Title:	Application of UWB1 code on tritium production calculations
Authors:	Mašata, David Vilímová, Eva Škoda, Radek Lovecký, Martin
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.
Issue Date:	2019
Publisher:	American Society of Mechanical Engineers (ASME)
Document type:	konferenční příspěvek conferenceObject
URI:	2-s2.0-85071372558 http://hdl.handle.net/11025/36550
ISBN:	978-4-88898-305-1
Keywords in different language:	tritium production;UWB1;nuclear fusion fuel;TPBAR
Abstract in different language:	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.
Rights:	Plný text je přístupný v rámci univerzity přihlášeným uživatelům. © ASME
Appears in Collections:	Konferenční příspěvky / Conference papers (RICE) Konferenční příspěvky / Conference papers (KEE) OBD

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