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- W2071593588 abstract "Release behavior of fission products from ZrC-coated UO2 particles was studied by a postirradiation heating test at 1600°C (1873 K) for 4500 h and subsequent postheating examinations. The fission gas release monitoring and the postheating examinations revealed that no pressure vessel failure occurred in the test. Ceramographic observations showed no palladium attack and thermal degradation of ZrC. Fission products of 137Cs 134Cs, 106Ru, 144Ce, 154Eu and 155Eu were released from the coated particles through the coating layers during the postirradiation heating. Diffusion coefficients of 137Cs and 106Ru in the ZrC coating layer were evaluated from the release curves based on a diffusion model. 137Cs retentiveness of the ZrC coating layer was much better than that of the SiC coating layer." @default.
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- W2071593588 date "1995-07-01" @default.
- W2071593588 modified "2023-10-14" @default.
- W2071593588 title "Fission product release from ZrC-coated fuel particles during postirradiation heating at 1600°C" @default.
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- W2071593588 doi "https://doi.org/10.1016/0022-3115(95)00032-1" @default.
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