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Experimental behavior of chromium-based pvd coated cladding materials during loca transient

The result's identifiers

  • Result code in IS VaVaI

    <a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F19%3AN0000076" target="_blank" >RIV/26722445:_____/19:N0000076 - isvavai.cz</a>

  • Alternative codes found

    RIV/68407700:21220/20:00340302 RIV/68407700:21340/20:00340302

  • Result on the web

    <a href="http://www.ans.org/store/item-700433/" target="_blank" >http://www.ans.org/store/item-700433/</a>

  • DOI - Digital Object Identifier

Alternative languages

  • Result language

    angličtina

  • Original language name

    Experimental behavior of chromium-based pvd coated cladding materials during loca transient

  • Original language description

    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 hightemperature 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, hightemperature 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.

  • 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

    Result was created during the realization of more than one project. More information in the Projects tab.

  • 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

    Global/Top Fuel 2019 Seattle, WA, September 22-2, 2019

  • ISBN

    978-0-89448-771-2

  • ISSN

  • e-ISSN

  • Number of pages

    8

  • Pages from-to

    904-911

  • Publisher name

    American Nuclear Society

  • Place of publication

  • Event location

    Seattle, USA

  • Event date

    Sep 22, 2019

  • Type of event by nationality

    WRD - Celosvětová akce

  • UT code for WoS article