Effect of strain and strain rate on crack initiation of 316L steel in the simulated PWR water

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

Effect of strain and strain rate on crack initiation of 316L steel in the simulated PWR water

Popis výsledku v původním jazyce

Austenitic stainless steels are widely used for nuclear power plants components thanks to their good mechanical properties at elevated temperatures and excellent corrosion resistance, especially in pressurised water reactors. This paper presents the study of the strain rate effect on environmentally assisted corrosion cracking initiation in pressurised water reactor chemistry. Slow strain rate testing of a non-cold worked 316L austenitic steel was performed using selected strain rates on tapered specimens with two surface treatments at 350 °C in pressurised water reactor simulated water and in air. Detailed prior- and post-testing characterisation of two types of surfaces including roughness, hardness, residual stresses measurements and microstructural analysis was made. Transgranular cleavage-like environmentally assisted corrosion initiation and growth was observed in pressurised water reactor chemistry. The effect of the surface finishes on the cracking initiation was described. The environmentally assisted corrosion initiation stress thresholds were evaluated. The results showed that the threshold values for the polished surfaces were lower than for the ground ones and are influenced by a plastic strain and strain rates.

Název v anglickém jazyce

Effect of strain and strain rate on crack initiation of 316L steel in the simulated PWR water

Popis výsledku anglicky

Austenitic stainless steels are widely used for nuclear power plants components thanks to their good mechanical properties at elevated temperatures and excellent corrosion resistance, especially in pressurised water reactors. This paper presents the study of the strain rate effect on environmentally assisted corrosion cracking initiation in pressurised water reactor chemistry. Slow strain rate testing of a non-cold worked 316L austenitic steel was performed using selected strain rates on tapered specimens with two surface treatments at 350 °C in pressurised water reactor simulated water and in air. Detailed prior- and post-testing characterisation of two types of surfaces including roughness, hardness, residual stresses measurements and microstructural analysis was made. Transgranular cleavage-like environmentally assisted corrosion initiation and growth was observed in pressurised water reactor chemistry. The effect of the surface finishes on the cracking initiation was described. The environmentally assisted corrosion initiation stress thresholds were evaluated. The results showed that the threshold values for the polished surfaces were lower than for the ground ones and are influenced by a plastic strain and strain rates.

Druh

D - Stať ve sborníku

CEP obor

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OECD FORD obor

20501 - Materials engineering

Projekt

Výsledek vznikl pri realizaci vícero projektů. Více informací v záložce Projekty.

Návaznosti

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

Rok uplatnění

2019

Kód důvěrnosti údajů

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

Název statě ve sborníku

Nineteenth International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors

ISBN

978-0-89448-765-1

ISSN

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e-ISSN

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Počet stran výsledku

9

Strana od-do

1001-1009

Název nakladatele

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Místo vydání

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Místo konání akce

Boston, USA

Datum konání akce

18. 8. 2019

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

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