Title:	Enhanced nuclear safety of spent fuel
Authors:	Závorka, Jiří Lovecký, Martin Jiřičková, Jana Škoda, Radek
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.
Issue Date:	2019
Publisher:	American Society of Mechanical Engineers (ASME)
Document type:	konferenční příspěvek conferenceObject
URI:	2-s2.0-85071394372 http://hdl.handle.net/11025/36552
ISBN:	978-4-88898-305-1
Keywords in different language:	spent fuel;nuclear safety;safety analysis;spent fuel cask
Abstract in different language:	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.
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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