Experimental behavior of chromium-based PVD coated cladding materials during LOCA transient
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21220%2F20%3A00340302" target="_blank" >RIV/68407700:21220/20:00340302 - isvavai.cz</a>
Alternative codes found
RIV/26722445:_____/19:N0000076 RIV/68407700:21340/20:00340302
Result on the web
<a href="http://globaltopfuel.ans.org/" target="_blank" >http://globaltopfuel.ans.org/</a>
DOI - Digital Object Identifier
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Alternative languages
Result language
angličtina
Original language name
Experimental behavior of chromium-based PVD coated cladding materials during LOCA transient
Original language description
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 high-temperature 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, high-temperature 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.
Czech name
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Czech description
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Classification
Type
D - Article in proceedings
CEP classification
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OECD FORD branch
20305 - Nuclear related engineering; (nuclear physics to be 1.3);
Result continuities
Project
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Continuities
N - Vyzkumna aktivita podporovana z neverejnych zdroju
Others
Publication year
2020
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Data specific for result type
Article name in the collection
Global/Top Fuel 2019: International Nuclear Fuel Cycle Conference/Light Water Reactor Fuel Performance Conference
ISBN
978-0-89448-771-2
ISSN
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e-ISSN
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Number of pages
8
Pages from-to
904-911
Publisher name
American Nuclear Society
Place of publication
La Grande Park, Illinois
Event location
Seattle, WA
Event date
Sep 22, 2019
Type of event by nationality
WRD - Celosvětová akce
UT code for WoS article
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