Assessment of oxygen diffusion coefficients by studying high-temperature oxidation behaviour of Zr1Nb fuel cladding in the temperature range of 1100?1300 °C
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21340%2F15%3A00225319" target="_blank" >RIV/68407700:21340/15:00225319 - isvavai.cz</a>
Alternative codes found
RIV/60193247:_____/14:UJP1614A RIV/46356088:_____/15:#0001733
Result on the web
<a href="http://www.sciencedirect.com/science/article/pii/S0022311514006254" target="_blank" >http://www.sciencedirect.com/science/article/pii/S0022311514006254</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1016/j.jnucmat.2014.09.035" target="_blank" >10.1016/j.jnucmat.2014.09.035</a>
Alternative languages
Result language
angličtina
Original language name
Assessment of oxygen diffusion coefficients by studying high-temperature oxidation behaviour of Zr1Nb fuel cladding in the temperature range of 1100?1300 °C
Original language description
The paper deals with high-temperature steam oxidation behaviour of Zr1Nb fuel cladding. First of all, comprehensive experimental program was conducted to provide sufficient experimental data, such as the thicknesses of evolved phase layers and the overall weight gain kinetics, as well as the oxygen concentration and nanohardness values at phase boundaries. Afterwards, oxygen diffusion coefficients in the oxide, in the ?-Zr(O) layer, in the double-phase (? + ?)-Zr region, and in the ?-phase region have been estimated based on the experimental data employing analytical solution of the multiphase moving boundary problem, assuming the equilibrium conditions being fulfilled at the interface boundaries. Eventually, the determined oxygen diffusion coefficients served as input into the in-house numerical code, which was designed to predict the high-temperature oxidation behaviour of Zr1Nb fuel cladding. Very good agreement has been achieved between the numerical calculations and the experiment
Czech name
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Czech description
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Classification
Type
J<sub>x</sub> - Unclassified - Peer-reviewed scientific article (Jimp, Jsc and Jost)
CEP classification
JF - Nuclear energy
OECD FORD branch
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Result continuities
Project
<a href="/en/project/TA02011025" target="_blank" >TA02011025: Creep and oxidation properties of E110 claddings under LOCA temperature transient</a><br>
Continuities
S - Specificky vyzkum na vysokych skolach
Others
Publication year
2015
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
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Volume of the periodical
456
Issue of the periodical within the volume
456
Country of publishing house
NL - THE KINGDOM OF THE NETHERLANDS
Number of pages
9
Pages from-to
211-219
UT code for WoS article
000347274500027
EID of the result in the Scopus database
2-s2.0-84908077466