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CLADDING SURVEY FOR THE ENRICO FERMI REACTOR U-15 Wt.% Mo BASE DISPERSION- TYPE FUEL ELEMENT

Technical Report ·
DOI:https://doi.org/10.2172/4184317· OSTI ID:4184317
Potential cladding materials for a flat-plate fuel element containing a dispersion of UC or UC/sub 2/ in U--15 wt.% Mo alloy were surveyed on the bases of compatibility with the fissile compounds, matrix material, protective cover materials, and liquid sodium as well as the feasibility of fabricating fuel plates by roll cladding. Radiative-capture cross sections, thermodynamic data, eutectic and intermediate compound formation, mechanical properties, and corrosion by 1000 tained F Na are reported for austenitic stainless steels, chromium, nickel, niobium, molybdenum, tantalum, vanadium, and zirconium. It was recommended that "A" nickel (molybdenum barrier), Zr-3 wt.% Al. Nb--2 wt.% Cr, and Fansteel 82 be relected for investigation. (auth)
Research Organization:
Oak Ridge National Lab., Tenn. (US)
Sponsoring Organization:
US Atomic Energy Commission (AEC)
NSA Number:
NSA-14-019314
OSTI ID:
4184317
Report Number(s):
CF-60-4-118
Country of Publication:
United States
Language:
English