IN-REACTOR CREEP OF ZIRCALOY-2, ZIRCALOY-4 AND ZR-1.15 WT PERCENT CR-0.1 WT PERCENT FE AT 568 K DERIVED FROM THEIR STRESS-RELAXATION BEHAVIOR

被引:20
作者
CAUSEY, AR [1 ]
机构
[1] ATOM ENERGY CANADA LTD,CHALK RIVER NUCL LABS,FUELS & MAT DIV,CHALK RIVER,ONTARIO,CANADA
关键词
D O I
10.1016/0022-3115(74)90076-2
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
引用
收藏
页码:64 / 72
页数:9
相关论文
共 33 条
[1]  
ADAMSON RB, 1972, NOV P BNES C LOND, P305
[2]   FRANK LOOP DEVELOPMENT IN NEUTRON-IRRADIATED OLD-WORKED TYPE-316 STAINLESS-STEEL [J].
BRAGER, HR ;
STRAALSUND, JL .
JOURNAL OF NUCLEAR MATERIALS, 1973, 47 (01) :105-109
[3]   IRRADIATION CREEP DUE TO GROWTH OF INTERSTITIAL LOOPS [J].
BRAILSFORD, AD ;
BULLOUGH, R .
PHILOSOPHICAL MAGAZINE, 1973, 27 (01) :49-64
[4]  
Buckley S. N., 1962, PROPERTIES REACTOR M, P413
[5]  
BUCKLEY SN, 1968, AERER5944 REP, V2, P547
[6]  
CAUSEY AR, 1973, AUG ASTM S ZIRC NUCL
[7]  
COLEMAN CE, TO BE PUBLISHED
[8]  
DANIEL RC, 1973, NUCL TECH, V14, P171
[9]  
ELLS CE, 1966, ELECTROCHEM TECHNOL, V4, P268
[10]  
ELLS CE, 1972, 6 EUR C IRR EMBR CRE