Development and validation of PCS heat transfer model in severe accident code

被引：0
|
作者：
Yang, Xiaoming [1 ]
Li, He [1 ]
Liu, Jiebin [1 ]
Ma, Rubing [1 ]
Yuan, Yidan [1 ]
机构：
[1] CNNC Key Laboratory on Severe Accident in Nuclear Power Safety, China Nuclear Power Engineering Co., Ltd., Beijing,100840, China
来源：
Harbin Gongcheng Daxue Xuebao/Journal of Harbin Engineering University | 2023年 / 44卷 / 07期
关键词：
Compilation and indexing terms; Copyright 2024 Elsevier Inc;
D O I：
暂无
中图分类号：
学科分类号：
摘要：
Accidents - Codes (symbols) - Heat convection
引用
收藏
页码：1131 / 1136
相关论文
共 50 条
  • [21] Validation of Fuel-Coolant Interaction Model for Severe Accident Simulations
    Melikhov, Vladimir
    Melikhov, Oleg
    Yakush, Sergey
    Rtishchev, Nikita
    SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2011, 2011
  • [22] Improvement and validation of the heat transfer model for the containment module in the RCS-containment integral system code
    Ge, Li
    Yang, Zijiang
    Li, Huaqi
    Shan, Jianqiang
    ANNALS OF NUCLEAR ENERGY, 2020, 144
  • [23] Extension of droplet/aerosol heat transfer model coupling Lagrangian approach in containment atmosphere under severe accident
    Wang, Fangnian
    Xiao, Jianjun
    Jordan, Thomas
    ANNALS OF NUCLEAR ENERGY, 2023, 193
  • [24] Severe accident code-to-code comparison for two accident scenarios in a spent fuel pool
    Coindreau, O.
    Jackel, B.
    Rocchi, F.
    Alcaro, F.
    Angelova, D.
    Bandini, G.
    Barnak, M.
    Behler, M.
    Da Cruz, D. F.
    Dagan, R.
    Drai, P.
    Ederli, S.
    Herranz, L. E.
    Hollands, T.
    Horvath, G.
    Kaliatka, A.
    Kljenak, I.
    Kotsuba, O.
    Lind, T.
    Lopez, C.
    Mancheva, K.
    Matejovic, R.
    Matkovic, M.
    Steinbrueck, M.
    Stempniewicz, M.
    Thomas, R.
    Vileiniskis, V.
    Visser, D. C.
    Vokac, P.
    Vorobyov, Y.
    Zhabin, O.
    ANNALS OF NUCLEAR ENERGY, 2018, 120 : 880 - 887
  • [25] THE ASTEC INTEGRAL CODE FOR SEVERE ACCIDENT SIMULATION
    Van Dorsselaere, J. P.
    Seropian, C.
    Chatelard, P.
    Jacq, F.
    Fleurot, J.
    Giordano, P.
    NUCLEAR TECHNOLOGY, 2009, 165 (03) : 293 - 307
  • [26] Code assessment in context of severe accident phenomenology
    Bratfisch, C.
    Agethen, K.
    Braehler, T.
    Risken, I.
    Koppers, V.
    Gremme, F.
    Hoffmann, M.
    Koch, M. K.
    ATW-INTERNATIONAL JOURNAL FOR NUCLEAR POWER, 2014, 59 (05): : 294 - +
  • [27] A RADIATION HEAT-TRANSFER MODEL FOR THE SCDAP CODE
    SOHAL, MS
    NUCLEAR TECHNOLOGY, 1986, 75 (02) : 196 - 204
  • [28] The code development and thermo-hydrodynamic analysis of the reflood during severe accident in PWR
    Niu, S. P.
    Zhang, Y. P.
    Tian, W. X.
    Qiu, S. Z.
    Su, G. H.
    ANNALS OF NUCLEAR ENERGY, 2017, 99 : 9 - 18
  • [29] Development and validation of the eutectic reaction model in JUPITER code
    Chai, Penghui
    Yamashita, Susumu
    Yoshida, Hiroyuki
    ANNALS OF NUCLEAR ENERGY, 2020, 145
  • [30] Development and Application of an Aerosol Model Under a Severe Nuclear Accident
    Yuan, Xianbao
    Wei, Jingyu
    Zhang, Binhang
    Guo, Yuefeng
    Shi, Qiang
    Guo, Pan
    Yang, Senquan
    Tan, Chao
    FRONTIERS IN ENERGY RESEARCH, 2022, 10
12345