High Temperature Creep in a Zr-1wt.%Nb Alloy

Result code in IS VaVaI
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Result on the web
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DOI - Digital Object Identifier
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Result language
angličtina
Original language name
High Temperature Creep in a Zr-1wt.%Nb Alloy
Original language description
This paper presents experimental results regarding high temperature behaviour of a Zr-1wt.%Nb alloy corresponding to LOCA situation of fuel cladding tubes for nuclear reactor. The tube exhibited equiaxed ? grains with an initial grain size of about 5 ?m.Constant stress uniaxial tensile creep tests were carried out at temperatures from 550 to 800° C over a wide range of the applied stress up to a true strain of about 40%. From the creep data was identified presence of power-law creep, which is dislocation climb controlled (self-diffusion controlled). Then the activation energy for creep Qc should be fairly consistent with that of self-diffusion. The determined activation energies of 243-269 kJ/mol fall within the range of self-diffusion activation energies.
Czech name
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Czech description
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Project
Result was created during the realization of more than one project. More information in the Projects tab.
Continuities
I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Publication year
2015
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

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