Multiphysics and multiscale simulation for an experimental sodium-cooled fast reactor

被引:0
|
作者
Lopez-Solis, Roberto [1 ]
Espinosa-Paredes, Gilberto [2 ]
Perez-Valseca, Alejandria D. [2 ]
Cruz-Lopez, Carlos- Antonio [2 ]
机构
[1] Natl Inst Nucl Res, Carr Toluca Mexico s-n, Marquesa 52750, Mexico
[2] Metropolitan Autonomous Univ, Energy Resources Engn Area, Ave San Rafael Atlixco 186, Mexico City 09340, Mexico
关键词
SFR nuclear reactor; Multiscale simulation; Upscaled heat-transfer coefficients; Upscaled Analysis; Multiphysics simulation; CFD Analysis; CODE AZNHEX; VERIFICATION; SYSTEM;
D O I
10.1016/j.nucengdes.2024.113167
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
This work aims to explore a new upscaling methodology to describe heat transfer simultaneously coupled with the neutronic process, in the core of a sodium-cooled reactor. The upscaling method, as demonstrated in this work, allows the development of models that describe reactor-scale phenomena, starting at the scale of a cell, composed of a nuclear fuel pin and liquid metal. In principle, this methodology allows high fidelity in the description of these multiphysics and multiscale phenomena. The main result is the two-upscaled energy no- equilibrium model to describe the temperature distribution of the fuel and coolant. These upscale models are described in terms of the upscaled heat transfer coefficient, which is presented and developed in this work, for the Experimental Sodium-cooled Fast Reactor. The use of the new proposed models/methodology leads good results within lower computational times compared with CFD codes, which is useful when computations have to be done a large number of times, for instance for sensitivity analyses to parameter choices in the conception phase of the reactor, and other applications such as plant analyzers, and for operator training in full-range simulators.
引用
收藏
页数:9
相关论文
共 50 条
  • [41] Calculation studies of coated particles performance in sodium-cooled fast reactor
    Maslov, N., V
    Grishanin, E., I
    Alekseev, P. N.
    KERNTECHNIK, 2021, 86 (01) : 45 - 49
  • [42] Basis of Technical Standard on Fuel for Sodium-Cooled Fast Breeder Reactor
    Nakae, Nobuo
    Baba, Toshikazu
    Kamimura, Katsuichiro
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2011, 48 (04) : 524 - 531
  • [43] A comparative physics study for an innovative sodium-cooled fast reactor (iSFR)
    Hartanto, Donny
    Kim, Chihyung
    Kim, Yonghee
    INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2018, 42 (01) : 151 - 162
  • [44] VENTING DEVICE FOR SODIUM-COOLED FAST CERAMIC REACTOR FUEL ELEMENTS
    GEROSA, A
    MARTINI, M
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1968, 11 (02): : 508 - &
  • [45] Modification and validation of ATHLET code for sodium-cooled fast reactor application
    Zhou, Chong
    Huber, Klaus
    Cheng, Xu
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2013, 47 (11): : 2053 - 2058
  • [46] Basic verification of THACS for sodium-cooled fast reactor system analysis
    Ma, Zaiyong
    Yue, Nina
    Zheng, Meiyin
    Hu, Benxue
    Su, Guanghui
    Qiu, Suizheng
    ANNALS OF NUCLEAR ENERGY, 2015, 76 : 1 - 11
  • [47] Refueling System Reliability Research about Sodium-cooled Fast Reactor
    Yan H.
    Yang H.
    Yang C.
    1600, Atomic Energy Press (55): : 672 - 677
  • [48] Research on Segment Design of Control Rod in Sodium-cooled Fast Reactor
    Xu L.
    Hu Y.
    Zhang J.
    1879, Atomic Energy Press (54): : 1879 - 1884
  • [49] IN-SERVICE INSPECTION OF LOOP SYSTEM SODIUM-COOLED FAST REACTOR
    PICKETT, AG
    HAWKESWO.W
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1970, 13 (01): : 120 - &
  • [50] Reliable leak detection in a heat exchanger of a sodium-cooled fast reactor
    Guepie, Blaise Kevin
    Grall-Maes, Edith
    Beauseroy, Pierre
    Nikiforov, Igor
    Michel, Frederic
    ANNALS OF NUCLEAR ENERGY, 2020, 142 (142)