THERMAL RECOVERY OF DEFECTS IN NEUTRON-IRRADIATED UO2

被引:38
作者
NAKAE, N [1 ]
IWATA, Y [1 ]
KIRIHARA, T [1 ]
机构
[1] NAGOYA UNIV,FAC ENGN,DEPT NUCL ENGN,CHIKUSA KU,NAGOYA,AICHI 464,JAPAN
关键词
D O I
10.1016/0022-3115(79)90194-6
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Thermal recovery of both lattice and volume expansions of UO2 irradiated to a dose of less than 9.97 × 1017 fissions/cm3 was studied in a temperature range from 200 to 1000°C. Two or three steps were observed in the recovery of lattice expansion. Volume expansion was also recovered in two or three steps. Recovery behavior of volume expansion of the specimen irradiated to 9.97 × 1017 fissions/cm3 was different from those irradiated to lower doses, and an abrupt volume increase was observed in the temperature range from 500 to 700 °C. This behavior might be related to the bubble swelling due to fission product gases. From the results on the recovery of lattice and volume expansions, the behavior of lattice point defects and defect clusters was discussed. © 1979.
引用
收藏
页码:314 / 322
页数:9
相关论文
共 12 条
[1]  
BRADBURY BT, 1967, STUDIES RAD EFFECTS, V2, P180
[2]   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
[3]   DENSITY MEASUREMENTS ON URANIUM DIOXIDE AND URANIUM CARBIDE SAMPLES IRRADIATED AT LOW TEMPERATURE [J].
KINGERY, WD ;
KAUFFMANN, Y ;
BRUET, M ;
DESIGOYE.BD .
JOURNAL OF NUCLEAR MATERIALS, 1968, 26 (02) :204-+
[4]  
KINGERY WD, 1967, CERR3289
[5]  
MATSUI H, 1975, J NUCL MATER, V56, P161, DOI 10.1016/0022-3115(75)90087-2
[6]  
MATSUI H, 1975, THESIS NAGOYA U
[7]   ELECTRICAL-CONDUCTIVITY AND THERMOELECTRIC-POWER IN IRRADIATED UO2+X [J].
NAKAE, N ;
KOIKE, T ;
KIRIHARA, T .
JOURNAL OF NUCLEAR MATERIALS, 1978, 73 (02) :217-221
[8]   IRRADIATION INDUCED VOLUME CHANGE IN UO2 [J].
NAKAE, N ;
KIRIHARA, T ;
NASU, S .
JOURNAL OF NUCLEAR MATERIALS, 1978, 74 (01) :1-9
[9]   IRRADIATION INDUCED LATTICE-DEFECTS IN UO2 [J].
NAKAE, N ;
HARADA, A ;
KIRIHARA, T ;
NASU, S .
JOURNAL OF NUCLEAR MATERIALS, 1978, 71 (02) :314-319
[10]  
NAKAE N, 1978, THESIS NAGOYA U