MODELING AND PARAMETRIC STUDIES OF THE EFFECT OF PU-MIXING HETEROGENEITY ON FISSION-GAS RELEASE FROM MIXED-OXIDE FUELS OF LWRS AND FBRS

被引:6
作者
ISHIDA, M [1 ]
KOREI, Y [1 ]
机构
[1] NIPPON NUCL FUEL DEV CO LTD,OARAI,IBARAKI 31113,JAPAN
关键词
D O I
10.1016/0022-3115(94)90238-0
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
A simple, practical method has been proposed for evaluation of the effect of heterogeneity in Pu-mixing on fission gas release (FGR) behavior in mixed oxide (MOX) fuels. In contrast to the usual PuO2 spherical particle model, the proposed model uses the measurable (by electron probe microanalysis, etc.) statistical frequency distribution of local Pu-content in as-fabricated MOX fuels in combination with the usual fission gas release model based on the diffusion theory for homogeneous UO2 fuel. From parametric studies using a binomial distribution model for the expression of the statistical frequency distribution of local Pu-content, it was confirmed that the enhancement of FGR in MOX fuels is caused by the simultaneous effects of (a) the fission-rate-enhanced diffusion of fission gas atoms and (b) the local (on the scale of fission fragment range) fission rate peaking in the fuel matrix, resulting from the Pu-mixing heterogeneity. The degree of FGR enhancement is greater in the MOX fuels of lower average Pu fraction under a given average power density, and is more apparent at lower operating temperatures as long as the temperature is high enough to cause the FGR. Since FBR-MOX fuels are of high average Pu fraction (approximately 20 wt%) and are used at relatively high operating temperatures compared with LWR-MOX fuels, the FGR enhancement due to their heterogeneity is insignificant.
引用
收藏
页码:203 / 215
页数:13
相关论文
共 17 条
[1]  
Bairiot H., 1987, Improvements in Water Reactor Fuel Technology and Utilization. Proceedings of an International Symposium, P363
[2]  
BILLAUX M, 1984, IWGFPT19, P441
[3]  
BOOTH AH, 1957, CRDC721 CAN REP
[4]  
CARSLAW HS, 1959, CONDUCTION HEAT SOLI, pCH9
[5]  
COQUERELLE M, 1990, IWGFPT35, P205
[6]  
HAAS D, 1990, IWGFPT35, P188
[7]   RADIOCHEMICAL STUDY OF RANGES IN METALLIC URANIUM OF FRAGMENTS FROM THERMAL NEUTRON FISSION [J].
NIDAY, JB .
PHYSICAL REVIEW, 1961, 121 (05) :1471-&
[8]  
SCHLEMMER FU, 1990, IWGFPT35, P193
[9]  
Stratton R. W., 1987, Improvements in Water Reactor Fuel Technology and Utilization. Proceedings of an International Symposium, P353
[10]   DEVELOPMENT OF QUALITY-CONTROL DATA-BASE DANTE AND RELATIONAL ANALYSIS BETWEEN FISSION-GAS RELEASE BEHAVIOR AND PLUTONIUM HOMOGENEITY IN MIXED-OXIDE FUEL BY DANTE [J].
TAKAHASHI, K ;
KAMIMURA, K ;
YAMAGUCHI, T ;
MASUDA, S .
JOURNAL OF NUCLEAR MATERIALS, 1988, 153 :232-238