Assessment of T inventory in ITER WCLL TBM with TESSIM-X

Wall Forum

  • Datum: 14.07.2021
  • Uhrzeit: 15:30 - 16:30
  • Vortragender: Rodrigo Arredondo
  • Ort: Seminarraum D3 / Zoom
  • Gastgeber: IPP
The ITER Test Blanket Module (TBM) is tasked with demonstrating efficient breeding and extraction of tritium inside the environment of a nuclear fusion reactor. In order to meet the strict requirements for tritium self-sufficiency necessary for future fusion power plants, and to address safety concerns and minimize radioactive waste, retained T inventory in and T losses out of the TBM must be accurately assessed. In this work, at the request of F4E, T losses due to retention and permeation in the ITER Water-Cooled Lithium Lead (WCLL) TMB are studied with the aid of the TESSIM-X diffusion-trapping code. Due to the presence of neutron-induced traps in the structural materials, T losses in the TBM are now expected to be a factor of 5 - 10 times larger than what was previously thought.
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