4.7 Article

Modelling of irradiated UO2 fuel behaviour under transient conditions

Journal

JOURNAL OF NUCLEAR MATERIALS
Volume 437, Issue 1-3, Pages 250-260

Publisher

ELSEVIER SCIENCE BV
DOI: 10.1016/j.jnucmat.2013.02.011

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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.

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