M. K. Lilley S. E. Sharapov
A discrete spectrum of compressional Alfvén eigenmodes and ion-ion hybrid eigenmodes is found to exist above the tritium ion cyclotron frequency in the deuterium-tritium D-T plasma of a spherical tokamak power plant STPP [H. R. Wilson and et al. , 19th IAEA Fusion Energy Conference IAEA, Lyon, France, (2002), No. FT/1-4]. An equilibrium magnetic w…
PublishedA.J. Koning M.Avrigeanu V.Avrigeanu P. Batistoni E. Bauge M.-M.Bé P.Bem D.Bernard O.Bersillon A. Bidaud O. Bouland A. Courcelle C.J.Dean P.Dos-Santos-Uzarralde B.Duchemin I.Duhamel M.C.Duijvestijn E. Dupont U. Fischer R.A. Forrest F.Gu
The status of the Joint Evaluated Fission and Fusion file (JEFF) is described. JEFF-3.1 comprises a significant update of actinide evaluations, materials evaluations that have emerged from various European nuclear data projects, the activation library JEFF-3.1/A, the decay data and fission yield sub-libraries, and fusion-related data files from the…
PublishedR. Pampin
Lithium-lead is a candidate tritium-generating material in conceptual designs of magnetic fusion power plants. Its prolonged utilization, ultimately during the entire lifetime of such a facility, has the potential to minimize amounts of active waste and improve the economic performance. Limits to a prolonged use are production of long-lived radioac…
PublishedM. J. Walsh M. Beurskens P. G. Carolan M. Gilbert M. Loughlin Et Al
The maximum temperature expected in ITER is in the region of 40 keV and the minimum average density of approximately 310 19 m -3 is also expected. The proven capability, convenience, and port occupancy of the LIDAR Thomson scattering approach, demonstrated on JET, makes it an excellent candidate for ITER. Nonetheless, there are formidable design ch…
PublishedR. S. Hemsworth D. Boilson B. Crowley D. Homfray H. P. L. De Esch Et Al
The Kamaboko III negative ion source, which was designed and built by JAERI, Naka, Japan, is a model 25% in linear dimensions of the reference design ion source for the International Thermonuclear Experimental Reactor ITER neutral beam injectors. The ion source is a magnetic multi-pole, arc discharge, source with 12 tungsten filaments. Cesium is ad…
PublishedYueqiang Liu M. S. Chu A. M. Garofalo R. J. La Haye Y. Gribov M. Gryaznevich T. C. Hender D. F. Howell P. De Vries M. Okabayashi S. D. Pinches H. Reimerdes EFDA-JET Contributors
Active control of the resistive wall mode RWM for DIII-D [Luxon and Davis, Fusion Technol. 8 , 441 (1985)] plasmas is studied using the MARS-F code [Y. Q. Liu, and et al. , Phys. Plasmas 7 , 3681 (2000)]. Control optimization shows that the mode can be stabilized up to the ideal wall beta limit, using the internal control coils I-coils and poloidal…
PublishedM. F. F. Nave H. R. Koslowski S. Coda J. Graves M. Brix R. Buttery C. Challis C. Giroud M. Stamp P. De Vries Jet-Feda Contributors
During a recent reversed toroidal field (B T) campaign at the Joint European Torus (JET), experiments were performed to investigate the effect on sawteeth of neutral beam injection (NBI)-driven toroidal plasma rotation counter to the direction of the toroidal plasma current and B T . A power scan at constant density has permitted analytical continu…
PublishedI.T. Chapman S. Saarelma T.C. Hender S.E. Sharapov G.T.A. Huysmans A.B. Mikhailovskii H. Meyer A. Kirk H.R. Wilson
Present day tokamaks are capable of generating toroidal flows approaching the ion sound speed. Such toroidal rotation is known to have a stabilising effect on resistive wall modes[1]. Here the effects of plasma rotation and diamagnetic drifts on the n = 1 internal kink mode and high n ballooning modes are presented with specific comparison to exper…
PublishedPanos J. Karditsas
The High Efficiency Thermal Shield (HETS) concept was proposed by ENEA for divertor application in the context of the ITER project and as part of the European Power Plant Conceptual Study. The design is modular, and the unit dimensions are of the order of centimeters for limiting mechanical and thermal stresses. This paper presents results of therm…
PublishedNeill P. Taylor
Studies of the safety and environmental impacts of fusion, both of future power plants and of ITER, have shown that a good performance can be achieved. Although it is difficult to anticipate the regulatory regime in which future fusion power stations will be licensed, the areas of public and occupational safety and short and long-term environmental…
Published