THE U-ZRHX ALLOY - ITS PROPERTIES AND USE IN TRIGA FUEL

被引:106
作者
SIMNAD, MT
机构
关键词
D O I
10.1016/0029-5493(81)90135-7
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
收藏
页码:403 / 422
页数:20
相关论文
共 40 条
[1]   IN-CORE FURNACE FOR HIGH-TEMPERATURE IRRADIATION TESTING OF REACTOR FUELS [J].
ANDERSON, EE ;
LANGER, S ;
BALDWIN, NL ;
VANSLAGER, FE .
NUCLEAR TECHNOLOGY, 1971, 11 (02) :259-+
[2]  
ANDRIYEVSKII RA, 1971, 4TH GEN C P, V10, P383
[3]  
[Anonymous], 1968, METAL HYDRIDES
[4]  
BALDWIN NL, 1980, E117830 GEN AT DOC
[5]  
BECK RL, 1962, T AM SOC MET, V55, P556
[6]  
BERLING JT, 1965, NAASR11649 USAEC REP
[7]  
BERNATH L, 1963, NAASR8590 USAEC REP
[8]  
BIRNEY KR, 1967, NAASR12284 USAEC REP
[9]   CREEP PROPERTIES OF A ZIRCONIUM-HYDROGEN URANIUM ALLOY [J].
BOKROS, JC .
JOURNAL OF NUCLEAR MATERIALS, 1961, 3 (02) :216-221
[10]  
BYRON GF, 1964, NAASR8617 USAEC REP