salt-cooled high-temperature test reactor[C]. International Topical Meeting on Advances in Thermal Hydraulics-2014 (ATH'14), 2014.

焦小伟 , 王凯 , 何兆忠 , . 固态熔盐堆全厂断电ATWS事故工况下的堆芯安全探讨 . 核技术 , 2015 . 38 ( 2 ): 020604 DOI: 10.11889/j.0253-3219.2015.hjs.38.020604 http://doi.org/10.11889/j.0253-3219.2015.hjs.38.020604 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract358.shtml .

Xiaowei JIAO , Kai WANG , Zhaozhong HE , . Core safety discussion under station blackout ATWS accident of solid fuel molten salt reactor . Nuclear Techniques , 2015 . 38 ( 2 ): 020604 DOI: 10.11889/j.0253-3219.2015.hjs.38.020604 http://doi.org/10.11889/j.0253-3219.2015.hjs.38.020604 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract358.shtml .

沈瑾 , 江光明 , 唐钢 , . 先进堆非能动余热排出系统应对全厂断电事故的能力分析 . 核动力工程 , 2007 . 28 ( 2 ): 87 - 90 . DOI: 10.3969/j.issn.0258-0926.2007.02.020 http://doi.org/10.3969/j.issn.0258-0926.2007.02.020 .

Jin SHEN , Guangming JIANG , Gang TANG , . Application of passive residual heat removal system under blackout accident of Chinese advanced nuclear power plant . Nuclear Power Engineering , 2007 . 28 ( 2 ): 87 - 90 . DOI: 10.3969/j.issn.0258-0926.2007.02.020 http://doi.org/10.3969/j.issn.0258-0926.2007.02.020 .

TMSR-SF1反应堆系统工程技术部. TMSR-SF1事故分析方法和计算程序[R]. 上海: 中国科学院上海应用物理研究所, 2014.

TMSR-SF1 Department of Reactor System Engineering Technology. TMSR-SF1 accident analysis method and calculation codes[R]. Shanghai:Shanghai Institute of Applied Physics, Chinese Academy of Sciences, 2014.

S Agamy , A M Metwally , M A Al-Ramady , . A RELAP5 model for the thermal-hydraulic analysis of a typical pressurized water reactor . Thermal Science , 2010 . 14 ( 1 ): 79 - 88 . DOI: 10.2298/TSCI1001079A http://doi.org/10.2298/TSCI1001079A .

李晓伟 , 吴莘馨 , 张丽 , . 模块式高温气冷堆非能动余热排出系统分析与研究 . 原子能科学技术 , 2011 . 45 ( 7 ): 790 - 795 . http://www.cnki.com.cn/Article/CJFDTOTAL-YZJS201107006.htm .

Xiaowei LI , Xinxin WU , Li ZHANG , . Analysis of passive residual heat removal system of modular high temperature gas-cooled reactor . Atomic Energy Science and Technology , 2011 . 45 ( 7 ): 790 - 795 . http://www.cnki.com.cn/Article/CJFDTOTAL-YZJS201107006.htm .

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