RETRAN-02 AND DYNODE-P ANALYSES OF A STEAM-GENERATOR TUBE BREAK TRANSIENT

被引:1
|
作者
CHAO, J
CHEXAL, VK
LAYMAN, WH
RAUTMANN, DA
PETERSON, CE
CRESS, LW
机构
[1] NO STATES POWER CO,MINNEAPOLIS,MN 55401
[2] ENERGY INC INC,DIV COMP SYST & ANAL,IDAHO FALLS,ID 83401
[3] NUCL ASSOCIATES INT,ROCKVILLE,MD 20852
关键词
D O I
10.13182/NT83-A33193
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:224 / 237
页数:14
相关论文
共 15 条
  • [1] RETRAN-02 AND DYNODE-P ANALYSES OF A STEAM GENERATOR TUBE BREAK TRANSIENT.
    Chao, Jason
    Chexal, V.K.
    Layman, William H.
    Rautmann, David A.
    Peterson, Craig E.
    [J]. Nuclear Technology, 1983, 16 (03) : 224 - 237
  • [2] RETRAN-02 ANALYSIS OF STEAM-GENERATOR TUBE RUPTURE FOR KEWAUNEE
    KIM, MH
    HAMMER, KE
    BARRY, J
    COEN, E
    CORRADINI, ML
    MOSES, GA
    [J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1984, 47 : 507 - 509
  • [3] RETRAN-02 ANALYSIS OF RADIOISOTOPE RELEASES FOLLOWING A STEAM-GENERATOR TUBE RUPTURE
    RHODES, CA
    INGRAM, CD
    [J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1985, 50 (NOV): : 331 - 333
  • [4] Pressurization transient analyses of the Lungmen ABWR plant using RETRAN-02
    Tzang, Yih-Chyun
    Chiang, Ray-Feng
    Yuan, Yng-Ruey
    Ferng, Yuh-Ming
    Pei, Bau-Shei
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2010, 240 (04) : 868 - 879
  • [5] THERMAL-HYDRAULIC ANALYSIS OF A STEAM-GENERATOR TUBE BREAK TRANSIENT
    CHAO, J
    CHEXAL, B
    LAYMAN, W
    RAUTMANN, D
    PETERSON, C
    ATCHISON, J
    HANSEN, B
    CRESS, LW
    [J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1982, 41 : 677 - 678
  • [6] STEAM-GENERATOR TUBE STRESSES DURING HYPOTHETICAL STEAM LINE BREAK
    GREGORIC, M
    CIZELJ, L
    [J]. ZEITSCHRIFT FUR ANGEWANDTE MATHEMATIK UND MECHANIK, 1989, 69 (04): : T230 - T232
  • [7] A COMPARISON STUDY OF THE WESTINGHOUSE MODEL-E STEAM-GENERATOR USING RELAP5/MOD2 AND RETRAN-02 COMPUTER CODES
    BLANCHAT, TK
    HASSAN, YA
    [J]. NUCLEAR TECHNOLOGY, 1990, 90 (03) : 326 - 339
  • [8] ANALYSIS OF STEAM-LINE-BREAK-INDUCED STEAM-GENERATOR TUBE RUPTURE
    DOBRANICH, D
    [J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1981, 38 (JUN): : 438 - 440
  • [9] ON THE ANALYSIS OF THE TRANSIENT STATE IN A FORCED CIRCULATION STEAM-GENERATOR TUBE
    MOLINARI, G
    PRESTI, P
    [J]. REVUE GENERALE DE THERMIQUE, 1983, 22 (263): : 739 - 746