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Review of sub-channel code development for pressurized water reactor and introduction of CORTH-V2.0 sub-channel code
Progress in Nuclear Energy ( IF 2.7 ) Pub Date : 2020-07-01 , DOI: 10.1016/j.pnucene.2020.103373
Jian Deng , Qi Lu , Yu Liu , Xiaoyu Wang , Xiaolei Yang , Yong Zhang , Jibin Zhang

Abstract In this paper, the development process of sub-channel code was described in detail, and some widely approved sub-channel codes were comprehensively reviewed, such as COBRA, FLICA, CORTH, and ASSERT applying to the commercial nuclear power plants. Moreover, the development of conservation equations and the corresponding constitutive equations were introduced, including the heat conduction model, the heat transfer model, the mixing model, and CHF (Critical Heat Flux) model. Finally, CORTH-V2.0 sub-channel code was introduced, which was autonomously developed by Nuclear Power Institute of China (NPIC) and served for ACP series PWR (Pressurized Water Reactor) as well as CF series fuel assembly.
更新日期:2020-07-01
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