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%2F68407700%3A21340%2F14%3A00223407" target="_blank" >RIV/68407700:21340/14:00223407 - 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

D - Stať ve sborníku

CEP obor

JL - Únava materiálu a lomová mechanika

OECD FORD obor

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Projekt

—

Návaznosti

S - Specificky vyzkum na vysokych skolach

Rok uplatnění

2014

Kód důvěrnosti údajů

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

Název statě ve sborníku

20th European Conference on Fracture

ISBN

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ISSN

2211-8128

e-ISSN

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Počet stran výsledku

6

Strana od-do

841-846

Název nakladatele

Elsevier

Místo vydání

Amsterdam

Místo konání akce

Trondheim

Datum konání akce

30. 6. 2014

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

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