Microstructure and failure processes of reactor pressure vessel austenitic cladding

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F61388998%3A_____%2F21%3A00547942" target="_blank" >RIV/61388998:_____/21:00547942 - isvavai.cz</a>

Nalezeny alternativní kódy

RIV/46356088:_____/21:N0000040 RIV/68407700:21340/21:00353377

Výsledek na webu

<a href="https://www.mdpi.com/journal/metals" target="_blank" >https://www.mdpi.com/journal/metals</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.3390/met11111676" target="_blank" >10.3390/met11111676</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Microstructure and failure processes of reactor pressure vessel austenitic cladding

Popis výsledku v původním jazyce

This paper is dedicated to an experimental program focused on the evaluation of microstructure and failure mechanisms of WWER 440 type nuclear reactor pressure vessel cladding made from Sv 08Kh19N10G2B stainless steel. Static fracture toughness tests performed on standard precracked single edge bend specimens revealed extreme variations in fracture toughness values, J0.2.nFractured halves of test specimens were subject to detailed fractographic and metallographic analyses in order to identify the causes of this behavior and to determine the relationship between localnmicrostructure, failure mode and fracture toughness. Results indicated that fracture toughness of the cladding was adversely affected by the brittle cracking of sigma particles which caused a considerable decrease in local ductile tearing resistance. Extreme variations in relative amounts of sigma phase, as well as the extreme overall structural heterogeneity of the cladding determined in individual specimens, provided a reasonable explanation for variations in fracture toughness values.

Název v anglickém jazyce

Microstructure and failure processes of reactor pressure vessel austenitic cladding

Popis výsledku anglicky

This paper is dedicated to an experimental program focused on the evaluation of microstructure and failure mechanisms of WWER 440 type nuclear reactor pressure vessel cladding made from Sv 08Kh19N10G2B stainless steel. Static fracture toughness tests performed on standard precracked single edge bend specimens revealed extreme variations in fracture toughness values, J0.2.nFractured halves of test specimens were subject to detailed fractographic and metallographic analyses in order to identify the causes of this behavior and to determine the relationship between localnmicrostructure, failure mode and fracture toughness. Results indicated that fracture toughness of the cladding was adversely affected by the brittle cracking of sigma particles which caused a considerable decrease in local ductile tearing resistance. Extreme variations in relative amounts of sigma phase, as well as the extreme overall structural heterogeneity of the cladding determined in individual specimens, provided a reasonable explanation for variations in fracture toughness values.

Druh

J_imp - Článek v periodiku v databázi Web of Science

CEP obor

—

OECD FORD obor

20501 - Materials engineering

Projekt

<a href="/cs/project/EF15_003%2F0000493" target="_blank" >EF15_003/0000493: Centrum pro výzkum nelineárního dynamického chování pokročilých materiálů ve strojírenství (CeNDYNMAT)</a><br>

Návaznosti

I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Rok uplatnění

2021

Kód důvěrnosti údajů

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

Název periodika

Metals

ISSN

2075-4701

e-ISSN

2075-4701

Svazek periodika

11

Číslo periodika v rámci svazku

11

Stát vydavatele periodika

CH - Švýcarská konfederace

Počet stran výsledku

10

Strana od-do

1676

Kód UT WoS článku

000727079500001

EID výsledku v databázi Scopus

2-s2.0-85117359122