HEAT-TRANSFER IN NUCLEAR-REACTOR SAFETY - BANKOFF,SG, AFGAN,NH

被引：0

作者：

YADIGAROGLU, G ^{[1
]}

机构：

[1] SWISS FED INST TECHNOL,INST ENERGIETECH,KERNTECH LAB,CH-8092 ZURICH,SWITZERLAND

来源：

MECHANICAL ENGINEERING | 1984年 / 106卷 / 04期

关键词：

D O I：

暂无

中图分类号：

TH [机械、仪表工业];

学科分类号：

0802 ;

摘要：

引用

页码：86 / 87

页数：2

共 50 条

[1] HEAT-TRANSFER IN NUCLEAR-REACTOR SAFETY - BANKOFF,SG, AFGAN,NH
WEISMAN, J
[J]. NUCLEAR TECHNOLOGY, 1983, 63 (02) : 351 - 352
[2] NUCLEAR-REACTOR SAFETY HEAT-TRANSFER - ICHMT 1980 - TECHNICAL NOTE
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[J]. NUCLEAR SAFETY, 1981, 22 (02): : 173 - 175
[3] BOILING HEAT-TRANSFER IN NUCLEAR-REACTOR TECHNOLOGY
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[J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1979, 32 (JUN): : 808 - 809
[4] HEAT-TRANSFER OF A SPRAY DROPLET IN A NUCLEAR-REACTOR CONTAINMENT
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[J]. NUCLEAR TECHNOLOGY, 1980, 47 (02) : 268 - 281
[5] HEAT-TRANSFER OF A NUCLEAR-REACTOR CONTAINMENT SPRAY DROP
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[J]. NUCLEAR ENGINEERING AND DESIGN, 1987, 101 (02) : 137 - 148
[6] EVALUATION OF LUMPED PARAMETER HEAT-TRANSFER TECHNIQUES FOR NUCLEAR-REACTOR APPLICATIONS
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[J]. NUCLEAR SCIENCE AND ENGINEERING, 1973, 51 (01) : 41 - 51
[7] EFFECT OF INTERNAL CIRCULATION ON HEAT-TRANSFER OF A NUCLEAR-REACTOR CONTAINMENT SPRAY DROPLET
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[J]. NUCLEAR TECHNOLOGY, 1977, 35 (03) : 603 - 610
[8] A NUMERICAL PERFORMANCE STUDY OF THE PGCR METHOD APPLIED TO NUCLEAR-REACTOR HEAT-TRANSFER CALCULATIONS
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[J]. NUCLEAR TECHNOLOGY, 1992, 100 (01) : 135 - 140
[9] COMPARISON OF SINGLE AND MULTICELL HEAT-TRANSFER ANALYSES NEAR NUCLEAR-REACTOR ASSEMBLY WALLS
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[J]. NUCLEAR ENGINEERING AND DESIGN, 1972, 23 (02) : 141 - 146
[10] MODELING OF TRANSIENT HEAT-TRANSFER IN A NUCLEAR-REACTOR FUEL ROD USING A VARIATIONAL PROCEDURE
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