Modelling fission gas behaviour in fast reactor (U,Pu)O2 fuel with BISON

JOURNAL OF NUCLEAR MATERIALS

卷:547

Article

Verdolin, Filippo¹  Novascone, Stephen²  Pizzocri, Davide¹  Pastore, Giovanni^2,3  Barani, Tommaso¹  Luzzi, Lelio¹ 

[1] Politecn Milan, Nucl Engn Div, Dept Energy, Via La Masa 34, I-20156 Milan, Italy

[2] Idaho Natl Lab, Computat Mech & Mat Dept, Idaho Falls, ID 83415 USA

[3] Univ Tennessee, Dept Nucl Engn, Knoxville, TN 37916 USA

关键词: Nuclear fuel;    MOX;    Fast reactors;    Finite element method;    Fission gas behaviour;   

DOI  :  10.1016/j.jnucmat.2020.152728

来源: Elsevier

【 摘 要 】

The physics-based fission gas behaviour model available in the BISON fuel performance code provides satisfactory predictive capabilities for application to light-water reactor conditions. In this work, we present a model extension for application to fast reactor (U,Pu)O-2 fuel. In particular, we detail the introduction of a lower bound to the number density of grain-face bubbles, representing a limit to the coalescence process once extensive bubble interconnection is achieved. This new feature is tested first against an experimental database for UO2-LWR, and secondly is validated against integral irradiation experiments for fast reactor (U,Pu)O-2 fuel rods irradiated in the FFTF (Fast Flux Test Facility) and in the JOYO reactors. The comparisons of BISON results with the experimental data are satisfactory and demonstrate an improvement compared to the standard version of the code. (C) 2020 Elsevier B.V. All rights reserved.

【 授权许可】

Free