CHROMIUM AND CHROMIUM NITRIDE COATED CLADDING FOR NUCLEAR REACTOR FUEL
Identifikátory výsledku
Kód výsledku v IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21220%2F17%3A00337519" target="_blank" >RIV/68407700:21220/17:00337519 - isvavai.cz</a>
Nalezeny alternativní kódy
RIV/68407700:21340/17:00337519
Výsledek na webu
<a href="http://toc.proceedings.com/39388webtoc.pdf" target="_blank" >http://toc.proceedings.com/39388webtoc.pdf</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1080/1478422X.2017.1410318" target="_blank" >10.1080/1478422X.2017.1410318</a>
Alternativní jazyky
Jazyk výsledku
angličtina
Název v původním jazyce
CHROMIUM AND CHROMIUM NITRIDE COATED CLADDING FOR NUCLEAR REACTOR FUEL
Popis výsledku v původním jazyce
Accident tolerant fuels (ATF) have been widely studied since the Fukushima accident in 2011. A coating technology for nuclear fuel cladding has been considered to decrease the high-temperature oxidation rate of zirconium-based alloys and to enhance accident tolerance of the cladding. This study is focused on high-temperature oxidation of Zr-1%Nb cladding alloys coated with Cr and CrN layers by PVD technique. Coated and reference uncoated samples of a Zr-1%Nb alloy were tested in the high-temperature steam environment at temperatures in the range between 1000 and 1400°C. The comparison between both types was made. The high-temperature oxidation tests showed a protective behavior of the coating in the steam environment. Optical microscopy, scanning microscopy (EDS, WDS) were used for the evaluation of microstructure and chemical composition after the high-temperature oxidation tests.
Název v anglickém jazyce
CHROMIUM AND CHROMIUM NITRIDE COATED CLADDING FOR NUCLEAR REACTOR FUEL
Popis výsledku anglicky
Accident tolerant fuels (ATF) have been widely studied since the Fukushima accident in 2011. A coating technology for nuclear fuel cladding has been considered to decrease the high-temperature oxidation rate of zirconium-based alloys and to enhance accident tolerance of the cladding. This study is focused on high-temperature oxidation of Zr-1%Nb cladding alloys coated with Cr and CrN layers by PVD technique. Coated and reference uncoated samples of a Zr-1%Nb alloy were tested in the high-temperature steam environment at temperatures in the range between 1000 and 1400°C. The comparison between both types was made. The high-temperature oxidation tests showed a protective behavior of the coating in the steam environment. Optical microscopy, scanning microscopy (EDS, WDS) were used for the evaluation of microstructure and chemical composition after the high-temperature oxidation tests.
Klasifikace
Druh
D - Stať ve sborníku
CEP obor
—
OECD FORD obor
20506 - Coating and films
Návaznosti výsledku
Projekt
—
Návaznosti
V - Vyzkumna aktivita podporovana z jinych verejnych zdroju
Ostatní
Rok uplatnění
2017
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
European Corrosion Congress (EUROCORR 2017) and 20th International Corrosion Congress and Process Safety Congress 2017
ISBN
978-1-5108-6250-0
ISSN
—
e-ISSN
—
Počet stran výsledku
11
Strana od-do
3189-3199
Název nakladatele
DECHEMA, European Federation of Chemical Engineering
Místo vydání
Frankfurt am Main
Místo konání akce
Prague
Datum konání akce
3. 9. 2017
Typ akce podle státní příslušnosti
WRD - Celosvětová akce
Kód UT WoS článku
—