Effect of Tensile Strain on Microstructure of Irradiated Core Internal Material

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F15%3A%230001144" target="_blank" >RIV/26722445:_____/15:#0001144 - 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

Effect of Tensile Strain on Microstructure of Irradiated Core Internal Material

Popis výsledku v původním jazyce

Irradiation Assisted Stress Corrosion Cracking (IASCC) is one of the most significant environmental degradation in the internal components made from austenitic stainless steels (ASS). This mechanism is still not fully understood and there are no suitablecriteria for prediction of the damage during operation. In this work, core basket material 08Ch18N10T austenitic stainless steel acquired from decommissioned NPP Nord / Greifswald Unit 1, VVER 440 - 230 type, operated for 15 years and irradiated to 5.2dpa is studied. This material was tensile tested at two different test temperatures and strain rates in air and at the elevated temperature under water environment. SEM observations of the fracture surface documented ductile fracture of the samples tested in air, but areas of IASCC if tested in water. This paper emphases the microscopic examination results from the mechanically tested samples to determine the underlying IASCC physical damage process.

Název v anglickém jazyce

Effect of Tensile Strain on Microstructure of Irradiated Core Internal Material

Popis výsledku anglicky

Irradiation Assisted Stress Corrosion Cracking (IASCC) is one of the most significant environmental degradation in the internal components made from austenitic stainless steels (ASS). This mechanism is still not fully understood and there are no suitablecriteria for prediction of the damage during operation. In this work, core basket material 08Ch18N10T austenitic stainless steel acquired from decommissioned NPP Nord / Greifswald Unit 1, VVER 440 - 230 type, operated for 15 years and irradiated to 5.2dpa is studied. This material was tensile tested at two different test temperatures and strain rates in air and at the elevated temperature under water environment. SEM observations of the fracture surface documented ductile fracture of the samples tested in air, but areas of IASCC if tested in water. This paper emphases the microscopic examination results from the mechanically tested samples to determine the underlying IASCC physical damage process.

Druh

D - Stať ve sborníku

CEP obor

JF - Jaderná energetika

OECD FORD obor

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Projekt

<a href="/cs/project/ED2.1.00%2F03.0108" target="_blank" >ED2.1.00/03.0108: Udržitelná energetika</a><br>

Návaznosti

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

Rok uplatnění

2015

Kód důvěrnosti údajů

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

Název statě ve sborníku

NENE 2015

ISBN

978-961-6207-38-6

ISSN

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e-ISSN

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Počet stran výsledku

8

Strana od-do

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Název nakladatele

Nuclear Society of Slovenia

Místo vydání

Ljubljana, Slovenia

Místo konání akce

Portorož, Slovenia

Datum konání akce

1. 1. 2015

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

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