Application of UWB1 code on tritium production calculations
| dc.contributor.author | Mašata, David | |
| dc.contributor.author | Vilímová, Eva | |
| dc.contributor.author | Škoda, Radek | |
| dc.contributor.author | Lovecký, Martin | |
| dc.date.accessioned | 2020-03-02T11:00:24Z | |
| dc.date.available | 2020-03-02T11:00:24Z | |
| dc.date.issued | 2019 | |
| dc.description.abstract-translated | The article focuses on the possibilities of the production of fusion reactors fuel - tritium. Nuclear fusion is one of the most promising ways to tackle rising power consumption. The aim of this research is to propose the most suitable tritium breeder. Numerous calculations were carried out by using the new fast computing code UWB1. A brief overview of reactions between thermal neutrons and natural isotopes of various types of elements was made. The reaction rates have been evaluated and resulted in a brief summary of the proposed materials. | en |
| dc.format | 4 s. | cs |
| dc.format.mimetype | application/pdf | |
| dc.identifier.citation | MAŠATA, D., VILÍMOVÁ, E., ŠKODA, R., LOVECKÝ, M. Application of UWB1 code on tritium production calculations. 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.2019.27.2016 | |
| dc.identifier.isbn | 978-4-88898-305-1 | |
| dc.identifier.obd | 43926249 | |
| dc.identifier.uri | 2-s2.0-85071372558 | |
| dc.identifier.uri | http://hdl.handle.net/11025/36550 | |
| dc.language.iso | en | en |
| dc.project.ID | TE01020455/Centrum pokročilých jaderných technologií (CANUT) | 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 | tritium production | en |
| dc.subject.translated | UWB1 | en |
| dc.subject.translated | nuclear fusion fuel | en |
| dc.subject.translated | TPBAR | en |
| dc.title | Application of UWB1 code on tritium production calculations | en |
| dc.type | konferenční příspěvek | cs |
| dc.type | conferenceObject | en |
| dc.type.status | Peer-reviewed | en |
| dc.type.version | publishedVersion | en |