Development and testing of multicomponent fuel cladding with enhanced accidental performance

Result code in IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F20%3AN0000020" target="_blank" >RIV/26722445:_____/20:N0000020 - isvavai.cz</a>

Alternative codes found

RIV/68407700:21220/20:00333943 RIV/68407700:21340/20:00333943

Result on the web

<a href="https://www.journals.elsevier.com/nuclear-engineering-and-technology/" target="_blank" >https://www.journals.elsevier.com/nuclear-engineering-and-technology/</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.net.2019.08.015" target="_blank" >10.1016/j.net.2019.08.015</a>

Result language

angličtina

Original language name

Development and testing of multicomponent fuel cladding with enhanced accidental performance

Original language description

Accident Tolerant Fuels have been widely studied since the Fukushima-Daiichi accident in 2011 as one of the options on how to further enhance the safety of nuclear power plants. Deposition of protective coatings on nuclear fuel claddings has been considered as a near-term concept that will reduce the high-temperature oxidation rate and enhance accidental tolerance of the cladding while providing additional benefits during normal operation and transients. This study focuses on experimental testing of Zr-based alloys coated with Cr-based coatings using Physical Vapour Deposition. The results of long-term corrosion tests, as well as tests simulating postulated accidents, are presented. Zr-1%Nb alloy used as nuclear fuel cladding serves as a substrate and Cr, CrN, CrxNy layers are deposited by unbalanced magnetron sputtering and reactive magnetron sputtering. The deposition procedures are optimized in order to improve coating properties. Coated as well as reference uncoated samples were experimentally tested. The presented results include standard long-term corrosion tests at 360 degrees C in WWER water chemistry, burst (creep) tests and mainly single and double-sided high-temperature steam oxidation tests between 1000 and 1400 degrees C related to postulated Loss-of-coolant accident and Design extension conditions. Coated and reference samples were characterized pre- and post-testing using mechanical testing (microhardness, ring compression test), Thermal Evolved Gas Analysis analysis (hydrogen, oxygen concentration), optical microscopy, scanning electron microscopy (EDS, WDS, EBSD) and X-ray diffraction.

Czech name

—

Czech description

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Type

J_imp - Article in a specialist periodical, which is included in the Web of Science database

CEP classification

—

OECD FORD branch

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

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

2020

Confidentiality

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

Name of the periodical

Nuclear Engineering and Technology

ISSN

1738-5733

e-ISSN

—

Volume of the periodical

52

Issue of the periodical within the volume

3

Country of publishing house

KR - KOREA, REPUBLIC OF

Number of pages

13

Pages from-to

597-609

UT code for WoS article

000516803800017

EID of the result in the Scopus database

2-s2.0-85071492736