Comparison of corrosion behavior of the austenitic steel 316L in static and flowing liquid lead
Identifikátory výsledku
Kód výsledku v IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F21%3AN0000015" target="_blank" >RIV/26722445:_____/21:N0000015 - isvavai.cz</a>
Výsledek na webu
<a href="https://asmedigitalcollection.asme.org/nuclearengineering/article-abstract/7/2/021605/1096361/Comparison-of-Corrosion-Behavior-of-the-Austenitic?redirectedFrom=fulltext" target="_blank" >https://asmedigitalcollection.asme.org/nuclearengineering/article-abstract/7/2/021605/1096361/Comparison-of-Corrosion-Behavior-of-the-Austenitic?redirectedFrom=fulltext</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1115/1.4049719" target="_blank" >10.1115/1.4049719</a>
Alternativní jazyky
Jazyk výsledku
angličtina
Název v původním jazyce
Comparison of corrosion behavior of the austenitic steel 316L in static and flowing liquid lead
Popis výsledku v původním jazyce
Development of liquid lead cooled nuclear systems requires consideration of compatibility issues with the construction materials. In order to understand the corrosion or passivation behavior of the 316 L austenitic stainless steel, the steel specimens were exposed for 1000 h in liquid lead with 1 × 10−7 wt % oxygen level at 480 °C in static and flowing (velocity 1.6 m/s) conditions. Post-test microscopy investigation using scanning electron microscope with focused ion beam (FIB) was performed and it demonstrated significant differences in the formation of thin oxide layers in the two conditions. Maximum oxide thickness was 2 μm in the static lead (Pb) and less than 0.1 μm in the flowing Pb. In the static condition, oxide scale was not continuous and local corrosion attack was indicated; but in flowing condition the oxide layer was continuous without any corrosion attacks.
Název v anglickém jazyce
Comparison of corrosion behavior of the austenitic steel 316L in static and flowing liquid lead
Popis výsledku anglicky
Development of liquid lead cooled nuclear systems requires consideration of compatibility issues with the construction materials. In order to understand the corrosion or passivation behavior of the 316 L austenitic stainless steel, the steel specimens were exposed for 1000 h in liquid lead with 1 × 10−7 wt % oxygen level at 480 °C in static and flowing (velocity 1.6 m/s) conditions. Post-test microscopy investigation using scanning electron microscope with focused ion beam (FIB) was performed and it demonstrated significant differences in the formation of thin oxide layers in the two conditions. Maximum oxide thickness was 2 μm in the static lead (Pb) and less than 0.1 μm in the flowing Pb. In the static condition, oxide scale was not continuous and local corrosion attack was indicated; but in flowing condition the oxide layer was continuous without any corrosion attacks.
Klasifikace
Druh
J<sub>imp</sub> - Článek v periodiku v databázi Web of Science
CEP obor
—
OECD FORD obor
20501 - Materials engineering
Návaznosti výsledku
Projekt
<a href="/cs/project/LQ1603" target="_blank" >LQ1603: Výzkum pro SUSEN</a><br>
Návaznosti
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)
Ostatní
Rok uplatnění
2021
Kód důvěrnosti údajů
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Údaje specifické pro druh výsledku
Název periodika
Journal of Nuclear Engineering and Radiation Science
ISSN
2332-8983
e-ISSN
2332-8975
Svazek periodika
7
Číslo periodika v rámci svazku
2
Stát vydavatele periodika
NL - Nizozemsko
Počet stran výsledku
8
Strana od-do
1-8
Kód UT WoS článku
000630005800016
EID výsledku v databázi Scopus
2-s2.0-85103157864