Fusion Technology 1986

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. Research R and D in Support of the 1500 MWe Fast Neutron Reactor in the Light of the Experience Gained on Super Phenix Large Experiments and Projects Technical Aspects of the New JET Development Plan The Development of the JET Electromagnetic System Wall Concepts and Density Control for JET Plans for Current Profile Control in JET Coil System of the NET Machine Maintenance of In-Vessel Components in NET Concluding RemarksOral Papers First Wall, Divertor, Limiter and Vacuum Technology - Experimental Systems The Environmental Impact of Future Fusion Reactors Overview of the JET ICRF Power Plant Operation and Development Start-up Performance of the DIII-D Tokamak Neutral Beam Heating Systems - Materials Pellet Fueling Development at ORNL Textor Neutralbeam-Injection System (NBI) Plasma Exhaust Purification : Experimental Basis for a Process Concept Tritium Handling - Data Acquisition and Control Systems Overview of the Compact Ignition Tokamak Current Requirements for OHMIC Ignition in OHTE and RFP Reactors Reactor Cost Driving Items Impact of the TF Coil Performance on Cost and Compactness of Next-Generation Tokamaks Magnet Technology - Reactor Studies - Remote Handling Reliability Characteristics of Major NET Components Strategy of Breeding Blanket Introduction in NET and Testing Requirements The TFTR Maintenance Manipulator Design and Operation Characteristics Pebble Bed Canister : A Ceramic Breeder Blanket with Helium Cooling for NETPoster Papers First Wall, Divertor, Limiter and Vacuum Technology - Experimental Systems First Wall Design for TORE SUPRA Simulation Experiment of First Wall Carbon Coating Study on Cryopump with High Load Numerical Analysis of Eddy Currents and Magnetic Forces in the Vacuum Vessel of ASDEX UPGRADE Development of the Brazed First Wall Concept for NET Compass Vacuum Vessel Assemblies Metal Seals for Vacuum Vessels at Temperatures up to 350°C A First Wall Concept with Radiatively Cooled Protection Tiles Operation and Performance of the Large Scale JET Cryopump System Parametric Stress Analysis of NET First Wall Designs Electromagnetic Effects on the NET First Wall Caused by a Plasma Disruption Event First Wall Design Criteria. Thermal Fatigue and Creep Experiments and Theoretical Modelling Thermal Structure of the First Wall and High Heat Removal in Cassette Compact Toroid Reactor Performance Analysis of a Full Graphite Armor for RFX Surface Conditioning Technique in the FTU Vacuum Chamber Evacuation of the NET Vacuum Chamber Titanium Getter Pump for the TORE SUPRA Neutral Beam Lines Concept, Calculation and Design of the Insulation Gap in the Vacuum Vessel of ASDEX UPGRADE Carbon Protection Tiles for JET CIT Vacuum Chamber Conceptual Design and Analysis NET Vacuum Vessel and Bulk Shield Design The Experimental Results on Gas Puffing Control on a Tokamak "Tuman-3 First Wall Concepts with Welded Steel Structures for NET The JET Belt Limiter Surface Analyses of TiC Coated Molybdenum Limiter Material Exposed to High Heat Flux Electron Beam Experiences with the ASDEX Neutralizer Plates and Construction of Water-Cooled Plates for Long-Pulse Heating New Textor Liner as a Supporting Structure for the Toroidal Pump Limiter ALT-II Designs for a TFTR Full-Power Pumped Limiter JT-60 Divertor Pumping System and its Initial Operation in Ohmically Heated Divertor Discharges A new Divertor Plates Design Concept for the Double Null NET Configuration Engineering Considerations for the TORE SUPRA Pump Limiter Engineering Aspect of Helical Axis Torsatron The Advanced Toroidal Facility The HBTX1B Reversed Field Pinch Torus Assembly Meqalac : A Low Beta Ion Accelerator with Application to Fusion Devices Field Errors in the RFX Magnetic Field Configuration TPE-1RM15 Reversed Field Pinch Experiment - Design and Construction Description of the Heliac TJ-II and its ECRH System Status of T—15 Engineering System Manufacture and Assembly Power Supplies - Plasma Equilibrium - High Frequency Heating Systems Equilibrium and Axisymmetric Stability of the Proposed TCV Tokamak Plasma Position and Shape Control in TORE SUPRA : Magnetic Measurements and Control Loop Electromagnetic Effects of the Use of Ferromagnetic Materials Within the NET Machine NET Plasma Engineering and Poloidal Field Coil Power Supplies Development and Testing of Components for the ASDEX and W VII as ICRF Long-Pulse Heating The ECRH System for DITE and Compass Experiments New ICRH System for Textor Compatible with ALT-II High-Power MM-Wave Transmitter at 60 GHz Progress in ICRF Heating Technology and Designs for Future Large Tokamak Heating Systems Microwave Technology for ECRH on TFR Modular Multijonction Launchers for 3.7 GHZ - 8 MW - CW Lower Hybrid Experiments on TORE SUPRA Technological Problems and Solutions for the FTU LHRH System A Ridged Waveguide Proposed for ICRH Heating at 120 MHZ in TORE SUPRA A 3.7 GHz 500 kW Klystron for TORE SUPRA The TORE SUPRA Lower Hybrid Transmitter Two Years of Experience with a 600 KW ECRH Installation on TFR The ASDEX ICRF Antennae in Their Uncooled and Cooled Versions Matching Calculation and RF Performance in ICRH on ASDEX Design and Manufacture of Water Cooled Electrostatic Screens for JET ICRF Antennae Non Evaporable Getter Pumping for JET ICRF Antennae Limits of Operation of Conventional RF Windows for Electron Cyclotron Waves Launchers in a Reactor The 70 GHz/1 MW Long-Pulse ECRH System on the Advanced Stellarator W VII-AS The Design of High Power Tetrodes for ICRH Applications Protection and Switching System for the RFX Power Supply Compass Poloidal Field Power Supply System Operating of the Textor Accel Power Supply on the Neutral Injection Test Stand The Development of the JET Poloidal Field Power Supplies to Reach the Nominal Flux Swing Capability The High Voltage Grid Interface in Present and Future JET Operational Requirements The TORE SUPRA Poloidal Field System Power Supplies Operation of the Magnet Power Supplies. Reliability and Improvements Sequential Control of TFTR Power Supplies The FTU Power Supply System : Final Design JT-60 Power Supply Operational Experience DC Thyristor Switching Elements for Fusion Experiments ASDEX UPGRADE Power Supply System ASDEX UPGRADE OHMIC Heating Circuit Prototype Tests on the Ion Source Power Supplies of the Textor NI-System Design, Commissioning and Early Operation of the Power Supply and Protection System for the Extraction Grid of the JET Neutral Injectors at 160kV The JET Neutral Injection 160kV Transmission Lines, the Associated Snubbers and the SF6 Tower for the Termination of the Transmission Lines Housing of the Snubbers and Voltage BreaksVolume II Neutral Beam Heating Systems - Materials Neon, Helium and Self-Ion Damage in Nickel Development of Low Activation Al Base Alloys for Fusion - Comparison Between I/M and P/M Alloys The Corrosion of Steels by Lithium Monoxide and by Lithium Silicate The Corrosion of 316 Steel by Lithium-Lead Alloys under Nitrogen The Influence of Helium on the High Temperature Fatigue Life of Austenitic Stainless Steel Corrosion of AISI 316L Steel in Liquid Lithium in the Presence of a High Magnetic Field Effect of Helium and Fission Neutrons on the Tensile Properties of V-5Ti Irradiation Effects on Mechanical Properties of the NET 316L Reference Heat Physico Chemical Properties of Porous γ LiA1O2 Fundamental Behavior of Shape Memory Alloy Coupler for Quick Replacement Handling of Fusion Core Parts in Cassette Compact Toroid Reactor The Preparation, Characterisation and Properties of Lithium Oxide and Lithium Meta-Zirconate Specimens Irradiated in HFR Petten in the Second and Third Exotic Experiments The Corrosion of Type 316 Stainless Steels in Static and Dynamic Liquid Lithium The Effect of Irradiation at 550°C on the Tensile and Impact Properties of Austenitic and Martensitic Steels The Effect of Irradiation at 150 and 300°C on the Tensile Properties of Cu and CuCrZr Magnetic Phase Induced by Plasma Disruption in AISI 316 SS Stored Energy in MgO and A12O3 Tensile and Fatigue Properties of 316 LN Austenitic Steel at Cryogenic Temperatures Quantification of Plasma Induced Defects in First Wall Materials Behavior of Graphites under Intense Heat Loads Electron Beam Disruption Simulation of Refractory Metals High Heat Flux Tests of Graphites for Limiter Applications Metal/Graphite-Composite Materials for Fusion Devices SIENA : A Spectrum Tailoring Device for Fusion Materials Irradiation in a MTR Neutron and Deuteron Irradiation Creep in Stainless Steel Alloys Textor Neutral Injector Beam Line Design Feedback Control System for Stable Ion Beam Extraction Achievements with the ASDEX Neutral Beam System During Operation Calculations and Measurements : Ion Removal System in the ASDEX/W VII-AS Long-Pulse Neutral-Injection Beam Line Test of an RF-Ion Source with a Large Scale Extraction System Inertia Targets and Acceleration Grids for NBI-Textor Performance of the First JET Neutral Beam Injector A Fast Shutter System for the JET Neutral Injectors The TORE-SUPRA Ion Source First Results from the TORE SUPRA Prototype Injector Interaction of Charged Particle with Fusion Material Blanket Technology - Refueling - Safety The Compatibility of H20 with Li7Pb2 and its Interactions with Hydrogen Isotopes Optimal Use of Beryllium for Fusion Reactor Blankets Interaction of Hydrogen Isotopes with the Liquid Eutectic Alloy 17Li83Pb An Alternative Neutronics Solution for Liquid Lithium Blankets BEATRIX - The International Breeder Materials Exchange Manufacturing Feasibility Study of Water Cooled Liquid Breeder Blanket Modules for NET Thermochemistry in the System LI-SI-BE-O A Low-Risk Aqueous Lithium Salt Blanket for Engineering Test Reactors Transient Analysis of the Water-Cooled Eutectic LiPb Blanket of NET Thermal and Stress Analysis of the Solid B.O.T. Blanket for NET Effects of Openings in a Fusion Reactor Blanket (Tokamak Type) Neutronic Experiments in a LI-PB Spherical Assembly Ceramic Tritium Breeder Materials - Promise and Performance Thermal Properties and Application of Potential Lithium Silicate Breeder Materials Progress in Fusion Reactors Blanket Analysis and Evaluation at CEA A Helium Cooled Lithium-Lead Blanket for a Demo Tokamak Reactor Liquid Metal Cooled Blanket Concept for NET Progress in Design and Analysis of the NET Water Cooled Liquid Breeder Blanket Design and Thermohydraulic Optimization of a Solid Ceramic Breeder Blanket for NET IL Mantello - A Helium Cooled Solid Breeder Blanket for NET First Wall Risk Analysis for a Loss of Coolant Accident in an Experimental Fusion Reactor Activation Studies for Potential Structural Materials of Fusion Reactors Tritium Atmospheric Release : A Simple Model for the Evaluation of HTO Formation Safety Analysis Related to the Possible Release of Activated Erosion Dust in Fusion Reactors First Wall and 17Li-83Pb Blanket Systems Accident Analysis for NET The Implications of γ Dose Rate Limits for the Recycling of Fusion Reactor First Wall Structural Material Device for Varying Pellet Size in a Centrifuge Pellet Injector D2 Pellet Injector for the Reversed Field Pinch Eta Beta II in Padova On Arc Heated Gas Gun Acceleration of Pellets Experimental Test of 6mm Diameter D2 Pellets Produced by In-Situ Condensation Pneumatic Pellet Injectors for TFTR and JET Development of a Two-Stage Injector for Solid H2 Pellets Tritium Handling - Data Acquisition and Control Systems The Compass Data System The Compass Control and Engineering Monitoring System The AMOS/D Data Analysis System for ASDEX UPGRADE Some Features of the Data-Handling Systems in Rijnhuizen Electronics for Data Preparation and Diagnostics Control in ASDEX The JET Pulse Termination Network Distributed Intelligence in a Lan Architecture Increases the Flexibility in Control Systems for Fusion Experiments The TORE SUPRA Control Computer System Application of the Fast Array Processor for JT-60 Plasma Control Structure of the RFX Control and Monitoring System Overview and Operation of the Control, Safety and Interlock on the JET Neutral Beam Injector The Diagnostic Subsystems of the AMOS/D System Computer-to-Process Interface in JET's Control and Diagnostic Systems A Fast Signal Acquisition System for the Time Resolved Lyman-Alpha Diagnostic on Textor Development Status of FTU Control System The TORE SUPRA Data Acquisition System The Tara Control, Monitoring, Data Acquisition, and Analysis System The JET Fast Transfer Diagnostic System - Installation & Commissioning Tritium Release from Neutron Irradiated Li7Pb2 and Li17Pb83 Air Detritiation Systems for Fusion Facilities Based on CANDU Developments Development of an Electrolysis Cell for the Recovery of Tritium from its Oxides Impact of Bubble Nucleation on Tritium Recovery from Blanket Containment Solidification of Tritiated Waste Out of Pile Tritium Release from Various Lithium Materials An Assessment of the Tritium Inventory in, Permeation Through and Releases from the NET Plasma Facing Materials Experimental Determination of the Kinetic Conversion Rate of Gaseous Tritium into HTO A Ceramic Container for Hydrogen Purification on Hot Uranium New Concepts for the Recovery and Isotopic Separation of Tritium in Fusion Reactors Progress in Tritium Technology in the IPP T-Laboratory Scale-Up of Gas Chromatograph System; Removal of Tritium from Secondary Containments Tritium Separation from LiPb Blankets by Permeation into a Gas Stream or into NaK Hydrogen Extraction from a Gas Mixture Torus Evacuation and Tritium Handling on NET : Requirements, Design Approaches and Development Issues Magnet Technology - Reactor Studies - Remote Handling Shear Strength of the ASDEX UPGRADE TF Coil Insulation : Rupture, Fatigue and Creep Behavior Laser Beam Welding of Advanced Superconducting Cable Conduits Geometrical Considerations for the Bending of Superconductors for Planar and Nonplanar Magnets TFTR Control Systems for Protection and for Normal Control of Magnetic Field Coils Mechanical Behavior of Medium Sized Modular Stellarator Coil Configurations Improvements in the FEM-Model of the EURATOM-LCT Coil and Comparison with Results Measured in the TOSKA Test The JET Magnets : Operational Experience and Plans for UPGRADE Different Manufacturing Process of Internal Connections of Toroidal Coils The Central Solenoid of NET Manufacturing of the LN2 Cooled Toroidal Coils of FTU A New Concept in the Design of High-Field Toroidal Magnets Fabrication and Test Results of the Conductor for the Toroidal Field Coils of TORE SUPRA Tests of the Toroidal Field Coils of TORE SUPRA Manufacture and Transport of the TORE SUPRA Large Poloidal Magnetic Field Coils Manufacture and Test of the TORE SUPRA OHMIC Heating Coil Development of a Forced-Cooled Superconducting Coil Design, Construction and Test on a Prototype of a Poloidal Coils of the F.T.U. Dimensional Accuracies Obtained in the TORE SUPRA Toroidal Field Coils Contact Resistance of Demountable Multi-Pin Joint for Superconducting Helical Coil Response of Superconducting Coils to Internal Heating Testing Electrical Insulation of LCT Coils and Instrumentation The Tara 24 MVA Magnet System First Results of the TESPE-S Magnet System Safety Experiments ASDEX UPGRADE Poloidal Field Coils - Concept, Manufacturing, Preliminary Tests Design of Superconducting Pulsed Coil by a CAD System Compass Magnetic Field Coils and Structure Systems A Low Loss Superconducting Cable for Poloidal Field Coils (Design, Development, Measurements) Progress in the NET Toroidal Field Coil Mechanical Design Experience With Cooldown of Superconducting Magnet Coils in the Large Coil Task Considerations on Magnet Design Based on Forced FLow of HE II in InternaLLy Cooled Cables Stress Analysis of the SIN Conductor for the NET TF-Coil The In-Vessel Inspection System on the JT-60 The JET In-Vessel Inspection System Remote Handling Tools for JET Tokamak-Reactor Configuration and Maintenance PLant Design for Reversed Field Pinch Reactor (TITAN) On Some Interesting Properties of the Working Temperature in a Tokamak Reactor Studies on Ignition Target and Reactor in ICF Research The Promise of Tritium Lean Fuels The Dense Z Pinch as a Fusion Power Reactor : Breeding and Radiation Damage Considerations TIBER II Configuration and Structural DesignAuthor Index