Modelling of irradiated UO2 fuel behaviour under transient conditions

被引:24
|
作者
Veshchunov, M. S. [1 ,2 ]
Tarasov, V. I. [1 ]
机构
[1] Russian Acad Sci, Nucl Safety Inst IBRAE, Moscow 115191, Russia
[2] MIPT, Dolgoprudnyi 141700, Russia
关键词
FISSION-GAS BUBBLES; GRAIN-GROWTH KINETICS; RE-SOLUTION; URANIUM-DIOXIDE; NUCLEAR-FUEL; LWR UO2; MIGRATION; EVOLUTION; RELEASE; BURNUP;
D O I
10.1016/j.jnucmat.2013.02.011
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
On the basis of a critical assessment of the Booth-Speight model for the fission gas release from irradiated fuel, a more consistent mechanigtic approach is developed for consideration of the microstructure evolution and fission gas release under conditions of power ramp tests. A new Model that modifies the Nelson model for gas atom resolution from bubbles and explains the observed formation of a new population of large bubbles, is developed and implemented in the MFPR code. Superposition of various mechanisms of gas transport: gas atom diffusion, bubbles random and biased migration, and gas sweeping by grain boundaries, results in a reasonable prediction of the measured fractional gas release and microstructure evolution, observed in the ramp tests. (C) 2013 Elsevier B.V. All rights reserved.
引用
收藏
页码:250 / 260
页数:11
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