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Enhanced nuclear safety of spent fuel

The result's identifiers

  • Result code in 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>

  • Alternative codes found

    RIV/68407700:21730/19:00339623

  • Result on the web

    <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>

Alternative languages

  • Result language

    angličtina

  • Original language name

    Enhanced nuclear safety of spent fuel

  • Original language description

    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.

  • Czech name

  • Czech description

Classification

  • Type

    D - Article in proceedings

  • CEP classification

  • OECD FORD branch

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

Result continuities

  • Project

    <a href="/en/project/TK01030103" target="_blank" >TK01030103: Ex-core Neutron Flux Measurement for the 4th. Generation Nuclear Reactors</a><br>

  • Continuities

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

Others

  • Publication year

    2019

  • Confidentiality

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

Data specific for result type

  • Article name in the collection

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

  • ISBN

    978-4-88898-305-1

  • ISSN

  • e-ISSN

    2424-2934

  • Number of pages

    4

  • Pages from-to

    1-4

  • Publisher name

    American Society of Mechanical Engineers (ASME)

  • Place of publication

    New York

  • Event location

    Ibaraki, Japan

  • Event date

    May 19, 2019

  • Type of event by nationality

    WRD - Celosvětová akce

  • UT code for WoS article