Estimation of tritium permeation rate to cooling water in fusion DEMO condition

Kazunari Katayama, Youji Someya, Kenji Tobita, Hirofumi Nakamura, Hisashi Tanigawa, Makoto Nakamura, Nobuyuki Asakura, Kazuo Hoshino, Takumi Chikada, Yuji Hatano, Satoshi Fukada

Research output: Contribution to journalArticlepeer-review

19 Citations (Scopus)


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 languageEnglish
Pages (from-to)261-267
Number of pages7
JournalFusion Science and Technology
Issue number3
Publication statusPublished - 2017 Apr
Externally publishedYes


  • Blanket
  • DEMO
  • Divertor
  • Permeation
  • Tritium

ASJC Scopus subject areas

  • Civil and Structural Engineering
  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering
  • General Materials Science
  • Mechanical Engineering


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