Application of serpent code calculations: tritium production using fast neutrons
dc.contributor.author | Vilímová, Eva | |
dc.contributor.author | Mašata, David | |
dc.contributor.author | Lovecký, Martin | |
dc.contributor.author | Škoda, Radek | |
dc.date.accessioned | 2020-03-02T11:00:27Z | |
dc.date.available | 2020-03-02T11:00:27Z | |
dc.date.issued | 2019 | |
dc.description.abstract-translated | This paper focuses on tritium production by fast neutrons (especially neutrons with energy 14.029 MeV). Research on tritium production is important and useful in designing future fusion reactors since tritium serves as the principal fuel in DT fusion. Many neutron reactions of different types of target elements have been explored and some observations have been made. The reaction rate is the basis for an evaluated summary in this paper. Numerous calculations were made using the relatively new Serpent code, the Monte Carlo code initially developed for reactor physics calculations, but continuously updated to become general purpose Monte Carlo particle transport code. | en |
dc.format | 6 s. | cs |
dc.format.mimetype | application/pdf | |
dc.identifier.citation | POÓR, P., BASL, J. Readiness of Companies in Relation to Industry 4.0 Implementation. In: Double-blind peer-reviewed proceedings part II. of the International Scientific Conference Hradec Economic Days 2019. Hradec Králové: University of Hradec Králové, 2019. s. 236-248. ISBN 978-80-7435-736-7 , ISSN 2464-6059. | en |
dc.identifier.doi | 10.1299/jsmeicone.2019.27.2044 | |
dc.identifier.isbn | 978-4-88898-305-1 | |
dc.identifier.obd | 43928390 | |
dc.identifier.uri | 2-s2.0-85071364565 | |
dc.identifier.uri | http://hdl.handle.net/11025/36574 | |
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 | serpent code | en |
dc.subject.translated | nuclear fusion fuel | en |
dc.subject.translated | reaction rate | en |
dc.subject.translated | fast neutrons | en |
dc.subject.translated | calculations | en |
dc.title | Application of serpent code calculations: tritium production using fast neutrons | en |
dc.type | konferenční příspěvek | cs |
dc.type | conferenceObject | en |
dc.type.status | Peer-reviewed | en |
dc.type.version | publishedVersion | en |