MIT PRESSURIZER PREDICTIONS DURING INSURGE TRANSIENTS USING TRAC-PF1 CODE

被引：0

作者：

HASSAN, YA ^{[1
]}

机构：

[1] BABCOCK & WILCOX CO, LYNCHBURG, VA 24505 USA

来源：

TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY | 1985年 / 50卷 / NOV期

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

页码：323 / 324

页数：2

共 49 条

[1] LEVEL SWELL TEST PREDICTIONS WITH TRAC-PF1 CODE
HASSAN, YA
MEERBAUM, MI
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1985, 49 (JUN): : 260 - 262
[2] TRAC-PF1/MOD1 COMPUTER CODE AND DEVELOPMENTAL ASSESSMENT
ADDESSIO, FL
SAHOTA, MS
LILES, DR
MAHAFFY, JH
NUCLEAR SAFETY, 1985, 26 (04): : 438 - 454
[3] Assessment of TRAC-PF1 condensation heat transfer model for analysis of ECC water injection transients
Asaka, Hideaki, 1600, (26):
[4] ASSESSMENT OF THE TRAC-PF1 STRATIFIED FLOW MODEL
CAPPIELLO, MW
LILES, DR
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1981, 39 : 564 - 565
[5] TRAC-PF1程序简介及其移植
严育华，高祖瑛，高承，李金才
核科学与工程, 1997, (03) : 215 - 219
[6] AUTOMATIC CONTROLLERS IN TRAC-PF1/MOD1
STEINKE, RG
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1984, 46 : 427 - 429
[7] Application of simplified condensation model to PWR LBLOCA transient analysis with TRAC-PF1 code
Akimoto, H
Murao, Y
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1996, 33 (04) : 290 - 297
[8] TRAC-PF1 THERMAL-HYDRAULIC PREDICTIONS OF A STEAMLINE BREAK IN A C-E PLANT
KOENIG, JE
SPRIGGS, G
SMITH, R
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1983, 45 : 442 - 444
[9] ASSESSMENT OF TRAC-PF1 CONDENSATION HEAT-TRANSFER MODEL FOR ANALYSIS OF ECC WATER INJECTION TRANSIENTS
ASAKA, H
MURAO, Y
KUKITA, Y
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1989, 26 (11) : 1045 - 1057
[10] TRANSIENT 2-PHASE BLOWDOWN PREDICTIONS OF AN INITIALLY STAGNANT SATURATED LIQUID STEAM IN A VESSEL USING TRAC-PF1
HASSAN, YA
NUCLEAR TECHNOLOGY, 1985, 69 (03) : 388 - 392

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