MODCIR - A 3-DIMENSIONAL TRANSIENT CODE USED IN THERMAL-HYDRAULIC ANALYSES OF CANDU POWER-REACTORS

被引：0
|
作者：
AUSTMAN, G [1 ]
SZYMANSKI, J [1 ]
MIDVIDY, WI [1 ]
机构：
[1] ONTARIO HYDRO,DEPT NUCL STUDIES & SAFETY,TORONTO,ONTARIO,CANADA
来源：
MATHEMATICS AND COMPUTERS IN SIMULATION | 1983年 / 25卷 / 06期
关键词：
D O I：
10.1016/0378-4754(83)90118-0
中图分类号：
TP39 [计算机的应用];
学科分类号：
081203 ; 0835 ;
摘要：
引用
收藏
页码：493 / 496
页数：4
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    [J]. JADERNA ENERGIE, 1982, 28 (03): : 116 - &
  • [2] THE THYC 3-DIMENSIONAL THERMAL-HYDRAULIC CODE FOR ROD BUNDLES - RECENT DEVELOPMENTS AND VALIDATION TESTS
    AUBRY, S
    CAREMOLI, C
    OLIVE, J
    RASCLE, P
    [J]. NUCLEAR TECHNOLOGY, 1995, 112 (03) : 331 - 345
  • [3] A TEST PROGRAM ON THERMOMECHANICAL AND THERMAL-HYDRAULIC ASPECTS OF NUCLEAR SYSTEMS FOR MAGNETICALLY CONFINED FUSION POWER-REACTORS
    NYGREN, RE
    HERMAN, H
    BAKER, CC
    [J]. NUCLEAR ENGINEERING AND DESIGN, 1982, 68 (03) : 311 - 321
  • [4] 3-DIMENSIONAL TRANSIENT ANALYSIS IN THERMAL POWER-REACTORS - EXTENSIVE COMPARISON BETWEEN FINITE-DIFFERENCE AND SPACE-TIME SYNTHESIS METHODS
    BREGA, E
    DIPASQUANTONIO, F
    SALINA, E
    [J]. ANNALS OF NUCLEAR ENERGY, 1978, 5 (3-4) : 117 - 132
  • [5] COMMIX-2 - STEADY-UNSTEADY, 3-DIMENSIONAL, 2-PHASE THERMAL-HYDRAULIC COMPUTER CODE
    BARTZIS, JG
    DOMANUS, HM
    KRAZINSKI, JL
    MIAO, CC
    SHA, WT
    SHAH, VL
    [J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1980, 35 (NOV): : 259 - 261
  • [6] BODYFIT-2PC - STEADY-STATE-TRANSIENT, 3-DIMENSIONAL, 2-PHASE THERMAL-HYDRAULIC COMPUTER CODE FOR RECTANGULAR ROD BUNDLES
    CHEN, BCJ
    CHIEN, TH
    SHA, WT
    KIM, JH
    SEHGAL, BR
    [J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1981, 38 (JUN): : 324 - 325
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  • [8] CODE TO CALCULATE TRANSIENT, 3-DIMENSIONAL POWER DISTRIBUTION IN LARGE LWR CORES
    SCHMIDT, A
    [J]. ATOMKERNENERGIE, 1974, 24 (01): : 20 - 24
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    YOKOMIZO, O
    SAKURAI, M
    YOSHIMOTO, Y
    KITAYAMA, K
    ENOMOTO, T
    FUKUDA, N
    CHUMAN, K
    [J]. NUCLEAR ENGINEERING AND DESIGN, 1987, 99 : 41 - 51
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    IZUTSU, S
    KUDO, Y
    ONUMA, J
    IWASAKI, T
    MUTO, S
    TOBA, A
    [J]. NUCLEAR TECHNOLOGY, 1990, 89 (01) : 92 - 102
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