THERMAL-HYDRAULIC ANALYSIS OF THE 1ST 16 HOURS OF THE TMI-2 ACCIDENT

被引:0
|
作者
COLE, RK
BASKES, MI
RUMBLE, ET
机构
[1] SANDIA LABS, LIVERMORE, CA 94550 USA
[2] SCI APPLICAT INC, PALO ALTO, CA 94303 USA
[3] SANDIA LABS, ALBUQUERQUE, NM 87115 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:562 / 563
页数:2
相关论文
共 50 条
  • [31] THERMAL-HYDRAULIC ANALYSIS OF LOW-ACTIVITY 1ST-WALL AND BLANKET DESIGNS FOR VARIOUS WALL LOADINGS
    BENENATI, RF
    POWELL, JR
    YU, WS
    LAZARETH, OW
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1976, 24 (NOV19): : 43 - 44
  • [32] A STUDY OF THE SENSITIVITY OF PWR CORE THERMAL-HYDRAULIC ANALYSIS FOR THE BLOWDOWN PHASE OF A LOSS-OF-COOLANT ACCIDENT .1. METHODS AND RESULTS OF ANALYSIS
    MISAK, J
    BAZSO, Z
    ZEISLER, P
    KERNENERGIE, 1985, 28 (03): : 113 - 118
  • [33] Thermal-hydraulic analyses of a steam generator tube rupture accident for the Kori Nuclear Unit 1 pressurized thermal shock study
    Hong, SJ
    Kim, JH
    Kim, YS
    Park, GC
    NUCLEAR TECHNOLOGY, 2002, 138 (03) : 273 - 283
  • [34] Transient thermal-hydraulic analysis for fuel assembly blockage accident by coupling CFD code with the neutron kinetics model
    Wang, Lizhi
    Jin, Ming
    Wang, Lei
    Zhang, Guangyu
    Wu, Guowei
    ANNALS OF NUCLEAR ENERGY, 2020, 137
  • [35] EVALUATION OF THE THERMAL-HYDRAULIC AND FUEL-ROD THERMAL AND MECHANICAL DEFORMATION-BEHAVIOR DURING THE 1ST POWER BURST FACILITY NUCLEAR BLOWDOWN TESTS
    MACDONALD, PE
    BROUGHTON, JM
    SPORE, JW
    NUCLEAR TECHNOLOGY, 1979, 44 (03) : 401 - 410
  • [36] Design and thermal-hydraulic analysis of PFC baking for SST-1 Tokamak
    Chaudhuri, P
    Reddy, DC
    Khirwadkar, S
    Prakash, NR
    Santra, P
    Saxena, YC
    FUSION ENGINEERING AND DESIGN, 2001, 55 (04) : 521 - 534
  • [37] RESEARCH OF SEAWATER EFFECTS ON THERMAL-HYDRAULIC BEHAVIOR AT SEVERE ACCIDENT (1) RESEARCH PLAN AND RESULTS OF PRELIMINARY EXPERIMENTS
    Liu, Wei
    Nagatake, Taku
    Takase, Kazuyuki
    Yoshida, Hiroyuki
    Nagase, Fumihisa
    PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 4, 2014,
  • [38] Transient thermal-hydraulic analysis of complete single channel blockage accident of generic 10 MW research reactor
    Son, Hyung Min
    Yang, Soo Hyung
    Park, Cheol
    Lee, Byung Chul
    ANNALS OF NUCLEAR ENERGY, 2015, 75 : 44 - 53
  • [39] RATT-1 CODE FOR THERMAL-HYDRAULIC ANALYSIS OF POWER CHANNEL BLOWDOWN
    MARTINI, R
    PIERINI, GC
    SANDRI, C
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1976, 23 (JUN18): : 288 - 290
  • [40] THERMAL-HYDRAULIC ANALYSIS OF FIRST SEMISCALE MOD-1 TEST SERIES
    MECHAM, DC
    CARTMILL, CE
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1975, 21 (JUN): : 339 - 340