Enhanced nuclear safety of spent fuel
| dc.contributor.author | Závorka, Jiří | |
| dc.contributor.author | Lovecký, Martin | |
| dc.contributor.author | Jiřičková, Jana | |
| dc.contributor.author | Škoda, Radek | |
| dc.date.accessioned | 2020-03-02T11:00:24Z | |
| dc.date.available | 2020-03-02T11:00:24Z | |
| dc.date.issued | 2019 | |
| dc.description.abstract-translated | Criticality safety analysis of highly enriched nuclear fuels requires sophisticated calculation techniques like burnup credit in order to show that fuel reactivity is below legislative limits. However, new fuel types are continuously introduced and the increase of the boron concentration in the absorbing tubes of spent fuel pool racks or spent fuel casks is necessary. Borated steel or aluminum alloys may not be economically reasonable and other types of absorber components can be feasible. Absorber tubes with neutron traps between them are very effective from the neutronics point of view; the only better solution is to place absorbers directly within the fuel assembly. This study shows a concept for enhanced nuclear safety of spent fuel. The analysis is dedicated to the selection and optimization of the most suitable materials for this concept. | en |
| dc.format | 4 s. | cs |
| dc.format.mimetype | application/pdf | |
| dc.identifier.citation | ZÁVORKA, J., LOVECKÝ, M., JIŘIČKOVÁ, J., ŠKODA, R. Enhanced nuclear safety of spent fuel. In: Proceedings of the 27th International Conference on Nuclear Engineering (ICONE27). New York: American Society of Mechanical Engineers (ASME), 2019. s. 1-4. ISBN 978-4-88898-305-1. | en |
| dc.identifier.doi | 10.1299/jsmeicone.2019.27.1906 | |
| dc.identifier.isbn | 978-4-88898-305-1 | |
| dc.identifier.obd | 43926259 | |
| dc.identifier.uri | 2-s2.0-85071394372 | |
| dc.identifier.uri | http://hdl.handle.net/11025/36552 | |
| dc.language.iso | en | en |
| dc.project.ID | TK01030103/Ex-core měření neutronového toku pro reaktory IV. generace | cs |
| dc.publisher | American Society of Mechanical Engineers (ASME) | en |
| dc.relation.ispartofseries | Proceedings of the 27th International Conference on Nuclear Engineering (ICONE27) | en |
| dc.rights | Plný text je přístupný v rámci univerzity přihlášeným uživatelům. | cs |
| dc.rights | © ASME | en |
| dc.rights.access | restrictedAccess | en |
| dc.subject.translated | spent fuel | en |
| dc.subject.translated | nuclear safety | en |
| dc.subject.translated | safety analysis | en |
| dc.subject.translated | spent fuel cask | en |
| dc.title | Enhanced nuclear safety of spent fuel | en |
| dc.type | konferenční příspěvek | cs |
| dc.type | conferenceObject | en |
| dc.type.status | Peer-reviewed | en |
| dc.type.version | publishedVersion | en |