Failure behaviour of cladding made from Sv 07Kh25N13 austenitic stainless steel

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F46356088%3A_____%2F21%3AN0000030" target="_blank" >RIV/46356088:_____/21:N0000030 - isvavai.cz</a>

Nalezeny alternativní kódy

RIV/61388998:_____/21:00536631 RIV/68407700:21340/21:00353380

Výsledek na webu

<a href="https://www.sciencedirect.com/science/article/pii/S0308016120302507" target="_blank" >https://www.sciencedirect.com/science/article/pii/S0308016120302507</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.ijpvp.2020.104275" target="_blank" >10.1016/j.ijpvp.2020.104275</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Failure behaviour of cladding made from Sv 07Kh25N13 austenitic stainless steel

Popis výsledku v původním jazyce

Sv 07Kh25N13 is austenitic stainless steel used in nuclear industry. Due to its excellent corrosion resistance in the environment of WWER type nuclear reactor primary circuit, it is applied as anticorrosive cladding of the reactor pressure vessel. In this paper, results of detailed experimental research of failure behaviour of the cladding are presented. Static fracture toughness values J(0.2) exhibited an extreme scatter. Metallographic analysis performed on the fractured specimens revealed large variations of structure within every single cladding layer. Fracto-graphic analysis performed on fracture surfaces revealed considerable variations of micromechanisms taking place during ductile crack propagation. Conclusions on the relationship between the local microstructure, the failure mode and the fracture toughness of the cladding were drawn. Results indicate that the fracture toughness of the cladding was primarily determined by local amount of sigma phase in the area of crack propagation.

Název v anglickém jazyce

Failure behaviour of cladding made from Sv 07Kh25N13 austenitic stainless steel

Popis výsledku anglicky

Sv 07Kh25N13 is austenitic stainless steel used in nuclear industry. Due to its excellent corrosion resistance in the environment of WWER type nuclear reactor primary circuit, it is applied as anticorrosive cladding of the reactor pressure vessel. In this paper, results of detailed experimental research of failure behaviour of the cladding are presented. Static fracture toughness values J(0.2) exhibited an extreme scatter. Metallographic analysis performed on the fractured specimens revealed large variations of structure within every single cladding layer. Fracto-graphic analysis performed on fracture surfaces revealed considerable variations of micromechanisms taking place during ductile crack propagation. Conclusions on the relationship between the local microstructure, the failure mode and the fracture toughness of the cladding were drawn. Results indicate that the fracture toughness of the cladding was primarily determined by local amount of sigma phase in the area of crack propagation.

Druh

J_imp - Článek v periodiku v databázi Web of Science

CEP obor

—

OECD FORD obor

20305 - Nuclear related engineering; (nuclear physics to be 1.3);

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

N - Vyzkumna aktivita podporovana z neverejnych zdroju

Rok uplatnění

2021

Kód důvěrnosti údajů

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

Název periodika

International Journal of Pressure Vessels and Piping

ISSN

0308-0161

e-ISSN

—

Svazek periodika

189

Číslo periodika v rámci svazku

February

Stát vydavatele periodika

GB - Spojené království Velké Británie a Severního Irska

Počet stran výsledku

7

Strana od-do

1-7

Kód UT WoS článku

000614145400017

EID výsledku v databázi Scopus

2-s2.0-85097455003