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Experimental behavior of chromium-based PVD coated cladding materials during LOCA transient

Identifikátory výsledku

  • Kód výsledku v IS VaVaI

    <a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21220%2F20%3A00340302" target="_blank" >RIV/68407700:21220/20:00340302 - isvavai.cz</a>

  • Nalezeny alternativní kódy

    RIV/26722445:_____/19:N0000076 RIV/68407700:21340/20:00340302

  • Výsledek na webu

    <a href="http://globaltopfuel.ans.org/" target="_blank" >http://globaltopfuel.ans.org/</a>

  • DOI - Digital Object Identifier

Alternativní jazyky

  • Jazyk výsledku

    angličtina

  • Název v původním jazyce

    Experimental behavior of chromium-based PVD coated cladding materials during LOCA transient

  • Popis výsledku v původním jazyce

    Development of nuclear fuels with enhanced accident tolerance (ATF) is one of the main current objectives of researchers worldwide. The contribution focuses on chromium-based PVD coated cladding concept (Cr and CrN+Cr) developed in cooperation of UJP PRAHA a.s. and Czech Technical University in Prague. The results presented in the past showed high oxidation resistance of thin Cr and multicomponent CrN+Cr coatings and improved cladding ductility of samples after high-temperature transients. A more complex approach to simulate LOCA transient is applied in the presented study. A set of experiments was performed to understand the behavior of chromium-based coated claddings during the whole LOCA phenomena. The presented results show the influence of studied coatings on high-temperature cladding creep and related phenomena such as ballooning size, time to burst, cracking of coating, high-temperature oxidation through cracked and intact coatings. Secondary oxidation and hydriding from the inner uncoated surface after cladding failure is discussed as well. Microhardness and microstructure analysis of the material after testing revealed local cladding damage. The mechanical properties of cladding after LOCA can locally deteriorate due to cracks in coating, but the influence on the bulk mechanical behavior of the whole fuel cladding and cladding bundles needs to be further investigated.

  • Název v anglickém jazyce

    Experimental behavior of chromium-based PVD coated cladding materials during LOCA transient

  • Popis výsledku anglicky

    Development of nuclear fuels with enhanced accident tolerance (ATF) is one of the main current objectives of researchers worldwide. The contribution focuses on chromium-based PVD coated cladding concept (Cr and CrN+Cr) developed in cooperation of UJP PRAHA a.s. and Czech Technical University in Prague. The results presented in the past showed high oxidation resistance of thin Cr and multicomponent CrN+Cr coatings and improved cladding ductility of samples after high-temperature transients. A more complex approach to simulate LOCA transient is applied in the presented study. A set of experiments was performed to understand the behavior of chromium-based coated claddings during the whole LOCA phenomena. The presented results show the influence of studied coatings on high-temperature cladding creep and related phenomena such as ballooning size, time to burst, cracking of coating, high-temperature oxidation through cracked and intact coatings. Secondary oxidation and hydriding from the inner uncoated surface after cladding failure is discussed as well. Microhardness and microstructure analysis of the material after testing revealed local cladding damage. The mechanical properties of cladding after LOCA can locally deteriorate due to cracks in coating, but the influence on the bulk mechanical behavior of the whole fuel cladding and cladding bundles needs to be further investigated.

Klasifikace

  • Druh

    D - Stať ve sborníku

  • CEP obor

  • OECD FORD obor

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

Návaznosti výsledku

  • Projekt

  • Návaznosti

    N - Vyzkumna aktivita podporovana z neverejnych zdroju

Ostatní

  • Rok uplatnění

    2020

  • Kód důvěrnosti údajů

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

Údaje specifické pro druh výsledku

  • Název statě ve sborníku

    Global/Top Fuel 2019: International Nuclear Fuel Cycle Conference/Light Water Reactor Fuel Performance Conference

  • ISBN

    978-0-89448-771-2

  • ISSN

  • e-ISSN

  • Počet stran výsledku

    8

  • Strana od-do

    904-911

  • Název nakladatele

    American Nuclear Society

  • Místo vydání

    La Grande Park, Illinois

  • Místo konání akce

    Seattle, WA

  • Datum konání akce

    22. 9. 2019

  • Typ akce podle státní příslušnosti

    WRD - Celosvětová akce

  • Kód UT WoS článku