DEVELOPMENT OF COMPUTER CODE FOR ANALYZING LIQUID-METAL MHD FLOW IN FUSION-REACTOR BLANKETS .1.

被引：0

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作者：

MADARAME, H

TOKOH, H

机构：

来源：

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY | 1988年 / 25卷 / 03期

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D O I：

10.1080/18811248.1988.9733583

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 ;

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页码：233 / 244

页数：12

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[1] DEVELOPMENT OF COMPUTER CODE FOR ANALYZING LIQUID-METAL MHD FLOW IN FUSION-REACTOR BLANKETS .2. FLOW IN CIRCULAR PIPE UNDER NON-UNIFORM TRANSVERSE FIELD
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[2] DEVELOPMENT OF COMPUTER CODE FOR ANALYZING LIQUID METAL MHD FLOW IN FUSION REACTOR BLANKETS, (I): FLOW IN CIRCULAR PIPE UNDER UNIFORM TRANSVERSE FIELD.
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[3] MAGNETOHYDRODYNAMIC CONSIDERATIONS FOR THE DESIGN OF SELF-COOLED LIQUID-METAL FUSION-REACTOR BLANKETS
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[4] SPECIAL FEATURES OF 1ST-WALL HEAT-TRANSFER IN LIQUID-METAL FUSION-REACTOR BLANKETS
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[5] Liquid metal MHD flow influence on heat transfer phenomena in fusion reactor blankets
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[6] A VANADIUM ALLOY FOR THE APPLICATION IN A LIQUID-METAL BLANKET OF A FUSION-REACTOR
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[7] Predicting adhesive properties of liquid-metal materials for fusion reactor blankets
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[8] Predicting adhesive properties of liquid-metal materials for fusion reactor blankets
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[9] COMPUTER CODE FOR ANALYZING LIQUID-METAL MHD FLOW IN RECTANGULAR DUCT UNDER STRONG TRANSVERSE MAGNETIC-FIELD
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[10] DEVELOPMENT OF A DIRECT INSULATION LAYER FOR A SELF-COOLED LIQUID-METAL FUSION-REACTOR BLANKET
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