Effects of bayonet tube leak on the heat transfer characteristics of fuel drain system in molten salt reactor

SUN Liangjie; LIANG Rongjian; JIANG Wentao; WANG Chaoqun; YANG Qun; HE Zhaozhong; ZOU Yang

doi:10.3724/j.0253-3219.2026.hjs.49.250003

您当前的位置：

首页 >

文章列表页 >

Effects of bayonet tube leak on the heat transfer characteristics of fuel drain system in molten salt reactor

NUCLEAR ENERGY SCIENCE AND ENGINEERING | 更新时间：2026-02-13

- Effects of bayonet tube leak on the heat transfer characteristics of fuel drain system in molten salt reactor
- NUCLEAR TECHNIQUES Vol. 49, Issue 2, Article number: 020605(2026)
- 作者机构：
  
  1.中国科学院上海应用物理研究所上海 201800
  2.中国科学院大学北京 100049
- 作者简介：
  
  SUN Liangjie, male, born in 1999, graduated from Huazhong University of Science and Technology in 2019, doctoral student, focusing on reactor safety
  YANG Qun, E-mail: yangqun@sinap.ac.cn
- 基金信息：
  
  Youth Innovation Promotion Association(E3292901);Shanghai Pilot Program for Basic Research–Chinese Academy of Sciences, Shanghai Branch(JCYJ-SHFY-2021-003)
- DOI：10.3724/j.0253-3219.2026.hjs.49.250003
  CLC： TL364
- Received：06 January 2025，
  
  Revised：2025-04-29，
  
  Published：15 February 2026
- 稿件说明：
移动端阅览
孙亮洁,梁荣健,蒋文涛等.熔盐堆应急排盐冷却系统换热管内层屏障破损传热影响[J].核技术,2026,49(02):020605.

SUN Liangjie,LIANG Rongjian,JIANG Wentao,et al.Effects of bayonet tube leak on the heat transfer characteristics of fuel drain system in molten salt reactor[J].NUCLEAR TECHNIQUES,2026,49(02):020605.
孙亮洁,梁荣健,蒋文涛等.熔盐堆应急排盐冷却系统换热管内层屏障破损传热影响[J].核技术,2026,49(02):020605. DOI： 10.3724/j.0253-3219.2026.hjs.49.250003. CSTR： 32193.14.hjs.CN31-1342/TL.2026.49.250003.

SUN Liangjie,LIANG Rongjian,JIANG Wentao,et al.Effects of bayonet tube leak on the heat transfer characteristics of fuel drain system in molten salt reactor[J].NUCLEAR TECHNIQUES,2026,49(02):020605. DOI： 10.3724/j.0253-3219.2026.hjs.49.250003. CSTR： 32193.14.hjs.CN31-1342/TL.2026.49.250003.

摘要

液体燃料熔盐堆是第四代先进核能系统的候选堆型之一，应急排盐冷却系统是其可设置的特殊安全设计。本文以熔盐实验堆（Molten Salt Reactor Experiment，MSRE）应急排盐冷却系统为研究对象，探究换热元件内层屏障破损对其正常余热导出功能的影响。该研究基于计算流体动力学（Computational Fluid Dynamics，CFD）模拟方法，通过构建传热和多相流动模型分析破损后的传热和流动现象，并对关键影响参数进行敏感性分析。结果表明，内层套管破损后，18.4%的冷却水从破损位置经气隙层流出，单根换热元件功率提升到29.434 kW，破损位置附近外层套管出现局部温度低点。敏感性分析结果表明，破损尺寸、破损位置和气隙层压力变化均会对换热元件传热产生明显影响，其中传热对破损尺寸的敏感性最强。该分析结果可以为熔盐堆应急排盐冷却系统工程设计提供研究数据。

Abstract

Background

The liquid-fueled molten salt reactor (MSR) is one of the candidates for the Generation IV reactor technologies

and the fuel drain system is a special safety design.

Purpose

This study aims to investigate the influence of inner barrier leak of one heat exchange element of MSR on heat transfer characteristics.

Methods

Firstly

the fuel drain system of Molten Salt Reactor Experiment (MSRE) was taken as the research object

and computational fluid dynamics (CFD) simulation methods were employed to construct heat transfer and multiphase flow models to analyze the heat transfer and flow phenomena under normal operation and bayonet tube leak scenario. Then

the sensitivity analyses of key influencing parameters

such as the leak size (3~8 mm)

leak location (10~1 500 mm above the lower end of the heat exchange element) and pressure in the annular gas space (ranging from -13 788 Pa to 13 788 Pa)

were carried out.

Results

The analysis results show that 18.4% of cooling water flows out from the leak location through the annular gas space when bayonet tube leak occurs and the power of one single heat exchange element increases to 29.434 kW. In addition

the lowest abnormal temperature appears in the thimble near the leak location. The sensitivity analysis results present that the heat transfer varies with the leak size

leak location and pressure of annular gas space and is most sensitive to leak size.

Conclusions

These analysis results of this study are valuable to the engineering design of the fuel drain system for MSRs.

关键词

Keywords

references

江绵恒 , 徐洪杰 , 戴志敏 . 未来先进核裂变能: TMSR核能系统 [J ] . 中国科学院院刊 , 2012 , 27 ( 3 ): 366 – 374 .

JIANG Mianheng , XU Hongjie , DAI Zhimin . Advanced fission energy program-TMSR nuclear energy system [J ] . Bulletin of Chinese Academy of Sciences , 2012 , 27 ( 3 ): 366 – 374 .

蔡翔舟 , 戴志敏 , 徐洪杰 . 钍基熔盐堆核能系统 [J ] . 物理 , 2016 , 45 ( 9 ): 578 – 590 . 10.7693/wl20160904 http://dx.doi.org/10.7693/wl20160904

CAI Xiangzhou , DAI Zhimin , XU Hongjie . Thorium molten salt reactor nuclear energy system [J ] . Physics , 2016 , 45 ( 9 ): 578 – 590 . 10.7693/wl20160904 http://dx.doi.org/10.7693/wl20160904

Abram T , Ion S . Generation-IV nuclear power: a review of the state of the science [J ] . Energy Policy , 2008 , 36 ( 12 ): 4323 – 4330 . DOI: 10.1016/j.enpol.2008.09.059 http://dx.doi.org/10.1016/j.enpol.2008.09.059 .

Li G C , Cong P , Yu C G , et al . Optimization of Th-U fuel breeding based on a single-fluid double-zone thorium molten salt reactor [J ] . Progress in Nuclear Energy , 2018 , 108 : 144 – 151 . DOI: 10.1016/j.pnucene.2018.04.017 http://dx.doi.org/10.1016/j.pnucene.2018.04.017 .

房勇汉 , 刘达 , 李林蔚 , 等 . 第四代核能系统发展现状分析与对策建议 [J ] . 产业与科技论坛 , 2022 , 21 ( 23 ): 19 – 20 .

FANG Yonghan , LIU Da , LI Linwei , et al . Analysis of the development status of the fourth generation nuclear energy system and countermeasures and suggestions [J ] . Industrial & Science Tribune , 2022 , 21 ( 23 ): 19 – 20 .

Jiao X , Shao S , Wang K , et al . Functional reliability analysis of a molten salt natural circulation system [J ] . Nuclear Engineering and Design , 2018 , 332 : 127 – 136 . DOI: 10.1016/j.nucengdes.2018.03.024 http://dx.doi.org/10.1016/j.nucengdes.2018.03.024 .

符晓铭 , 王捷 . 高温气冷堆在我国的发展综述 [J ] . 现代电力 , 2006 , 23 ( 5 ): 70 – 75 . DOI: 10.19725/j.cnki.1007-2322.2006.05.011 http://dx.doi.org/10.19725/j.cnki.1007-2322.2006.05.011 .

FU Xiaoming , WANG Jie . Summary of development of high temperature gas cooled reactor in China [J ] . Modern Electric Power , 2006 , 23 ( 5 ): 70 – 75 . DOI: 10.19725/j.cnki.1007-2322.2006.05.011 http://dx.doi.org/10.19725/j.cnki.1007-2322.2006.05.011 .

Liu Y B , Meng X Y , Wang X S , et al . Transient analysis and optimization of passive residual heat removal heat exchanger in advanced nuclear power plant [J ] . Nuclear Science and Techniques , 2022 , 33 ( 8 ): 106 . DOI: 10.1007/s41365-022-01083-1 http://dx.doi.org/10.1007/s41365-022-01083-1 .

梅牡丹 , 周翀 , 傅瑶 , 等 . 熔盐堆下舱室非能动冷却系统的优化设计 [J ] . 核技术 , 2024 , 47 ( 8 ): 080602 . DOI: 10.11889/j.0253-3219.2024.hjs.47.080602 http://dx.doi.org/10.11889/j.0253-3219.2024.hjs.47.080602 .

MEI Mudan , ZHOU Chong , FU Yao , et al . Optimal design of passive cooling system for the reactor lower cavity of molten salt reactor [J ] . Nuclear Techniques , 2024 , 47 ( 8 ): 080602 . DOI: 10.11889/j.0253-3219.2024.hjs.47.080602 http://dx.doi.org/10.11889/j.0253-3219.2024.hjs.47.080602 .

Xu H X , Lin J , Zhong Y J , et al . Characterization of molten 2LiF–BeF 2 salt impregnated into graphite matrix of fuel elements for thorium molten salt reactor [J ] . Nuclear Science and Techniques , 2019 , 30 ( 5 ): 74 . DOI: 10.1007/s41365-019-0600-8 http://dx.doi.org/10.1007/s41365-019-0600-8 .

朱贵凤 , 严睿 , 邹杨 , 等 . 反应堆瞬时短周期与反应性引入速率约束问题研究 [J ] . 核技术 , 2024 , 47 ( 3 ): 030601 . DOI: 10.11889/j.0253-3219.2024.hjs.47.030601 http://dx.doi.org/10.11889/j.0253-3219.2024.hjs.47.030601 .

ZHU Guifeng , YAN Rui , ZOU Yang , et al . Toward the instantaneous short reactor period and rate constraint of reactivity insertion [J ] . Nuclear Techniques , 2024 , 47 ( 3 ): 030601 . DOI: 10.11889/j.0253-3219.2024.hjs.47.030601 http://dx.doi.org/10.11889/j.0253-3219.2024.hjs.47.030601 .

Jiang X Y , Lu H J , Chen Y S , et al . Numerical and experimental investigation of a new conceptual fluoride salt freeze valve for thorium-based molten salt reactor [J ] . Nuclear Science and Techniques , 2020 , 31 ( 2 ): 16 . DOI: 10.1007/s41365-020-0729-5 http://dx.doi.org/10.1007/s41365-020-0729-5 .

Robertson R C . MSRE design and operations report. Part I. Description of reactor design [R ] . Oak Ridge, TN, United States : Oak Ridge National Laboratory (ORNL) , 1965 . 10.2172/4654707 http://dx.doi.org/10.2172/4654707

梁荣健 , 孙亮洁 , 焦小伟 , 等 . 熔盐堆堆芯应急排盐系统可靠性分析及优化 [J ] . 核技术 , 2023 , 46 ( 3 ): 030604 . DOI: 10.11889/j.0253-3219.2023.hjs.46.030604 http://dx.doi.org/10.11889/j.0253-3219.2023.hjs.46.030604 .

LIANG Rongjian , SUN Liangjie , JIAO Xiaowei , et al . Reliability analysis and optimization of core fuel salt emergency drain system for the molten salt reactor experiment [J ] . Nuclear Techniques , 2023 , 46 ( 3 ): 030604 . DOI: 10.11889/j.0253-3219.2023.hjs.46.030604 http://dx.doi.org/10.11889/j.0253-3219.2023.hjs.46.030604 .

Guymon R . MSRE design and operations report. Part VIII. Operating procedures [R ] . Oak Ridge, TN, United States : Oak Ridge National Laboratory (ORNL) , 1966 . 10.2172/4447572 http://dx.doi.org/10.2172/4447572

Scott D , Grindell A G . Components and systems development for molten-salt breeder reactors [R ] . Oak Ridge, TN, United States : Oak Ridge National Laboratory (ORNL) , 1967 . 10.2172/4367859 http://dx.doi.org/10.2172/4367859

Beall S E , Haubenreich P N , Lindauer R B , et al . MSRE design and operations report. Part V. Reactor safety analysis report [R ] . Oak Ridge, TN, United States : Oak Ridge National Laboratory (ORNL) , 1964 .

Ishiguro T , van Rooijen W F G , Shimazu Y , et al . Design of a passive residual heat removal system for the FUJI- 233 Um molten salt reactor system [J ] . Annals of Nuclear Energy , 2014 , 64 : 398 – 407 . DOI: 10.1016/j.anucene.2013.08.037 http://dx.doi.org/10.1016/j.anucene.2013.08.037 .

孙露 , 孙立成 , 阎昌琪 , 等 . 10 MW熔盐堆非能动余热排出系统概念设计 [J ] . 核动力工程 , 2013 , 34 ( 6 ): 107 – 110 . DOI: 10.3969/j.issn.0258-0926.2013.06.025 http://dx.doi.org/10.3969/j.issn.0258-0926.2013.06.025 .

SUN Lu , SUN Licheng , YAN Changqi , et al . Conceptual design of passive residual heat removal system for 10 MW molten salt reactor [J ] . Nuclear Power Engineering , 2013 , 34 ( 6 ): 107 – 110 . DOI: 10.3969/j.issn.0258-0926.2013.06.025 http://dx.doi.org/10.3969/j.issn.0258-0926.2013.06.025 .

孙露 . 熔盐堆非能动余热排出系统设计及排盐罐换热特性 [D ] . 哈尔滨 : 哈尔滨工程大学 , 2015 .

SUN Lu . Design of a passive residual heat removal system for msr and heat transfer characteristics of the fuel drain tank involved [D ] . Harbin : Harbin Engineering University , 2015 .

Chen K L , Meng Z M , Yan C Q , et al . Experimental study on start-up and steady state characteristics of passive residual heat removal system for 2  MW molten salt reactor [J ] . Energy , 2018 , 147 : 826 – 838 . DOI: 10.1016/j.energy.2018.01.057 http://dx.doi.org/10.1016/j.energy.2018.01.057 .

Wu X C , Yan C Q , Meng Z M , et al . Numerical analysis of the passive heat removal system for molten salt reactor at steady state [J ] . Applied Thermal Engineering , 2016 , 102 : 1337 – 1344 . DOI: 10.1016/j.applthermaleng.2016. 03.176 http://dx.doi.org/10.1016/j.applthermaleng.2016.03.176 .

Yang Z H , Meng Z M , Yan C Q , et al . Heat transfer and flow characteristics of a cooling thimble in a molten salt reactor residual heat removal system [J ] . Nuclear Engineering and Technology , 2017 , 49 ( 8 ): 1617 – 1628 . DOI: 10.1016/j.net.2017.07.026 http://dx.doi.org/10.1016/j.net.2017.07.026 .

黄婉珏 , 徐博 , 周翀 , 等 . 373 MW熔盐堆非能动余热排出系统换热元件的优化设计 [J ] . 核技术 , 2019 , 42 ( 7 ): 070602 . DOI: 10.11889/j.0253-3219.2019.hjs.42.070602 http://dx.doi.org/10.11889/j.0253-3219.2019.hjs.42.070602 .

HUANG Wanjue , XU Bo , ZHOU Chong , et al . Optimal design of the bayonet cooling tube in the passive decay heat removal system for the 373 MW molten salt reactor [J ] . Nuclear Techniques , 2019 , 42 ( 7 ): 070602 . DOI: 10.11889/j.0253-3219.2019.hjs.42.070602 http://dx.doi.org/10.11889/j.0253-3219.2019.hjs.42.070602 .

渠鹏荣 , 周翀 , 王纳秀 , 等 . 液态燃料熔盐堆排盐罐非能动余热排出特性研究 [J ] . 核技术 , 2023 , 46 ( 5 ): 050602 . DOI: 10.11889/j.0253-3219.2023.hjs.46.050602 http://dx.doi.org/10.11889/j.0253-3219.2023.hjs.46.050602 .

QU Pengrong , ZHOU Chong , WANG Naxiu , et al . Passive residual heat removal characteristics of liquid fuel molten salt reactor salt drain tank [J ] . Nuclear Techniques , 2023 , 46 ( 5 ): 050602 . DOI: 10.11889/j.0253-3219.2023.hjs.46.050602 http://dx.doi.org/10.11889/j.0253-3219.2023.hjs.46.050602 .

Brackbill J U , Kothe D B , Zemach C . A continuum method for modeling surface tension [J ] . Journal of Computational Physics , 1992 , 100 ( 2 ): 335 – 354 . DOI: 10.1016/0021-9991(92)90240-Y http://dx.doi.org/10.1016/0021-9991(92)90240-Y .

Liu Z , Yu Z Y , Sun W H , et al . Evaluation of several liquid–vapor phase change models for numerical simulation of subcooled flow boiling [J ] . Case Studies in Thermal Engineering , 2023 , 47 : 103057 . DOI: 10.1016/j.csite. 2023.103057 http://dx.doi.org/10.1016/j.csite.2023.103057 .

Thomson G W . The antoine equation for vapor-pressure data [J ] . Chemical Reviews , 1946 , 38 ( 1 ): 1 – 39 . 10.1021/cr60119a001 http://dx.doi.org/10.1021/cr60119a001

Gordon A J , Walton K L , Ghosh T K , et al . Hemispherical total emissivity of Hastelloy N with different surface conditions [J ] . Journal of Nuclear Materials , 2012 , 426 ( 1–3 ): 85 – 95 . DOI: 10.1016/j.jnucmat.2012.03.026 http://dx.doi.org/10.1016/j.jnucmat.2012.03.026 .

Todreas N E , Kazimi M S . Nuclear systems Volume I: Thermal hydraulic fundamentals [M ] . CRC Press , 2021 . 10.1201/9781351030502 http://dx.doi.org/10.1201/9781351030502

何龙 , 余呈刚 , 郭威 , 等 . 外围熔盐层堵塞状态下熔盐堆内部温度分布分析 [J ] . 核技术 , 2018 , 41 ( 5 ): 050601 . DOI: 10.11889/j.0253-3219.2018.hjs.41.050601 http://dx.doi.org/10.11889/j.0253-3219.2018.hjs.41.050601 .

HE Long , YU Chenggang , GUO Wei , et al . The temperature distribution of molten salt reactor under the outer salt layer blocked situation [J ] . Nuclear Techniques , 2018 , 41 ( 5 ): 050601 . DOI: 10.11889/j.0253-3219.2018.hjs.41.050601 http://dx.doi.org/10.11889/j.0253-3219.2018.hjs.41.050601 .

国家能源局. 轻水堆核电厂假想管道破损事故防护设计准则: NB/T 20516—2018 [S ] . 北京 : 原子能出版社 , 2018 .

National Energy Bureau of the People's Republic of China . Design basis for protection of light water nuclear power plants against the effects of postulated pipe rupture: NB/T 20516—2018 [S ] . Beijing : Atomic Energy Press , 2018 .

Views

下载量

CSCD

Alert me when the article has been cited

提交

Tools

Publicity Resources

A prediction model based on LSTM for key parameters of the molten salt-to-air heat exchanger

Prediction of multi-parameters of molten salt reactor based on deep learning methods

Optimization of power control parameters for molten salt reactor based on multi-objective particle swarm optimization algorithm

Comprehensive analysis of CFD application in thermal-hydraulic of Generation IV reactors

Effects of heat exchange element thimble leakage on the thermal transfer characteristics of emergency water-cooled fuel salt drain system of molten salt reactor

Related Author

ZHANG Jinlong

CHENG Maosong

ZUO Xiandi

LI Qiming

DAI Zhimin

WANG Kai

YANG Qun

WANG Naxiu

Related Institution

ShanghaiTech University

College of Nuclear Science and Technology, Harbin Engineering University

School of Energy and Power Engineering, Xi'an Jiaotong University

China Nuclear Power Technology Research Institute

Xiapu Nuclear Power Corporation

AI脑图

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：1035494 Visits Today：44

⁰