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Search: WFRF:(Semerok A.) > (2006)

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1.
  • Counsell, G., et al. (author)
  • Tritium retention in next step devices and the requirements for mitigation and removal techniques
  • 2006
  • In: Plasma Physics and Controlled Fusion. - 0741-3335 .- 1361-6587. ; 48:12B, s. B189-B199
  • Journal article (peer-reviewed)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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2.
  • Grisolia, C., et al. (author)
  • JET contributions to ITER technology issues
  • 2006
  • In: Fusion engineering and design. - : Elsevier BV. - 0920-3796 .- 1873-7196. ; 81:07-jan, s. 149-154
  • Journal article (peer-reviewed)abstract
    • The Joint European Torus (JET) fusion machine is the only device capable of operation with tritium and of handling Be and therefore is best suited to the study of tritium and fusion-related issues. A large variety of activities are performed within the JET fusion technology task force (FT-TF). In this paper, some topics such as erosion/deposition and material transport, characterisation of flakes and detritiation techniques are highlighted. Recent examples of results obtained on waste management studies are also given. Data on some ITER-relevant components that have been tested at JET, such as a pumping cryopanel and hardened optics fibers, are presented. In all fields, the work to be addressed in future JET work programmes is discussed.
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