Irradiation assisted stress corrosion cracking of austenitic stainless steel WWER reactor core internals
The result's identifiers
Result code in 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>
Result on the web
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DOI - Digital Object Identifier
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Alternative languages
Result language
angličtina
Original language name
Irradiation assisted stress corrosion cracking of austenitic stainless steel WWER reactor core internals
Original language description
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
Czech name
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Czech description
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Classification
Type
D - Article in proceedings
CEP classification
JK - Corrosion and material surfaces
OECD FORD branch
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Result continuities
Project
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Continuities
N - Vyzkumna aktivita podporovana z neverejnych zdroju
Others
Publication year
2011
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Data specific for result type
Article name in the collection
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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Number of pages
16
Pages from-to
1-16
Publisher name
Wiley
Place of publication
USA
Event location
Colorado Springs, USA
Event date
Aug 7, 2011
Type of event by nationality
WRD - Celosvětová akce
UT code for WoS article
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