EXPERIMENTAL BEHAVIOR OF CHROMIUM-BASED COATINGS

Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21220%2F18%3A00337524" target="_blank" >RIV/68407700:21220/18:00337524 - isvavai.cz</a>
Alternative codes found
RIV/68407700:21340/18:00337524
Result on the web
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DOI - Digital Object Identifier
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Result language
angličtina
Original language name
EXPERIMENTAL BEHAVIOR OF CHROMIUM-BASED COATINGS
Original language description
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.
Czech name
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Czech description
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Type
D - Article in proceedings
CEP classification
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OECD FORD branch
20305 - Nuclear related engineering; (nuclear physics to be 1.3);

Publication year
2018
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

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