Experimental Behaviour of Chromium Based Coatings

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F18%3AN0000141" target="_blank" >RIV/26722445:_____/18:N0000141 - isvavai.cz</a>

Výsledek na webu

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DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

Experimental Behaviour of Chromium Based Coatings

Popis výsledku v původním jazyce

Accident Tolerant Fuels have been widely studied since the Fukushima accident in 2011. Deposition of protective coatings on nuclear fuel claddings has been considered as a near-term concept that will reduce the high-temperature oxidation rate of zirconium-based alloys and enhance accident tolerance of reactor cores by providing additional coping time. This study is focused on low-temperature oxidation and LOCA experimental behavior of Zr-1%Nb cladding alloys coated with Cr and CrN based layers by PVD technique. Coated and reference uncoated samples of Zr-1%Nb alloy were tested in several experiments. The presented results include standard corrosion tests at 360°C in WWER water chemistry, burst tests and mainly single and double-sided high-temperature steam oxidation between 1000 and 1400°C. Coated and reference samples were characterized pre- and post-testing using mechanical testing (microhardness, ring compression test), TEA analysis (hydrogen, oxygen measurements), optical microscopy, scanning electron microscopy (EDS, WDS, EBSD) and other techniques including X-ray diffraction. Presented at TopFuel 2018, 30 September - 04 October 2018 in Prague Czech Republic.

Název v anglickém jazyce

Experimental Behaviour of Chromium Based Coatings

Popis výsledku anglicky

Accident Tolerant Fuels have been widely studied since the Fukushima accident in 2011. Deposition of protective coatings on nuclear fuel claddings has been considered as a near-term concept that will reduce the high-temperature oxidation rate of zirconium-based alloys and enhance accident tolerance of reactor cores by providing additional coping time. This study is focused on low-temperature oxidation and LOCA experimental behavior of Zr-1%Nb cladding alloys coated with Cr and CrN based layers by PVD technique. Coated and reference uncoated samples of Zr-1%Nb alloy were tested in several experiments. The presented results include standard corrosion tests at 360°C in WWER water chemistry, burst tests and mainly single and double-sided high-temperature steam oxidation between 1000 and 1400°C. Coated and reference samples were characterized pre- and post-testing using mechanical testing (microhardness, ring compression test), TEA analysis (hydrogen, oxygen measurements), optical microscopy, scanning electron microscopy (EDS, WDS, EBSD) and other techniques including X-ray diffraction. Presented at TopFuel 2018, 30 September - 04 October 2018 in Prague Czech Republic.

Druh

O - Ostatní výsledky

CEP obor

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OECD FORD obor

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

Projekt

<a href="/cs/project/LQ1603" target="_blank" >LQ1603: Výzkum pro SUSEN</a><br>

Návaznosti

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Rok uplatnění

2018

Kód důvěrnosti údajů

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