Analysis of the Effect of the Stress-Strain State of Irradiated Zirconium-Alloy Fuel-Element Cladding on Hydride Orientation

The effect of the stress distribution on the hydride distribution in zirconium cladding of fuel elements with dispersion fuel is analyzed. It is shown that reorientation of zirconium hydrides can occur in fuel-element cladding under the action of tensile stresses, which can result in the appearance...

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Published inAtomic energy (New York, N.Y.) Vol. 122; no. 2; pp. 87 - 92
Main Authors Kulakov, G. V., Vatulin, A. V., Konovalov, Yu. V., Kosaurov, A. A., Peregud, M. M., Korotchenko, E. A., Shishin, V. Yu, Shel’dyakov, A. A.
Format Journal Article
LanguageEnglish
Published New York Springer US 01.06.2017
Springer
Subjects
Alloys
Analysis
Building materials
Hadrons
Heavy Ions
Hydrogen
Hydrogen fuels
Nuclear Chemistry
Nuclear Energy
Nuclear Physics
Nuclear reactors
Physics
Physics and Astronomy
Specialty metals industry
Zirconium
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Summary:The effect of the stress distribution on the hydride distribution in zirconium cladding of fuel elements with dispersion fuel is analyzed. It is shown that reorientation of zirconium hydrides can occur in fuel-element cladding under the action of tensile stresses, which can result in the appearance of radially oriented hydrides and plasticity reduction in the cladding upon cool-down of the fuel elements. The threshold tensile stresses are determined in the cladding in the unirradiated and irradiated states, in which hydride reorientation from tangential to radial occurs.
ISSN:1063-4258
1573-8205
DOI:10.1007/s10512-017-0240-1