Assessment of the possibility of irradiating tungsten and Cu-alloys in IFMIF-DONES using a realistic specimens configuration

IFMIF-DONES (International Fusion Materials Irradiation Facility-DEMO Oriented NEutron Source) is a facility whose purpose is to obtain data on materials by irradiating them under conditions equivalent to those of the DEMO (DEMOstration) fusion reactor. Tungsten and CuCrZr alloy are two candidate ma...

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Main Authors: Irene Álvarez, Marta Anguiano, Fernando Mota, Rebeca Hernández, David Sosa, Fabio Moro, Simone Noce, Yuefeng Qiu, Jin Hun Park, Frederik Arbeiter, Iole Palermo
Format: Article
Language:English
Published: IOP Publishing 2025-01-01
Series:Nuclear Fusion
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Online Access:https://doi.org/10.1088/1741-4326/ada6da
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author Irene Álvarez
Marta Anguiano
Fernando Mota
Rebeca Hernández
David Sosa
Fabio Moro
Simone Noce
Yuefeng Qiu
Jin Hun Park
Frederik Arbeiter
Iole Palermo
author_facet Irene Álvarez
Marta Anguiano
Fernando Mota
Rebeca Hernández
David Sosa
Fabio Moro
Simone Noce
Yuefeng Qiu
Jin Hun Park
Frederik Arbeiter
Iole Palermo
author_sort Irene Álvarez
collection DOAJ
description IFMIF-DONES (International Fusion Materials Irradiation Facility-DEMO Oriented NEutron Source) is a facility whose purpose is to obtain data on materials by irradiating them under conditions equivalent to those of the DEMO (DEMOstration) fusion reactor. Tungsten and CuCrZr alloy are two candidate materials to be used in DEMO, tungsten for the first wall and divertor (DIV) and CuCrZr alloy for the DIV. So, studying the behavior of these materials in IFMIF-DONES facility and comparing the results with the DEMO environment is crucial. In the high flux test module in IFMIF-DONES has been considered a realistic distribution of specimens. The IFMIF-EVEDA beam have been used with a footprint size of 20 × 5 cm ^2 , the nominal energy is 40 MeV with a current of 125 mA, for the calculation other energies have been considered 25, 30 and 35 MeV. The results of IFMIF-DONES have been compared with different DEMO concepts, Dual Coolant Lithium Lead, Water Cooled Lithium Lead and Helium Cooled Pebble Bed. In general, the primary displacement damage rate meets between IFMIF-DONES and DEMO, while the gas production is at the limit for W and fulfilled for the CuCrZr alloy.
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spelling doaj-art-47092f8e3799465f8cdcf2e97e9043702025-01-28T15:16:47ZengIOP PublishingNuclear Fusion0029-55152025-01-0165202605810.1088/1741-4326/ada6daAssessment of the possibility of irradiating tungsten and Cu-alloys in IFMIF-DONES using a realistic specimens configurationIrene Álvarez0https://orcid.org/0000-0002-1654-3187Marta Anguiano1Fernando Mota2https://orcid.org/0000-0002-1337-2482Rebeca Hernández3David Sosa4https://orcid.org/0009-0000-5319-5575Fabio Moro5Simone Noce6Yuefeng Qiu7Jin Hun Park8Frederik Arbeiter9Iole Palermo10https://orcid.org/0000-0001-8725-8167Department of Atomic, Molecular and Nuclear Physics, University of Granada, UGR , Granada, SpainDepartment of Atomic, Molecular and Nuclear Physics, University of Granada, UGR , Granada, SpainLaboratorio Nacional de Fusión por Confinamiento Magnético, CIEMAT , Madrid, SpainDivisión de Materiales de Interés energético, CIEMAT , Madrid, SpainLaboratorio Nacional de Fusión por Confinamiento Magnético, CIEMAT , Madrid, SpainNuclear Department, ENEA Frascati , Rome, ItalyNuclear Department, ENEA Frascati , Rome, ItalyKarlsruhe Institute of Technology, KIT , Karlsruhe, GermanyKarlsruhe Institute of Technology, KIT , Karlsruhe, GermanyKarlsruhe Institute of Technology, KIT , Karlsruhe, GermanyLaboratorio Nacional de Fusión por Confinamiento Magnético, CIEMAT , Madrid, SpainIFMIF-DONES (International Fusion Materials Irradiation Facility-DEMO Oriented NEutron Source) is a facility whose purpose is to obtain data on materials by irradiating them under conditions equivalent to those of the DEMO (DEMOstration) fusion reactor. Tungsten and CuCrZr alloy are two candidate materials to be used in DEMO, tungsten for the first wall and divertor (DIV) and CuCrZr alloy for the DIV. So, studying the behavior of these materials in IFMIF-DONES facility and comparing the results with the DEMO environment is crucial. In the high flux test module in IFMIF-DONES has been considered a realistic distribution of specimens. The IFMIF-EVEDA beam have been used with a footprint size of 20 × 5 cm ^2 , the nominal energy is 40 MeV with a current of 125 mA, for the calculation other energies have been considered 25, 30 and 35 MeV. The results of IFMIF-DONES have been compared with different DEMO concepts, Dual Coolant Lithium Lead, Water Cooled Lithium Lead and Helium Cooled Pebble Bed. In general, the primary displacement damage rate meets between IFMIF-DONES and DEMO, while the gas production is at the limit for W and fulfilled for the CuCrZr alloy.https://doi.org/10.1088/1741-4326/ada6daIFMIF-DONESneutronicscomparativeDEMODPAgas-production
spellingShingle Irene Álvarez
Marta Anguiano
Fernando Mota
Rebeca Hernández
David Sosa
Fabio Moro
Simone Noce
Yuefeng Qiu
Jin Hun Park
Frederik Arbeiter
Iole Palermo
Assessment of the possibility of irradiating tungsten and Cu-alloys in IFMIF-DONES using a realistic specimens configuration
Nuclear Fusion
IFMIF-DONES
neutronics
comparative
DEMO
DPA
gas-production
title Assessment of the possibility of irradiating tungsten and Cu-alloys in IFMIF-DONES using a realistic specimens configuration
title_full Assessment of the possibility of irradiating tungsten and Cu-alloys in IFMIF-DONES using a realistic specimens configuration
title_fullStr Assessment of the possibility of irradiating tungsten and Cu-alloys in IFMIF-DONES using a realistic specimens configuration
title_full_unstemmed Assessment of the possibility of irradiating tungsten and Cu-alloys in IFMIF-DONES using a realistic specimens configuration
title_short Assessment of the possibility of irradiating tungsten and Cu-alloys in IFMIF-DONES using a realistic specimens configuration
title_sort assessment of the possibility of irradiating tungsten and cu alloys in ifmif dones using a realistic specimens configuration
topic IFMIF-DONES
neutronics
comparative
DEMO
DPA
gas-production
url https://doi.org/10.1088/1741-4326/ada6da
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