CORROSION RESISTANCE AND HIGH-TEMPERATURE BEHAVIOR OF CHROME-NICKEL ALLOY CLADDING MATERIAL

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F60193247%3A_____%2F22%3AN0000026" target="_blank" >RIV/60193247:_____/22:N0000026 - 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

CORROSION RESISTANCE AND HIGH-TEMPERATURE BEHAVIOR OF CHROME-NICKEL ALLOY CLADDING MATERIAL

Popis výsledku v původním jazyce

Cr-Ni alloys has been recently proposed as a potential ATF concept, primarily due to its high corrosion resistance under normal operation conditions and hightemperature oxidation. It is tested by UJP PRAHA in collaboration with CTU in Prague in the frame of the project sponsored by the Technology Agency of the Czech Republic. A set of experiments determining a wide range of material properties were performed. The investigations in this contribution followed previous work. Material in as-received state was evaluated using TEM, SEM-EBSD, DSC, and XRD methods. The ongoing long-term autoclave tests revealed superb corrosion resistance compared to reference Zr-cladding material under simulated WWER normal operating conditions (at 360 °C), in steam at 400 °C, in steam at 500 °C, and water containing 70 ppm of Li (at 360 °C). A set of hightemperature steam oxidation experiments were performed to determine behavior at LOCA and DEC conditions. Weight gain, hydrogen content were measured. Microstructure analysis (LOM, EDS) and mechanical properties (offset-strain) were evaluated. Thermomechanical tests were performed to understand the cladding deformation and the burst conditions during high-temperature transients. The ballooning size, prolongation of time to burst, burst opening dimensions. Presented results reveal substantial corrosion resistance comparing to zirconium alloys.

Název v anglickém jazyce

CORROSION RESISTANCE AND HIGH-TEMPERATURE BEHAVIOR OF CHROME-NICKEL ALLOY CLADDING MATERIAL

Popis výsledku anglicky

Cr-Ni alloys has been recently proposed as a potential ATF concept, primarily due to its high corrosion resistance under normal operation conditions and hightemperature oxidation. It is tested by UJP PRAHA in collaboration with CTU in Prague in the frame of the project sponsored by the Technology Agency of the Czech Republic. A set of experiments determining a wide range of material properties were performed. The investigations in this contribution followed previous work. Material in as-received state was evaluated using TEM, SEM-EBSD, DSC, and XRD methods. The ongoing long-term autoclave tests revealed superb corrosion resistance compared to reference Zr-cladding material under simulated WWER normal operating conditions (at 360 °C), in steam at 400 °C, in steam at 500 °C, and water containing 70 ppm of Li (at 360 °C). A set of hightemperature steam oxidation experiments were performed to determine behavior at LOCA and DEC conditions. Weight gain, hydrogen content were measured. Microstructure analysis (LOM, EDS) and mechanical properties (offset-strain) were evaluated. Thermomechanical tests were performed to understand the cladding deformation and the burst conditions during high-temperature transients. The ballooning size, prolongation of time to burst, burst opening dimensions. Presented results reveal substantial corrosion resistance comparing to zirconium alloys.

Druh

O - Ostatní výsledky

CEP obor

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OECD FORD obor

20501 - Materials engineering

Projekt

<a href="/cs/project/TK03020034" target="_blank" >TK03020034: Využití pokročilých materiálů pro nové typy jaderného paliva</a><br>

Návaznosti

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

Rok uplatnění

2022

Kód důvěrnosti údajů

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