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Utilization of thorium in LWR fuels aiming at thermal conductivity improvements

The result's identifiers

  • Result code in IS VaVaI

    <a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21220%2F16%3A00310234" target="_blank" >RIV/68407700:21220/16:00310234 - isvavai.cz</a>

  • Result on the web

    <a href="http://dx.doi.org/10.1115/ICONE24-60300" target="_blank" >http://dx.doi.org/10.1115/ICONE24-60300</a>

  • DOI - Digital Object Identifier

    <a href="http://dx.doi.org/10.1115/ICONE24-60300" target="_blank" >10.1115/ICONE24-60300</a>

Alternative languages

  • Result language

    angličtina

  • Original language name

    Utilization of thorium in LWR fuels aiming at thermal conductivity improvements

  • Original language description

    One of the main drawbacks of uranium dioxide, which is used in almost all nuclear power reactors, is its low thermal conductivity. As a consequence, temperature at the center of fuel pellet is relatively high, because heat is poorly conducted away. To reach a higher level of safety, maximal temperature in any fuel pellet is one of the main limiting parameters, which restrict the fuel thermal output. This paper deals with the use of thorium in LWR fuels with the objective of fuel pellet maximal temperature reduction. Research investigating homogenous distribution of thorium dioxide (thoria) in uranium dioxide fuel has already been done and did not lead to considerable thermal conductivity improvements. The aim of this study is to investigate heterogeneous distribution of thorium in commonly used uranium dioxide fuel in the form of uranium and thorium pellets placed together.

  • Czech name

  • Czech description

Classification

  • Type

    D - Article in proceedings

  • CEP classification

    JF - Nuclear energy

  • OECD FORD branch

Result continuities

  • Project

    <a href="/en/project/TE01020455" target="_blank" >TE01020455: Centre for Advanced Nuclear Technologies (CANUT)</a><br>

  • Continuities

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

Others

  • Publication year

    2016

  • Confidentiality

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

Data specific for result type

  • Article name in the collection

    2016 24th International Conference on Nuclear Engineering, ICONE 24

  • ISBN

    978-0-7918-5001-5

  • ISSN

  • e-ISSN

  • Number of pages

    10

  • Pages from-to

  • Publisher name

    American Society of Mechanical Engineers - ASME

  • Place of publication

    New York

  • Event location

    Charlotte, North Carolina

  • Event date

    Jun 26, 2016

  • Type of event by nationality

    WRD - Celosvětová akce

  • UT code for WoS article

    000387191000014