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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

  • Czech description

Classification

  • Type

    J<sub>imp</sub> - 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);

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