RADIATION ENHANCED DIFFUSION IN NUCLEAR CARBIDES
The radiation enhanced diffusion (coefficient D*) of 238-Pu and 233-U in polycrystalline and single crystalline UC and in sintered (U,Pu)C and 3 and 15 % Pu was measured in a nuclear reactor during fission. Conventional diffusion sandwiches with thin tracer layers and a RF furnace for temperature variation (130 to 1400 degrees C) were used. D* was found to be completely athermal below 1100 degrees C and to increase linearly with fission rate, F, according to D* = AF with A = (2.5 +- 0.5) x 10**-30cm**5. The mechanism of enhancement is discussed as well as the implications on technologically important processes. The results are related to recent fission damage studies and compared with those obtained on other nuclear fuels, UO-2 and UN.
Bibliographic Reference: TRANSPORT IN NON-STOICHIOMETRIC COMPOUNDS, PUBLISHED BY PLENUM PUBLISHING CORPORATION, 1985, PP. 331-342.
Record Number: 1989124104600 / Last updated on: 1987-01-01
Available languages: en