Kinetics of fission product gas release during grain growth

被引:17
作者
Forsberg, K.
Massih, A. R.
机构
[1] Quantum Technol, SE-75183 Uppsala, Sweden
[2] Malmo Univ, Div Mat Sci, SE-20506 Malmo, Sweden
关键词
D O I
10.1088/0965-0393/15/3/011
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
A theoretical framework for the calculation of fission product gas release by diffusion, irradiation-induced re-solution, grain boundary saturation and grain growth in ceramic nuclear fuel (UO2) under time-varying loads is presented. The diffusion equation is subjected to boundary conditions, which account for the aforementioned effects. Analytical solutions to the equation are obtained. The theory is applied to calculate fission gas release and grain growth as functions of temperature and time. Correlation between grain growth and gas release is calculated and the results are discussed in the light of experimental data.
引用
收藏
页码:335 / 353
页数:19
相关论文
共 34 条
[1]  
Abramowitz M., 1964, HDB MATH FUNCTIONS F, V55
[2]   ISOTHERMAL GRAIN-GROWTH KINETICS IN SINTERED UO2 PELLETS [J].
AINSCOUGH, JB ;
OLDFIELD, BW ;
WARE, JO .
JOURNAL OF NUCLEAR MATERIALS, 1973, 49 (02) :117-128
[3]  
[Anonymous], IAEATECDOC957
[4]  
Booth A., 1957, AECL 496 CRDC-721
[5]   RECRYSTALLIZATION AND GRAIN GROWTH [J].
BURKE, JE ;
TURNBULL, D .
PROGRESS IN METAL PHYSICS, 1952, 3 :220-292
[6]   FISSION-GAS RELEASE UNDER TIME-VARYING CONDITIONS [J].
FORSBERG, K ;
MASSIH, AR .
JOURNAL OF NUCLEAR MATERIALS, 1985, 127 (2-3) :141-145
[7]   DIFFUSION-THEORY OF FISSION-GAS MIGRATION IN IRRADIATED NUCLEAR-FUEL UO2 [J].
FORSBERG, K ;
MASSIH, AR .
JOURNAL OF NUCLEAR MATERIALS, 1985, 135 (2-3) :140-148
[8]  
FORSBERG K, 2001, T 16 INT C STRUCT ME
[9]  
GRAPENGIESSER B, 1988, INT TOP M LWR FUEL P
[10]  
HARGREAVES R, 1976, J BRIT NUCL ENER SOC, V15, P311