Experimental behavior of chromium-based pvd coated cladding materials during loca transient

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F19%3AN0000076" target="_blank" >RIV/26722445:_____/19:N0000076 - isvavai.cz</a>

Nalezeny alternativní kódy

RIV/68407700:21220/20:00340302 RIV/68407700:21340/20:00340302

Výsledek na webu

<a href="http://www.ans.org/store/item-700433/" target="_blank" >http://www.ans.org/store/item-700433/</a>

DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

Experimental behavior of chromium-based pvd coated cladding materials during loca transient

Popis výsledku v původním jazyce

Development of nuclear fuels with enhanced accident tolerance (ATF) is one of the main current objectives of researchers worldwide. The contribution focuses on chromium-based PVD coated cladding concept (Cr and CrN+Cr) developed in cooperation of UJP PRAHA a.s. and Czech Technical University in Prague. The results presented in the past showed high oxidation resistance of thin Cr and multicomponent CrN+Cr coatings and improved cladding ductility of samples after hightemperature transients. A more complex approach to simulate LOCA transient is applied in the presented study. A set of experiments was performed to understand the behavior of chromium-based coated claddings during the whole LOCA phenomena. The presented results show the influence of studied coatings on high-temperature cladding creep and related phenomena such as ballooning size, time to burst, cracking of coating, hightemperature oxidation through cracked and intact coatings. Secondary oxidation and hydriding from the inner uncoated surface after cladding failure is discussed as well. Microhardness and microstructure analysis of the material after testing revealed local cladding damage. The mechanical properties of cladding after LOCA can locally deteriorate due to cracks in coating, but the influence on the bulk mechanical behavior of the whole fuel cladding and cladding bundles needs to be further investigated.

Název v anglickém jazyce

Experimental behavior of chromium-based pvd coated cladding materials during loca transient

Popis výsledku anglicky

Development of nuclear fuels with enhanced accident tolerance (ATF) is one of the main current objectives of researchers worldwide. The contribution focuses on chromium-based PVD coated cladding concept (Cr and CrN+Cr) developed in cooperation of UJP PRAHA a.s. and Czech Technical University in Prague. The results presented in the past showed high oxidation resistance of thin Cr and multicomponent CrN+Cr coatings and improved cladding ductility of samples after hightemperature transients. A more complex approach to simulate LOCA transient is applied in the presented study. A set of experiments was performed to understand the behavior of chromium-based coated claddings during the whole LOCA phenomena. The presented results show the influence of studied coatings on high-temperature cladding creep and related phenomena such as ballooning size, time to burst, cracking of coating, hightemperature oxidation through cracked and intact coatings. Secondary oxidation and hydriding from the inner uncoated surface after cladding failure is discussed as well. Microhardness and microstructure analysis of the material after testing revealed local cladding damage. The mechanical properties of cladding after LOCA can locally deteriorate due to cracks in coating, but the influence on the bulk mechanical behavior of the whole fuel cladding and cladding bundles needs to be further investigated.

Druh

D - Stať ve sborníku

CEP obor

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OECD FORD obor

20305 - Nuclear related engineering; (nuclear physics to be 1.3);

Projekt

Výsledek vznikl pri realizaci vícero projektů. Více informací v záložce Projekty.

Návaznosti

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

Rok uplatnění

2019

Kód důvěrnosti údajů

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

Název statě ve sborníku

Global/Top Fuel 2019 Seattle, WA, September 22-2, 2019

ISBN

978-0-89448-771-2

ISSN

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e-ISSN

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Počet stran výsledku

8

Strana od-do

904-911

Název nakladatele

American Nuclear Society

Místo vydání

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Místo konání akce

Seattle, USA

Datum konání akce

22. 9. 2019

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

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