High Power Laser and Particle Beams, Volume. 35, Issue 9, 096001(2023)
Influence of wire wrap mixing model on sub-channel analysis of sodium-cooled fast reactor assembly
[3] Chen Xuanxiang, Wu Pan, Shan Jianqiang. Subchannel model of analysis code ATHAS-LMR for LMFBR[J]. Atomic Energy Science and Technology, 46, 695-700(2012).
[5] Wu Zongyun, Liu Tiancai, Wu Mingyu. Development and validation of subchannel analysis program based on two-region model for sodium cooled fast reactor assembly[J]. Atomic Energy Science and Technology, 56, 672-683(2022).
[7] [7] Rowe D S. COBRA IIIC: digital computer program f steady state transient thermalhydraulic analysis of rod bundle nuclear fuel elements[R]. Richl, WA, USA: Battelle Pacific Nthwest Labs. , 1973.
[14] [14] Bogoslovskaya G P, Zhukov A V, Sokin A P. Models acteristics of interchannel exchange in pin bundles cooled by liquid metal[R]. Vienna, Austria: International Atomic Energy Agency, 2000.
[15] [15] Zheng S G. Constitutive crelations f wirewrapped subchannel analysis under fced mixed convection conditions[D]. Cambridge: Massachusetts Institute of Technology, 1984.
[16] [16] Fontana M H, MacPherson R, Gnadt P, et al. Temperature distribution in a 19rod simulated LMFBR fuel assembly in a hexagonal duct (fuel failure mockup bundle 2A): Recd of experimental data[J]. NLTM4113, 1973.
Get Citation
Copy Citation Text
Wentao Fang, Lili Tong, Xuewu Cao. Influence of wire wrap mixing model on sub-channel analysis of sodium-cooled fast reactor assembly[J]. High Power Laser and Particle Beams, 2023, 35(9): 096001
Category: Nuclear Science and Engineering
Received: Mar. 10, 2023
Accepted: Jun. 12, 2023
Published Online: Oct. 17, 2023
The Author Email: Tong Lili (lltong@sjtu.edu.cn)