Mechanical properties degradation of Cr-coated cladding under the loss-of-coolant accident conditions

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21220%2F21%3A00375476" target="_blank" >RIV/68407700:21220/21:00375476 - isvavai.cz</a>

Výsledek na webu

<a href="https://publikationen.bibliothek.kit.edu/1000141824" target="_blank" >https://publikationen.bibliothek.kit.edu/1000141824</a>

DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

Mechanical properties degradation of Cr-coated cladding under the loss-of-coolant accident conditions

Popis výsledku v původním jazyce

Development of nuclear fuels with enhanced accident tolerance is one of the main current objectives of researchers around the world. The contribution focuses on Cr-coated cladding concept developed in cooperation of UJP Praha a.s. and CTU in Prague. Presented results show highly protective behavior of thin Cr-layers against high temperature steam oxidation and improved mechanical ductility of samples after transients. A more complex approach to simulate LOCA transient is applied in presented study. A set of experiments was performed to understand with the behavior of Cr-coated claddings during the whole phenomena. The presented results show the influence of coatings on high-temperature creep, ballooning size, time to burst, cracking of coating, high temperature oxidation through cracked and intact coating. Secondary oxidation and hydriding from 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 needs to be further investigated.

Název v anglickém jazyce

Mechanical properties degradation of Cr-coated cladding under the loss-of-coolant accident conditions

Popis výsledku anglicky

Development of nuclear fuels with enhanced accident tolerance is one of the main current objectives of researchers around the world. The contribution focuses on Cr-coated cladding concept developed in cooperation of UJP Praha a.s. and CTU in Prague. Presented results show highly protective behavior of thin Cr-layers against high temperature steam oxidation and improved mechanical ductility of samples after transients. A more complex approach to simulate LOCA transient is applied in presented study. A set of experiments was performed to understand with the behavior of Cr-coated claddings during the whole phenomena. The presented results show the influence of coatings on high-temperature creep, ballooning size, time to burst, cracking of coating, high temperature oxidation through cracked and intact coating. Secondary oxidation and hydriding from 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 needs to be further investigated.

Druh

O - Ostatní výsledky

CEP obor

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OECD FORD obor

20506 - Coating and films

Projekt

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Návaznosti

I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Rok uplatnění

2021

Kód důvěrnosti údajů

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