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Molybdenum-UO2 cermet irradiation at 1145 K.Two molybdenum-uranium dioxide cermet fuel pins with molybdenum clad were fission-heated in a forced-convection helium coolant for sufficient time to achieve 5.3% burnup. The cermet core contained 20 wt % of 93.2% enriched uranium dioxide. The results were as follows: there was no visible change in the appearance of the molybdenum clad during irradiation; the maximum increase in diameter of the fuel pins was 0.8%; there was no migration of uranium dioxide along grain boundaries and no evident interaction between molybdenum and uranium dioxide; and, finally, approximately 12% of the fission gas formed was released from the cermet core into the gas plenum.
Document ID
Document Type
Conference Paper
Mcdonald, G.
(NASA Lewis Research Center Cleveland, Ohio, United States)
Date Acquired
August 6, 2013
Publication Date
October 1, 1971
Subject Category
Nuclear Engineering
Meeting Information
American Nuclear Society, Winter Meeting(Miami Beach, FL)
Distribution Limits
No Preview Available