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Protection of Zircaloy nuclear fuel rods using nanocrystalline diamond coatings
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SYSNO ASEP 0456468 Document Type A - Abstract R&D Document Type The record was not marked in the RIV R&D Document Type Není vybrán druh dokumentu Title Protection of Zircaloy nuclear fuel rods using nanocrystalline diamond coatings Author(s) Ashcheulov, Petr (FZU-D) ORCID, RID
Taylor, Andrew (FZU-D) RID, ORCID
Cháb, Vladimír (FZU-D) RID, ORCID
Fekete, Ladislav (FZU-D) RID, ORCID
Horáková, Kateřina (FZU-D) ORCID
Klimša, Ladislav (FZU-D) ORCID
Škoda, R. (CZ)
Škarohlíd, J. (CZ)
Kalvoda, L. (CZ)
Vratislav, S. (CZ)
Mortet, Vincent (FZU-D) RID, ORCID
Kopeček, Jaromír (FZU-D) RID, ORCID
Kratochvílová, Irena (FZU-D) RID, ORCID, SAISource Title Diamond Conference. - Coventry : University of Warwick, 2015 / Newton M.
O12.1-O12.3Number of pages 3 s. Publication form Print - P Action De Beers Diamond Conference 2015 Event date 06.07.2015 - 09.07.2015 VEvent location Warwick Country GB - United Kingdom Event type WRD Language eng - English Country GB - United Kingdom Keywords zircaloy ; LWR ; nuclear ; nanocrystalline diamond Subject RIV BM - Solid Matter Physics ; Magnetism R&D Projects TA04020156 GA TA ČR - Technology Agency of the Czech Republic (TA ČR) TA01011165 GA TA ČR - Technology Agency of the Czech Republic (TA ČR) GA14-10279S GA ČR - Czech Science Foundation (CSF) GA13-31783S GA ČR - Czech Science Foundation (CSF) Institutional support FZU-D - RVO:68378271 Annotation Due to a combination of low thermal neutron absorption and corrosion resistance in water at 300 °C, zirconium alloys (widely known as Zircaloy) are used as nuclear fuel cladding (in the form of tubes) in commercial nuclear light water reactors (LWR), where uranium dioxide is used as a fuel. Each LWR typically requires up to seventy five thousand fuel rods with lengths up to 4 m. Currently, more than 350 LWRs are in operation worldwide, with more under construction. Since the Fukushima Daiichi nuclear accident new emphasis has been put on discovering accident-tolerant fuel systems, as over prolonged use, a major problem in the use of Zircaloy is its oxidative reaction with water accompanied by a release of hydrogen gas and consequent nuclear rod embrittlement caused by diffusion of hydrogen into the alloy.
Workplace Institute of Physics Contact Kristina Potocká, potocka@fzu.cz, Tel.: 220 318 579 Year of Publishing 2016
Number of the records: 1