Polycrystalline diamond films as protection of Zircaloy fuel cladding

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21220%2F14%3A00227174" target="_blank" >RIV/68407700:21220/14:00227174 - isvavai.cz</a>

Výsledek na webu

<a href="http://dx.doi.org/10.1115/ICONE22-30873" target="_blank" >http://dx.doi.org/10.1115/ICONE22-30873</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1115/ICONE22-30873" target="_blank" >10.1115/ICONE22-30873</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Polycrystalline diamond films as protection of Zircaloy fuel cladding

Popis výsledku v původním jazyce

Polycrystalline diamond coating is a promising possibility for prevention, or reduction of high temperature oxidation of zirconium alloys. Zirconium alloys are used as cladding material in almost all types of nuclear reactors, where creates a barrier between nuclear fuel and cooling water in the primary circuit. Hydrogen and considerable amount of heat is released during steam oxidation that may occur in an eventual accident. In this paper Zircaloy-2 alloy was covered by polycrystalline diamond layer using Plasma Enhanced Linear Antennas Microwave Chemical Vapor Deposition system reactor. X-Ray Diffraction and Raman spectroscopy measurements confirmed coverage of the surface area with crystalline and amorphous carbon layer. Characterizations were donefor zirconium alloy covered with diamond layer before and after corrosion and irradiation tests - ion beam irradiation tests and high temperature steam exposure.

Název v anglickém jazyce

Polycrystalline diamond films as protection of Zircaloy fuel cladding

Popis výsledku anglicky

Polycrystalline diamond coating is a promising possibility for prevention, or reduction of high temperature oxidation of zirconium alloys. Zirconium alloys are used as cladding material in almost all types of nuclear reactors, where creates a barrier between nuclear fuel and cooling water in the primary circuit. Hydrogen and considerable amount of heat is released during steam oxidation that may occur in an eventual accident. In this paper Zircaloy-2 alloy was covered by polycrystalline diamond layer using Plasma Enhanced Linear Antennas Microwave Chemical Vapor Deposition system reactor. X-Ray Diffraction and Raman spectroscopy measurements confirmed coverage of the surface area with crystalline and amorphous carbon layer. Characterizations were donefor zirconium alloy covered with diamond layer before and after corrosion and irradiation tests - ion beam irradiation tests and high temperature steam exposure.

Druh

D - Stať ve sborníku

CEP obor

JF - Jaderná energetika

OECD FORD obor

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Projekt

<a href="/cs/project/TE01020455" target="_blank" >TE01020455: Centrum pokročilých jaderných technologií (CANUT)</a><br>

Návaznosti

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

Rok uplatnění

2014

Kód důvěrnosti údajů

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

Název statě ve sborníku

22nd International Conference on Nuclear Engineering

ISBN

978-0-7918-4589-9

ISSN

—

e-ISSN

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Počet stran výsledku

5

Strana od-do

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Název nakladatele

ASME

Místo vydání

New York

Místo konání akce

Prague

Datum konání akce

7. 7. 2014

Typ akce podle státní příslušnosti

EUR - Evropská akce

Kód UT WoS článku

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