Modeling Tritium Retention in Graphite for Fluoride-Salt-Cooled High-Temperature Reactors
| Autor: | Steven Huang, Kieran Dolan, Lin-Wen Hu, Micah Hackett |
|---|---|
| Rok vydání: | 2021 |
| Předmět: |
Nuclear and High Energy Physics
Materials science 020209 energy Radiochemistry Thermal desorption chemistry.chemical_element 02 engineering and technology Condensed Matter Physics 020303 mechanical engineering & transports 0203 mechanical engineering Nuclear Energy and Engineering chemistry Nuclear graphite 0202 electrical engineering electronic engineering information engineering Lithium Tritium Graphite Beryllium Molten salt Pebble |
| Zdroj: | Nuclear Technology. 207:1578-1598 |
| ISSN: | 1943-7471 0029-5450 |
| DOI: | 10.1080/00295450.2020.1829428 |
| Popis: | Mitigating the release of tritium produced from neutron irradiation of molten salts containing lithium or beryllium is a technical challenge for several advanced reactor designs. In a pebble bed Fl... |
| Databáze: | OpenAIRE |
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