Stress Corrosion Cracking of Austenitic Stainless Steels in Simulated Nuclear Reactor Conditions
Identifikátory výsledku
Kód výsledku v IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21340%2F10%3A00173841" target="_blank" >RIV/68407700:21340/10:00173841 - isvavai.cz</a>
Výsledek na webu
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DOI - Digital Object Identifier
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Alternativní jazyky
Jazyk výsledku
angličtina
Název v původním jazyce
Stress Corrosion Cracking of Austenitic Stainless Steels in Simulated Nuclear Reactor Conditions
Popis výsledku v původním jazyce
Stress corrosion cracking (SCC) susceptibility of selected austenitic stainless steels was investigated within the SAFELIFE and HPLWR-2 projects. The aim was to identify and describe the specific failure mechanisms in simulated reactor conditions, i.e.,a combination of slow strain rate and high temperature in different environments. Slow J-R and standard SCC tests of AISI 304L stainless steel with different degree of cold working were carried out under BWR condition. Slow strain-rate tensile (SSRT) tests of 316L stainless steel were carried out in ultra-pure demineralized supercritical water (SCW) solution. Tested specimens were subjected to fractographic analysis in order to characterize the failure mechanisms. The specimens failed due to a combination of transgranular SCC and transgranular ductile fracture. The ratio of SCC and ductile fracture was affected by the parameters of tests, in particular by temperature, pressure, oxygen content and strain rate.
Název v anglickém jazyce
Stress Corrosion Cracking of Austenitic Stainless Steels in Simulated Nuclear Reactor Conditions
Popis výsledku anglicky
Stress corrosion cracking (SCC) susceptibility of selected austenitic stainless steels was investigated within the SAFELIFE and HPLWR-2 projects. The aim was to identify and describe the specific failure mechanisms in simulated reactor conditions, i.e.,a combination of slow strain rate and high temperature in different environments. Slow J-R and standard SCC tests of AISI 304L stainless steel with different degree of cold working were carried out under BWR condition. Slow strain-rate tensile (SSRT) tests of 316L stainless steel were carried out in ultra-pure demineralized supercritical water (SCW) solution. Tested specimens were subjected to fractographic analysis in order to characterize the failure mechanisms. The specimens failed due to a combination of transgranular SCC and transgranular ductile fracture. The ratio of SCC and ductile fracture was affected by the parameters of tests, in particular by temperature, pressure, oxygen content and strain rate.
Klasifikace
Druh
D - Stať ve sborníku
CEP obor
JL - Únava materiálu a lomová mechanika
OECD FORD obor
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Návaznosti výsledku
Projekt
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Návaznosti
Z - Vyzkumny zamer (s odkazem do CEZ)
Ostatní
Rok uplatnění
2010
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
New Methods of Damage and Failure Analysis of Structural Parts
ISBN
978-80-248-2265-5
ISSN
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e-ISSN
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Počet stran výsledku
10
Strana od-do
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Název nakladatele
Technická univerzita Ostrava
Místo vydání
Ostrava
Místo konání akce
Ostrava
Datum konání akce
6. 9. 2010
Typ akce podle státní příslušnosti
EUR - Evropská akce
Kód UT WoS článku
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