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Degradation of fuel rods materials based on zirconium after operation in WWER-type reactors
https://doi.org/10.22349/1994-6716-2018-95-3-191-205
Abstract
The paper presents microstructural studies of specimens cut from fuel elements made of E110 spongy zirconium-based alloy after operation in WWER-1000 before reaching the burnout of ~35 MW per day/kg U. As a result of exposure to high temperatures and neutron irradiation significant changes in the phase composition of the material of fuel rods claddings appear in particles β-Nb’ size, density, and composition; composition of the Laves phase, formation of dislocation loops of α-type, as well as δ and γ hydrides. The main structural elements determining the degradation of the mechanical properties of the E110 alloy under irradiation are dislocation loops and fine-phase precipitates due to their relatively large density. The data obtained can be used to construct dose dependences of microstructural changes with the aim of predicting the residual life of claddings and fuel assemblies as a whole.
Keywords
WWER reactors,
fuel rods shells,
alloy based on spongy zirconium,
neutron irradiation,
degradation of properties,
forecasting of residual resource
Supporting agencies: the grant of the President of the Russian Federation No MK-4420.2018.8
About the Authors
B. A. Gurovich
National Research Center “Kurchatov Institute”
Russian Federation
Russian Federation
Dr. Sci. (Eng)
1 Kurchatova Sq, 123182 Moscow
A. S. Frolov
National Research Center “Kurchatov Institute”
Russian Federation
Russian Federation
Cand. Sci. (Eng)
1 Kurchatova Sq, 123182 Moscow
E. A. Kuleshova
National Research Center “Kurchatov Institute”; National Research Nuclear University MEPhI (Moscow Engineering Physics Institute)
Russian Federation
Russian Federation
Dr. Sci. (Eng)
1 Kurchatova Sq, 123182 Moscow; 31 Kashirskoe shosse, 115409 Moscow
D. A. Maltsev
National Research Center “Kurchatov Institute”
Russian Federation
Russian Federation
Cand. Sci. (Eng)
1 Kurchatova Sq, 123182 Moscow
D. V. Safonov
National Research Center “Kurchatov Institute”
Russian Federation
Russian Federation
1 Kurchatova Sq, 123182 Moscow
V. N. Kochkin
National Research Center “Kurchatov Institute”
Russian Federation
Russian Federation
Cand. Sci. (Eng)
1 Kurchatova Sq, 123182 Moscow
E. V. Alexeeva
National Research Center “Kurchatov Institute”
Russian Federation
Russian Federation
Cand. Sci. (Eng)
1 Kurchatova Sq, 123182 Moscow
N. V. Stepanov
National Research Center “Kurchatov Institute”
Russian Federation
Russian Federation
1 Kurchatova Sq, 123182 Moscow
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Review
For citations:
Gurovich B.A., Frolov A.S., Kuleshova E.A., Maltsev D.A., Safonov D.V., Kochkin V.N., Alexeeva E.V., Stepanov N.V. Degradation of fuel rods materials based on zirconium after operation in WWER-type reactors. Voprosy Materialovedeniya. 2018;(3(95)):191-205. (In Russ.) https://doi.org/10.22349/1994-6716-2018-95-3-191-205
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