PROGRESS IN US LEU FUEL DEVELOPMENT

Year
2008
Author(s)
D M Wachs - Idaho National Laboratory
D D Keiser - Idaho National Laboratory
D E Burkes - Idaho National Laboratory
J F Jue - Idaho National Laboratory
A B Robinson - Idaho National Laboratory
C R Clark - Idaho National Laboratory
S E Steffler - Idaho National Laboratory
N E Woolstenhulme - Idaho National Laboratory
Y S Kim - Argonne National Laboratory
L Jollay - Y-12 National Security Complex
J Gooch - Y-12 National Security Complex
Abstract
Very high uranium density nuclear fuels are currently under development in the U.S. to enable the conversion of many research reactors worldwide to LEU based fuels. Significant progress has been made in both the uranium-molybdenum based dispersion and monolithic fuel forms. The efficacy of silicon additions to the matrix of dispersion fuel meats has been demonstrated. Full size dispersion plates with loadings greater than 8.0 g-U/cc have been fabricated with silicon additions to the matrix and are ready for irradiation testing. Monolithic mini-plates with modified fuel/cladding interfaces (both silicon enhanced and zirconium diffusion barriers) have been fabricated by both friction bonding and hot isostatic pressing and have nearly completed irradiation to demonstrate their impact on fuel/clad interface chemistry. Full size monolithic plates have been fabricated with both types of interlayer by friction bonding and are currently under irradiation to evaluate mechanical response at prototypic scale. The plans for future development and qualification are discussed.