Tritium retention in next step devices and the requirements for mitigation and removal techniques

G. Counsell, P. Coad, C. Grisola, C. Hopf, W. Jacob, A. Kirschner, A. Kreter, K. Krieger, Jari Likonen, V. Philipps, J. Roth, M. Rubel, E. Salancon, A. Semerok, F.L. Tabares, A. Widdowson, JET-EFDA Contributores

Research output: Contribution to journalArticleScientificpeer-review

78 Citations (Scopus)


Mechanisms underlying the retention of fuel species in tokamaks with carbon plasma-facing components are presented, together with estimates for the corresponding retention of tritium in ITER. The consequential requirement for new and improved schemes to reduce the tritium inventory is highlighted and the results of ongoing studies into a range of techniques are presented, together with estimates of the tritium removal rate in ITER in each case. Finally, an approach involving the integration of many tritium removal techniques into the ITER operational schedule is proposed as a means to extend the period of operations before major intervention is required.
Original languageEnglish
JournalPlasma Physics and Controlled Fusion
Issue number12B
Publication statusPublished - 2006
MoE publication typeA1 Journal article-refereed



  • JET
  • plasma
  • fusion energy
  • fusion reactors
  • tokamak
  • ITER
  • tritium
  • tritium inventory control
  • tritium retention

Cite this

Counsell, G., Coad, P., Grisola, C., Hopf, C., Jacob, W., Kirschner, A., Kreter, A., Krieger, K., Likonen, J., Philipps, V., Roth, J., Rubel, M., Salancon, E., Semerok, A., Tabares, F. L., Widdowson, A., & Contributores, JET-EFDA. (2006). Tritium retention in next step devices and the requirements for mitigation and removal techniques. Plasma Physics and Controlled Fusion, 48(12B).