NUMERICAL MODELING OF THERMOHYDRODYNAMIC SYSTEMS BY RELAP5/MOD2 COMPUTER CODE

被引：0

|

作者：

SENCAR, M

PETELIN, S

机构：

来源：

ZEITSCHRIFT FUR ANGEWANDTE MATHEMATIK UND MECHANIK | 1991年 / 71卷 / 05期

关键词：

D O I：

暂无

中图分类号：

O29 [应用数学];

学科分类号：

070104 ;

摘要：

引用

收藏

页码：T519 / T524

页数：6

相关论文

共 50 条

[21] TRANSIENT ANALYSIS IN THE ASCO NUCLEAR-POWER-PLANT USING RELAP5 MOD2
REVENTOS, F
SANCHEZBAPTISTA, J
NAVAS, AP
NUCLEAR TECHNOLOGY, 1990, 90 (03) : 294 - 307
[22] MODELING AND LOSS-OF-COOLANT ACCIDENT ANALYSIS OF A NUCLEAR-POWER-PLANT USING RELAP5/MOD2
SALIM, P
HASSAN, YA
NUCLEAR TECHNOLOGY, 1990, 90 (03) : 275 - 285
[23] RELAP5/MOD3 code coupling model
Martin, RP
NUCLEAR SAFETY, 1995, 36 (02): : 290 - 299
[24] RELAP5／MOD2冷凝回流传热关系式分析
杨鲁伟
陈听宽
胡志宏
徐进良
核科学与工程, 1996, (04) : 87 - 91
[25] ATWS SCOPING CALCULATIONS FOR A BWR PLANT PERFORMED USING RELAP5/MOD2 AND CONTAIN CODES
MARSILI, P
PASCULLI, A
CAMICIOLA, P
NUCLEAR ENGINEERING AND DESIGN, 1990, 121 (03) : 409 - 419
[26] USING THE RELAP5/MOD2 CODE UNDER LOW-PRESSURE-LOW-TEMPERATURE LOSS-OF-COOLANT-ACCIDENT CONDITIONS
WANG, JL
KUNZE, JF
NUCLEAR TECHNOLOGY, 1989, 85 (03) : 285 - 293
[27] ASSESSMENT OF HORIZONTAL STRATIFICATION ENTRAINMENT MODEL IN RELAP5 MOD2 BY COMPARISON WITH SEPARATE EFFECTS EXPERIMENTS
ARDRON, KH
BRYCE, WM
NUCLEAR ENGINEERING AND DESIGN, 1990, 122 (1-3) : 263 - 271
[28] Implementation of a two-phase boiling model into the RELAP5/MOD2 computer code to predict void distribution in low-pressure subcooled boiling flows
Yeoh, GH
Tu, JY
NUCLEAR SCIENCE AND ENGINEERING, 2002, 140 (02) : 181 - 188
[29] LOFT EXPERIMENT LP-02-6 ANALYSIS BY RELAP5 MOD2 CODE WITH IMPROVED MINIMUM FILM BOILING TEMPERATURE
KOIZUMI, Y
ANODA, Y
TASAKA, K
MIMURA, Y
MAEDA, A
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1988, 25 (04) : 395 - 403
[30] Comparison study of the Westinghouse model E steam generator using RELAP5/MOD2 and RETRAN-02 computer codes
Blanchat, Thomas K., 1600, (90):

← 1 2 3 4 5 →