Temperature field analysis for the main shielding of the 2-MW thorium-based molten salt experimental reactor

Jie HE; Xiaobin XIA; Jun CAI; Deng PAN; Yu PENG; Jianping HUANG; Guoqing ZHANG

doi:10.11889/j.0253-3219.2016.hjs.39.040601

您当前的位置：

首页 >

文章列表页 >

Temperature field analysis for the main shielding of the 2-MW thorium-based molten salt experimental reactor

更新时间：2021-05-25

- Temperature field analysis for the main shielding of the 2-MW thorium-based molten salt experimental reactor
- NUCLEAR TECHNIQUES Vol. 39, Issue 4, Article number: 040601(2016)
- 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：
- DOI：10.11889/j.0253-3219.2016.hjs.39.040601
  CLC： TL364
- Received：07 January 2016，
  
  Accepted：2016-02-24，
  
  Published：25 April 2016
- 稿件说明：
移动端阅览
Jie HE, Xiaobin XIA, Jun CAI, et al. Temperature field analysis for the main shielding of the 2-MW thorium-based molten salt experimental reactor[J]. Nuclear techniques, 2016, 39(4): 040601
DOI：

Jie HE, Xiaobin XIA, Jun CAI, et al. Temperature field analysis for the main shielding of the 2-MW thorium-based molten salt experimental reactor[J]. Nuclear techniques, 2016, 39(4): 040601 DOI： 10.11889/j.0253-3219.2016.hjs.39.040601.

摘要

反应堆主屏蔽是核反应堆的重要组成部分

用来有效降低反应堆运行时屏蔽体外的辐射剂量水平

以满足反应堆部件材料对辐射限制的要求。温度是影响反应堆主屏蔽性能的重要因素。针对2MWth液态熔盐堆(2-MW liquid-fueled molten salt experimental reactor

TMSR-LF1)

采用MCNP软件获得功率分布后

利用Fluent软件对主屏蔽进行温度场计算。计算过程中利用Python语言编写了程序(MCNP to Fluent

MTF)来实现将MCNP(Monte Carlo N Particle Transport Code)计算结果转换为功率密度的空间分布

以用户自定义函数(User-Defined Function

UDF)形式导入到Fluent

解决了MCNP计算结果不能直接导入到Fluent的问题

并分别计算了TMSR-LF1熔盐堆不同环境温度下的主屏蔽温度场分布情况。结果表明

在环境温度为5℃、18℃、25℃、30℃、35℃、40℃情况下

TMSR-LF1熔盐堆主屏蔽普通混凝土墙温度均低于要求限值

达到设计要求。

Abstract

Background:

Molten salt reactor is a fourth generation advanced reactor. The concrete wall is the key part of this high-temperature reactor shielding

so temperature field analysis is important.

Purpose:

This study attempts to calculate the temperature field of the TMSR-LF1(2-MW liquid-fueled molten salt experimental reactor) shielding

and judge if it meets the design requirements.

Methods:

In accordance with the problem that MCNP(Monte Carlo N Particle Tran

sport Code) results cannot be directly imported into Fluent

a program which converts MCNP results to the spatial distribution of power density

and imports the spatial distribution of power density into the Fluent in the form of User-Defined Function(UDF) was developed by using Python programming language to realize the coupling of the two. According to TMSR-LF1 design parameters

a one-eight physical and thermal model of the whole reactor is established

using code MCNP and Fluent. Reactor radiation shielding thermal analysis adopts the assumptions that the different environment temperatures are 5℃

18℃

25℃

30℃

35℃ and 40℃

respectively.

Results:

The maximal values of temperature and temperature gradient in the radiation shielding concrete wall are 67.42℃ and 78.40℃·m

-1

which are lower than limit values.

Conclusion:

The radiation shielding concrete wall can meet the design requirements.

关键词

Keywords

references

Bettis E S , Schroeder R W , Cristy G A , . The aircraft reactor experiment-design and construction . Nuclear Science and Engineering , 1957 . 2 ( 6 ): 804 - 825 .

Robertson R C . MSRE design and operations report Part I:description of reactor design . Oak Ridge, TN:Oak Ridge National Laboratory , 1965 .

Rosenthal M W , Kasten P R , Briggs R B . Molten-salt reactors-history status and potential . Nuclear Technology , 1970 . 8 ( 2 ): 107 - 117 .

Ignatiev V , Feynberg O , Gnidoi I , . Progress in development of Li, Be, Na/F molten salt actinide recycler & transmuter concept . Nice, France:Proceedings of the ICAPP , 2007 .

Furukawa K , LECOCQ A , Kato Y , . Thorium molten-salt nuclear energy synergetics . Journal of Nuclear Science and Technology , 1990 . 27 ( 12 ): 1157 - 1178 .

TMSR设计中心 . 2 MW固态燃料钍基熔盐实验堆概念设计报告 . 中国科学院钍基熔盐堆核能系统研究中心 , 2013 . 9 1 - 2 .

TMSR Design Center . Conceptual design report of solid fuel thorium based molten salt experimental reactor . Thorium Based Molten Salt Reactor Nuclear Energy System Research Center of Chinese Academy of Sciences , 2013 . 9 1 - 2 .

中华人民共和国国家能源局 . 压水堆核动力厂厂内辐射屏蔽设计准则:NB/T 20194-2012 . 压水堆核动力厂厂内辐射屏蔽设计准则 , 2013 .

National Energy Bureau of the people's Republic of China . Design criteria for radiation shielding in the plant of a pressurized water reactor nuclear power plant:NB/T 20194-2012 . Design criteria for radiation shielding in the plant of a pressurized water reactor nuclear power plant:NB/T 20194-2012 , 2013 .

Haubenreich P N , Engel J R , Prince B E , . MSRE design and operations report Part Ⅲ:nuclear analysis . Oak Ridge, TN:Oak Ridge National Laboratory , 1964 .

马晓 , 张东辉 . CEFR 堆顶固定屏蔽冷却系统流动特性数值研究 . 原子能科学技术 , 2015 . 49 ( 7 ): 1220 - 1226 .

MA Xiao , ZHANG Donghui . Numerical research on flow characteristic of cooling system for CEFR fixed shielding platform . Atomic Energy Science and Technology , 2015 . 49 ( 7 ): 1220 - 1226 .

傅守信 , 于维德 , 刘桂莲 . 5 MW低功率堆主屏蔽设计与安全分析 . 核动力工程 , 1992 . 13 ( 4 ): 49 - 54 .

FU Shouxin , YU Weide , LIU Guilian . Bulk shielding design and safety analysis of 5 MW low power reactor . Nuclear Power Engineering , 1992 . 13 ( 4 ): 49 - 54 .

杨寿海 , 陈义学 , 王伟金 , . 三维离散纵标方法在堆内构件释热率计算中的初步应用 . 核动力工程 , 2012 . 33 ( 1 ): 25 - 28 .

YANG Shouhai , CHEN Yixue , WANG Weijin , . Preliminary study on heating rate calculation for PWR internals by three-dimensional SN method . Nuclear Power Engineering , 2012 . 33 ( 1 ): 25 - 28 .

靳忠敏 . 基于蒙特卡罗方法的压水堆堆内构件核热分布计算分析 . 北京:华北电力大学 , 2011 .

JIN Zhongmin . Heat rate analysis of the PWR reactor internals based on the Monte Carlo method . Beijing:North China Electric Power University , 2011 .

盛选禹 , 王联奎 . 高温气冷堆生物屏蔽层温度场分析 . 科技导报 , 2008 . 26 ( 13 ): 29 - 33 .

SHENG Xuanyu , WANG Liankui . Calculation of temperature field of biological shield in HTR . Science and Technology Review , 2008 . 26 ( 13 ): 29 - 33 .

Zhang D , Rineiski A , Wang C , . Development of a kinetic model for safety studies of liquid-fuel reactors . Progress in Nuclear Energy , 2015 . 81 104 - 112 .

Wang C , Guo Z , Zhang D , . Transient behavior of the sodium-potassium alloy heat pipe in passive residual heat removal system of molten salt reactor . Progress in Nuclear Energy , 2013 . 68 142 - 152 .

Wang C , Xiao Y , Zhou J , . Computational fluid dynamics analysis of a fluoride salt-cooled pebble-bed test reactor . Nuclear Science and Engineering , 2014 . 178 ( 1 ): 86 - 102 .

梅龙伟 , 蔡翔舟 , 蒋大真 , . MCNP 温度相关热中子散射数据库研制 . 核科学与工程 , 2013 . 33 ( 4 ): 362 - 367 .

MEI Longwei , CAI Xiangzhou , JIANG Dazhen , . Development of temperature related thermal neutron scattering database for MCNP . Nuclear Power Engineering , 2013 . 33 ( 4 ): 362 - 367 .

Snoj L , Ravnik M . Calculation of power density with MCNP in TRIGA reactor . Slovenia:International Conference Nuclear Energy for New Europe , 2006 . 18 - 21 .

Views

下载量

CSCD

Alert me when the article has been cited

提交

Tools

Publicity Resources

Nuclear safety analysis of molten salt reactor criticality with changes in ⁷Li abundance

Uncertainty and sensibility analysis of reactivity insertion transient accident of a 150 MWt molten salt reactor (SM-MSR)

Development and validation of a thermal-hydraulic analysis code for dual cooled assemblies in molten salt reactors

Applicability analysis of reduced order modeling methods for fluid dynamics in molten salt reactor

Criticality safety analysis of nuclear fuel storage of molten salt reactor

Related Author

YANG Zhen

DAI Zhimin

ZOU Yang

YAO Yongkui

WANG Kai

WANG Chaoqun

YANG Qun

HE Zhaozhong

Related Institution

Shanghai Institute of Applied Physics, Chinese Academy of Sciences

North-Western China Regional Office of Nuclear and Radiation Safety Inspection, National Nuclear Safety Administration

North-Western China Regional Office of Nuclear and Radiation Saftety Inspection, National Nuclear Safety Administration

ShanghaiTech University

Chengdu University of Technology

AI问答

Address：2019 Jialuo Road, Jiading, Shanghai, China Postal code：201800
Tel：021-39194977 Email：LHB@sinap.ac.cn
Technical support is provided by Beijing Founder electronics co., LTD 沪ICP备05005479号-1 京公网安备11010802024621
It is recommended to read the content of this site in Chrome&IE9+. Please switch to extreme mode in browser 360.
Cookies We use cookies to help provide and enhance our service and tailor content. By continuing, you agree to the use of cookies.
Total Visits：881268 Visits Today：795

⁰