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Li Kaiwen; Guo Juanjuan; Wang Kan; Liu Shichang, E-mail: wangkan@mail.tsinghua.edu.cn
Proceedings of reactor physics Asia conference 2019 (RPHA19)2020
Proceedings of reactor physics Asia conference 2019 (RPHA19)2020
AbstractAbstract
[en] Internal coupling interface for the CTF Thermal-Hydraulics code developed in the RMC Monte Carlo code has been implemented for multi-physics simulations on nuclear reactors. Fixed-point iteration scheme is utilized to take the Thermal-Hydraulic feedback into account during the neutronic transport calculation in RMC. This paper introduces the scheme of internal coupling, the novel hybrid parallelism method and the validation results based on a simple single fuel pin test case and a checkerboard 2-by-2 assemblies case. The results demonstrated the accuracy and parallel capability of the coupling system. (author)
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Pyeon, Cheol Ho; Yamanaka, Masao (Kyoto University, Institute for Integrated Radiation and Nuclear Science, Kumatori, Osaka (Japan)) (eds.); Ohoka, Yasunori (ed.) (Nuclear Fuel Industries, Ltd., Yokohama, Kanagawa (Japan)); Tsujita, Kosuke (ed.) (Nuclear Engineering, Ltd., Osaka (Japan)); Kyoto University, Institute for Integrated Radiation and Nuclear Science, Kumatori, Osaka (Japan); [321 p.]; Nov 2020; p. 308-311; RPHA19: Reactor physics Asia conference 2019; Osaka (Japan); 2-3 Dec 2019; Also available from https://www.rri.kyoto-u.ac.jp/PUB/report/09_kurns/temp/kurns-ekr-005.pdf; 17 refs., 4 figs., 2 tabs.
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