CR-NI ALLOY AS A SUITABLE FUEL CLADDING REPLACEMENT FOR ZR-ALLOYS

Result code in IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F60193247%3A_____%2F21%3AN0000013" target="_blank" >RIV/60193247:_____/21:N0000013 - isvavai.cz</a>

Alternative codes found

RIV/26722445:_____/21:N0000103

Result on the web

<a href="https://www.euronuclear.org/scientific-resources/conference-proceedings/#1559592636459-42447d8c-0fcc" target="_blank" >https://www.euronuclear.org/scientific-resources/conference-proceedings/#1559592636459-42447d8c-0fcc</a>

DOI - Digital Object Identifier

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Result language

angličtina

Original language name

CR-NI ALLOY AS A SUITABLE FUEL CLADDING REPLACEMENT FOR ZR-ALLOYS

Original language description

"Following the Fukushima Daiichi accident, new nuclear fuel cladding designs improving the performance and enhancing nuclear power plants' safety have been widely investigated. Cr-Ni alloys have been recently proposed as a promising ATF concept, primarily due to their high corrosion resistance under normal operating conditions and high-temperature oxidation resistance. The alloy 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 and failure mechanisms has been performed. The presented results with the Cr-Ni alloy directly compare the proposed ATF cladding with a reference Zr-based alloy. The ongoing long-term autoclave tests revealed superb corrosion resistance compared to uncoated cladding material under simulated WWER normal operating conditions (at 360 °C), steam at 400 °C, and water containing 70 ppm of Li (at 360 °C). A set of high-temperature steam oxidation experiments were performed to determine behavior during LOCA and DEC scenarios. Weight gain and hydrogen content were measured post-testing. Microstructure analysis (EDS) and mechanical properties were evaluated. The presented results reveal extraordinary corrosion resistance in comparison with the zirconium alloys.these materials was evaluated by both gravimetry and metallographic analysis. The comparison of both steels showed that although they do not differ chemically from each other, their corrosion behaviour is different due to different grain size on both surfaces. Sanicro 6R44 steel with a larger austenitic grain corrodes faster than the 347H FG steel, but the mechanism is the same. The bending process does not affect this behaviour."

Czech name

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Czech description

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Type

D - Article in proceedings

CEP classification

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OECD FORD branch

20501 - Materials engineering

Project

Result was created during the realization of more than one project. More information in the Projects tab.

Continuities

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

Publication year

2021

Confidentiality

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

Article name in the collection

Sborník z konference TopFuel 2021

ISBN

978-92-95064-35-5

ISSN

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e-ISSN

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Number of pages

9

Pages from-to

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Publisher name

Europian Nuclear Society

Place of publication

Brussels, Belgium

Event location

Santander, Spain

Event date

Oct 24, 2021

Type of event by nationality

WRD - Celosvětová akce

UT code for WoS article

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