TFTR Tritium Inventory Accountability System

Saville, C.; Ascione, G.; Elwood, S.; Nagy, A.; Raftopoulos, S.; Rossmassler, R.; Stencel, J.R.; Voorhees, D.; Tilson, C.

doi:10.13182/fst95-a30550

Cited by 5 publications

(5 citation statements)

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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%

“…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. An excessive tritium inventory in the torus would present a safety hazard in the form of a potential tritium release to the atmosphere in case of a loss-of-vacuum accident.…”

Section: In-vessel Tritium Inventory In Plasma Facing Componentsmentioning

confidence: 99%

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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%

Section: In-vessel Tritium Inventory In Plasma Facing Componentsmentioning

confidence: 99%

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

et al. 2001

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“…The f i i t is associated with regulatory considerations (Bell et al, 1992;DeLooper, 1994). The quantity of tritium retained must be accounted for since special controls are imposed on the handling of tritium (LaMarche et al, Saville, et al, 1995, Nagy et al, 1996.…”

Section: Tritium Retentionmentioning

confidence: 99%

Results from deuterium-tritium tokamak confinement experiments

Hawryluk

1998

Rev. Mod. Phys.

123

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Recent scientific and technical progress in magnetic fusion experiments has resulted in the achievement of plasma parameters (density and temperature) which enabled the production of significant bursts of fusion power from deuterium-tritium fuels and the first studies of the physics of burning plasmas. The key scientific issues in the reacting plasma core are plasma confinement, magnetohydrodynamic (MHD) stability, and the confinement and loss of energetic fusion products from the reacting fuel ions. Progress in the development of regimes of operation which have both good confinement and are MHD stable have enabled a broad study of burning plasma physics issues.

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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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TFTR Tritium Inventory Accountability System

Cited by 5 publications

References 0 publications

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

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

Results from deuterium-tritium tokamak confinement experiments

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

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