Research on Simulation Approach of Inter-wrapper Flow in Liquid Metal Cooled Fast Reactor Based on Subchannel Method

Liang Yu; Wang Xiaoyu; Deng Jian; Liu Yu; Song Gongle; Zhong Ruicheng; Zhang Dalin; Zhu Dahuan

doi:10.13832/j.jnpe.2023.S2.0061

Volume 44 Issue S2

Dec. 2023

Turn off MathJax

Article Contents

Article Navigation > Nuclear Power Engineering > 2023 > 44(S2): 61-66

Liang Yu, Wang Xiaoyu, Deng Jian, Liu Yu, Song Gongle, Zhong Ruicheng, Zhang Dalin, Zhu Dahuan. Research on Simulation Approach of Inter-wrapper Flow in Liquid Metal Cooled Fast Reactor Based on Subchannel Method[J]. Nuclear Power Engineering, 2023, 44(S2): 61-66. doi: 10.13832/j.jnpe.2023.S2.0061

Citation:

Liang Yu, Wang Xiaoyu, Deng Jian, Liu Yu, Song Gongle, Zhong Ruicheng, Zhang Dalin, Zhu Dahuan. Research on Simulation Approach of Inter-wrapper Flow in Liquid Metal Cooled Fast Reactor Based on Subchannel Method[J]. Nuclear Power Engineering, 2023, 44(S2): 61-66. doi: 10.13832/j.jnpe.2023.S2.0061

Citation:

Liang Yu, Wang Xiaoyu, Deng Jian, Liu Yu, Song Gongle, Zhong Ruicheng, Zhang Dalin, Zhu Dahuan. Research on Simulation Approach of Inter-wrapper Flow in Liquid Metal Cooled Fast Reactor Based on Subchannel Method[J]. Nuclear Power Engineering, 2023, 44(S2): 61-66. doi: 10.13832/j.jnpe.2023.S2.0061

PDF( 15766 KB)

Research on Simulation Approach of Inter-wrapper Flow in Liquid Metal Cooled Fast Reactor Based on Subchannel Method

doi: 10.13832/j.jnpe.2023.S2.0061

Liang Yu^{1, 2
,},
Wang Xiaoyu^{1, 2},
Deng Jian^{1, 2},
Liu Yu^{1, 2},
Song Gongle^{1, 2},
Zhong Ruicheng^{1, 2},
Zhang Dalin³,
Zhu Dahuan^{1, 2}

1.
Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China
2.
Nuclear Power Institute of China, Chengdu, 610213, China
3.
School of Nuclear Science and Technology,Xi'an Jiaotong University, Xi'an, 710049, China

Received Date: 2023-07-11
Rev Recd Date: 2023-08-17
Publish Date: 2023-12-30

Abstract

Abstract

In order to explore the conjugate heat transfer effect of the coolant between the assmblies and inter-wrapper channels, the subchannel method is applied to provide a new simulation approach for the inter-wrapper flow (IWF). The subchannel model of IWF is solved based on the stable and efficient SIMPLE algorithm to address the issue that the classical subchannel algorithm is difficult to converge in the face of low flow, reverse flow and backflow phenomena. Through the 3-subassembly test using sodium working fluid (CCTL-CFR), the reliability of the subchannel simulation method for IWF is demonstrated by comparing the temperatures of the coolant and wall. Taking the typical liquid metal cooled fast reactor as the object, the thermal-hydraulic analysis of the full core is conducted. It is found that IWF can greatly flatten the radial temperature distribution of the core and reduce the temperature peak value, which proves the necessity of considering the effect of IWF in thermal-hydraulic analysis. This study provides a feasible analysis method for the thermal and safety analysis of liquid metal cooled fast reactors.
- Liquid metal cooled fast reactor,
- Inter-wrapper flow (IWF),
- Subchannel anslysis,
- SIMPLE algorithm

FullText(HTML)

References(10)

References

[1]	NISHIMURA M, OHSHIMA H, KAMIDE H. Fast reactor core thermal-hydraulic analyses during transition from forced to natural circulation: IAEA-TECDOC-1157[R]. Vienna: International Atomic Energy Agency, 2000.
[2]	YUE N N, ZHANG D L, CHEN J, et al. The development and validation of the inter-wrapper flow model in sodium-cooled fast reactors[J]. Progress in Nuclear Energy, 2018, 108: 54-65. doi: 10.1016/j.pnucene.2018.05.007
[3]	LODI F, GRASSO G, MATTIOLI D, et al. ANTEO+: a subchannel code for thermal-hydraulic analysis of liquid metal cooled systems[J]. Nuclear Engineering and Design, 2016, 301: 128-152. doi: 10.1016/j.nucengdes.2016.03.001
[4]	KIM W S, KIM Y G, KIM Y J. A subchannel analysis code MATRA-LMR for wire wrapped LMR subassembly[J]. Annals of Nuclear Energy, 2002, 29(3): 303-321. doi: 10.1016/S0306-4549(01)00041-X
[5]	PARTHASARATHY U, SUNDARARAJAN T, BALAJI C, et al. Decay heat removal in pool type fast reactor using passive systems[J]. Nuclear Engineering and Design, 2012, 250: 480-499. doi: 10.1016/j.nucengdes.2012.05.014
[6]	VELUSAMY K, CHELLAPANDI P, CHETAL S C, et al. Overview of pool hydraulic design of Indian prototype fast breeder reactor[J]. Sadhana, 2010, 35(2): 97-128. doi: 10.1007/s12046-010-0022-0
[7]	LIANG Y, CHEN Y T, ZHANG D L, et al. Experimental and numerical investigation on flow characteristics of inter-wrapper channel in LMFBR[J]. Annals of Nuclear Energy, 2021, 151: 107918. doi: 10.1016/j.anucene.2020.107918
[8]	邱仁森. 钠技术和液金属钠回路[M]. 北京: 科学出版社,1987.
[9]	KAMIDE H. Investigation on thermal hydraulics phenomena in a sodium-cooled fast reactor core during natural circulation decay heat removals[D]. Tokyo: Tokyo Institute of Technology, 2010.
[10]	薛秀丽. 中国实验快堆堆芯出口区域温度分布研究[D]. 北京: 中国原子能科学研究院,2006.