QUANTIFYING REACTOR SAFETY MARGINS .4. UNCERTAINTY EVALUATION OF LBLOCA ANALYSIS BASED ON TRAC-PF1/MOD 1

被引:17
作者
LELLOUCHE, GS
LEVY, S
BOYACK, BE
CATTON, I
DUFFY, RB
GRIFFITH, P
KATSMA, KR
MAY, R
ROHATGI, US
WILSON, G
WULFF, W
ZUBER, N
机构
[1] UNIV CALIF LOS ALAMOS SCI LAB, LOS ALAMOS, NM 87544 USA
[2] UNIV CALIF LOS ANGELES, SCH ENGN & APPL SCI, LOS ANGELES, CA 90024 USA
[3] IDAHO NATL ENGN LAB, IDAHO FALLS, ID 83415 USA
[4] ASSOC UNIV INC, BROOKHAVEN NATL LAB, UPTON, NY 11973 USA
[5] US NUCL REGULATORY COMMISS, DIV REACTOR SAFETY RES, WASHINGTON, DC 20555 USA
关键词
D O I
10.1016/0029-5493(90)90074-8
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
The Nuclear Regulatory Commission (NRC) has issued a revised Emergency Core Cooling System (ECCS) rule allowing the use of best estimate computer codes for safety analysis. The rule also requires an estimation of the uncertainty in the calculated system response and a comparison of the resulting bound with the acceptance limits of 10CFR Part 50. To support this revised rule the NRC and its consultants and contractors have developed and demonstrated the Code Scaling, Applicability and Uncertainty Methodology (CSAU). The last of the three elements of the methodology - Uncertainty Evaluation - is described in this paper. © 1990.
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页码:67 / 95
页数:29
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