Zirconium Dioxide as a Protective Layer of Zirconium Fuel Cladding

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21220%2F14%3A00227178" target="_blank" >RIV/68407700:21220/14:00227178 - 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

Zirconium Dioxide as a Protective Layer of Zirconium Fuel Cladding

Popis výsledku v původním jazyce

Zirconium is important because of its mechanical and neutronics properties combined with its extraordinary resistance against corrosion. It?s mainly usage in nuclear engineering is as a nuclear fuel cladding. Even though Zr layers are very resistant to neutron fluence at reactor operating temperatures, high pressure and high radiation doses, exothermic Zr oxidation in accident scenario still occurs. Hydrogen, and a newly created layer of zirconium dioxide, are undesirable products of the high temperature steam oxidation. ZrO2 adopts a monoclinic crystal structure at room temperature and transitions to tetragonal and cubic at higher temperatures. The volume expansion caused by the cubic to tetragonal to monoclinic transformation induces large stresses and these stresses cause ZrO2 to crack upon cooling from high temperatures. To stabilize ZrO2 other oxides may be added. Therefore ZrO2 with its high ionic conductivity makes it one of the most promising ceramics to protect fuel cladding a

Název v anglickém jazyce

Zirconium Dioxide as a Protective Layer of Zirconium Fuel Cladding

Popis výsledku anglicky

Zirconium is important because of its mechanical and neutronics properties combined with its extraordinary resistance against corrosion. It?s mainly usage in nuclear engineering is as a nuclear fuel cladding. Even though Zr layers are very resistant to neutron fluence at reactor operating temperatures, high pressure and high radiation doses, exothermic Zr oxidation in accident scenario still occurs. Hydrogen, and a newly created layer of zirconium dioxide, are undesirable products of the high temperature steam oxidation. ZrO2 adopts a monoclinic crystal structure at room temperature and transitions to tetragonal and cubic at higher temperatures. The volume expansion caused by the cubic to tetragonal to monoclinic transformation induces large stresses and these stresses cause ZrO2 to crack upon cooling from high temperatures. To stabilize ZrO2 other oxides may be added. Therefore ZrO2 with its high ionic conductivity makes it one of the most promising ceramics to protect fuel cladding a

Druh

D - Stať ve sborníku

CEP obor

JF - Jaderná energetika

OECD FORD obor

—

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

—

Počet stran výsledku

5

Strana od-do

—

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

—