Home / Publications / Journals / Nuclear Technology / Volume 118 / Number 2
Nuclear Technology / Volume 118 / Number 2 / May 1997 / Pages 123-131
Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT97-A35372
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Fractional release of cesium from coated UO2 particles for the high-temperature gas-cooled reactor (HTGR) is investigated. Data are measured in an irradiation test that utilizes three kinds of coated particles of artificially failed particles; they are simulating through-coatings failed particles, as-manufactured SiC-failed particles, and intact particles. Through the comparison of measured and calculated fractional releases, a model is revised to accurately evaluate cesium fractional release. The fractional releases of cesium from fuel compacts, which are manufactured by the same method as the high-temperature engineering test reactor fuel and are irradiated in the sweep gas capsule, are also evaluated. The result shows that the revised model can accurately predict measured fractional releases.