Yttria stabilized zirconia as a hot corrosion protection of fuel cladding

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21220%2F15%3A00240655" target="_blank" >RIV/68407700:21220/15:00240655 - isvavai.cz</a>

Výsledek na webu

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DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

Yttria stabilized zirconia as a hot corrosion protection of fuel cladding

Popis výsledku v původním jazyce

The zirconium alloys are used in nuclear engineering for decades, as a fuel cladding or other parts of the fuel assembly. It is an extraordinary material thanks to its good mechanical and neutronic properties. Unfortunately due to the high temperature oxidation it is necessary to protect parts of reactor against the cracking of material which could be severe for whole reactor. One of the promising protecting material is a zirconium dioxide which is forming on a pure zirconium in contact with air. But this dioxide, zirconia, is not stable because of destabilization and transformation of phases upon the cooling. To stabilize zirconia many other oxides may be added (MgO, Y2O3, CeO2, etc.). Especially the yttrium stabilized zirconia (YSZ) shown significant advantages. In order to enhance the stability of YSZ beyond 1200°C, the further doping of system with other elements is required. So far the Ta2O5 addition, creating TaYSZ, is the best candidate with the best hot corrosion resistance properties, so the most promising material for protection of fuel cladding against corrosion degradation.

Název v anglickém jazyce

Yttria stabilized zirconia as a hot corrosion protection of fuel cladding

Popis výsledku anglicky

The zirconium alloys are used in nuclear engineering for decades, as a fuel cladding or other parts of the fuel assembly. It is an extraordinary material thanks to its good mechanical and neutronic properties. Unfortunately due to the high temperature oxidation it is necessary to protect parts of reactor against the cracking of material which could be severe for whole reactor. One of the promising protecting material is a zirconium dioxide which is forming on a pure zirconium in contact with air. But this dioxide, zirconia, is not stable because of destabilization and transformation of phases upon the cooling. To stabilize zirconia many other oxides may be added (MgO, Y2O3, CeO2, etc.). Especially the yttrium stabilized zirconia (YSZ) shown significant advantages. In order to enhance the stability of YSZ beyond 1200°C, the further doping of system with other elements is required. So far the Ta2O5 addition, creating TaYSZ, is the best candidate with the best hot corrosion resistance properties, so the most promising material for protection of fuel cladding against corrosion degradation.

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

2015

Kód důvěrnosti údajů

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

Název statě ve sborníku

International Conference on Nuclear Engineering, Proceedings, ICONE

ISBN

978-4-88898-256-6

ISSN

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e-ISSN

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Počet stran výsledku

4

Strana od-do

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Název nakladatele

ASME

Místo vydání

New York

Místo konání akce

Makuhari

Datum konání akce

17. 5. 2015

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

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