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

页码：843 / 844

页数：2

共 50 条

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