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Thermomechanical assessment of fuel rod cladding made of zirconium alloy and silicon carbide material during reactivity-initiated accident

The result's identifiers

  • Result code in IS VaVaI

    <a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F00216305%3A26210%2F18%3APU124953" target="_blank" >RIV/00216305:26210/18:PU124953 - isvavai.cz</a>

  • Result on the web

    <a href="http://dx.doi.org/10.1080/00295639.2017.1373518" target="_blank" >http://dx.doi.org/10.1080/00295639.2017.1373518</a>

  • DOI - Digital Object Identifier

    <a href="http://dx.doi.org/10.1080/00295639.2017.1373518" target="_blank" >10.1080/00295639.2017.1373518</a>

Alternative languages

  • Result language

    angličtina

  • Original language name

    Thermomechanical assessment of fuel rod cladding made of zirconium alloy and silicon carbide material during reactivity-initiated accident

  • Original language description

    This paper presents a thermomechanical assessment of various types of fuel cladding during a reactivity-initiated accident (RIA) which is simulated by the finite element analysis program ANSYS. Four cladding concepts are analyzed; one concept considers currently used zirconium alloy and three concepts consider silicon carbide (SiC) material. The SiC claddings consist either of composite material or of a twolayered structure formed of SiC composite and monolithic SiC. Each cladding is analyzed for two states of nuclear fuel: fresh and high burnup. A gap that exists between fuel pellets and cladding in fresh state is either reduced or removed in a high burnup state. It was shown that zirconium cladding resists RIA conditions very well in fresh state, however, in high burnup state significant stress and plastic strain occur. The SiC cladding was shown to have many advantages over zirconium alloy. Nevertheless, its lower strength appears to be critical in RIA conditions when cladding needs to withstand exceeding loading after the fuel-cladding gap disappears due to the expansion of the fuel pellet.

  • Czech name

  • Czech description

Classification

  • Type

    J<sub>imp</sub> - Article in a specialist periodical, which is included in the Web of Science database

  • CEP classification

  • OECD FORD branch

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

Result continuities

  • Project

    <a href="/en/project/LO1202" target="_blank" >LO1202: NETME CENTRE PLUS</a><br>

  • Continuities

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

Others

  • Publication year

    2018

  • Confidentiality

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

Data specific for result type

  • Name of the periodical

    NUCLEAR SCIENCE AND ENGINEERING

  • ISSN

    0029-5639

  • e-ISSN

    1943-748X

  • Volume of the periodical

    189

  • Issue of the periodical within the volume

    1

  • Country of publishing house

    US - UNITED STATES

  • Number of pages

    13

  • Pages from-to

    69-81

  • UT code for WoS article

    000426587700005

  • EID of the result in the Scopus database

    2-s2.0-85036618658