ASSESSMENT OF THE RELAP4-MOD6 REACTOR TRANSIENT THERMAL-HYDRAULIC CODE

被引:0
|
作者
HAIGH, WS [1 ]
CHARLTON, TR [1 ]
DEARIEN, JA [1 ]
机构
[1] EG&G IDAHO INC, IDAHO FALLS, ID 83401 USA
来源
关键词
D O I
暂无
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
引用
收藏
页码:493 / 494
页数:2
相关论文
共 50 条
  • [21] Development and validation of a thermal hydraulic transient analysis code for offshore floating nuclear reactor based on RELAP5/SCDAPSIM/MOD3.4
    Cheng, Kun
    Meng, Tao
    Zhao, Fulong
    Tan, Sichao
    ANNALS OF NUCLEAR ENERGY, 2019, 127 : 215 - 226
  • [22] Thermal hydraulic analysis of Syrian MNSR research reactor using RELAP5/Mod3.2 code
    Omar, H.
    Ghazi, N.
    Alhabit, F.
    Hainoun, A.
    ANNALS OF NUCLEAR ENERGY, 2010, 37 (04) : 572 - 581
  • [23] Transient thermal-hydraulic analysis of a space thermionic reactor
    Zhang, Wenwen
    Ma, Zaiyong
    Zhang, Dalin
    Tian, Wenxi
    Qiu, Suizheng
    Su, G. H.
    ANNALS OF NUCLEAR ENERGY, 2016, 89 : 38 - 49
  • [24] Development and validation of transient thermal-hydraulic evaluation code for a lead-based fast reactor
    Wei, Shiying
    Ma, Weimin
    Wang, Chenglong
    Chen, Ronghua
    Tian, Wenxi
    Qiu, Suizheng
    Su, G. H.
    INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2021, 45 (08) : 12215 - 12233
  • [25] TEST PREDICTION FOR THE GERMAN PKL TEST K5A USING RELAP4-MOD6
    CHEN, YS
    HAIGH, WS
    SULLIVAN, LH
    FISCHER, SR
    NUCLEAR TECHNOLOGY, 1979, 46 (02) : 199 - 204
  • [26] Development and Validation of Multiscale Coupled Thermal-Hydraulic Code Combining RELAP5 and Fluent Code
    Sun, Lin
    Peng, Minjun
    Xia, Genglei
    Wang, Xuesong
    Wu, Mingyu
    FRONTIERS IN ENERGY RESEARCH, 2021, 8
  • [27] COTRAN - A COUPLED NEUTRONIC AND THERMAL-HYDRAULIC TRANSIENT ANALYSIS CODE
    PRUITT, DW
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1982, 41 : 602 - 603
  • [28] DEVELOPMENT OF A THERMAL-HYDRAULIC ANALYSIS CODE AND TRANSIENT ANALYSIS FOR A FHTR
    Xiao, Yao
    Hu, Lin-wen
    Qiu, Suizheng
    Zhang, Dalin
    Su, Guanghui
    Tian, Wenxi
    PROCEEDINGS OF THE 22ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2014, VOL 5, 2014,
  • [29] A RELAP5 MODEL FOR THE THERMAL-HYDRAULIC ANALYSIS OF A TYPICAL PRESSURIZED WATER REACTOR
    Agamy, Said
    Metwally, Adul Mohsen
    Al-Ramady, Amir Mohammad
    Elaraby, Sayed Mohamed
    THERMAL SCIENCE, 2010, 14 (01): : 79 - 88
  • [30] USER EFFECTS ON THE THERMAL-HYDRAULIC TRANSIENT SYSTEM CODE CALCULATIONS
    AKSAN, SN
    DAURIA, F
    STADTKE, H
    NUCLEAR ENGINEERING AND DESIGN, 1993, 145 (1-2) : 159 - 174