Transient analysis with 1-GW solid fuel molten salt reactor

Jie ZHANG; Minghai LI; Long HE; Yang YANG; Ye DAI; Xiangzhou CAI

doi:10.11889/j.0253-3219.2016.hjs.39.100605

您当前的位置：

首页 >

文章列表页 >

Transient analysis with 1-GW solid fuel molten salt reactor

Nuclear Energy Science and Engineering | 更新时间：2021-05-24

- Transient analysis with 1-GW solid fuel molten salt reactor
- NUCLEAR TECHNIQUES Vol. 39, Issue 10, Article number: 100605(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.39.100605
  CLC： TL362
- Received：15 June 2016，
  
  Revised：29 June 2016，
  
  Published：2016-10
- 稿件说明：
移动端阅览
Jie ZHANG, Minghai LI, Long HE, et al. Transient analysis with 1-GW solid fuel molten salt reactor[J]. Nuclear techniques, 2016, 39(10): 100605
DOI：

Jie ZHANG, Minghai LI, Long HE, et al. Transient analysis with 1-GW solid fuel molten salt reactor[J]. Nuclear techniques, 2016, 39(10): 100605 DOI： 10.11889/j.0253-3219.2016.hjs.39.100605.

摘要

钍基熔盐堆（Thorium-based Molten Salt Reactor，TMSR）作为一种新的堆型，具有独特的安全与运行特性。研究其热工水力特性，对其进行瞬态分析，将有助于深刻理解该反应堆。本文介绍了1 GW固态熔盐堆的堆芯设计方案，并描述了用于瞬态分析的详细程序结构。其中，利用RELAP5对其热工水力模型进行模拟；利用Simulink对其控制系统模型进行模拟。通过预期运行瞬态，例如功率降低、堆芯反应性引入、二回路温度变化等工况显示了其运行特性，并验证了控制系统可以使反应堆达到安全稳定状态，而不触发保护系统动作。

Abstract

Background

As a new type of reactor

thorium-based molten salt reactor (TMSR) has unique safety and operation characteristics. Its thermal-hydraulic features are enormously different from other reactors

thus worth doing transient analysis.

Purpose

This study aims at disturbed transient analysis of TMSR for fundamental comprehension of its safety and operation characteristics.

Methods

The structure and design scheme of the core of 1-GW solid fuel thorium-based molten salt reactor (TMSR-SF) have been presented. Structural emulation platform for transient analysis is proposed with the thermo-hydraulic model being developed on the basis of RELAP5

and the control system model being constructed by using the MATLAB/Simulink software.

Results

The results of emulation test for operational transient

such as rapid power reduction

step load reducing

linear load reducing and temperature of secondary loop inlet reducing show that the reactor control system is effective to bring the reactor into a safe and steady state without actuation of reactor protection system.

Conclusion

Analysis results show that the design satisfied the requirements of 1-GW TMSR-SF operational transient. It also indicates that the platform can perfectly simulate the variable power transient conditions.

关键词

Keywords

references

Yang Y, Fu Y, Zou Y, et al. Reactivity-insertion-transient analysis of a fluoride salt cooled high temperature reactor[C]. International Topical Meeting on Advances in Reactor Physics (PHYSOR 2014), Kyoto, 2014

Li M H, Zhang J, Zou Y, et al. Disturbed transient analysis with stable operation mode of TMSR-SF1[C]. 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16), Chicago, 2015:6959

汪全全 , 尹聪聪 , 孙雪静 , . TMSR核功率控制系统的PID设计与仿真 . 核技术 , 2015 . 38 ( 2 ): 020601 DOI: 10.11889/j.0253-3219.2015.hjs.38.020601 http://doi.org/10.11889/j.0253-3219.2015.hjs.38.020601 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract359.shtml .

Quanquan WANG , Congcong YIN , Xuejing SUN , . PID design and simulation of TMSR nuclear power control system . Nuclear Techniques , 2015 . 38 ( 2 ): 020601 DOI: 10.11889/j.0253-3219.2015.hjs.38.020601 http://doi.org/10.11889/j.0253-3219.2015.hjs.38.020601 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract359.shtml .

C C Yin , N Zhang , Y P Li , . The design of RMT-based IOC redundancy at RCPI experimental platform in TMSR . Nuclear Science and Techniques , 2014 . 25 ( 6 ): 060402 DOI: 10.13538/j.1001-8042/nst.25.060402 http://doi.org/10.13538/j.1001-8042/nst.25.060402 .

林萌 , 杨燕华 , 胡锐 , . RELAP5作为核电站模拟器热工水力系统程序的改造 . 核动力工程 , 2005 . 26 ( 2 ): 125 - 129 . http://www.cnki.com.cn/Article/CJFDTOTAL-HDLG200502006.htm .

Meng LIN , Yanhua YANG , Rui HU , . Renovation of RELAP5 as thermal-hydraulic system code for simulator in nuclear power plant . Nuclear Power Engineering , 2005 . 26 ( 2 ): 125 - 129 . http://www.cnki.com.cn/Article/CJFDTOTAL-HDLG200502006.htm .

侯东 , 林萌 , 许志红 , . 用Simulink扩展RELAP5的控制与保护系统仿真功能 . 核动力工程 , 2007 . 28 ( 6 ): 112 - 116 . http://www.cnki.com.cn/Article/CJFDTOTAL-HDLG200706027.htm .

Dong HOU , Meng LIN , Zhihong XU , . Expansion of RELAP5 control and protection simulation functions with Simulink . Nuclear Power Engineering , 2007 . 28 ( 6 ): 112 - 116 . http://www.cnki.com.cn/Article/CJFDTOTAL-HDLG200706027.htm .

林桦 , 林萌 , 侯东 , . 反应堆功率控制系统的建模及闭环验证 . 核动力工程 , 2009 . 30 ( 4 ): 96 - 99 . http://www.cnki.com.cn/Article/CJFDTOTAL-HDLG200904024.htm .

Hua LIN , Meng LIN , Dong HOU , . Modeling of reactor power control system and closed loop verification . Nuclear Power Engineering , 2009 . 30 ( 4 ): 96 - 99 . http://www.cnki.com.cn/Article/CJFDTOTAL-HDLG200904024.htm .

戴叶. 1000 MW固体燃料规则球床熔盐堆初步物理设计报告[R].上海:中国科学院上海应用物理研究所, 2013

DAI Ye. 1000 MW ordered bed fluoride-salt-cooled high-temperature reactor concept[R]. Shanghai:Shanghai Institute of Applied Physics, Chinese Academy of Sciences, 2013

龚湛 , 林萌 , 刘鹏飞 , . AP1000核电站仿真分析平台的研发 . 热力发电 , 2012 . 41 ( 3 ): 32 - 36 . http://www.cnki.com.cn/Article/CJFDTOTAL-RLFD201203010.htm .

Zhan GONG , Meng LIN , Pengfei LIU , . Development of emulation analysis platform for AP1000 nuclear power plant . Thermal Power Generation , 2012 . 41 ( 3 ): 32 - 36 . http://www.cnki.com.cn/Article/CJFDTOTAL-RLFD201203010.htm .

刘立欣 , 郑利民 , 周全福 . AP1000核电厂典型的运行瞬态分析 . 核技术 , 2012 . 35 ( 11 ): 869 - 876 . http://www.cnki.com.cn/Article/CJFDTOTAL-HJSU201211015.htm .

Lixin LIU , Limin ZHENG , Quanfu ZHOU . Preliminary study on operational transient analysis for AP1000 . Nuclear Techniques , 2012 . 35 ( 11 ): 869 - 876 . http://www.cnki.com.cn/Article/CJFDTOTAL-HJSU201211015.htm .

Views

下载量

CSCD

Alert me when the article has been cited

提交

Tools

Publicity Resources

Applicability of secondary-developed RELAP5 code for PRS operation analysis under inclined conditions

Development and analysis of passive residual heat-removal system on secondary side of small reactor

Development and validation of real-time modeling and simulation platform for molten salt reactor based on EPICS framework

Accident analyses of station blackout for TMSR-SF2

Super homogenization method applied in diffusion calculation for pebble-bed fluoride-salt-cooled high-temperature reac

Related Author

ZHANG Hao

YU Qiao

SUN Yan

XU Huitian

WANG Yu

LIANG Tiebo

WANG Tao

ZHAO Jing

Related Institution

No. Unit of PLA

Nuclear Power Institute of China

School of Mechanical Engineering, Shanghai Jiao Tong University

College of Smart Energy, Shanghai Jiao Tong University

Shanghai Institute of Applied Physics, Chinese Academy of Sciences

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：881246 Visits Today：773

⁰