Degradation of fuel rods materials based on zirconium after operation in WWER-type reactors-Reference-Cited by-同舟云学术

Degradation of fuel rods materials based on zirconium after operation in WWER-type reactors

Published:2019-01-10 Issue:3(95) Volume: Page:191-205
ISSN:1994-6716
Container-title:Voprosy Materialovedeniya
language:
Short-container-title:Vopr. materialoved.

Author:

Gurovich B. A.¹,Frolov A. S.¹,Kuleshova E. A.²,Maltsev D. A.¹,Safonov D. V.¹,Kochkin V. N.¹,Alexeeva E. V.¹,Stepanov N. V.¹

Affiliation:

1. National Research Center “Kurchatov Institute”

2. National Research Center “Kurchatov Institute”; National Research Nuclear University MEPhI (Moscow Engineering Physics Institute)

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.

Publisher

FSUE CRISM Prometey

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