Fusion Technology 1982
Proceedings of the Twelfth Symposium 13-17 September 1982
Published on 2. October 2013
768 pages
978-1-4832-8374-6 (ISBN)
Description
Fusion Technology 1982, Volume 1 contains the proceedings of the 12th Symposium on Fusion Technology held at the Jülich Nuclear Research Center in Germany on September 13-17, 1982. The symposium provided a forum for assessing the state of the art in nuclear fusion as a source of energy. The discussions are organized around the following themes: first wall and vacuum systems; power supplies; divertor technology; tritium handling; remote handling; blanket technology and shielding; and safety. Comprised of 99 chapters, this volume first deals with nuclear fusion and spallation sources for breeding fissile fuel, followed by a discussion on the effects of pulsed loads on supply networks. The reader is then introduced to key issues for remote inspection and repair of a Tokamak; large-scale commercial facility for production of elemental tritium; and in situ coating of titanium carbide. Subsequent chapters explore the use of turbomolecular pumps for plasma fusion experiments; alternative for protecting ion sources of neutral injectors against damage from high voltage sparking; the effect of capacitive stored energy on neutral beam accelerator performance; and cooling of the divertor collector plates in the international Tokamak reactor. This monograph will be of interest to practitioners and research workers engaged in fusion technology.
More details
Content
Volume IOpening Addresses Board of Directors, Kernforschungsanlage Jülich GmbH Head of Technology, Division of the Fusion Program of the Commission of the European Communities Chairman of the ConferenceInvited Lectures Perspectives of Nuclear Fusion and Spallation Sources for Breeding Fissile Fuel Effects of Pulsed Loads on Supply Networks INTOR Impurity Control and First Wall System Key Issues for Remote Inspection and Repair of a Tokamak What are We Learning from INTOR ? Features of the Test Programme The Industry's Role and Experience in Fusion The First Wall in JET - Status and Perspectives Electron-Cyclotron Heating in Toroidal Plasmas Materials and Design Solutions for Breeding Tritium in INTOR Large D- Ion Source for Energetic Neutral Beam Large Scale Commercial Facility for Production of Elemental TritiumOral Presentations Energy Accounting for Heavy Ion ICF Reactor The FTU Project The Advanced Stellarator Wendelstein VII-AS Design and Fabrication of the Superconducting Magnet System for the Mirror Fusion Test Facility (MFTF-B) Heavy Ion Beams for Inertial Confinement fusion : The HIBALL Scenario The Design of the ELMO Bumpy Torus Proof-of-Principle Device ASDEX Upgrade - A Tokamak Experiment with a Reactor-Compatible Poloidal Divertor A Proposed RF-Technology R&D Plan for the United States Extraction of 75 KEV, 70 A, 10 SEC Ion Beam at the Prototype Injector Unit for JT-60 T-15 Installation. The Main Characteristics.
