PRELIMINARY IRRADIATIONS OF THE CERAMIC FUELS UO$sub 2$, UO$sub 2$-Zr, AND ThO$sub 2$-UO$sub 2$. Final Report on Metallurgy Program 6.2.2
A series of preliminary irradiations has been made on ceramic fuels of interest for thermal reactors. Most of the studies were devoted to ThO/sub 2/-U0/ sub 2/ compositions because of certain advantages possessed by this material. ThO/sub 2/-2.5 wt.% U0/sub 2/ and ThO/sub 2/-10 wt.% pellets were irradiated bare and in stainless steel, Zircaloy, and aluminum alloy claddings, with the annulus between the ceramic pellets and the cladding filled with air, a helium -argon mixture, NaK, or lead. It was found that the ThO/sub 2/-U0/sub 2/ specimens were highly stable under irradiation. The U0/sub 2/ and U0/sub 2/-Zr specimens showed a relatively greater tendency to fracture during irradiation. Assemblies of ThO/ sub 2/-10 wt.% U0/sub 2/ pellets leadbonded to aluminum alloy cladding were found to be able to withstand higher heat fluxes without damage than similar assemblies with helium -argon bonding. (auth)
- Research Organization:
- Argonne National Lab., Lemont, Ill.
- DOE Contract Number:
- W-31109-ENG-38
- NSA Number:
- NSA-13-002527
- OSTI ID:
- 4295274
- Report Number(s):
- ANL-5675
- Country of Publication:
- United States
- Language:
- English
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