TFTR tritium accounting system for DT-operation

Nagy, A.; Alling, P.; Amerescu, E.; Bashore, D.; Blanchard, W.; Camp, Roderic Ai; Corneliussen, M.; Diesso, M.; Dong, J.; Hosea, J. C.; LaMarche, P. H.; Mika, R.; Pearson, Gavin; Raftopoulos, S.; Rossmassler, R.; Saville, C.; Schobert, J.; Voorhees, D.

doi:10.1109/fusion.1995.534288

Cited by 10 publications

(2 citation statements)

References 2 publications

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“…schedule and safety. Special controls imposed on the handling of tritium [195][196][197] require that the quantity of tritium retained in the torus be accounted for and the inventory limited [198,199] in order to permit continued operation within the licensed site inventory limit.…”

Section: Other Plasma Disturbances Eg Elmsmentioning

confidence: 99%

Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

et al. 2001

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The major increase in discharge duration and plasma energy in a next step DT fusion reactor will give rise to important plasma-material effects that will critically influence its operation, safety and performance. Erosion will increase to a scale of several centimetres from being barely measurable at a micron scale in today's tokamaks. Tritium co-deposited with carbon will strongly affect the operation of machines with carbon plasma facing components. Controlling plasma-wall interactions is critical to achieving high performance in present day tokamaks, and this is likely to continue to be the case in the approach to practical fusion reactors. Recognition of the important consequences of these phenomena stimulated an internationally co-ordinated effort in the field of plasma-surface interactions supporting the Engineering Design Activities of the International Thermonuclear Experimental Reactor project (ITER), and significant progress has been made in better understanding these issues. The paper reviews the underlying physical processes and the existing experimental database of plasma-material interactions both in tokamaks and laboratory simulation facilities for conditions of direct relevance to next step fusion reactors. Two main topical groups of interaction are considered: (i) erosion/redeposition from plasma sputtering and disruptions, including dust and flake generation and (ii) tritium retention and removal. The use of modelling tools to interpret the experimental results and make projections for conditions expected in future devices is explained. Outstanding technical issues and specific recommendations on potential R&D avenues for their resolution are presented.

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Section: Other Plasma Disturbances Eg Elmsmentioning

confidence: 99%

Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

et al. 2001

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“…Tritium retention in plasma-facing materials has emerged as a primary concern for next-step fusion devices fuelled with mixtures of D and T, with strong implications for in-vessel component design, material selection, operational schedule and safety. Special controls imposed on the handling of tritium [195][196][197] require that the quantity of tritium retained in the torus be accounted for and the inventory limited [198,199] in order to permit continued operation within the licensed site inventory limit.…”

Section: Control Of the In-vessel Tritium Inventory 2331 In-vessementioning

confidence: 99%

Plasma-material Interactions in Current Tokamaks and their Implications for Next-step Fusion Reactors

Federici¹,

Skinner²,

Brooks³

et al. 2001

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This Max-Planck-Institut für Plasmaphysik (IPP), Garching, Germany, report is intended for internal use. IPP reports express the views of the authors at the time of writing and do not necessarily reflect the opinions of the Max-Planck-Institut für Plasmaphysik or the final opinion of the authors on the subject. Neither the Max-Planck-Institut für Plasmaphysik, nor the Euratom Commission, nor any person acting on behalf of either of these: (1) gives any guarantee as to the accuracy and completeness of the information contained in this report, or that the use of any information, apparatus, method or process disclosed therein may not constitute an infringement of private owned right; or (2) assumes any liability for damage resulting from the use of any information, apparatus, method or process in this report.

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