Published July 2016 | Version v1
Journal article

Neutronic and thermal analysis of composite fuel for potential deployment in fast reactors

Description

Highlights: • Neutronic and heat transfer performance of composite fuels on the macro-scale. • Methodology to guide flexible fuel design using high fidelity simulation tools. • Viability of composite fuels for ultra-high burnup fast reactor deployment. - Abstract: Composite fuels are promising candidates for high-burnup fast reactors because of their accommodation of swelling, limited fuel-cladding interactions and flexibility in design. While a proof-of-concept fuel consisting of granules of U-alloys and PuO2 dispersed within a porous zirconium matrix was successfully manufactured and irradiated, its neutronic and thermal performance remains to be optimized as compared to currently utilized fuels. MCNP6, COMSOL and a sphere packing algorithm were employed to perform the analysis. We found that both the theoretical maximum burnup reached and the temperature profiles are comparable to that of the currently considered alternative fuel. The results are promising and do not indicate any substantial limitation to the deployment of composite fuel. The fuel type merits further research, including full-core simulations. The methodology followed herein also provides a basis for screening different material compositions and guiding materials selection in composite fuels.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2016.04.010

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2016.04.010;
PII
S0029-5493(16)30028-0;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
303
Journal Page Range
p. 50-57
ISSN
0029-5493
CODEN
NEDEAU

Optional Information

Copyright
Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.