Home / Publications / Journals / Nuclear Technology / Volume 14 / Number 1
Nuclear Technology / Volume 14 / Number 1 / April 1972 / Pages 65-70
Technical Paper / Session on Physics of Nuclear Materials Safeguards / Fuel / dx.doi.org/10.13182/NT72-A31099
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A fuel-specimen model is developed to describe the diametral swelling behavior of W-Re clad, oxide fuel specimens irradiated at a clad surface temperature in excess of 1200°C. The model is based on experimental observations at elevated fuel temperatures that fission-gas bubbles form to expand the fuel but that bubble and lenticular void movement, as a result of vaporphase transport, provide a mechanism for redensifying the fuel so that swelling is a continuous steady-state process. Good agreement with experimentally measured diametral changes is obtained by application of the model.