Irradiation hardening and materials embrittlement in light water reactor (LWR) environments

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F10%3A%230000750" target="_blank" >RIV/26722445:_____/10:#0000750 - isvavai.cz</a>

Výsledek na webu

<a href="http://dx.doi.org/10.1533/9781845699956" target="_blank" >http://dx.doi.org/10.1533/9781845699956</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1533/9781845699956" target="_blank" >10.1533/9781845699956</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Irradiation hardening and materials embrittlement in light water reactor (LWR) environments

Popis výsledku v původním jazyce

This chapter deals with the explanation of the effect of neutron irradiation damage as one of the most important ageing mechanisms in ferritic reactor pressure vessel (RPV) materials. Irradiation conditions, as well as the initial mechanical properties of the RPV material, are the leading parameters that determine the value and character/nature of irradiation damage that can be characterized as irradiation hardening and irradiation embrittlement. While the first one is usually detected by the increase in the yield stress of materials, the latter is characterized by the shift to higher temperatures of the ductile-to-brittle transition temperature (DBTT) obtained from different types of tests - Charpy notch impact or static/dynamic/arrest fracture toughness tests.

Název v anglickém jazyce

Irradiation hardening and materials embrittlement in light water reactor (LWR) environments

Popis výsledku anglicky

This chapter deals with the explanation of the effect of neutron irradiation damage as one of the most important ageing mechanisms in ferritic reactor pressure vessel (RPV) materials. Irradiation conditions, as well as the initial mechanical properties of the RPV material, are the leading parameters that determine the value and character/nature of irradiation damage that can be characterized as irradiation hardening and irradiation embrittlement. While the first one is usually detected by the increase in the yield stress of materials, the latter is characterized by the shift to higher temperatures of the ductile-to-brittle transition temperature (DBTT) obtained from different types of tests - Charpy notch impact or static/dynamic/arrest fracture toughness tests.

Druh

C - Kapitola v odborné knize

CEP obor

JF - Jaderná energetika

OECD FORD obor

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Projekt

—

Návaznosti

Z - Vyzkumny zamer (s odkazem do CEZ)

Rok uplatnění

2010

Kód důvěrnosti údajů

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

Název knihy nebo sborníku

Understanding and mitigating ageing in nuclear power plants: Materials and operational aspects of plant life management (PLIM)

ISBN

978-1-84569-511-8

Počet stran výsledku

17

Strana od-do

357-373

Počet stran knihy

914

Název nakladatele

Woodhead Publ Ltd

Místo vydání

Cambridge, England

Kód UT WoS kapitoly

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