Home / Publications / Journals / Nuclear Technology / Volume 81 / Number 1
Nuclear Technology / Volume 81 / Number 1 / April 1988 / Pages 7-12
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT88-A34074
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Release characteristics of volatile metallic fission products from the coated fuel particle and the reactor core for a very high temperature gas-cooled reactor during its power operation has been studied using numerical analysis. A computer code FORNAX, based on Fick’s diffusion law and the evaporation mass transfer relation, has been developed, which considers, in particular, distributions and time histories of power density, fuel temperature, and failed and degraded fuel particle fractions in the core. Applicability of the code to evaluate the core design has been shown and the following have been indicated on the release of cesium from the reactor: