Fusion Technology 1982

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. Electromagnetic SystemPoster PresentationsFirst Wall and Vacuum Systems In-Situ Coating of Titanium Carbide Mechanical Calculations for Tore Supra Vacuum Vessels - Tests of Models Manufacture, Testing and Assembly Preparation of the JET Vacuum Vessel Tore-Supra : Design of Thermal Radiation Shield at 80 K High Current Vacuum Bushing for Liner-Heating of TEXTOR The Ignitor Plasma Chamber Heating and Cooling System for the Vacuum Vessel of TEXTOR Using an Organic Heat Transfer Fluid Preliminary Analysis of the Vacuum Vessel and Short-Time-Constant Copper Shell of the FTU Device The Dimensional Survey of Vacuum Vessel Sectors Comparison of Three Options for Fast Pumping of the Tokamak de Varennes Turbomolecular Pumps for Use on Plasma Fusion Experiments Pre-Operational Testing of TFTR Systems Control of CO and O2 Impurities in Hydrogen by Metal Gettering The JET Gas Baking and Cooling Plant Electromagnetic Forces and Mechanical Stresses in the Vacuum Vessel for ASDEX Upgrade Tests of a Cooling and Heating System Model for JT-60 Vacuum Vessel Development of Hard-Seal Gate Valve and Fast Shutter for JT-60 Neutral Beam Injectors Dynamic Analysis of the Vacuum Vessel of Ignitor Experiment Electrical, Thermal and Mechanical Aspects in the Design of the RFX Vacuum Vessel Eddy Current Analysis in JT-60 ECR Discharge Cleaning of Torus Devices High Capacity Cryopump System for a Neutral Beam Test-Bed Evaluation of Fatigue Strength of the JT-60 Vacuum Vessel Based on the Dynamic Response Analysis Under the Electromagnetic Force Calculation of the Hydrogen Recycling from the TEXTOR First Wall at Various Temperatures and Under the Influence of a Thermal Plasma Load The TEXTOR RG-Discharge Cleaning SystemPower Supplies 200 kW Gyrotron Power Supply and Protection System for the Electron Cyclotron Resonant Heating Experiment on Thor, CNR, Milano A 5 MW, 1kHz Thyristor Chopper for Plasma Equilibrium on TFR 600 The Mains Harmonic Filter of TEXTOR The Power Supply and Protection System for the Extraction Grid of the JET Neutral Injectors The FTU Power Supply System : A Preliminary Design Evaluation of the Performance of Thyristor-Controlled Pulsed power Supplies for TEXTOR Power Supply Characteristics and Operating Scenarios for the Varennes Tokamak High Voltage Control and Protection System for the Culham Multi-Megawatt Beam Line Design, Construction and Tests of the Power Crowbar and Predischarge Circuit of the SPICA II Experiment The Design Study of High Voltage Plasma Focus for 1020 Fluence Neutron Source by Using a Water Capacitor Bank A Proposed Alternative for Protecting Ion Sources of Neutral Injectors Against Damage from High Voltage Sparking A High-Bandwidth, High-Voltage Divider for Neutral Injectors The Effect of Capacitive Stored Energy on Neutral Beam Accelerator Performance A Preliminary Study on Feeding Power and Energy to the Poloidal Field Power Supply for a Tokamak Reactor Study of Ohmic Heating (OH) Power Supply System Using DC Thyristor Circuit Breaker The TFTR Neutral Beam Power System Development of Thyristor Phase Control System with Cos-1 CharacteristicsPivertor Technology Experimental Tests Concerning the Use of the Tungsten-Copper Couple Design Concept on the Divertor System Advanced Limiter Test (ALT-I) in the TEXTOR Tokamak - Concept and Experimental Design A Coil System to Perturbe the Magnetic Surfaces at the Tokamak Boundary Graphite Limiter and Armor Damage in Doublet III The Cooling of the Divertor Collector Plates in the International Tokamak ReactorTritium Handling The Development of Tritium Technology at the Tritium Systems Test Assembly Hydrogen Isotope Separation Using Palladium Alloy Membranes The Diffusivity of Tritium in the System Li20-Al203 A Pilot Plant for the Recovery and Separation of Tritium from the Spent Fuel of Fusion Experiments Thermal Release of Tritium from Neutron Irradiated Glass Design and Performance of a Thermal Diffusion Column for Separation of the Hydrogen Isotopes Tritium and Deuterium Permeation Through the First Wall of a Fusion Reactor The TROC Process - Tritium Removal with Organic CompoundsRemote Handling Mechanical Configuration and System Integration Studies of INTOR/NET Design Consideration and Remote Maintenance of INTOR J-II Status of Remote Handling in JET The Gas Cushion Technique as a Handling Means for the Remote Removal of Tokamak SegmentsBlanket Technology and Shielding Demonstration Tokamak Power Plant Blanket Designs with Li-Pb Liquid Breeders An Electricity Producing and Tritium Breeding Blanket Sector for INTOR Enhencement of Benchmark Experiments for CTR Blankets Lay-Out Studies for Inpile-Testing of Blanket Materials and Sub-Modules Neutronic Implications of Lead-Lithium Blankets Thermodynamic Stability of Aluminum Ceramics in Liquid Lithium Tritium Recovery from Liquid Li17Pb83 Thermodynamic Properties of Li17Pb83 Osaka University 14MEV Intense Neutron Source and its Utilizations for Fusion Studies (OKTAVIAN Program) Guide Lines of Fusion Reactor Blanket Nuclear Design Measurements of Neutron Multiplication by Lead Shells and Leakage Spectra from Lithium, Graphite and Stainless Steel Slabs Neutron Transport Calculations for JET Neutron Diagnostics A Study of the Interaction of Tritium with Liquid Li17Pb83Safety Studies on Site and Facilities in R-Project Safety Design of the JT-60 Control System Safety Analysis of NET/INTOR First Wall and Blanket Safety and Environmental Problems of INTOR/NET The Safety and Security System of TEXTORVolume IIMaterials for Fusion Devices A Comparison of Helium Bubble Behavior in an Austenitic and a Ferritic Steel FATMAC : A Machine for the Fatigue Testing of CT Type Samples in the HFR, Petten, The Netherlands The Technology Development Facility (TDF) Spontaneous and Continuous Structure and Surface Transformations of Refractory Transition Metals by Hydrogen Structural and Mechanical Anisotropy of a Nuclear Grade AISI 316 Stainless Steel Helium Bubbles at Grain Boundaries in an Austenitic Steel Irradiation Creep in First Wall Model Alloys Tritium in Vanadium Plastic Flow and Fracture of Ti - Modified 316 Austenitic Atainless Steel After High Temperature Aging in Hydrogen Thermal Fatigue Test Facilities for Simulating the First Wall and Limiter Operating Conditions A Programme for the Study of Fatigue of Fusion Reactor Structural Materials Prospects for Low Activity Aluminum Structures The Cyclotron Facility for Radiation Damage Experiments at the JRC - Ispra Helium Ion Damage in an Amorphous Fe-NI-Mo-B Alloy The Surface Topography of Inconel, Stainless Steel and Copper After Argon Ion BombardmentReactor Studies Evaluation of the Energy Required for Constructing and Operating a Fusion Power Plant The Design of a 316 Stainless Steel First Wall for a Pulsed Fusion Reactor with Wall Loading Greater than 10 MWn-2 Tokamak and Reversed Field Pinch Reactor Cost Scaling Lifetime Considerations for the First Wall of a Demo Reactor Overview of the Hyfire Power/Electrolysis Reactor Design Inertial Confinement Fusion Concepts for Advanced Fuels Tokamak Design for Reacting Plasma Experiment at IPP Nagoya Inertial Fusion Reactor Studies at Lawrence Livermore NationaI Laboratory Studies of First Wall/Blanket/Shield Systems for Fusion Reactors Behavior of Fuel and Helium Particles in Tokamak Reactor on the Model of Starfire Fed Reactor Engineering Features Low-Shear-Stress Toroidal Magnet for "OMITRON" : An Ohmic Ignition TokamakExperimental Systems Modular Mechanical Design of the Advanced Stellarator Wendelstein VII-AS Completion and Operation of the HBTXIA Reversed Field Pinch Apparatus Optimization Criteria in the Electromagnetic Design of RFP Devices Construction of the High-Beta Experiment SPICA II Performance of the TEXTOR Structure Under Rated Loads Design, Fabrication, and Testing of Tandem Mirror Gamma 10Magnet Technology Development of Large Bore-High Current Nb3Sn Coil Considerations on Heat Deposition by Eddy Currents in the Cold Structure of INTOR/NET Eddy Current Calculations for the Tore Supra Toroidal Field Magnet New Supporting Concept for Larqe Twisted Coils Computational Aspects for a Modular Stellarator Fusion Reactor Magnet Mechanical Stress Analysis for the Twisted Coils of the Advanced Stellarator Wendelstein VII-AS Development of Material for the JET Mechanical Structure Mechanical Analysis of Tore Supra Superconducting Toroidal Field Coils Poloidal Field Coils for the International Tokamak Reactor Study "INTOR Mechanical Tests on Components Used in the Tore Supra Superconducting Coils Toroidal Field Coils for INTOR Employment of the Large Coil Test Facility in Toroidal Field Coil Development Numerical Calculations of an Effective Elasticity Tensor and Peak Stresses for the Large Fusion Magnets The Toroidal Field Magnet Concept of ASDEX Upgrade On Strength of Welded Joints in High Strength, Large Scale Copper Coils for Nuclear Fusion Equipment Vacuum Magnetic Fields and Modular Coil System of the Advanced Stellarator Wendelstein VII-AS Strength Analysis of Cooling Pipe Joints for Poloidal Field Coil for Nuclear Fusion Equipment The Technical Concept of the ASDEX UG Poloidal Field Coils Electromagnetic Systems for High-Field Tokamak Pulsed Ion Source of Br-Diode Type with Cryogenic Anode Experience of T-7 Operation in Plasma Experiments Manufacturing of the European LCT-Coil for the Large Coil Task Numerical Analysis of the Metal Forming Process During the Winding Procedure of the European LCT Coil A Procedure for the Computation of Magnetic Field, Temperature and Force Distributions in the Design of Tokamak Toroidal Coils The Design Bending Stress Criterion for JT-60 Coil Toroidal Field Magnet for FT-U Device Manufacture, Assembly and Testing of the Inner Poloidal Coil Stacks of JET and TFTR Manufacture and Test of the TEXTOR BT-Coils Finite-Element Stress Analysis and its Impact on the Design of the Swiss LCT Coil The Toroidal Field Coil Support Structure for the Culham MKIIC Tokamak Reactor Electrical Insulation System Fit for Cyclic High Strain (Development of Insulation of JT-60 Poloidal Field Coil) Design-Relevant Local Mechanical Effects Under Fault Conditions of the European LCT CoilPlasma Equilibrium The Tore Supra Poloidal Field System Efficiency of Passive Circuits for Vertical Stability in INTOR Reactor Measurement and Dynamic Control of Plasma Position in TEXTOR Tokamak Control System of Plasma Position and Current in a Tokamak with Strong Magnetic Field Plasma Parameter Control Experiments on "Tuman-3 The Computational Model for the Control of Plasma Position in TEXTOR Equilibrium and Stability of Plasma Motion in an Iron-Core Tokamak T-15 Poloidal Field Control System The FTU Poloidal Field System Time Evolution of the Coil Currents Shaping and Centering a D-Shaped Reactor Plasma Experience with Feedback and Feedforward for Plasma Control in ASDEX Applicability Verification of Tokamak Plasma Equilibrium Control ModelsHeating Systems The JET Neutral Beam Line, Component Design Features and Assembly The 1 MW Lower Hybrid Frascati F.T. Heating-System Configuration and First Operating Experience A Megawatt Power Transfer System for RFC-XX Test Bed for a Long Pulse 160 KeV Neutral Beam-Line High Power Neutral Beam Operation at 120 KEV with a Single Stage Extraction System The High Power, Long Pulse Ion Cyclotron Resonance Heating System for TEXTOR Long Pulse Operation of the ASDEX Ion Sources with Edge Cooled Extraction Grids Large Area Ion Source for Neutral Beam Injection The Technique of Alfven Wave Heating in the TCA Tokamak Design of a Water Cooled Extraction System for a 55 KV, 22 A, 10 sec Hydrogen Ion Source Some Technological Problems of the Coupling Structure for the FT Lower Hybrid Heating System Compared Behavior of Stainless Steel and Titanium Tests Lines for a L.H.H. Grill Launcher The RF-Ion Source RIG for Neutral Injection The JET Neutral Injection Deflection Magnet Long Pulse Neutral Injectors for JET Electron Tubes for Controlled Thermonuclear Fusion Systems Concurrent Correction of Ion and Electron Space Charge in Ion Beam Simulation Code Line Density Measurements on a Two-Stage Neutralizer Long Pulse High Power Ion Cyclotron Resonance Heating Generator for TEXTOR A 100KV, 80A, 10 sec Power Supply for Neutral Beam Injector The Jülich Ion Source Design and Related Thermomechanical Pre-Testing Development of an Ion Source for Long-Pulse (30-s) Neutral Beam Injection Compact Launching Structures for Lower Hybrid Waves Improved Performance of the ASDEX Neutral Beam Injectors Design of 3 MW ICRH System for ASDEX and W VIIData Acquisition and Control An Electronic Energy Measuring System for Pulsed Neutral Beam Calorimeters An Integrated System for Data Acquisition, Archiving and Analysis in Eta-Beta II Computer Control and Data Acquisition for Neutral Beam Injectors Monitoring and Control of the TEXTOR Grounding System Software Tool for Design and Maintenance of a Large CAMAC System Computer Control System Development for Large Fusion Experiments System Design of ZENKEI, the Central Control System of JT-60 The TEXTOR Diagnostic Data Acquisition System Development Status and First Experience Structure of the Main Control System for the FTU Device Control and Data Acquisition System for the RF Heatinq Plant of the FT Tokamak The Data Acquisition System for ASDEX Experience with Software-Driven Control and Acquisition System The Control and Data Acquisition System of SPICA II PCM Recorder for Raw Diagnostic Data Storage A High Speed Transient Recorder for Fusion Research AppIications Designing & Development of the Real-Time Control System for JT-60 Plasma DischargeRefueling D2 Pellet Acceleration with a Centrifuge Launching of D2-Pellets Through Guide Tubes Pellet Fueling Development at Oak Ridge National Laboratory On the Injection of Deuterium PelletsAuthor Index