Crack Initiation due to Liquid Metal Embrittlement for the Steel T91 and Two ODS Steels in Liquid Lead 103
Identifikátory výsledku
Kód výsledku v IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F16%3AN0000096" target="_blank" >RIV/26722445:_____/16:N0000096 - isvavai.cz</a>
Nalezeny alternativní kódy
RIV/26722445:_____/16:N0000037
Výsledek na webu
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DOI - Digital Object Identifier
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Alternativní jazyky
Jazyk výsledku
angličtina
Název v původním jazyce
Crack Initiation due to Liquid Metal Embrittlement for the Steel T91 and Two ODS Steels in Liquid Lead 103
Popis výsledku v původním jazyce
Ferritic–martensitic steels and oxide dispersion strengthened steels are materials intensively studied because of their potential to be used for construction of Gen IV fast nuclear reactors. Steels were developed for fast breeder reactors (high-temperature strength and swelling resistance under irradiation). In this study the effect of liquid lead on the crack growth rate of the steels was evaluated. Steels T91, MA957, PM2000 were used to evaluate their interaction with liquid lead under stress corresponding to maximum requested design condition. Liquid Metal Embrittlement (LME) initiation tests were conducted on pre-loaded specimens in flowing liquid metal loops. The experiments were carried out at 400°C and post-test evaluation was performed. Some specimens were pre-treated with a chemical flux, to induce wetting of Pb on the steel; some were polished or ground. Liquid Metal Embrittlement was not observed on the surface of any of the pre-loaded specimens after the exposure in liquid lead at 400˚C for 500 hours. The results are discussed and compared with previous accelerated tests.
Název v anglickém jazyce
Crack Initiation due to Liquid Metal Embrittlement for the Steel T91 and Two ODS Steels in Liquid Lead 103
Popis výsledku anglicky
Ferritic–martensitic steels and oxide dispersion strengthened steels are materials intensively studied because of their potential to be used for construction of Gen IV fast nuclear reactors. Steels were developed for fast breeder reactors (high-temperature strength and swelling resistance under irradiation). In this study the effect of liquid lead on the crack growth rate of the steels was evaluated. Steels T91, MA957, PM2000 were used to evaluate their interaction with liquid lead under stress corresponding to maximum requested design condition. Liquid Metal Embrittlement (LME) initiation tests were conducted on pre-loaded specimens in flowing liquid metal loops. The experiments were carried out at 400°C and post-test evaluation was performed. Some specimens were pre-treated with a chemical flux, to induce wetting of Pb on the steel; some were polished or ground. Liquid Metal Embrittlement was not observed on the surface of any of the pre-loaded specimens after the exposure in liquid lead at 400˚C for 500 hours. The results are discussed and compared with previous accelerated tests.
Klasifikace
Druh
D - Stať ve sborníku
CEP obor
JF - Jaderná energetika
OECD FORD obor
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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
2016
Kód důvěrnosti údajů
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Údaje specifické pro druh výsledku
Název statě ve sborníku
Advances in Materials Science for Environmental and Energy Technologies V: Ceramic Transactions, Volume 260
ISBN
9781119323624
ISSN
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e-ISSN
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Počet stran výsledku
9
Strana od-do
103-111
Název nakladatele
The American Ceramic Society
Místo vydání
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Místo konání akce
Columbus, Ohio
Datum konání akce
1. 1. 2015
Typ akce podle státní příslušnosti
WRD - Celosvětová akce
Kód UT WoS článku
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