STABILITY OF BeO-UO$sub 2$ REACTOR FUEL MATERIAL DURING IRRADIATION. MARITIME GAS-COOLED REACTOR PROGRAM
Technical Report
·
OSTI ID:4032209
Fuel pellets composed of 19 vol.% UO/sub 2/ dispersed in a beryllium oxide matrix were irradiated to an exposure of approximately 2 x 10/sup 20/ fissions/cm/sup 3/ at an estimated pellet temperature of 2200 deg to 2300 deg F. The UO/sub 2/ was present in the form of irregularly shaped grains of approximately 125 mu average diameter. No significant change in the dimensions of the pellets or in the lattice parameters of the beryllia matrix was observed. The crushing strength of the pellets and their resistance to abrasion were reduced as a result of the irradiation. (auth)
- Research Organization:
- General Atomic Div., General Dynamics Corp., San Diego, Calif.
- NSA Number:
- NSA-15-016126
- OSTI ID:
- 4032209
- Report Number(s):
- GA-2065
- Country of Publication:
- United States
- Language:
- English
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