Thermal creep in a pre-hydrided Zr1 % Nb nuclear fuel cladding tube
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68081723%3A_____%2F24%3A00585475" target="_blank" >RIV/68081723:_____/24:00585475 - isvavai.cz</a>
Result on the web
<a href="https://www.sciencedirect.com/science/article/pii/S0022311524001867?via%3Dihub" target="_blank" >https://www.sciencedirect.com/science/article/pii/S0022311524001867?via%3Dihub</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1016/j.jnucmat.2024.155084" target="_blank" >10.1016/j.jnucmat.2024.155084</a>
Alternative languages
Result language
angličtina
Original language name
Thermal creep in a pre-hydrided Zr1 % Nb nuclear fuel cladding tube
Original language description
The effect of hydrogen on the thermal creep behaviour of Zr1 %Nb alloy fuel cladding tubes for use in light water-cooled nuclear reactors was investigated. The tubes were hydrogen charged using an alternative method with a hydrogen content in the range 371–656 wppm H. Comparative constant-stress creep tests were carried out at 350 °C, under stress ranging from 150 to 225 MPa, on both non-hydrided and hydrided tubes. These creep tests were followed by a microstructural analysis of the specimens exposed to creep using SEM and TEM. It was found that these creep tests were conducted in the transition zone between the power-law and power-law breakdown creep regions. Hydrogen, either in solid solution (atomic hydrogen) or as precipitated zirconium hydrides, altered the creep behaviour of the hydrided tubes, and the impact of hydrogen depended on the hydrogen content CH. It was observed that under the creep loading conditions considered here with a hydrogen content CH < 450 wppm H, the presence of hydrogen resulted in an increase in the creep rate, however, a higher concentration of hydrogen caused a decrease in the creep rate. The difference in the effects of hydrogen on the creep rate was explained by the different roles of hydrogen in solid solution and in the form of zirconium hydride precipitates.
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
20501 - Materials engineering
Result continuities
Project
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Continuities
I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace
Others
Publication year
2024
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 Nuclear Materials
ISSN
0022-3115
e-ISSN
1873-4820
Volume of the periodical
596
Issue of the periodical within the volume
AUG
Country of publishing house
NL - THE KINGDOM OF THE NETHERLANDS
Number of pages
14
Pages from-to
155084
UT code for WoS article
001230897400001
EID of the result in the Scopus database
2-s2.0-85190341283