Modeling of neutral hydrogen velocities in the Tokamak Fusion Test Reactor

Stotler, D.P.; Skinner, C. H.; Budny, R.; Ramsey, A. T.; Ruzic, D. N.; Turkot, R. B.

doi:10.1063/1.871540

Cited by 59 publications

(56 citation statements)

References 41 publications

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“…In contrast, Tα was relatively slow to appear in T-NBI fuelled discharges, the maximum Tα/Tα+Dα fraction was only 11% after 8 T-only NBI discharges [746]. The Balmer-alpha spectrum reflects the isotopic composition of hydrogen recycled from the limiter [747] and clearly much of the tritium gas puff went to the limiter.…”

Section: Insert Fig 66mentioning

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: Insert Fig 66mentioning

confidence: 99%

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

et al. 2001

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“…In JET with the walls initially at 3000 C, Andrew et aL, (1993), reported that as a result of an air leak about 10% of the tritium in the vessel 7x109 Bq (0.2 Ci) was liberated. In a planned moist air purge experiment on TFTR about 15% of the tritium was released from the vessel surfaces 7.8 x 10 Bq (2.lkCi) and subsequently processed by the cleanup system (Skinner, 1996~). The experience on TFTR has shown that it is possible to control the quantity of tritium in the vessel within stringent regulatory requirements.…”

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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“…The rates and kinetic treatment of molecular dissociation and ionization are described in Ref. [12]. Balmer-α photons arising from the dissociation process are not significant in these simulations and are not included.…”

Section: Description Of Simulationmentioning

confidence: 99%