Simulation of isothermal fission gas release

被引：25
作者：
Denis, A
Piotrkowski, R
机构：
[1] Depto. Combustibles Nuckares, Comn. Nac. de Ener. Atómica, 1429 Buenos Aires
来源：
JOURNAL OF NUCLEAR MATERIALS | 1996年 / 229卷 / 01期
关键词：
D O I：
10.1016/0022-3115(95)00203-0
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
A fission gas release model is presented, which considers the atomic diffusion with trapping of Xe and Kr atoms generated during irradiation of the UO2 fuel, precipitation of gas in intra and intergranular bubbles, its resolution due to impact of energetic fission fragments, interconnection of grain boundary bubbles and sweeping of gas by the grain boundary movement. The diffusion equation is solved by the finite difference method and the results compare well with isothermal experimental determinations.
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页码：149 / 154
页数：6
相关论文
共 15 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]  
CHANTOIN P, 1994, P TECHN COMM M WAT R
[3]   FISSION-GAS BUBBLE BEHAVIOR IN URANIUM-DIOXIDE [J].
CHKUASELI, VF ;
MATZKE, H .
JOURNAL OF NUCLEAR MATERIALS, 1993, 201 :92-96
[4]   SIMULATION WITH THE HITO CODE OF THE INTERACTION OF ZIRCALOY WITH URANIUM-DIOXIDE AND STEAM AT HIGH-TEMPERATURES [J].
DENIS, A ;
GARCIA, EA .
JOURNAL OF NUCLEAR MATERIALS, 1991, 185 (01) :96-113
[5]  
DENIS A, 1994, TECHN COMM M WAT REA
[6]   BACO(BARRA COMBUSTIBLE), COMPUTER CODE FOR SIMULATING A REACTOR-FUEL ROD PERFORMANCE [J].
HARRIAGUE, S ;
COROLI, G ;
SAVINO, EJ .
NUCLEAR ENGINEERING AND DESIGN, 1980, 56 (01) :91-103
[7]   FINITE-ELEMENT MODEL FOR ANALYSIS OF FISSION-GAS RELEASE FROM UO2 FUEL [J].
ITO, K ;
IWASAKI, R ;
IWANO, Y .
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1985, 22 (02) :129-138
[8]   A COMPARISON BETWEEN FISSION-GAS RELEASE DATA AND FEMAXI-IV CODE CALCULATIONS [J].
NAKAJIMA, T ;
SAITO, H .
NUCLEAR ENGINEERING AND DESIGN, 1987, 101 (03) :267-279
[9]  
NOTLEY MFJ, 1980, AECL6585
[10]  
Olander D., 1976, FUNDAMENTAL ASPECTS
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