Publication | Open Access
A METHOD OF CALCULATING FISSION GAS DIFFUSION FROM UO$sub 2$ FUEL AND ITS APPLICATION TO THE X-2-f LOOP TEST
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1957
Year
Nuclear CeramicChemical EngineeringEngineeringNuclear FissionNuclear FuelNuclear ReactorsNuclear Fuel EnrichmentNatural SciencesOxide CylinderThermodynamicsNuclear ExperimentsChemical KineticsNuclear EngineeringSheath Puncture ExperimentsNuclear EnergyFission Gas
A method for calculating the fraction of rare gas fission products that diffuses out of a UO/sub 2/ fuel element under reactor conditions is outlined. The method is based on the values of the diffusion constant found in laboratory experiments, and assumes that these remain unaltered during the period that the fuel is in the reactor. The method has been applied to two types of oxide in the X-2-f loop test of 1956 and the results compared with the amounts of fission gas found by analysis of the gases collected in sheath puncture experiments. The calculated values depend heavily on the estimated temperatures in the fuel. They are in close agreement with the experimental values provided that, in calculating the temperature, certain assumptions are made regarding the thermal expansion of the oxide cylinder. (auth)