Open AccessFuel System Compatibility Issues for Prometheus-1
Author(s) -
D. Noe,
KB Gibbard,
MH Krohn
Publication year - 2006
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/884677
Subject(s) - cladding (metalworking) , compatibility (geochemistry) , limiting , fission products , nuclear engineering , fission , materials science , silicon carbide , nuclear fission product , fuel element failure , zirconium , nuclear fuel , process engineering , forensic engineering , mechanical engineering , composite material , spent nuclear fuel , engineering , metallurgy , nuclear physics , neutron , physics
Compatibility issues for the Prometheus-1 fuel system have been reviewed based upon the selection of UO{sub 2} as the reference fuel material. In particular, the potential for limiting effects due to fuel- or fission product-component (cladding, liner, spring, etc) chemical interactions and clad-liner interactions have been evaluated. For UO{sub 2}-based fuels, fuel-component interactions are not expected to significantly limit performance. However, based upon the selection of component materials, there is a potential for degradation due to fission products. In particular, a chemical liner may be necessary for niobium, tantalum, zirconium, or silicon carbide-based systems. Multiple choices exist for the configuration of a chemical liner within the cladding; there is no clear solution that eliminates all concerns over the mechanical performance of a clad/liner system. A series of tests to evaluate the performance of candidate materials in contact with real and simulated fission products is outlined
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