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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

  • DOI - Digital Object Identifier

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

  • Czech description

Classification

  • Type

    D - Article in proceedings

  • CEP classification

    JK - Corrosion and material surfaces

  • OECD FORD branch

Result continuities

  • Project

  • 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

  • e-ISSN

  • 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