Irradiation assisted stress corrosion cracking of austenitic stainless steel WWER reactor core internals
Identifikátory výsledku
Kód výsledku v IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F46356088%3A_____%2F11%3A%230001128" target="_blank" >RIV/46356088:_____/11:#0001128 - 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
Irradiation assisted stress corrosion cracking of austenitic stainless steel WWER reactor core internals
Popis výsledku v původním jazyce
The neutron irradiation changes the material's microstructure and mechanical properties, basis of occurrence and increased sensitivity to IASCC. This paper surveys new results regarding IASCC of irradiated austenitic Ti-stabilized stainless steel 08Ch18N10T from WWER 440 Greifswald decommissioned after 15 years in service. Three components LWR irradiated to 2-19 dpa were tested. IASCC was investigated by Slow Strain Rate and Crack Growth Rate tests in simulated water 320°C. IASCC was judged according IG+TG fracture occurrence. Without irradiation components do not suffer SCC in the water. However, areas of mixed IG and TG fracture appeared on specimens. Tests represent different stress strain conditions for IASCC initiation and growth. Effects of SSRTstrain rate and CGR test load level were found to be significant for IASCC. Total IG+TG fraction of SSRT ranged 1 to 18% and decreased with decreasing strain rate. Results are compared with previous data on the fast reactor irradiated mat
Název v anglickém jazyce
Irradiation assisted stress corrosion cracking of austenitic stainless steel WWER reactor core internals
Popis výsledku anglicky
The neutron irradiation changes the material's microstructure and mechanical properties, basis of occurrence and increased sensitivity to IASCC. This paper surveys new results regarding IASCC of irradiated austenitic Ti-stabilized stainless steel 08Ch18N10T from WWER 440 Greifswald decommissioned after 15 years in service. Three components LWR irradiated to 2-19 dpa were tested. IASCC was investigated by Slow Strain Rate and Crack Growth Rate tests in simulated water 320°C. IASCC was judged according IG+TG fracture occurrence. Without irradiation components do not suffer SCC in the water. However, areas of mixed IG and TG fracture appeared on specimens. Tests represent different stress strain conditions for IASCC initiation and growth. Effects of SSRTstrain rate and CGR test load level were found to be significant for IASCC. Total IG+TG fraction of SSRT ranged 1 to 18% and decreased with decreasing strain rate. Results are compared with previous data on the fast reactor irradiated mat
Klasifikace
Druh
D - Stať ve sborníku
CEP obor
JK - Koroze a povrchové úpravy materiálu
OECD FORD obor
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Návaznosti výsledku
Projekt
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Návaznosti
N - Vyzkumna aktivita podporovana z neverejnych zdroju
Ostatní
Rok uplatnění
2011
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
Environmental Degradation of Materials in Nuclear Power Systems: Water Reactors (Proceedings of the 15th International Conference)
ISBN
978-1-118-13241-8
ISSN
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e-ISSN
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Počet stran výsledku
16
Strana od-do
1-16
Název nakladatele
Wiley
Místo vydání
USA
Místo konání akce
Colorado Springs, USA
Datum konání akce
7. 8. 2011
Typ akce podle státní příslušnosti
WRD - Celosvětová akce
Kód UT WoS článku
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