Three-dimensional Coupled Analysis of Liquid-fuel MSR in Transient State

doi:10.19596/j.cnki.1001-246x.7785

CHINESE JOURNAL OF COMPUTATIONAL PHYSICS ›› 2018, Vol. 35 ›› Issue (6): 649-656.DOI: 10.19596/j.cnki.1001-246x.7785

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Three-dimensional Coupled Analysis of Liquid-fuel MSR in Transient State

ZHOU Jianjun^1,2, MAO Zhangliang¹, SHI Xiaotao², YUAN Xianbao¹, XIAO Renzheng¹, MA Xiaoqiang¹, DU Xiaochao¹

1. College of Mechanical & Power Engineering of China Three Gorges University, Hubei Yichang 443000, China;
2. Engineering Research Center of Eco-environment in Three Gorges Reservoir Region, Ministry of Education, China Three Gorges University, Yichang 443002, China

Received:2017-10-25 Revised:2017-12-05 Online:2018-11-25 Published:2018-11-25

Abstract

Abstract: Considering fuel flow effect of reactor, neutron dynamic model was derived based on particle conservation equation and coupled with flow and heat transfer model. We developed a three-dimensional neutron/thermal-hydraulic coupled code and analyzed psychical property and thermal hydraulic characteristic of MOSART in transient state. It indicates that thermal hydraulic parameters influence greatly to psychical property of the core. Temperature negative feedback of liquid-fuel MSR is obvious.

Key words: molten salt reactor, three-dimensional simulation, coupled neutronics and thermal hydraulics, transient state analysis

CLC Number:

TL33

ZHOU Jianjun, MAO Zhangliang, SHI Xiaotao, YUAN Xianbao, XIAO Renzheng, MA Xiaoqiang, DU Xiaochao. Three-dimensional Coupled Analysis of Liquid-fuel MSR in Transient State[J]. CHINESE JOURNAL OF COMPUTATIONAL PHYSICS, 2018, 35(6): 649-656.

References

[1] KREPEL J, et al. DYN3D-MSR spatial dynamics code for molten salt reactors[J]. Annals of Nuclear Energy, 2007, 34(6):449-462.
[2] 张大林, 秋穗正,刘长亮,等.新概念熔盐堆堆芯稳态热工水力计算[J].工程热物理学报, 2008, 29.
[3] 张大林, 秋穗正,刘长亮,等. 新概念熔盐堆物理计算方法研究及程序设计[J].原子能科学技术, 2008, 42.
[4] ZHANG D L, QIU S Z, SU G H. Development of a steady state analysis code for a molten salt reactor[J].Annals of Nuclear Energy, 2009, 36(5):590-603.
[5] ZHANG D L, QIU S Z, SU G H, et al. Analysis on the neutron kinetics for a molten salt reactor[J]. Progress in Nuclear Energy, 2009, 51(4-5):624-636.
[6] BOGDÁN YAMAJI, D G C, Dr ATTILA ASZÓDI. Three-dimensional numerical investigation of a molten salt peactor concept with the code CFX-5.5[C].Nuclear Energy for New Europe 2002, Kranjska Gora, 2002.
[7] IGNATIEV V, FEYNBERG O, GNIDOI I, et al. Progress in development of Li,Be,Na/F molten salt actinide recycler & transmuter concept[C]. Proceedings of ICAPP 2007, Nice, France, 2007.
[8] IAEA. The basic nuclear data file is avaible on-line at the website[DB/OL]. http://www-nds.iaea.org.
[9] DING Y, WENG P.The compare of three kinds of turbulence model in calculating 3D separating flow of right-angle bend[J].Chinese Journal of Computational Physics, 2003,20(5):386-390.
[10] 陶文铨. 数值传热学[M]. 西安:西安交通大学出版社,2001.
[11] YANG Y. Solution of three-dimensional neutron diffusion equation using SIP and SSIP method[J]. Chinese Journal of Computational Physics,1984, 1(2):152-163.
[12] LV G, SUN S. A finite directional difference meshless method for diffusion equations[J]. Chinese Journal of Computational Physics,2015,32(6):649-661.
[13] TAKEDA T, IKEDA H. 3D neutron transport benchmark[C]. OECD/NEA Committee on Reactor Physics, Suita,Osaka, 1991.
[14] BEYA B B, LILI T. Transient natural convection in 3D tilted enclosure heated from two opposite sides[J]. International Communications in Heat and Mass Transfer, 2009, 36(6):604-613.

Three-dimensional Coupled Analysis of Liquid-fuel MSR in Transient State

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