Experimental investigation and predictive modeling of the thermal creep behavior of Zr1Nb alloy cladding
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68081723%3A_____%2F25%3A00638107" target="_blank" >RIV/68081723:_____/25:00638107 - isvavai.cz</a>
Result on the web
<a href="https://link.springer.com/article/10.1007/s10853-025-11268-9" target="_blank" >https://link.springer.com/article/10.1007/s10853-025-11268-9</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1007/s10853-025-11268-9" target="_blank" >10.1007/s10853-025-11268-9</a>
Alternative languages
Result language
angličtina
Original language name
Experimental investigation and predictive modeling of the thermal creep behavior of Zr1Nb alloy cladding
Original language description
Zirconium alloys are used as a fuel cladding material in light water reactors due to their low neutron cross section, good corrosion resistance, appropriate high-temperature strength, and dimensional stability under radiation. Thermal creep is considered one of the severe degradation factors during the reactor core operation. Therefore, an understanding of the creep flow processes and fracture control is necessary for predicting the lifetime of the cladding component. This paper summarizes the results from an extensive experiment on the characteristics of creep flow of the non-irradiated Zr1%Nb cladding alloy in the form of a thin-walled cladding tube. The study is based on the experimental results of the constant stress creep tests and the sophisticated helicoid spring specimen technique. Finally, the modified creep rate model has been proposed, where the driving force is expressed as effective stress instead of the applied stress. The effective stress was described as linear dependence on the applied stress with some small residual stress below the threshold.
Czech name
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Czech description
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Classification
Type
J<sub>imp</sub> - Article in a specialist periodical, which is included in the Web of Science database
CEP classification
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OECD FORD branch
20305 - Nuclear related engineering; (nuclear physics to be 1.3);
Result continuities
Project
<a href="/en/project/TN02000018" target="_blank" >TN02000018: National Centre of Competence ENGINEERING</a><br>
Continuities
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)
Others
Publication year
2025
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Data specific for result type
Name of the periodical
Journal of Materials Science
ISSN
0022-2461
e-ISSN
1573-4803
Volume of the periodical
60
Issue of the periodical within the volume
39
Country of publishing house
US - UNITED STATES
Number of pages
7
Pages from-to
18352-18358
UT code for WoS article
001545108000001
EID of the result in the Scopus database
2-s2.0-105012752799