Microscopy of Samara experiment specimens Report No. 1: Thin foil sample preparation for TEM analysis of B54 and B60 specimen structure

Kód výsledku v IS VaVaI

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Výsledek na webu

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DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

Microscopy of Samara experiment specimens Report No. 1: Thin foil sample preparation for TEM analysis of B54 and B60 specimen structure

Popis výsledku v původním jazyce

Internals of pressurized water reactors are exposed to a high neutron irradiation. During the extended period of service, the neutron irradiation of austenitic stainless steels leads to a deep modification of their microstructure and their sensitivity to Irradiation Assisted Stress Corrosion Cracking (IASCC). An important R&D program has been initiated by Electricité de France (EDF) applying to irradiations in different experimental reactors. In order to study the effect of the helium content and microstructure, an irradiation was performed in SM reactor (Samara experiment), RIAR, Russia (Agreement RNE T41-7E8571). This report covers the first part of the contract n°1020099924 related to the sample preparation of 1 mm thin foils by using the methodology applied during the previous project to achieve the transparent foils for: - characterization of the microstructure defect population in the deformed zone - shank of B54 and B60 specimens from CW 316 austenitic stainless steel irradiated both to higher dose (~15 dpa) in different spectra (mixed spectrum, fast spectrum),  - nanoindentation examinations of B54 and B60 specimens to confirm the local structural or chemical changes described by TEM analysis.

Název v anglickém jazyce

Microscopy of Samara experiment specimens Report No. 1: Thin foil sample preparation for TEM analysis of B54 and B60 specimen structure

Popis výsledku anglicky

Internals of pressurized water reactors are exposed to a high neutron irradiation. During the extended period of service, the neutron irradiation of austenitic stainless steels leads to a deep modification of their microstructure and their sensitivity to Irradiation Assisted Stress Corrosion Cracking (IASCC). An important R&D program has been initiated by Electricité de France (EDF) applying to irradiations in different experimental reactors. In order to study the effect of the helium content and microstructure, an irradiation was performed in SM reactor (Samara experiment), RIAR, Russia (Agreement RNE T41-7E8571). This report covers the first part of the contract n°1020099924 related to the sample preparation of 1 mm thin foils by using the methodology applied during the previous project to achieve the transparent foils for: - characterization of the microstructure defect population in the deformed zone - shank of B54 and B60 specimens from CW 316 austenitic stainless steel irradiated both to higher dose (~15 dpa) in different spectra (mixed spectrum, fast spectrum),  - nanoindentation examinations of B54 and B60 specimens to confirm the local structural or chemical changes described by TEM analysis.

Druh

V_souhrn - Souhrnná výzkumná zpráva

CEP obor

JL - Únava materiálu a lomová mechanika

OECD FORD obor

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Projekt

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Návaznosti

N - Vyzkumna aktivita podporovana z neverejnych zdroju

Rok uplatnění

2015

Kód důvěrnosti údajů

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

Počet stran výsledku

17

Místo vydání

Řež

Název nakladatele resp. objednatele

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Verze

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