Ponente
Descripción
The primary objective of the IFMIF-DONES Project is the testing and validation of fusion materials. The requirements from critical fusion experiments, such as the High Flux Test Modules (HFTM) for structural materials in fusion reactors, have driven the facility's overall design. The HFTM is crucial for qualifying structural materials for the future DEMO nuclear fusion reactor.
Given the anticipated delays in the deuterium-tritium phase of ITER, the initial results from the Test Breeder Module (TBM) are not expected before 2040. Therefore, it is essential to design experiments that can validate breeder blanket technologies under equivalent irradiation conditions. Within this context, the IFMIF-DONES project has resumed its development program, focusing on experiments to validate these technologies.
While significant progress was made in previous phases of the IFMIF-DONES project (IFMIF-EVEDA phase) concerning the design of various modules, this work shifts focus to the Test Blanket Unit (TBU) for testing liquid breeder blanket technologies, like WCLL and DCLL DEMO concept. Then, the main objective of TBU will be instrumental in approving liquid breeder blanket (BB) technologies, unlike the Liquid Breeder Validation Module (LBVM), which primarily tests BB materials through physical experiments.
This work presents neutron transport calculations to re-evaluate the radiation conditions in the medium-flux area of the latest IFMIF-DONES TC to hold the TBU. The TBU is being designed to test the behavior of liquid Breeder Blanket technologies under irradiation conditions equivalent to those in future liquid BB DEMO concepts. The optimal location for the TBU within the TC has been determined to maximize the tritium production rate. Additionally, we explore the radiation effects expected in the future DEMO on various coatings, such as tritium anti-permeation, anti-corrosion, and coatings designed to reduce Magnetohydrodynamic (MHD) effects.
