Implementation of the instrumented hardness test method in the process of the nuclear power plants components structural materials assessment

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F46356088%3A_____%2F14%3A%230001469" target="_blank" >RIV/46356088:_____/14:#0001469 - isvavai.cz</a>

Výsledek na webu

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DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

Implementation of the instrumented hardness test method in the process of the nuclear power plants components structural materials assessment

Popis výsledku v původním jazyce

"The subject of this paper is the use of instrumented hardness test for determination of the mechanical properties of the long term operated components of nuclear power plant, which are difficult to replace. These include the reactor pressure vessel, reactor pressure vessel?s internals and the components of the primary circuit. The method is derived from technological processes which allow for a small amount of the studied material to be obtained directly from the component while preserving its structural integrity. The use of remote control operated test devices provides the option of the in-situ studies of the components during reactor outage. The base principle of instrumented hardness testing is multiple indentations by spherical indenters at the same test location on the surface of test sample with intermediate partial unloading. Testing is automated, rapid and localized, and allows determination of the true stress versus true plastic strain characteristic of metallic materials ha

Název v anglickém jazyce

Implementation of the instrumented hardness test method in the process of the nuclear power plants components structural materials assessment

Popis výsledku anglicky

"The subject of this paper is the use of instrumented hardness test for determination of the mechanical properties of the long term operated components of nuclear power plant, which are difficult to replace. These include the reactor pressure vessel, reactor pressure vessel?s internals and the components of the primary circuit. The method is derived from technological processes which allow for a small amount of the studied material to be obtained directly from the component while preserving its structural integrity. The use of remote control operated test devices provides the option of the in-situ studies of the components during reactor outage. The base principle of instrumented hardness testing is multiple indentations by spherical indenters at the same test location on the surface of test sample with intermediate partial unloading. Testing is automated, rapid and localized, and allows determination of the true stress versus true plastic strain characteristic of metallic materials ha

Druh

O - Ostatní výsledky

CEP obor

JS - Řízení spolehlivosti a kvality, zkušebnictví

OECD FORD obor

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Projekt

<a href="/cs/project/TA03011266" target="_blank" >TA03011266: Vývoj inovativní metodiky semidestruktivního hodnocení degradace vysoce aktivních materiálů pro hodnocení životnosti jaderných zařízení</a><br>

Návaznosti

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Rok uplatnění

2014

Kód důvěrnosti údajů

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