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

[21] ANALYSIS OF TRAC-PF1 CALCULATED CORE HEAT-TRANSFER FOR A CCTF TEST
AKIMOTO, H
NUCLEAR ENGINEERING AND DESIGN, 1985, 88 (02) : 215 - 227
[22] TRAC-PF1 BEST-ESTIMATE LOCA ANALYSIS OF A COMBINED ECC-INJECTION PWR
CAPPIELLO, MW
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1983, 45 : 809 - 810
[23] DEVELOPMENT OF WCOBRA/TRAC-TF2 COMPUTER CODE: COUPLING OF THE 3D MODULE (COBRA-TF) WITH THE 1D MODULE OF TRAC-PF1/MOD2
Frepoli, Cesare
Ohkawa, Katsuhiro
Nissley, Mitch
ICONE 17: PROCEEDINGS OF THE 17TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 3, 2009, : 829 - 841
[24] Features and performance of a coupled three-dimensional thermal-hydraulic/kinetics TRAC-PF1/NEM pressurized water reactor (PWR) analysis code
Ivanov, KN
Macian-Juan, R
Irani, A
Baratta, AJ
ANNALS OF NUCLEAR ENERGY, 1999, 26 (15) : 1407 - 1417
[25] Verification of a three-dimensional nodal transient neutronics routine for the TRAC-PF1/MOD3 thermal-hydraulic system analysis code
Bandini, BR
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Steinke, RG
NUCLEAR TECHNOLOGY, 1998, 123 (01) : 1 - 20
[26] ASSESSMENT OF TRAC-PF1 AND RELAP5/MOD1 CODES WITH GE LARGE VESSEL BLOWDOWN TEST
JO, JH
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1983, 45 : 875 - 876
[27] QUANTIFYING REACTOR SAFETY MARGINS .4. UNCERTAINTY EVALUATION OF LBLOCA ANALYSIS BASED ON TRAC-PF1/MOD 1
LELLOUCHE, GS
LEVY, S
BOYACK, BE
CATTON, I
DUFFY, RB
GRIFFITH, P
KATSMA, KR
MAY, R
ROHATGI, US
WILSON, G
WULFF, W
ZUBER, N
NUCLEAR ENGINEERING AND DESIGN, 1990, 119 (01) : 67 - 95
[28] ANALYSIS OF FLECHT-SEASET STEAM-GENERATOR TESTS WITH TRAC-PF1 AND RELAP5/MOD1
SLOVIK, G
SAHA, P
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1983, 44 : 594 - 595
[29] A TRAC-PF1 ANALYSIS OF LOSS-OF-FLUID TEST L6-7/L9-2
MEIER, JK
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1984, 46 : 140 - 141
[30] QUANTIFYING REACTOR SAFETY MARGINS .4. UNCERTAINTY EVALUATION OF LBLOCA ANALYSIS BASED ON TRAC-PF1/MOD1 - COMMENTS
LELLOUCHE, GS
NUCLEAR ENGINEERING AND DESIGN, 1994, 150 (01) : 191 - 191

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