A study of irradiation-induced growth of advanced zirconium alloys after irradiation in the VVER-1000 reactor core at Temelin NPP

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F21%3AN0000092" target="_blank" >RIV/26722445:_____/21:N0000092 - isvavai.cz</a>

Výsledek na webu

<a href="https://www.euronuclear.org/scientific-resources/conference-proceedings/#1559592636459-42447d8c-0fcc" target="_blank" >https://www.euronuclear.org/scientific-resources/conference-proceedings/#1559592636459-42447d8c-0fcc</a>

DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

A study of irradiation-induced growth of advanced zirconium alloys after irradiation in the VVER-1000 reactor core at Temelin NPP

Popis výsledku v původním jazyce

Since 2014, the irradiation of material samples manufactured from Russian advanced zirconium cladding materials has been performed in the VVER-1000 reactor core of Temelin NPP Unit 1, focused on the study of irradiation-induced growth and related microstructural changes. The material samples differ from each other by alloying elements and heat treatment, which provides a variety of initial microstructural characteristics. The test matrix allows to study the evolution of these different microstructures with neutron irradiation and how it adds up to macroscopic irradiation induced growth. The expected outcome of this large research program is to obtain new experimental data on the irradiation-induced growth of zirconium alloys and the underlying microstructural changes under standard irradiation conditions in a commercial VVER-1000 reactor. Six material cluster assemblies (MCA) containing ampoules with longitudinal segments of cladding tubes of the size of 50 × 6 × 0,6 mm were irradiated in five irradiation cycles to achieve six different values of neutron fluence. One or two MCAs were removed from the reactor core after each irradiation cycle and then cooled in the spent fuel pool. A unique cutting equipment called POMA installed in the transport container pit is used to separate the ampoules with material samples from the remaining part of the MCA. Irradiated materials are being evaluated in the hot-cell facilities of UJV Rez and the Research Center Rez. The material tests and analyses include: - Determination of neutron fluence based on the activities of activation monitors; - Sample geometry measurement and evaluation; - Transmission electron microscopy (TEM); - Metallographic analysis and micronardness measurement. The irradiation of all material samples has been completed. The irradiation-induced growth has been measured for the first four batches and related to the accumulated neutron fluence and to the changes in the microstructure. The alloys of multicomponent Zr-Nb-Sn-Fe systems exhibit significantly higher values of irradiation-induced growth in comparison to the Zr-Nb-(Fe, O) alloys at the same neutron fluences.

Název v anglickém jazyce

A study of irradiation-induced growth of advanced zirconium alloys after irradiation in the VVER-1000 reactor core at Temelin NPP

Popis výsledku anglicky

Since 2014, the irradiation of material samples manufactured from Russian advanced zirconium cladding materials has been performed in the VVER-1000 reactor core of Temelin NPP Unit 1, focused on the study of irradiation-induced growth and related microstructural changes. The material samples differ from each other by alloying elements and heat treatment, which provides a variety of initial microstructural characteristics. The test matrix allows to study the evolution of these different microstructures with neutron irradiation and how it adds up to macroscopic irradiation induced growth. The expected outcome of this large research program is to obtain new experimental data on the irradiation-induced growth of zirconium alloys and the underlying microstructural changes under standard irradiation conditions in a commercial VVER-1000 reactor. Six material cluster assemblies (MCA) containing ampoules with longitudinal segments of cladding tubes of the size of 50 × 6 × 0,6 mm were irradiated in five irradiation cycles to achieve six different values of neutron fluence. One or two MCAs were removed from the reactor core after each irradiation cycle and then cooled in the spent fuel pool. A unique cutting equipment called POMA installed in the transport container pit is used to separate the ampoules with material samples from the remaining part of the MCA. Irradiated materials are being evaluated in the hot-cell facilities of UJV Rez and the Research Center Rez. The material tests and analyses include: - Determination of neutron fluence based on the activities of activation monitors; - Sample geometry measurement and evaluation; - Transmission electron microscopy (TEM); - Metallographic analysis and micronardness measurement. The irradiation of all material samples has been completed. The irradiation-induced growth has been measured for the first four batches and related to the accumulated neutron fluence and to the changes in the microstructure. The alloys of multicomponent Zr-Nb-Sn-Fe systems exhibit significantly higher values of irradiation-induced growth in comparison to the Zr-Nb-(Fe, O) alloys at the same neutron fluences.

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

<a href="/cs/project/LQ1603" target="_blank" >LQ1603: Výzkum pro SUSEN</a><br>

Návaznosti

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

Rok uplatnění

2021

Kód důvěrnosti údajů

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

Název statě ve sborníku

TopFuel2021

ISBN

978-92-95064-35-5

ISSN

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e-ISSN

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Počet stran výsledku

10

Strana od-do

1-10

Název nakladatele

European Nuclear Society

Místo vydání

Brussels, Belgium

Místo konání akce

Santander, Spain

Datum konání akce

24. 10. 2021

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

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