Full metadata record
| DC pole | Hodnota | Jazyk |
|---|---|---|
| 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.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.isbn | 978-4-88898-305-1 | |
| dc.identifier.uri | 2-s2.0-85071364565 | |
| dc.identifier.uri | http://hdl.handle.net/11025/36574 | |
| dc.format | 6 s. | cs |
| dc.format.mimetype | application/pdf | |
| dc.language.iso | en | en |
| 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.title | Application of serpent code calculations: tritium production using fast neutrons | en |
| dc.type | konferenční příspěvek | cs |
| dc.type | conferenceObject | en |
| dc.rights.access | restrictedAccess | en |
| dc.type.version | publishedVersion | en |
| 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.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.identifier.doi | 10.1299/jsmeicone.2019.27.2044 | |
| dc.type.status | Peer-reviewed | en |
| dc.identifier.obd | 43928390 | |
| dc.project.ID | TE01020455/Centrum pokročilých jaderných technologií (CANUT) | cs |
| Vyskytuje se v kolekcích: | Konferenční příspěvky / Conference papers (KEE) Konferenční příspěvky / Conference papers (RICE) OBD | |
Soubory připojené k záznamu:
| Soubor | Velikost | Formát | |
|---|---|---|---|
| Vilimova_ICONE27-2044F.pdf | 513,57 kB | Adobe PDF | Zobrazit/otevřít Vyžádat kopii |
Použijte tento identifikátor k citaci nebo jako odkaz na tento záznam:
http://hdl.handle.net/11025/36574Všechny záznamy v DSpace jsou chráněny autorskými právy, všechna práva vyhrazena.