Modelling of plasma tritium concentration and wall tritium inventory at JET

A. Rossi, T. Loarer, G. Saibene, R.D. Monk, L.D. Horton, M.L. Apicella, B. Annaratone

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Abstract

In this paper a method for the calculation of the wall particle inventory in a Tokamak is proposed and applied for a series of discharges carried out during the recent Joint European Torus (JET) D-T experiments. These results are subsequently used to validate a new model for the calculation and prediction of the wall particle inventory on the pulse by pulse time scale. This model, known as the `Wall Retention' model, includes the effect of codeposition and is able to reproduce both the total and the tritium wall inventory if it is assumed that between 0.8% to 2% of the ion flux to the divertor is codeposited. It is demonstrated that the Wall Retention model can be used predictively while maintaining good agreement with the experiments. Extrapolations to ITER give a tritium retention per pulse of 54 g.
Original languageEnglish
Pages (from-to)922 - 927
Number of pages6
JournalJournal of Nuclear Materials
Volume266
DOIs
Publication statusPublished - 2 Mar 1999
Externally publishedYes

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All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Materials Science(all)
  • Nuclear Energy and Engineering

Cite this

Rossi, A., Loarer, T., Saibene, G., Monk, R. D., Horton, L. D., Apicella, M. L., & Annaratone, B. (1999). Modelling of plasma tritium concentration and wall tritium inventory at JET. Journal of Nuclear Materials, 266, 922 - 927. https://doi.org/10.1016/S0022-3115(98)00891-5