Ponente
Descripción
Kyoto Fusioneering (KF) is advancing the field of fusion materials through internal research and major demonstration projects. With the establishment of integrated testing facilities, UNITY-1 and UNITY-2, KF is developing fusion power thermal and fuel cycle systems. These facilities simulate and evaluate material performance under conditions relevant to a fusion power plant in terms of temperature, magnetic field, and tritium presence. However, they lack the expected fusion neutronic environment achievable at IFMIF-DONES.
We present a comprehensive mapping of existing fusion testing facilities, identifying the unique capabilities of IFMIF-DONES, reviewing literature on corrosion under irradiation, and defining specific irradiation conditions and experimental requirements. The study investigates the materials development and testing needs of the burgeoning private fusion industry and highlights the range of experiments that must be performed for current prototype fusion power plant concepts to be taken forward. The possibility for IFMIF-DONES to include these advanced tests is discussed. We show how KF will support fusion materials research, demonstrating the broader applicability and versatility of the IFMIF-DONES facility beyond its primary focus on DEMO-related materials.
As a case study for such an experiment at IFMIF-DONES, an irradiation campaign aligned with KF’s blanket development is presented. Our recent neutronics activities involved modelling the IFMIF-DONES neutron source using OpenMC and PHITS, with benchmarking performed through dual methodologies to ensure reliable results. The proposed irradiation aims to investigate the synergy of corrosion and high-dose neutron irradiation on fusion materials, focusing on KF’s SCYLLA© breeder blanket concept, which utilizes SiCf/SiC composites and lithium lead (LiPb) as coolant and breeding material. Specifically for SCYLLA ©, it is critical to understand the corrosion behaviour of SiCf/SiC composites alongside LiPb breeder under fusion neutron irradiation to be capable of designing a useable blanket for commercial fusion power plants.
Keywords: SiCf/SiC; lithium-lead; SCYLLA; IFMIF-DONES; UNITY; corrosion; neutron irradiation; fusion material; Neutronics Modelling, OpenMC; PHITS.
