DAMAGE MECHANISMS TO CABLES IN REACTOR LOSS-OF-COOLANT ACCIDENT ENVIRONMENTS

被引：0

作者：

LEADON, RE ^{[1
]}

LURIE, NA ^{[1
]}

机构：

[1] IRT CORP,SAN DIEGO,CA 92138

来源：

NUCLEAR TECHNOLOGY | 1979年 / 46卷 / 03期

关键词：

D O I：

10.13182/NT79-A32351

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：442 / 446

页数：5

共 50 条

[41] PROBABILITY DISTRIBUTION OF INHALATION DOSE FOLLOWING A LOSS-OF-COOLANT ACCIDENT
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TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1969, 12 (02): : 684 - &
[42] CONDENSING HEAT-TRANSFER FOLLOWING A LOSS-OF-COOLANT ACCIDENT
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[43] Possibility on the thermal quench of the superconducting coil at the loss-of-coolant accident
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[44] INVESTIGATION OF CRITICAL FLOW CONDITION DURING A LOSS-OF-COOLANT ACCIDENT
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[45] LARGE BREAK LOSS-OF-COOLANT ACCIDENT ANALYSIS OF VVER-1000 REACTOR USING CATHARE CODE
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[46] PIPE SUPPORTS TAKEN INTO ACCOUNT IN LOSS-OF-COOLANT ACCIDENT ANALYSES
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[47] IMPACT OF FUEL ROD DESIGN ON LOSS-OF-COOLANT ACCIDENT ANALYSIS
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[48] LOSS-OF-COOLANT ACCIDENT (LOCA) ANALYSIS - LOOP CODE DEVELOPMENT
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[49] COMPARISON BETWEEN CODE CALCULATION AND BLOWDOWN EXPERIMENTS SIMULATING A LOSS-OF-COOLANT ACCIDENT IN A PRESSURIZED WATER REACTOR
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[50] INVESTIGATION OF WARM PRESTRESS FOR THE CASE OF SMALL DELTA-T DURING A REACTOR LOSS-OF-COOLANT ACCIDENT
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