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Title: Thermal compatibility studies of unirradiated uranium silicide dispersed in aluminum. [Reduced Enrichment for Research and Test Reactor]

Technical Report ·
DOI:https://doi.org/10.2172/6286269· OSTI ID:6286269

Powder metallurgy dispersions of uranium silicides in an aluminum matrix have been developed by the international Reduced Enrichment for Research and Test Reactors program as a new generation of proliferation-resistant fuels. A major issue of concern is the compatibility of the fuel with the matrix material and the dimensional stability of this fuel type. A total of 45 miniplate-type fuel plates were annealed at 400/sup 0/C for up to 1981 hours. A data base for the thermal compatibility of unirradiated uranium silicide dispersed in aluminum was established. No modification tested of a standard fuel plate showed any significant reduction of the plate swelling. The cause of the thermal growth of silicide fuel plates was determined to be a two-step process: (1) the reaction of the uranium silicide with aluminum to form U(AlSi)/sub 3/ and (2) the release of hydrogen and subsequent creep and pillowing of the fuel plate. 9 references, 4 figures, 6 tables.

Research Organization:
Argonne National Lab. (ANL), Argonne, IL (United States)
DOE Contract Number:
W-31-109-ENG-38
OSTI ID:
6286269
Report Number(s):
CONF-8410173-4; ON: DE85004037
Resource Relation:
Conference: International meeting on reduced enrichment for research and test reactors, Argonne, IL, USA, 14 Oct 1984
Country of Publication:
United States
Language:
English