Enhanced nuclear safety of spent fuel

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F49777513%3A23220%2F19%3A43955260" target="_blank" >RIV/49777513:23220/19:43955260 - isvavai.cz</a>

Nalezeny alternativní kódy

RIV/68407700:21730/19:00339623

Výsledek na webu

<a href="https://www.jstage.jst.go.jp/article/jsmeicone/2019.27/0/2019.27_1906/_article/-char/en" target="_blank" >https://www.jstage.jst.go.jp/article/jsmeicone/2019.27/0/2019.27_1906/_article/-char/en</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1299/jsmeicone.2019.27.1906" target="_blank" >10.1299/jsmeicone.2019.27.1906</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Enhanced nuclear safety of spent fuel

Popis výsledku v původním jazyce

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.

Název v anglickém jazyce

Enhanced nuclear safety of spent fuel

Popis výsledku anglicky

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.

Druh

D - Stať ve sborníku

CEP obor

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OECD FORD obor

20305 - Nuclear related engineering; (nuclear physics to be 1.3);

Projekt

<a href="/cs/project/TK01030103" target="_blank" >TK01030103: Ex-core měření neutronového toku pro reaktory IV. generace</a><br>

Návaznosti

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Rok uplatnění

2019

Kód důvěrnosti údajů

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Název statě ve sborníku

Proceedings of the 27th International Conference on Nuclear Engineering (ICONE27)

ISBN

978-4-88898-305-1

ISSN

—

e-ISSN

2424-2934

Počet stran výsledku

4

Strana od-do

1-4

Název nakladatele

American Society of Mechanical Engineers (ASME)

Místo vydání

New York

Místo konání akce

Ibaraki, Japan

Datum konání akce

19. 5. 2019

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

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