Study of Creep and Hydride Re-Orientation Behaviour in E110 Fuel Cladding at Dry Storage Conditions
Identifikátory výsledku
Kód výsledku v IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F18%3AN0000083" target="_blank" >RIV/26722445:_____/18:N0000083 - isvavai.cz</a>
Výsledek na webu
<a href="http://dx.doi.org/10.14621/ce.20180106" target="_blank" >http://dx.doi.org/10.14621/ce.20180106</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.14621/ce.20180106" target="_blank" >10.14621/ce.20180106</a>
Alternativní jazyky
Jazyk výsledku
angličtina
Název v původním jazyce
Study of Creep and Hydride Re-Orientation Behaviour in E110 Fuel Cladding at Dry Storage Conditions
Popis výsledku v původním jazyce
Zirconium based alloys are commonly used as material for fuel claddings in the light water reactors. Claddings act as first metallic barriers against loss of fission products during the nuclear power plant operation, intermittent storage or final dry storage. During the reactor operation, claddings are subjected to different stress levels at high temperatures as well as neutron radiation. This results in their creep and the integrity of claddings is always critical issue for the safe performance of the power plants and storage. In this work, E110 cladding creep behaviour at dry storage conditions having different hydrogen levels is studied. Test specimen was oxidized in an autoclave to have desired hydrogen content. Creep test was performed in a horizontal furnace with internal pressure by applying thermo-mechanical cycle. The failure of the fuel cladding occurred by extensive ballooning and wall thinning. Optical and transmission electron microscopy investigations were made on creep tested specimen to study the deformation process and identify the mode of deformation. The examination of samples from the deformed regions showed formation of dislocations, secondary precipitate particles and precipitation of hydrides on the grain boundaries. Creep deformation was associated with the grain boundary sliding.
Název v anglickém jazyce
Study of Creep and Hydride Re-Orientation Behaviour in E110 Fuel Cladding at Dry Storage Conditions
Popis výsledku anglicky
Zirconium based alloys are commonly used as material for fuel claddings in the light water reactors. Claddings act as first metallic barriers against loss of fission products during the nuclear power plant operation, intermittent storage or final dry storage. During the reactor operation, claddings are subjected to different stress levels at high temperatures as well as neutron radiation. This results in their creep and the integrity of claddings is always critical issue for the safe performance of the power plants and storage. In this work, E110 cladding creep behaviour at dry storage conditions having different hydrogen levels is studied. Test specimen was oxidized in an autoclave to have desired hydrogen content. Creep test was performed in a horizontal furnace with internal pressure by applying thermo-mechanical cycle. The failure of the fuel cladding occurred by extensive ballooning and wall thinning. Optical and transmission electron microscopy investigations were made on creep tested specimen to study the deformation process and identify the mode of deformation. The examination of samples from the deformed regions showed formation of dislocations, secondary precipitate particles and precipitation of hydrides on the grain boundaries. Creep deformation was associated with the grain boundary sliding.
Klasifikace
Druh
J<sub>ost</sub> - Ostatní články v recenzovaných periodicích
CEP obor
—
OECD FORD obor
20501 - Materials engineering
Návaznosti výsledku
Projekt
Výsledek vznikl pri realizaci vícero projektů. Více informací v záložce Projekty.
Návaznosti
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)
Ostatní
Rok uplatnění
2018
Kód důvěrnosti údajů
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Údaje specifické pro druh výsledku
Název periodika
International Journal of Contemporary Energy
ISSN
2363-6440
e-ISSN
—
Svazek periodika
4
Číslo periodika v rámci svazku
1
Stát vydavatele periodika
DE - Spolková republika Německo
Počet stran výsledku
11
Strana od-do
50-60
Kód UT WoS článku
—
EID výsledku v databázi Scopus
—