SENSITIVITY ANALYSIS OF THERMAL HYDRAULIC RESPONSE IN CONTAINMENT AT CORE MELTDOWN ACCIDENT.

被引：0
|
作者：
Kobayashi, Kensuke [1 ]
Horii, Hideo [1 ]
Ishigami, Tsutomu [1 ]
Chiba, Takemi [1 ]
机构：
[1] Japan Atomic Energy Research Inst, Jpn, Japan Atomic Energy Research Inst, Jpn
来源：
Nippon Genshiryoku Gakkaishi/Journal of the Atomic Energy Society of Japan | 1985年 / 27卷 / 01期
关键词：
D O I：
暂无
中图分类号：
学科分类号：
摘要：
11
引用
收藏
页码：56 / 65
相关论文
共 50 条
  • [31] SENSITIVITY STUDY ON CORE HEATUP AND MELTDOWN BY VARIATION OF HEAT-CONDUCTIVITY AND THERMAL EMISSIVITY
    KORBER, H
    UNGER, HE
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1974, 18 (JUN23): : 234 - 235
  • [32] Uncertainty and Sensitivity Analysis of the Generic Containment SB-LOCA Accident
    Povilaitis, Mantas
    Urbonavicius, Egidijus
    Kelm, Stephan
    24TH INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE, (NENE 2015), 2015,
  • [33] Thermal-hydraulic and aerosol containment phenomena modelling in ASTEC severe accident computer code
    Kljenak, Ivo
    Dapper, Maik
    Dienstbier, Jiri
    Herranz, Luis E.
    Koch, Marco K.
    Fontanet, Joan
    NUCLEAR ENGINEERING AND DESIGN, 2010, 240 (03) : 656 - 667
  • [34] PWR CORE RESPONSE FOR A STEAMLINE BREAK ACCIDENT - SENSITIVITY STUDIES
    KERN, RC
    ELZEFTAWY, MM
    SALAH, S
    NORIAN, PE
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1980, 34 (JUN): : 496 - 498
  • [35] Verification calculation of multinode containment thermal hydraulic analysis code
    Sun Y.
    Zheng Y.
    Wang D.
    Chen Q.
    Harbin Gongcheng Daxue Xuebao/Journal of Harbin Engineering University, 2023, 44 (07): : 1144 - 1149
  • [36] Creep Analysis of Reactor Pressure Vessel Lower Head under Core Meltdown Severe Accident
    Luo J.
    Luo J.
    Li P.
    Sun L.
    Tang P.
    Hedongli Gongcheng/Nuclear Power Engineering, 2019, 40 (02): : 37 - 41
  • [37] AN ANALYSIS OF CONTAINMENT FAILURE BY A STEAM EXPLOSION FOLLOWING A POSTULATED CORE MELTDOWN IN A LIGHT WATER-REACTOR
    CORRADINI, ML
    SWENSON, DV
    WOODFIN, RL
    VOELKER, LE
    NUCLEAR ENGINEERING AND DESIGN, 1981, 66 (02) : 287 - 298
  • [38] Coupling characteristics of thermal-hydraulic power and passive a containment heat removal system in a containment vessel during the loss of coolant accident
    Chu W.
    Cong J.
    Li W.
    Zhang N.
    Meng Z.
    Harbin Gongcheng Daxue Xuebao/Journal of Harbin Engineering University, 2023, 44 (07): : 1104 - 1111
  • [39] THERMAL HYDRAULIC ANALYSIS OF A SCWR CORE CONCEPT
    Zhang, Weizhong
    PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 2, 2014,
  • [40] BWR core thermal-hydraulic uncertainty and sensitivity analysis with improved bypass modeling features
    Ziyad, Devshibhai
    Abarca, Agustin
    Avramova, Maria
    NUCLEAR ENGINEERING AND DESIGN, 2025, 435
12345