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
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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
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OECD FORD obor
20305 - Nuclear related engineering; (nuclear physics to be 1.3);
Návaznosti výsledku
Projekt
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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
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e-ISSN
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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
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