Helium, iron and electron particle transport and energy transport studies on the TFTR tokamak

Synakowski, E.J.; Efthimion, P. C.; Rewoldt, G.; Stratton, B.; Tang, W. M.; Bell, R. E.; Grek, B.; Hülse, R.; Johnson, D.; Hill, K.; Mansfield, D.K.; McCune, D.; Mikkelsen, D. R.; Park, H.K.; Ramsey, A. T.; Scott, S.D.; Taylor, G.; Timberlake, J.; Zarnstorff, M. C.

doi:10.2172/10141674

Cited by 1 publication

(1 citation statement)

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“…Calculations of the pumping requirements for helium exhaust using the detailed models described above indicate that the proposed pumping speed should be adequate, provided it is possible to achieve a sufficiently rapid transport of helium ions from the plasma centre, where they are produced, to the edge, where they can be pumped. Experimental results from TFTR [31], TEXTOR [32] and JT-60 [33] indicate that the ratio of the particle confinement time for the thermalized alpha particles to the energy confinement time, TJT E , is between 1 and 3, so that, at least for L-mode conditions, the ratio of the alpha particle density to the plasma density, n^n,., in the core should not exceed the value adopted in the guidelines (10%, Table XXII).…”

Section: Power and Particle Controlmentioning

confidence: 99%

ITER conceptual design

Tomabechi¹,

Gilleland²,

Sokolov³

et al. 1991

Nucl. Fusion

176

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The Conceptual Design Activities of the International Thermonuclear Experimental Reactor (ITER) were carried out jointly by the European Community, Japan, the Soviet Union and the United States of America, under the auspices of the International Atomic Energy Agency. The European Community provided the site for joint work sessions at the Max-Planck-Institut für Plasmaphysik in Garching, Germany. The Conceptual Design Activities began in the spring of 1988 and ended in December 1990. The objectives of the activities were to develop the design of ITER, to perform a safety and environmental analysis, to define the site requirements as well as the future research and development needs, to estimate the cost and manpower, and to prepare a schedule for detailed engineering design, construction and operation. On the basis of the investigation and analysis performed, a concept of ITER was developed which incorporated maximum flexibility of the performance of the device and allowed a variety of operating scenarios to be adopted. The heart of the machine is a tokamak having a plasma major radius of 6 m, a plasma minor radius of 2.15 m, a nominal plasma current of 22 MA and a nominal fusion power of 1 GW. The conceptual design can meet the technical objectives of the ITER programme. Because of the success of the Conceptual Design Activities, the Parties are now considering the implementation of the next phase, called the Engineering Design Activities.

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Section: Power and Particle Controlmentioning

confidence: 99%