A method of calculating fission gas diffusion from UO2 fuel and its application to the X-2-f loop test
Description
A method for calculating the fraction of the rare gas fission products that diffuses out of a UO2 fuel element under conditions In a reactor is outlined, The method is based on the values of the diffusion constant found in laboratory experiments, as described In CRDC-718, 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, as described in CRDC-719. 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. (author)
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43123872.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 22 p.
- Report number
- AECL--496
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 43123872
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- FISSION PRODUCTS; FISSION RATIO; GASEOUS DIFFUSION; NUCLEAR FUELS; RARE GASES; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; DIFFUSION; DIMENSIONLESS NUMBERS; ELEMENTS; ENERGY SOURCES; FLUIDS; FUELS; GASES; ISOTOPES; MATERIALS; NONMETALS; OXIDES; OXYGEN COMPOUNDS; RADIOACTIVE MATERIALS; REACTOR MATERIALS; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Notes
- 8 refs., 4 figs.
- Secondary number(s)
- CRDC--721