A Model for the Transient Release of Fission Products from UO2Fuel: Gasout Code Description
| Autor: | Walter P. Dovigo, Lorne D. Macdonald, Mukesh Tayal, Erl Kohn |
|---|---|
| Rok vydání: | 1989 |
| Předmět: |
Equiaxed crystals
Nuclear and High Energy Physics Fission products Nuclear fission product Fission Chemistry 020209 energy Nuclear engineering food and beverages Radioactive waste chemistry.chemical_element 02 engineering and technology Uranium Condensed Matter Physics Nuclear physics Grain growth 020303 mechanical engineering & transports 0203 mechanical engineering Nuclear Energy and Engineering 0202 electrical engineering electronic engineering information engineering Grain boundary |
| Zdroj: | Nuclear Technology. 85:300-313 |
| ISSN: | 1943-7471 0029-5450 |
| DOI: | 10.13182/nt89-a34252 |
| Popis: | The GASOUT computer code calculates fission gas release, activity release, and fission product swelling in a Canada deuterium uranium (CANDU) fuel element during transient (nonequilibrium) conditions such as load following, postulated accidents involving high temperatures, and temporary postdryout operation of fuel. The phenomena modeled in the code described in this paper include production of isotypes; diffusion; grain growth, both equiaxed and columnar; sweeping by grain boundaries; growth of grain-boundary bubbles; interlinkage of bubbles; grain-face separation; release by melting; radioactive decay; and effect of precursors. |
| Databáze: | OpenAIRE |
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