Fusion Technology 1986
Proceedings of the Fourteenth Symposium, Congress Center of the Palais Des Papes, Avignon, France, 8-12 September 1986
Published on 2. October 2013
1918 pages
978-1-4832-8376-0 (ISBN)
Description
Fusion Technology 1986, Volume 1 contains the proceedings of the 14th Symposium on Fusion Technology held in Avignon, France, on September 8-12, 1986. The symposium provided a forum for assessing the state of the art in nuclear fusion as a source of energy. Topics covered range from first wall, divertor, limiter, and vacuum technology to power supplies, neutral beam heating systems, and blanket technology. Tritium handling and magnet technology are also discussed, along with reactor studies and remote handling. Comprised of 118 chapters, this volume first provides an overview of the European Fusion Technology Program and its evolution towards NET (Next European Torus), followed by a discussion on the status of Tokamak physics. The reader is methodically introduced to fusion technology in the U.S. Magnetic Fusion Program; technical aspects of heating and current drive by lower hybrid waves on Tokamaks; and digitized high-power modulation. Subsequent chapters focus on tritium production and processing in a Tokamak reactor; the environmental impact of future fusion reactors; plasma exhaust purification; and operation of magnet power supplies. This book will be of interest to practitioners and research workers engaged in fusion technology.
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Content
Volume IOpening Chairman's RemarksInvited Papers Opening Session Welcome Address and Opening Remarks The Evolution of the European Fusion Technology Program Towards NET Status of Tokamak Physics The Impact of First JET Results on the Development of Fusion First Wall, Divertor, Limiter and Vacuum Technology - Experimental Systems Progress in Fusion Technology in the U.S. Magnetic Fusion Program Plasma-Wall Interaction: Recent TFTR Results and Implications on Design and Construction of Limiters Power Supplies - Plasma Equilibrium - High Frequency Heating Systems Technical Aspects of ECRH Systems ICRH Results and Technological Limitations Technical Aspects of Heating and Current Drive by Lower Hybrid Waves on Tokamaks Synthesis of Invited Lectures on R.F. Systems for Heating, Current-Drive and M.H.D. Stabilization Neutral Beam Heating Systems - Materials Long-Pulse Neutral Injection for ASDEX, ASDEX UPGRADE, and Wendelstein VII-AS: Design, Development and Systems Performance Digitized High Power Modulation Blanket Technology - Refueling - Safety Experimental Systems The Wendelstein VII-AS Experiment The FTU Frascati Tokamak Upgrade Technical Features and Progress of ASDEX UPGRADE The RFX Experiment Status Report on TORE SUPRA Tritium Handling - Data Acquisition and Control Systems Tritium Production and Processing in a Tokamak Reactor Preparation for D-T Phase Operation in Jet Magnet Technology - Reactor Studies - Remote Handling Phebus : A New and Powerfull Laser Facility for I.C.F.
