CORROSION RESISTANCE AND HIGH-TEMPERATURE BEHAVIOUR OF ZR-BASED CLADDING MATERIALS WITH CHROMIUM-BASED PVD COATINGS

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21220%2F21%3A00375232" target="_blank" >RIV/68407700:21220/21:00375232 - isvavai.cz</a>

Nalezeny alternativní kódy

RIV/26722445:_____/21:N0000101 RIV/60193247:_____/21:N0000012

Výsledek na webu

<a href="http://hdl.handle.net/10467/114520" target="_blank" >http://hdl.handle.net/10467/114520</a>

DOI - Digital Object Identifier

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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.

Druh

D - Stať ve sborníku

CEP obor

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OECD FORD obor

20506 - Coating and films

Projekt

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Návaznosti

I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Rok uplatnění

2021

Kód důvěrnosti údajů

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

Název statě ve sborníku

2021 TopFuel conference proceedings

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

European Nuclear Society

Místo vydání

Brusel

Místo konání akce

Santander

Datum konání akce

24. 10. 2021

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

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