THE IRRADIATION BEHAVIOR OF BERYLLIUM OXIDE DISPERSION FUELS
Technical Report
·
OSTI ID:4673299
Specimens of beryllium oxide-based dispersion fuels containing between 3 and 26 vol % of UO/sub 2/--ThO/sub 2/ solid solution were irradiated to fission densities of 2 to 14 X 10/sup 19/ fissions/cm/sup 3/ of total specimens (equivalent burnups of 80 to 230%) at temperatures of 600 to 850 deg C. The experiment was primarily designed to investigate fission product damage although some fast neutron damage did occurr in the matrix. The specimens showed excellent resistance to fission product damage; dimenisional changes were small, fission product escape was generally only that expected by recoil and there was no sign of cracking due to thermal stresses although these reached estimated values of about 30,000 psi in some specimens. Metallographic examination showed that some weakening of the matrix grain boundaries had occurred and some preliminary x-ray results suggested that the matrix was in a state of strain. It is suggested that these effects could be due either to fast neutron damage in the matrix or swelling of the fuel particles. The experiment did not provide any conclusive evidence for the superiority of coarse fuel particles (100 to 180 mu ) over fine fuel particles (<10 mu ) although the dimensional changes and the degree of matrix strain were higher in the latter specimens. (auth)
- Research Organization:
- Australia. Atomic Energy Commission Research Establishment, Lucas Heights, New South Wales
- NSA Number:
- NSA-17-031016
- OSTI ID:
- 4673299
- Report Number(s):
- AAEC/E-106
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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