Fractographic Evaluation of the Fracture Toughness Tests of PWR Materials after Neutron Irradiation

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F46356088%3A_____%2F14%3A%230001640" target="_blank" >RIV/46356088:_____/14:#0001640 - isvavai.cz</a>

Výsledek na webu

<a href="http://dx.doi.org/10.1016/j.mspro.2014.06.137" target="_blank" >http://dx.doi.org/10.1016/j.mspro.2014.06.137</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.mspro.2014.06.137" target="_blank" >10.1016/j.mspro.2014.06.137</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Fractographic Evaluation of the Fracture Toughness Tests of PWR Materials after Neutron Irradiation

Popis výsledku v původním jazyce

The Reactor pressure vessel is a main component of a nuclear power plant's primary circuit. WWER 440 is one of the most widely used nuclear reactors of the second generation. The main structural material of the WWER 440 is the base metal, ferritic steel15Kh2MFA. For the purpose of anti-corrosive protection, the pressure vessels? inner surface is covered with austenitic cladding. The cladding is made from the stainless steels Sv 07Kh25N13 (first layer) and Sv 08Kh19N10G2B (second layer). In frame of pressure vessel materials properties surveillance, fractographic analysis was performed on specimens (both in the neutron-irradiated and non-irradiated state) subjected to static fracture toughness testing. Specimens were collected from the area of the interfaces of the base metal and the austenitic cladding layers. Detailed fractographic analysis of fractured specimens was undertaken. Based on fractographic findings, individual failure micromechanisms taking place during the crack propagat

Název v anglickém jazyce

Fractographic Evaluation of the Fracture Toughness Tests of PWR Materials after Neutron Irradiation

Popis výsledku anglicky

The Reactor pressure vessel is a main component of a nuclear power plant's primary circuit. WWER 440 is one of the most widely used nuclear reactors of the second generation. The main structural material of the WWER 440 is the base metal, ferritic steel15Kh2MFA. For the purpose of anti-corrosive protection, the pressure vessels? inner surface is covered with austenitic cladding. The cladding is made from the stainless steels Sv 07Kh25N13 (first layer) and Sv 08Kh19N10G2B (second layer). In frame of pressure vessel materials properties surveillance, fractographic analysis was performed on specimens (both in the neutron-irradiated and non-irradiated state) subjected to static fracture toughness testing. Specimens were collected from the area of the interfaces of the base metal and the austenitic cladding layers. Detailed fractographic analysis of fractured specimens was undertaken. Based on fractographic findings, individual failure micromechanisms taking place during the crack propagat

Druh

J_x - Nezařazeno - Článek v odborném periodiku (Jimp, Jsc a Jost)

CEP obor

JL - Únava materiálu a lomová mechanika

OECD FORD obor

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Projekt

—

Návaznosti

N - Vyzkumna aktivita podporovana z neverejnych zdroju

Rok uplatnění

2014

Kód důvěrnosti údajů

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

Název periodika

Procedia Materials Science

ISSN

2211-8128

e-ISSN

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Svazek periodika

3

Číslo periodika v rámci svazku

June

Stát vydavatele periodika

NL - Nizozemsko

Počet stran výsledku

6

Strana od-do

841-846

Kód UT WoS článku

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EID výsledku v databázi Scopus

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