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Development of Cr Cold-Spray Coated Fuel Cladding with Enhanced Accident Tolerance

Identifikátory výsledku

  • Kód výsledku v IS VaVaI

    <a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21340%2F18%3A00317521" target="_blank" >RIV/68407700:21340/18:00317521 - isvavai.cz</a>

  • Výsledek na webu

    <a href="https://www.sciencedirect.com/science/article/pii/S1738573317307283" target="_blank" >https://www.sciencedirect.com/science/article/pii/S1738573317307283</a>

  • DOI - Digital Object Identifier

    <a href="http://dx.doi.org/10.1016/j.net.2017.12.011" target="_blank" >10.1016/j.net.2017.12.011</a>

Alternativní jazyky

  • Jazyk výsledku

    angličtina

  • Název v původním jazyce

    Development of Cr Cold-Spray Coated Fuel Cladding with Enhanced Accident Tolerance

  • Popis výsledku v původním jazyce

    Accident Tolerant Fuels (ATF) are currently of high interest to researchers in the nuclear industry as well as in governmental and international organizations. One widely studied ATF concept is multi-layer cladding (also known as coated cladding). This concept is based on a traditional Zr-based alloy (Zircaloy-4, M5, E110, ZIRLO etc.) serving as a substrate. Different protective materials are applied to the substrate surface by various techniques, thus enhancing the accident tolerance of the fuel. This study focuses on the results of testing of Zircaloy-4 coated with pure chromium metal using the cold spray technique. In comparison with other deposition methods, e.g. PVD, laser coating or CVD, the cold spray technique is more cost efficient due to lower energy consumption and high deposition rates, making it more suitable for industry-scale production. The Cr-coated samples were tested at different conditions (500°C steam, 1200°C steam, PWR pressurization test), pre-characterized and post-characterized by various techniques such as SEM, EDX or nanoindentation; results are discussed. Results of the steady-state fuel performance simulations using the Bison code predicted the concept’s feasibility. It is concluded that cold-spray Cr-coating has high potential benefits but requires further optimization and out-of-pile and in-pile testing.

  • Název v anglickém jazyce

    Development of Cr Cold-Spray Coated Fuel Cladding with Enhanced Accident Tolerance

  • Popis výsledku anglicky

    Accident Tolerant Fuels (ATF) are currently of high interest to researchers in the nuclear industry as well as in governmental and international organizations. One widely studied ATF concept is multi-layer cladding (also known as coated cladding). This concept is based on a traditional Zr-based alloy (Zircaloy-4, M5, E110, ZIRLO etc.) serving as a substrate. Different protective materials are applied to the substrate surface by various techniques, thus enhancing the accident tolerance of the fuel. This study focuses on the results of testing of Zircaloy-4 coated with pure chromium metal using the cold spray technique. In comparison with other deposition methods, e.g. PVD, laser coating or CVD, the cold spray technique is more cost efficient due to lower energy consumption and high deposition rates, making it more suitable for industry-scale production. The Cr-coated samples were tested at different conditions (500°C steam, 1200°C steam, PWR pressurization test), pre-characterized and post-characterized by various techniques such as SEM, EDX or nanoindentation; results are discussed. Results of the steady-state fuel performance simulations using the Bison code predicted the concept’s feasibility. It is concluded that cold-spray Cr-coating has high potential benefits but requires further optimization and out-of-pile and in-pile testing.

Klasifikace

  • Druh

    J<sub>imp</sub> - Článek v periodiku v databázi Web of Science

  • CEP obor

  • OECD FORD obor

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

Návaznosti výsledku

  • Projekt

  • Návaznosti

    S - Specificky vyzkum na vysokych skolach

Ostatní

  • Rok uplatnění

    2018

  • Kód důvěrnosti údajů

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

Údaje specifické pro druh výsledku

  • Název periodika

    Nuclear Engineering and Technology

  • ISSN

    1738-5733

  • e-ISSN

  • Svazek periodika

    50

  • Číslo periodika v rámci svazku

    2

  • Stát vydavatele periodika

    KR - Korejská republika

  • Počet stran výsledku

    8

  • Strana od-do

    229-236

  • Kód UT WoS článku

    000427561100004

  • EID výsledku v databázi Scopus

    2-s2.0-85043362218