MICROSTRUCTURE-DEPENDENT MODEL FOR FISSION-PRODUCT GAS-RELEASE AND SWELLING IN UO2 FUEL

被引:37
作者
NOTLEY, MJF
HASTINGS, IJ
机构
关键词
D O I
10.1016/0029-5493(80)90180-6
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:163 / 175
页数:13
相关论文
共 30 条
[1]   ISOTHERMAL GRAIN-GROWTH KINETICS IN SINTERED UO2 PELLETS [J].
AINSCOUGH, JB ;
OLDFIELD, BW ;
WARE, JO .
JOURNAL OF NUCLEAR MATERIALS, 1973, 49 (02) :117-128
[2]  
BOOTH AH, 1957, AECL496 AT EN CAN LT
[3]   THERMAL-GRADIENT MIGRATION OF HELIUM BUBBLES IN URANIUM-DIOXIDE [J].
BUESCHER, BJ ;
MEYER, RO .
JOURNAL OF NUCLEAR MATERIALS, 1973, 48 (02) :143-156
[4]  
CAMPBELL FR, 1974, AECL4912 AT EN CAN L
[6]  
FINDLAY JR, 1971, BNES C CHEM NUCLEAR
[7]  
HARGREAVES R, 1976, J BRIT NUCL ENER SOC, V15, P311
[8]   IDENTIFICATION OF PRECIPITATES ASSOCIATED WITH INTERGRANULAR FISSION-GAS BUBBLES IN IRRADIATED UO2 FUEL [J].
HASTINGS, IJ ;
ROSE, DH ;
BAIRD, J .
JOURNAL OF NUCLEAR MATERIALS, 1976, 61 (02) :229-231
[9]   IRRADIATION-INDUCED VOLUME CHANGES IN COMMERCIAL UO2 FUEL - COMPARISON WITH MODEL PREDICTION [J].
HASTINGS, IJ ;
NOTLEY, MJF ;
ROSE, DH .
JOURNAL OF NUCLEAR MATERIALS, 1978, 75 (02) :301-303
[10]   DENSIFICATION ALGORITHM FOR IRRADIATED UO2 FUEL [J].
HASTINGS, IJ ;
EVANS, LE .
JOURNAL OF THE AMERICAN CERAMIC SOCIETY, 1979, 62 (3-4) :217-218