PRELIMINARY IRRADIATIONS OF PuC AND UC-PuC
Preliminary irradiations were made of arc-cast specimens of RaC andd UC- PuC andd of pressed and sintered pellets of UC--RaC to determine the suitability of these materials for further development as possible fuels for liquid metal- cooled fast reactors. The PuC content in the mixedcarbide specimens was near 20 wt%. The specimens were irradiated as fuel rods in the fast reactor EBR-I. Maximum fuel burnup and temperature during irradiation were respectively 0. 10 metal atom percent and 650 deg C. The cast PuC specimens were found to have fractured to a greater extent under irradiation than did the cast mixed-carbide specimens. Dimensional chandges in those specimens which did not fracture were negligible. Fission gas release from the cast specimens was 0.24% of the theoretical yield. The pressed andd sintered pellets did not fracture under irradiation and showed negligible dimensional chandges. Fission gas release from the pellets was 12.0% of theoretical. The high gas release from the pressed and sintered specimens is attributed to a relatively high degree of open porosity which existed in the pellets. (auth)
- Research Organization:
- Argonne National Lab., Ill.
- DOE Contract Number:
- W-31109-ENG-38
- NSA Number:
- NSA-18-005813
- OSTI ID:
- 4127983
- Report Number(s):
- ANL-6678
- Country of Publication:
- United States
- Language:
- English
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