IN-CORE STUDY OF DIMENSIONAL BEHAVIOR OF UO2 FUEL RODS

被引：0

作者：

KJAERHEI.G

ROLSTAD, E

机构：

来源：

TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY | 1969年 / 12卷 / 01期

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：205 / &

共 50 条

[21] RECOVERY OF TRITIUM FROM ZIRCALOY-CLAD UO2 FUEL-RODS
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[22] IN-PILE LENGTH CHANGES OF ZRCU-SHEATHED UO2 FUEL RODS
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[23] DENSIFICATION IN IRRADIATED UO2 FUEL
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[24] UO2 FUEL FABRICATION DEVELOPMENT
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[27] A COMPREHENSIVE MODEL OF FISSION-GAS BEHAVIOR IN UO2 FUEL
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[28] DIRECT RECOVERY OF UO2 SCRAP POWDERS AND THEIR INFLUENCE ON THE QUALITY OF THE UO2 FUEL
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[29] IRRADIATION TESTS OF FUEL RODS CONTAINING UO2 AND (U,PU)O2 FOR GCFR
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[30] THERMAL-NEUTRON FLUX DEPRESSION IN CYLINDRICAL UO2 FUEL-RODS - COMMENT
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