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

被引：0

作者：

KROEGER, PG

COLMAN, J

ARAJ, KJ

机构：

[1] Brookhaven Natl Lab, Dep of Nuclear, Energy, Upton, NY, USA, Brookhaven Natl Lab, Dep of Nuclear Energy, Upton, NY, USA

来源：

关键词：

All Open Access; Green;

D O I：

10.1016/0029-5493(85)90041-X

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：

NUCLEAR REACTORS, GAS COOLED

引用

页码：11 / 23

页数：13

共 10 条

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GOODIN, DT
[J]. JOURNAL OF THE AMERICAN CERAMIC SOCIETY, 1982, 65 (05) : 238 - 242
[4] KENT LA, 1982, NUREGCR2279 SAND NAT
[5] KROEGER PG, 1983, 1ST P NUCL THERM HYD
[6] SCHNEIDER U, 1981, NUCL ENG DES, V67, P245
[7] SCHWARTZ MH, 1975, GAA12462 GEN AT CO
[8] SCHWARTZTRAUBER KE, 1974, GAA12868 GEN AT CO
[9] 1982, PC000040 GEN AT CO H
[10] 1978, GAA15000 GEN AT CO H