Irradiation-assisted stress corrosion cracking of Ti-stabilized austenitic stainless steel

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

Irradiation-assisted stress corrosion cracking of Ti-stabilized austenitic stainless steel

Popis výsledku v původním jazyce

IASCC has been widely observed in reactor vessel internals (RVI) in BWRs and pressurized water PWRs of the western type. In the eastern type of PWRs, also called WWERs, IASCC has been reported in only a few cases. The main differences between the PWRs of western and eastern designs are the construction materials of RVI (Type 321 in WWERs) and the operational environment. New crack growth disposition curves for RVI materials in PWR of western type (the proposed 75th percentile PWR curve in the ASME Section XI Code Case N-889, and the PWR mean curve) were used to verify the curves applicability also for RVI materials in WWERs.

Název v anglickém jazyce

Irradiation-assisted stress corrosion cracking of Ti-stabilized austenitic stainless steel

Popis výsledku anglicky

IASCC has been widely observed in reactor vessel internals (RVI) in BWRs and pressurized water PWRs of the western type. In the eastern type of PWRs, also called WWERs, IASCC has been reported in only a few cases. The main differences between the PWRs of western and eastern designs are the construction materials of RVI (Type 321 in WWERs) and the operational environment. New crack growth disposition curves for RVI materials in PWR of western type (the proposed 75th percentile PWR curve in the ASME Section XI Code Case N-889, and the PWR mean curve) were used to verify the curves applicability also for RVI materials in WWERs.

Druh

D - Stať ve sborníku

CEP obor

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OECD FORD obor

20501 - Materials engineering

Projekt

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Návaznosti

V - Vyzkumna aktivita podporovana z jinych verejnych zdroju

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

7

Strana od-do

1268-1274

Název nakladatele

American Nuclear Society

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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