Post Irradiation Examination of Zr-based fuel claddings including (E)ATF concepts

Kód výsledku v IS VaVaI

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Výsledek na webu

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DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

Post Irradiation Examination of Zr-based fuel claddings including (E)ATF concepts

Popis výsledku v původním jazyce

Monitoring of radiation-induced defects evolution and changes in mechanical properties with increasing neutron fluence is crucial to determine a degree of degradation of fuel claddings at operation, during long-term storage and for future transport and storage of the spent fuel assemblies in a deep geological repository. Comprehensive testing of currently operated Zr-based alloys including (E)ATF concepts is carried out in CVR. The obtained data from irradiation programs are essential for computational analyses related to fuel operation and storage. Additionally, they enhance the transferability and applicability of measurements in research programs involving non-irradiated samples. Since 2018, the Alvel-UJV-CVR research program has conducted six cycles of material sample irradiation under the real operating conditions of the Czech NPP Temelín (VVER-1000). Various Zr-based alloys, produced through different manufacturing processes, were tested to observe radiation growth of samples with different reference microstructure as neutron fluence increased. Moreover, the program was highly focused on the evolution of radiation defects in relation to the reference microstructure (ie. chemical composition and manufacturing process), with evaluations completed up to the fourth cycle of irradiation. In addition to testing under actual NPP conditions, the dry irradiation in the research reactor LVR-15 is a part of several experimental programs, particularly those focused on the effect of low fast neutron fluence on radiation growth and radiation-induced creep, supported by detailed microstructural investigations. As part of the OECD NEA and the FIDES-I Irradiation Experiments Framework, which began in 2021, the data obtained will enable the optimization and qualification of EATF/ATF claddings by comparing their performance with standard and optimized Zr-based claddings. The subsequent FIDES-II program includes post irradiation examination of a broad range of EATF/ATF materials, such as coated Zr-alloys, SiC/SiC, FeCrAl-ODS and others. Currently the irradiation capsules with selected materials are being prepared for irradiation in LVR-15. Additionally, part of the program focuses on irradiating chromium-coated Zr-based alloys under VVER conditions, building on previous research conducted on standard Zr-based alloys. The presentation will outline the goals, results of the irradiation programs, and future activities based on the current state of knowledge. Presented at Konference PWR Prague 2024.

Název v anglickém jazyce

Post Irradiation Examination of Zr-based fuel claddings including (E)ATF concepts

Popis výsledku anglicky

Monitoring of radiation-induced defects evolution and changes in mechanical properties with increasing neutron fluence is crucial to determine a degree of degradation of fuel claddings at operation, during long-term storage and for future transport and storage of the spent fuel assemblies in a deep geological repository. Comprehensive testing of currently operated Zr-based alloys including (E)ATF concepts is carried out in CVR. The obtained data from irradiation programs are essential for computational analyses related to fuel operation and storage. Additionally, they enhance the transferability and applicability of measurements in research programs involving non-irradiated samples. Since 2018, the Alvel-UJV-CVR research program has conducted six cycles of material sample irradiation under the real operating conditions of the Czech NPP Temelín (VVER-1000). Various Zr-based alloys, produced through different manufacturing processes, were tested to observe radiation growth of samples with different reference microstructure as neutron fluence increased. Moreover, the program was highly focused on the evolution of radiation defects in relation to the reference microstructure (ie. chemical composition and manufacturing process), with evaluations completed up to the fourth cycle of irradiation. In addition to testing under actual NPP conditions, the dry irradiation in the research reactor LVR-15 is a part of several experimental programs, particularly those focused on the effect of low fast neutron fluence on radiation growth and radiation-induced creep, supported by detailed microstructural investigations. As part of the OECD NEA and the FIDES-I Irradiation Experiments Framework, which began in 2021, the data obtained will enable the optimization and qualification of EATF/ATF claddings by comparing their performance with standard and optimized Zr-based claddings. The subsequent FIDES-II program includes post irradiation examination of a broad range of EATF/ATF materials, such as coated Zr-alloys, SiC/SiC, FeCrAl-ODS and others. Currently the irradiation capsules with selected materials are being prepared for irradiation in LVR-15. Additionally, part of the program focuses on irradiating chromium-coated Zr-based alloys under VVER conditions, building on previous research conducted on standard Zr-based alloys. The presentation will outline the goals, results of the irradiation programs, and future activities based on the current state of knowledge. Presented at Konference PWR Prague 2024.

Druh

O - Ostatní výsledky

CEP obor

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OECD FORD obor

20501 - Materials engineering

Projekt

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Návaznosti

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Rok uplatnění

2024

Kód důvěrnosti údajů

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