Speaker
Petr Stupka
(TEO)
Description
Envisioned fusion facilities for energy production are currently under development within EUROfusion program. In these devices, a D-T plasma is used as energy source. While deuterium is abundant, tritium has to be produced on-site. Tritium, as one of the hydrogen isotopes, easily diffuses through metallic walls of its confinements. Such ‘tritium leakage’ can be limited by developing an efficient anti-permeation barrier. For the purpose, coatings based on Al2O3 are under thorough investigation. To determine their efficiency in decreasing the tritium losses, permeation tests are carried out in a variety of conditions replicating different aspects of the process. One of such tests is an in-pile irradiation of a capsule filled with Pb-17Li alloy and coated sample tubes. The aim of the test is to verify the effect of radiation on tritium permeation rates.
To evaluate the tests, a mathematical model describing tritium permeation within the complex geometry of the PbLi capsule is being developed. In this contribution, a parametric study of the tritium permeation within the PbLi capsule is presented.
Co-authors
Lukas Kosek
(TEO, Centrum výzkumu Řež, Husinec - Řež, Czech Republic)
Michal Kordac
(TEO, Centrum výzkumu Řež, Husinec - Řež, Czech Republic)
Petr Stupka
(TEO, Centrum výzkumu Řež, Husinec - Řež, Czech Republic)
