FHR在全厂断电事故下对RVACS散热能力的要求

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

Nuclear Techniques

• NUCLEAR PHYSICS, INTERDISCIPLINARY RESEARCH • Previous Articles Next Articles

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

ZHAO Jing^1,2, WANG Kai¹, JIAO Xiaowei^1,2, HE Zhaozhong¹, CHEN Kun¹

1. Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Jiading Campus, Shanghai 201800, China;
2. University of Chinese Academy of Sciences, Beijing 100049, China

Received:2017-04-20 Revised:2017-06-09 Online:2017-09-10 Published:2017-09-06
Supported by:
Supported by Strategic Priority Research Program of Chinese Academy of Sciences (No.XDA02050100)

Abstract

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.

Key words: FHR, RVACS, RELAP5-MS, Station blackout

CLC Number:

TL364

ZHAO Jing, WANG Kai, JIAO Xiaowei, HE Zhaozhong, CHEN Kun. 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): 90603-090603.

References

1 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.
2 Serp J, Allibert M, Beneš O, et al. The molten salt reactor (MSR) in generation IV:overview and perspectives[J]. Progress in Nuclear Energy, 2014, 77:308-319. DOI:10.1016/j.pnucene.2014.02.014.
3 Forsberg C W, Peterson P F, Pickard P S. Molten-salt-cooled advanced high-temperature reactor for production of hydrogen and electricity[J]. Nuclear Technology, 2003, 144(3):289-302. DOI:10.13182/NT03-1.
4 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.
5 Žáková J. Analysis of an advanced graphite moderated and molten salt cooled high temperature reactor[M]. Sweden:Kungliga Tekniska Högskolan, 2006.
6 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.
7 沈苏, 苏宏. 高温气冷堆的特点及发展概况[J]. 东方电气评论, 2004, 18(1):50-54. DOI:10.13661/j.cnki.issn 1001-9006.2004.01.013. SHEN Su, SU Hong. Status of high temperature gas-cooled reactor[J]. Dongfang Electric Review, 2004, 18(1):50-54. DOI:10.13661/j.cnki.issn1001-9006.2004. 01.013.
8 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.
9 Rouch H, Geoffroy O, Rubiolo P, et al. Preliminary thermal-hydraulic core design of the molten salt fast reactor (MSFR)[J]. Annals of Nuclear Energy, 2014, 64:449-456. DOI:10.1016/j.anucene.2013.09.012.
10 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.
11 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.
12 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.
13 沈瑾, 江光明, 唐钢, 等. 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[J]. 核动力工程, 2007, 28(2):87-90. DOI:10.3969/j.issn.0258-0926.2007.02. 020. SHEN Jin, JIANG Guangming, TANG Gang, et al. Application of passive residual heat removal system under blackout accident of Chinese advanced nuclear power plant[J]. Nuclear Power Engineering, 2007, 28(2):87-90. DOI:10.3969/j.issn.0258-0926.2007.02.020.
14 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.
15 Agamy S, Metwally A M, Al-Ramady M A, et al. A RELAP5 model for the thermal-hydraulic analysis of a typical pressurized water reactor[J]. Thermal Science, 2010, 14(1):79-88. DOI:10.2298/TSCI1001079A.
16 李晓伟, 吴莘馨, 张丽, 等. 模块式高温气冷堆非能动余热排出系统分析与研究[J]. 原子能科学技术, 2011, 45(7):790-795. LI Xiaowei, WU Xinxin, ZHANG Li, et al. Analysis of passive residual heat removal system of modular high temperature gas-cooled reactor[J]. Atomic Energy Science and Technology, 2011, 45(7):790-795.

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

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