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

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Abstract

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
Volume48
Issue number12B
DOIs
Publication statusPublished - 2006
MoE publication typeA1 Journal article-refereed

Fingerprint

Tritium
tritium
requirements
Facings
estimates
schedules
Plasmas
Carbon
carbon

Keywords

  • 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., ... 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). https://doi.org/10.1088/0741-3335/48/12B/S18
Counsell, G. ; Coad, P. ; Grisola, C. ; Hopf, C. ; Jacob, W. ; Kirschner, A. ; Kreter, A. ; Krieger, K. ; Likonen, Jari ; Philipps, V. ; Roth, J. ; Rubel, M. ; Salancon, E. ; Semerok, A. ; Tabares, F.L. ; Widdowson, A. ; Contributores, JET-EFDA. / Tritium retention in next step devices and the requirements for mitigation and removal techniques. In: Plasma Physics and Controlled Fusion. 2006 ; Vol. 48, No. 12B.
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abstract = "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.",
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author = "G. Counsell and P. Coad and C. Grisola and C. Hopf and W. Jacob and A. Kirschner and A. Kreter and K. Krieger and Jari Likonen and V. Philipps and J. Roth and M. Rubel and E. Salancon and A. Semerok and F.L. Tabares and A. Widdowson and JET-EFDA Contributores",
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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, FL, 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, vol. 48, no. 12B. https://doi.org/10.1088/0741-3335/48/12B/S18

Tritium retention in next step devices and the requirements for mitigation and removal techniques. / Counsell, G.; Coad, P.; Grisola, C.; Hopf, C.; Jacob, W.; Kirschner, A.; Kreter, A.; Krieger, K.; Likonen, Jari; Philipps, V.; Roth, J.; Rubel, M.; Salancon, E.; Semerok, A.; Tabares, F.L.; Widdowson, A.; Contributores, JET-EFDA.

In: Plasma Physics and Controlled Fusion, Vol. 48, No. 12B, 2006.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - Tritium retention in next step devices and the requirements for mitigation and removal techniques

AU - Counsell, G.

AU - Coad, P.

AU - Grisola, C.

AU - Hopf, C.

AU - Jacob, W.

AU - Kirschner, A.

AU - Kreter, A.

AU - Krieger, K.

AU - Likonen, Jari

AU - Philipps, V.

AU - Roth, J.

AU - Rubel, M.

AU - Salancon, E.

AU - Semerok, A.

AU - Tabares, F.L.

AU - Widdowson, A.

AU - Contributores, JET-EFDA

PY - 2006

Y1 - 2006

N2 - 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.

AB - 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.

KW - JET

KW - plasma

KW - fusion energy

KW - fusion reactors

KW - tokamak

KW - ITER

KW - tritium

KW - tritium inventory control

KW - tritium retention

U2 - 10.1088/0741-3335/48/12B/S18

DO - 10.1088/0741-3335/48/12B/S18

M3 - Article

VL - 48

JO - Plasma Physics and Controlled Fusion

JF - Plasma Physics and Controlled Fusion

SN - 0741-3335

IS - 12B

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