Abstract
The approximate estimation of tritium permeation rate under the acceptable assumption from a safety point of view is surely useful to progress the design activities for a fusion DEMO reactor. Tritium permeation rates in the blanket and the divertor were estimated by the simplified evaluation model under the recent DEMO conditions in the water-cooled blanket with solid breeder as a first step. Plasma driven permeation rates in tungsten wall were calculated by applying Doyle & Brice model and gas driven permeation rates in F82H were calculated for hydrogen-tritium twocomponent system. In the representative recent DEMO condition, the following tritium permeation\ rates were obtained, 1.8 g/day in the blanket first wall, 2.3 g/day in the blanket tritium breeding region and 1.6 g/day in the divertor. Total tritium permeation rate into the cooling water was estimated to be 5.7 g/day.
Original language | English |
---|---|
Pages (from-to) | 261-267 |
Number of pages | 7 |
Journal | Fusion Science and Technology |
Volume | 71 |
Issue number | 3 |
DOIs | |
Publication status | Published - 2017 Apr |
Keywords
- Blanket
- DEMO
- Divertor
- Permeation
- Tritium