From Micro to Nano Materials Characterization Methods for Testing of Nuclear Core and Structural Materials

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F17%3AN0000141" target="_blank" >RIV/26722445:_____/17:N0000141 - isvavai.cz</a>

Výsledek na webu

<a href="http://susen2020.cz/en/nuclear-technologies-for-21st-century-international-conference-in-rez/" target="_blank" >http://susen2020.cz/en/nuclear-technologies-for-21st-century-international-conference-in-rez/</a>

DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

From Micro to Nano Materials Characterization Methods for Testing of Nuclear Core and Structural Materials

Popis výsledku v původním jazyce

Zirconium-based nuclear fuel claddings act as a barrier against release of fuel particles into the coolant water during plant operation, handling and dry storage of the spent fuel rods. One part of CVR´s long-term investigation of Zr-claddings contributes to the characterization of materials behaviour under different conditions by means of standard as well as advanced methods of specimen preparation and microscopy investigation. Microstructure studies are currently focused on creep behaviour of non-irradiated Zralloys. In the microstructure of Zr-1Nb cladding, which is the one of examined alloys, hydrides can be significantly studied by Light, Scanning as well as Transmission Electron Microscopy. Within these studies, no radial hydride distributions have been observed in specimens after subjection to internal pressure of 55 MPa at 530°C up to 30 hours exposure time. SEM particularly contributes to observe the hydrides in α-Zr phase matrix in detail. Characteristic micrographs of hydride orientation can be obtained by EBSD technique. The methodology for in-situ SEM-EBSD at mechanical testing are going to be developed. Wave Dispersive Spectroscopy method has been optimized for oxygen profile concentration measurements in order to refine the O-content due to the high affinity of Zralloys to the oxygen. TEM studies on Zr-1Nb cover the hydride location as well as identification of secondary precipitates β-Nb and Laves phase Zr (Nb,Fe)2, interaction of dislocations, degree of recrystallization, with special focus on deformed/ballooned regions after creep.

Název v anglickém jazyce

From Micro to Nano Materials Characterization Methods for Testing of Nuclear Core and Structural Materials

Popis výsledku anglicky

Zirconium-based nuclear fuel claddings act as a barrier against release of fuel particles into the coolant water during plant operation, handling and dry storage of the spent fuel rods. One part of CVR´s long-term investigation of Zr-claddings contributes to the characterization of materials behaviour under different conditions by means of standard as well as advanced methods of specimen preparation and microscopy investigation. Microstructure studies are currently focused on creep behaviour of non-irradiated Zralloys. In the microstructure of Zr-1Nb cladding, which is the one of examined alloys, hydrides can be significantly studied by Light, Scanning as well as Transmission Electron Microscopy. Within these studies, no radial hydride distributions have been observed in specimens after subjection to internal pressure of 55 MPa at 530°C up to 30 hours exposure time. SEM particularly contributes to observe the hydrides in α-Zr phase matrix in detail. Characteristic micrographs of hydride orientation can be obtained by EBSD technique. The methodology for in-situ SEM-EBSD at mechanical testing are going to be developed. Wave Dispersive Spectroscopy method has been optimized for oxygen profile concentration measurements in order to refine the O-content due to the high affinity of Zralloys to the oxygen. TEM studies on Zr-1Nb cover the hydride location as well as identification of secondary precipitates β-Nb and Laves phase Zr (Nb,Fe)2, interaction of dislocations, degree of recrystallization, with special focus on deformed/ballooned regions after creep.

Druh

D - Stať ve sborníku

CEP obor

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OECD FORD obor

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

Projekt

Výsledek vznikl pri realizaci vícero projektů. Více informací v záložce Projekty.

Návaznosti

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

Rok uplatnění

2017

Kód důvěrnosti údajů

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

Název statě ve sborníku

Nuclear Technologies for the 21st Centruy, September 13th 2017

ISBN

978-80-270-3233-4

ISSN

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e-ISSN

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Počet stran výsledku

8

Strana od-do

9-16

Název nakladatele

Centrum výzkumu Řež, s.r.o

Místo vydání

Řež

Místo konání akce

Řež

Datum konání akce

13. 9. 2017

Typ akce podle státní příslušnosti

CST - Celostátní akce

Kód UT WoS článku

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