The present CRP proposal is the continuity of former highly successful ones, which:
- Contributed to stimulation and promotion of Inertial Fusion Energy (IFE) development by improving international cooperation (Elements of power plant design for inertial fusion energy, 2000–2004);- Covered research relevant to development of IFE and to enhancement of awareness in Member States regarding beam-plasma and beam-matter interaction, development of building blocks for IFE and on IFE power plants structure and integration (Pathways to Energy from Inertial Fusion: An Integrated Approach, 2006–2010);- Provided an assessment of the material requirements, consequences and characteristic behaviours in pulsed, repetitively cycled IFE systems (Pathways to Energy from Inertial Fusion: Materials beyond Ignition, 2015–2019).
This CRP seeks to advance the fundamental fusion-material research and -technologies, in close connection with high gain target development, and enhance information exchange on Inertial Fusion Energy R&D, establishing an international network of working groups. This will open the door for more Member States to join the research efforts at different levels and contribute to moving forward in developing the peaceful use of fusion energy, serving the needs of both IFE and Magnetic Fusion Energy (MFE) communities.
The CRP will comprise a coordinated set of research activities:
1. To advance the underlying science and develop novel materials for fusion energy.2. To understand the key processes in the target chamber.3. To assess tritium inventory and its handling.4. To develop next generation targets and diagnostics, that will also help enhance knowledge on high gain target materials.5. To develop driver (including materials research) and target fabrication technologies with an emphasis on repetition systems.
For that aim, it is planned:
1.1. To conduct supporting experiments in repetitive regimes of mechanical, thermal and radiation loads in relevant high-power pulsed plasma, beam and laser installations to understand the science of evolving materials (due to continuous erosion, re-deposition and continuous exposure to particles, radiation and plasma);1.2. To understand the physics of electronic excitation in optical and dielectric materials which is the basic mechanism of material damage under high irradiation doses both in IFE and MFE;1.3. To identify the limits in radiation power, particle flux, and radiation handling, for solid and liquid plasma facing component materials, and extend their performance to IFE and MFE reactor relevant conditions;1.4. To coordinate experimental and modelling efforts towards common standards on material properties.2.1. To investigate the interactions of the “dry” first wall material with deposited capsule, pellet debris/aerosol materials;2.2. To examine the possible use of liquid metals as a “wet” first wall material; 2.3. To assess the requirements for chamber clearing in a reactor operating in the high repetition mode when considering driver and target injection, and first wall responses to implosions.3.1. To evaluate chamber gas/exhaust compositions and the resulting chamber gas-wall interactions, to determine tritium inventory in an IFE power plant;3.2. To understand mechanisms of permeation of hydrogen isotopes in the proposed materials, including the assessment of coatings from the manufacturing, adhesion and resistance;3.3. To specify material requirements, and engineering strategies, for tritium breeding blankets and related systems, their development pathways and impact on the integrated power plant design with regard to confinement, storage and fuel cycle management.4.1. To investigate alternative direct-drive ignition and high gain schemes including shock and fast ignition at intermediate and megajoule-scale laser facilities, in order to evaluate and validate their feasibility for IFE production;4.2. To evaluate the neutron, particle, debris fluxes and inventory from next generation targets and their characterization for the chamber and blanket environment, first wall and final optics studies;4.3. To evaluate target composition effects on neutron production and material modifications during the burning phase of the target, with newly developed in-line neutron diagnostics.5.1. To develop technologies and appropriate structural and optical materials for rep-rate diode-pumped solid-state and KrF laser operation at the IFE relevant level with a high wall-plug efficiency;5.2. To develop materials options and technologies for mass production, target injection and tracking systems for next generation targets with a low aspect ratio and increased robustness.
The efforts made by national and collaborative projects within this internationally coordinated framework will help advance nuclear fusion science and technology.
The overall objective of this CRP is to advance the fundamental fusion-material research and -technologies, and enhance information exchange on Inertial Fusion Energy R&D, establishing an international network of working groups.
To advance the underlying science and develop novel materials for fusion energy.
To understand the key processes in the target chamber.
To assess tritium inventory and its handling.
To develop next generation targets and diagnostics
To develop driver and target fabrication technologies
This CRP has advanced fusion energy research, particularly in the optimization and understanding of plasma-facing materials and plasma-material interactions. A key focus has been the development of dual-phase tungsten alloys, incorporating high-entropy alloys and high-melting-point elements such as VTiTaCr and VMoTaCr as secondary phases. These alloys demonstrated improved hardness (up to 6500 MPa) and a significant reduction in crack formation compared to pure tungsten, making them more resilient under fusion-relevant heat fluxes. Plasma irradiation tests revealed that these dual-phase alloys experienced significantly lower crack depths (20–30 µm) and reduced surface roughness, indicating their superior performance in extreme fusion environments. These findings underscore the potential of dual-phase tungsten alloys as robust plasma-facing materials capable of mitigating erosion and tungsten dust generation in fusion reactors.
Additionally, advancements in diagnostic tools and experimental techniques have played a crucial role in optimizing material testing. The calibration and application of plasma focus devices (PF-2J and PF-2kJ) as tuneable damage factor irradiators have enabled precise studies of material responses under extreme conditions relevant for fusion machines. The integration of precision micrometre positioning for samples, along with calibration of damage factors and comparative irradiation studies, has demonstrated the devices' potential for replicating fusion-relevant material damage. Additionally, multifractal analysis has emerged as an effective method for predicting surface damage evolution, allowing for the distinction of defect patterns and irradiation conditions. These advancements enhance the understanding of material degradation and support the development of next-generation fusion reactor materials.
The project also made significant progress in the development of novel materials and coatings for fusion applications. Notably, research on radiation-resistant optical materials and advanced coatings for permeation and corrosion barriers has identified promising materials like KS-4V glass and Al2O3, with UV pulse treatments enhancing their durability. Additionally, the study of titanium, stainless steel, and tungsten under various irradiation conditions has provided valuable insights into material performance, while the investigation of Laser Induced Breakdown Spectroscopy as a method for hydrogen-isotope detection offers a novel approach to improving reactor monitoring and safety.
Furthermore, the project has contributed to the refinement of computational models and simulations, enhancing the understanding of material behaviour under extreme irradiation scenarios. Studies on tungsten nanostructures under irradiation, along with work on advanced coatings for permeation and corrosion barriers, have led to the development of materials with improved resistance to hydrogen isotopes and corrosion, crucial for the long-term operation of fusion reactors.
Overall, the research has been able to advance the understanding of material performance in fusion environments, paving the way for the development of more durable, efficient, and reliable materials for fusion reactors. The project’s findings not only contribute to material science but also provide practical solutions for the design and operation of next-generation fusion machines.
This coordinated research project (CRP) addresses key challenges in fusion energy, primarily the development of advanced plasma-facing materials and the control of tritium inventory within reactors. The project focuses on finding radiation-resistant alternatives to tungsten (W), enhancing materials that can withstand extreme plasma conditions and reduce erosion and dust generation. It also tackles tritium management by designing ceramic breeding blankets and coatings that act as tritium permeation and corrosion barriers, ensuring safety and reducing embrittlement in reactor components. The development of small, low-cost irradiation devices, such as plasma focus systems, helped in replicating fusion reactor conditions and test materials under extreme environments. These devices, when optimized, enable more accurate assessments of material performance and degradation mechanisms. Additionally, the project advances computational models to predict material behaviour and supports the development of innovative target manufacturing and delivery technologies for inertial fusion energy (IFE) systems. Overall, the research is crucial for overcoming current limitations in fusion technology, supporting the development of materials and systems essential for the practical realization of fusion energy as a safe and sustainable power source.