Fourth DONES Users Workshop

Sesión

Qualification of materials for the fusion programme, DEMO and fusion power plant

14 oct 2026, 9:30

Main Auditorium (CIEMAT)

101. EUROfusion material development and qualification roadmap for baseline and advanced materials for fusion in-vessel components

Gerald Pintsuk (FZJ)

14/10/26, 9:30

The first objective of the EUROfusion Work Package Materials is the characterization and qualification of the three baseline materials, i.e. EUROFER97 steel for blankets and divertor cassette structure, tungsten as plasma facing armor material, and copper-chromium-zirconium (CuCrZr) for divertor heat-sinks. Qualification of the industrially available baseline materials, up to a level...

102. Small Specimen Test Technique to investigate neutron irradiation effects: development performed within EUROfusion project in 2021-2025

Dmitry Terentyev

14/10/26, 9:55

D. Terentyev1,2, E. Gaganidze3, Mario Walter3, M. Carrington4, K. Amjad4, D. Cinger5, A. Zinovev1, D. Bermudez1,6, M. Serrano7, R. Hernandez7, R. Molak8, G. Pintsuk9, G. Aiello10

1. Belgian Nuclear Research Centre, SCK CEN, Mol, 2400, Belgium
2. Ghent University, Department of Materials, Textiles and Chemical Engineering, Ghent, Belgium
3. Karlsruhe Institute of Technology (KIT),...

120. Pre-Qualification of Small-Scale Tensile Testing Methodologies for EUROFER97 and CuCrZr Towards Future IFMIF-DONES Irradiation Campaigns

Francisco Canillas (CIEMAT - National Fusion Laboratory)

14/10/26, 10:10

The qualification of structural and functional materials for fusion reactors requires extensive mechanical testing under neutron irradiation. However, the limited irradiation volume available in current facilities and in future neutron sources such as IFMIF-DONES makes the use of conventional tensile specimens impractical. Small Specimen Test Technology (SSTT) has therefore emerged as a key...

115. Fracture Data Acquisition Approach for Reliability Assessment of RAFM Steel in Fusion DEMO Reactors

Dr. Takashi Nozawa (National Institutes for Quantum Science and Technology)

14/10/26, 11:00

The qualification assessment of low-activation ferritic-martensitic steel (RAFM), a key structural material for fusion DEMO reactors, is a critical challenge for the realization of such reactors. The IFMIF-DONES program identifies the acquisition of neutron irradiation data as a key strategy to support this qualification assessment. The design of future in-vessel components will be verified...

100. Bridging the Gap: Fusion-Fission Synergies to Accelerate Material Qualification for DEMO and Fusion Power Plants

Prof. Marta Serrano Garcia (CIEMAT)

14/10/26, 11:25

Future fusion power systems will expose materials to some of the harshest operating conditions ever considered in nuclear engineering, combining intense neutron irradiation, helium production, thermal cycling, high temperatures, and chemically aggressive environments. While fusion introduces unique challenges, many of the underlying degradation mechanisms and qualification needs are closely...

138. Materials selection for the DONES High Flux Test Module

Frederik Arbeiter (KIT)

14/10/26, 11:50

The DONES High Flux Test Module shall serve to irradiate material samples up to 50 dpa in a temperature range of 250 - 550 °C in a 14 MeV type neutron spectrum. Inevitably, the same and even slightly higher structural damage will be effected in the HFTM's structural and functional components. The HFTM design responds to this challenge by separation of functions and avoiding the most critical...

126. Development Challenges for Tungsten-Based Materials and Joints Under Fusion-Relevant Neutron Loading in Plasma-Facing Components

Hanns Gietl (Max Planck Institute for Plasma Physics)

14/10/26, 12:15

A key challenge in the development of magnetic confinement fusion power plants is the reliable exhaust of heat and particles. Divertor plasma-facing components (PFCs) must therefore withstand extreme thermal and particle loads, including neutron irradiation, which progressively degrades critical material properties. Current divertor PFC concepts typically rely on a monolithic tungsten (W)...

109. Towards Fusion-Relevant Materials Qualification: Insights from the UK NEURONE Programme

Slava Kuksenko (United Kingdom Atomic Energy Authority)

14/10/26, 12:30

The UK Atomic Energy Authority–led NEURONE programme is a multi-year initiative aimed at accelerating the development and deployment of advanced nuclear steels. Its primary objective is to fast-track the development, screening, and qualification of next-generation reduced-activation steels for both fusion and fission applications. These materials are designed to withstand the extreme...

121. Study of the W-based High Entropy Alloy in DiFU as support facility for pre-selection of materials for DONES

Andreja Gajović (Ruđer Bošković Institute)

14/10/26, 12:45

The two processes relevant when testing a material for fusion environments are its response to (1) displacement damage and (2) transmutation reactions [1] can be mirrored by ion beam irradiation by heavy ion irradiation, and by helium implantation. The best effect can be achieved when these two types of ion irradiations are applied simultaneously in the dual-beam irradiation setup, like the...