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Hybrid medium model for conjugate heat transfer modeling in the core of sodium-cooled fast reactor
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Liang, Yu
Zhang, Yapei
Zhang, Dalin
Wang, X.A.
Wang, Shibao
Wang, Mingjun
Tian, Wenxi
Su, G.H.
Song, Ping
Qiu, Suizheng
Korean Nuclear Society[2020]
Google Scholar네이버 전문정보
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Prediction of dryout-type CHF for rod bundle in natural circulation loop under motion condition
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Chen, Ronghua
Yue, Nina
Xi, Mengmeng
Wang, Xiaoyang
Tian, Wenxi
Su, G.H.
Qiu, Suizheng
Huang, Siyang
Korean Nuclear Society[2020]
Google Scholar네이버 전문정보
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Thermal-hydraulic analysis of a new conceptual heat pipe cooled small nuclear reactor system
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Qiu, Suizheng
Wang, Chenglong
Tian, Wenxi
Tang, Simiao
Sun, Hao
Su, Guanghui
Korean Nuclear Society[2020]
Google Scholar네이버 전문정보
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Assessment of ECCMIX component in RELAP5 based on ECCS experiment
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Chen, Guo
Zhang, Dalin
Tian, Wenxi
Su, G.H.
Song, Gongle
Qiu, Suizheng
Korean Nuclear Society[2020]
Google Scholar네이버 전문정보
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PIV measurement and numerical investigation on flow characteristics of simulated fast reactor fuel subassembly
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Ju, Haoran
Zhang, Dalin
Zhang, Cheng
Xu, Yijun
Wu, Yingwei
Wu, Shuijin
Su, G.H.
Qiu, Suizheng
한국원자력학회[2020]
Google Scholar네이버 전문정보
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Performance analysis of automatic depressurization system in advanced PWR during a typical SBLOCA transient using MIDAC
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Qiu, Suizheng
Zhang, Yapei
Tian, Wenxi
Sun, Hongping
Su, Guanghui
Korean Nuclear Society[2020]
Google Scholar네이버 전문정보
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