| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 7968182 | Journal of Nuclear Materials | 2014 | 6 Pages |
Abstract
The motivation for exploring the potential development of accident tolerant fuels in light water reactors to replace existing Zr alloy clad monolithic (U, Pu) oxide fuel is outlined. The evaluation includes a brief review of core degradation processes under design-basis and beyond-design-basis transient conditions. Three general strategies for accident tolerant fuels are being explored: modification of current state-of-the-art zirconium alloy cladding to further improve oxidation resistance (including use of coatings), replacement of Zr alloy cladding with an alternative oxidation-resistant high-performance cladding, and replacement of the monolithic ceramic oxide fuel with alternative fuel forms.
Related Topics
Physical Sciences and Engineering
Energy
Nuclear Energy and Engineering
Authors
S.J. Zinkle, K.A. Terrani, J.C. Gehin, L.J. Ott, L.L. Snead,