CORROSION RESISTANCE AND HIGH-TEMPERATURE BEHAVIOUR OF ZR-BASED CLADDING MATERIALS WITH CHROMIUM-BASED PVD COATINGS
Identifikátory výsledku
Kód výsledku v IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F60193247%3A_____%2F21%3AN0000012" target="_blank" >RIV/60193247:_____/21:N0000012 - isvavai.cz</a>
Nalezeny alternativní kódy
RIV/26722445:_____/21:N0000101
Výsledek na webu
<a href="https://www.euronuclear.org/scientific-resources/conference-proceedings/#1559592636459-42447d8c-0fcc" target="_blank" >https://www.euronuclear.org/scientific-resources/conference-proceedings/#1559592636459-42447d8c-0fcc</a>
DOI - Digital Object Identifier
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Alternativní jazyky
Jazyk výsledku
angličtina
Název v původním jazyce
CORROSION RESISTANCE AND HIGH-TEMPERATURE BEHAVIOUR OF ZR-BASED CLADDING MATERIALS WITH CHROMIUM-BASED PVD COATINGS
Popis výsledku v původním jazyce
"Following the Fukushima Daiichi accident, new nuclear fuel cladding designs improving the performance and enhancing nuclear power plants' safety have been extensively investigated. The chromium-based accident tolerant fuel cladding coating designs were developed by ALVEL in the frame of the project sponsored by the Ministry of Industry and Trade and UJP PRAHA in collaboration with CTU in Prague. This study introduces a set of experiments determining a wide range of coated cladding material properties. Metallic Cr, CrAl and multicomponent CrN + Cr were tested, focusing on long-term corrosion resistance during normal operating conditions, high-temperature oxidation in the steam environment and mechanical properties during an accidental transient. All coatings revealed enhancement in corrosion resistance when compared to Zr alloy. However, diffusion of chromium into the zirconium substrate was observed for the metallic chromium coatings at temperatures above Cr-Zr eutectic. Coating deposition is further beneficial for claddings' mechanical properties. Overall, all tested coatings may be attractive candidates as possible ATF claddings."
Název v anglickém jazyce
CORROSION RESISTANCE AND HIGH-TEMPERATURE BEHAVIOUR OF ZR-BASED CLADDING MATERIALS WITH CHROMIUM-BASED PVD COATINGS
Popis výsledku anglicky
"Following the Fukushima Daiichi accident, new nuclear fuel cladding designs improving the performance and enhancing nuclear power plants' safety have been extensively investigated. The chromium-based accident tolerant fuel cladding coating designs were developed by ALVEL in the frame of the project sponsored by the Ministry of Industry and Trade and UJP PRAHA in collaboration with CTU in Prague. This study introduces a set of experiments determining a wide range of coated cladding material properties. Metallic Cr, CrAl and multicomponent CrN + Cr were tested, focusing on long-term corrosion resistance during normal operating conditions, high-temperature oxidation in the steam environment and mechanical properties during an accidental transient. All coatings revealed enhancement in corrosion resistance when compared to Zr alloy. However, diffusion of chromium into the zirconium substrate was observed for the metallic chromium coatings at temperatures above Cr-Zr eutectic. Coating deposition is further beneficial for claddings' mechanical properties. Overall, all tested coatings may be attractive candidates as possible ATF claddings."
Klasifikace
Druh
D - Stať ve sborníku
CEP obor
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OECD FORD obor
20506 - Coating and films
Návaznosti výsledku
Projekt
Výsledek vznikl pri realizaci vícero projektů. Více informací v záložce Projekty.
Návaznosti
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)
Ostatní
Rok uplatnění
2021
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
Sborník z konference TopFuel 2021
ISBN
978-92-95064-35-5
ISSN
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e-ISSN
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Počet stran výsledku
10
Strana od-do
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Název nakladatele
Europian Nuclear Society
Místo vydání
Brussels, Belgium
Místo konání akce
Santander, Spain
Datum konání akce
24. 10. 2021
Typ akce podle státní příslušnosti
WRD - Celosvětová akce
Kód UT WoS článku
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