THERMOHYDRAULICS IN A HIGH-TEMPERATURE GAS-COOLED REACTOR PRESTRESSED CONCRETE REACTOR VESSEL DURING UNRESTRICTED CORE HEATUP ACCIDENTS

被引：0
|
作者：
KROEGER, PG [1 ]
COLMAN, J [1 ]
ARAJ, K [1 ]
机构：
[1] BROOKHAVEN NATL LAB, UPTON, NY 11973 USA
来源：
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY | 1983年 / 45卷
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
收藏
页码：843 / 844
页数：2
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