TEM examinations of radiation-induced damage and nanoindentation on CW 316 steel irradiated in different neutron spectra

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F18%3AN0000134" target="_blank" >RIV/26722445:_____/18:N0000134 - isvavai.cz</a>

Výsledek na webu

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DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

TEM examinations of radiation-induced damage and nanoindentation on CW 316 steel irradiated in different neutron spectra

Popis výsledku v původním jazyce

Stainless steels are widely used material for structural components that are important in current and advanced reactor technologies. However, many in-core failures have resulted from environment-induced cracking due to contact with high-temperature water, significant mechanical stress level and varying radiation levels in iron based alloy components [1]. Irradiation Assisted Stress Corrosion Cracking (IASCC) is regarded as a major degradation mechanism in Reactor Vessel Internals (RVI), most often causing baffle bolts damage of 300 series Austenitic Stainless Steels in PWR [2, 3] and BWR conditions [4]. The sensitivity of stainless steels to IASCC leads to a deep understanding of radiation-induced damage behavior, so far have observed from real damaged reactor components or specimens irradiated in test reactors. In this work, influence of IASCC on microstructure exposed to fast and mixed spectrum is studied. Presented at Fontevraud9 conference (Contribution of Materials Investigations and Operating Experience to Light Water NPPs’ Safety, Performance and Reliability), 17.-20.9.2018, Avignon, France.

Název v anglickém jazyce

TEM examinations of radiation-induced damage and nanoindentation on CW 316 steel irradiated in different neutron spectra

Popis výsledku anglicky

Stainless steels are widely used material for structural components that are important in current and advanced reactor technologies. However, many in-core failures have resulted from environment-induced cracking due to contact with high-temperature water, significant mechanical stress level and varying radiation levels in iron based alloy components [1]. Irradiation Assisted Stress Corrosion Cracking (IASCC) is regarded as a major degradation mechanism in Reactor Vessel Internals (RVI), most often causing baffle bolts damage of 300 series Austenitic Stainless Steels in PWR [2, 3] and BWR conditions [4]. The sensitivity of stainless steels to IASCC leads to a deep understanding of radiation-induced damage behavior, so far have observed from real damaged reactor components or specimens irradiated in test reactors. In this work, influence of IASCC on microstructure exposed to fast and mixed spectrum is studied. Presented at Fontevraud9 conference (Contribution of Materials Investigations and Operating Experience to Light Water NPPs’ Safety, Performance and Reliability), 17.-20.9.2018, Avignon, France.

Druh

O - Ostatní výsledky

CEP obor

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OECD FORD obor

20305 - Nuclear related engineering; (nuclear physics to be 1.3);

Projekt

<a href="/cs/project/LQ1603" target="_blank" >LQ1603: Výzkum pro SUSEN</a><br>

Návaznosti

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Rok uplatnění

2018

Kód důvěrnosti údajů

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů