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Technology of Controlled Thermonuclear Fusion Experiments and the Engineering Aspects of Fusion Reactors Proceedings of a symposium held at Austin, Texas November 20-22, 1972

机译:控制热核聚变实验技术和聚变反应堆的工程方面1972年11月20日至22日在德克萨斯州奥斯汀举行的研讨会论文集

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Princeton Reactor Studies ProgramnAlpha-Particle Heating of Mirror PlasmanDesign Study of a 14,000-Ampere Injection System for a Fusion ReactornNumerical Analysis of Thermal Stability in an Inhomogeneous D—T Fusion PlasmanAn Effusion—Permeation Extractor SystemnLaser Isotope Separation and Controlled Thermonuclear ReactorsnTritium Inventories and Leakages: A Review and Some Additional ConsiderationsnSome Problems Associated with Tritium in Fusion ReactorsnThe Fusion—Fission Breeder: Its Potential in a Fuel-Starved Thermal Reactor EconomynModel Tokamak Reactors Limited by Anomalous Diffusion and Synchrotron RadiationnParameter Study of a Pulsed High-Beta Fusion Reactor Based on the Theta PinchnDesign Options and Trade-Offs in Superconducting Magnetic Energy Storage with Irreversible SwitchingnReversible Magnetic-Energy Transfer and Storage SystemsnSelf-Consistent Energy-Balance Studies for CTR Tokamak PlasmasnInductive Energy Storage Requirements for a Tokamak Feasibility ExperimentnHomopolar Motor-Generator Designs for Cheap Inertial Energy StoragenA Novel HVDC Circuit Interrupter for Inductive Energy Storage SystemsnSwitching Equipment for Inductive Energy Storage Systems in Nuclear Fusion ResearchnD—D Plasma Fusion Power-Balance CalculationsnPower-Balance Parameters Q. and e as Measures of Performance for Fusion Power ReactorsnA Comparison of Warm- and Cold-Reinforcement Magnet Systems for Tokamak Fusion ReactorsnAn Analysis of the Material Constraints on Superconducting Magnets for Controlled Thermonuclear ReactorsnPerformance of a 12-Coil Superconducting "Bumpy-Torus" Magnet FacilitynSurvey of Main Technological Activities at the Centre Etudes Nucleaires at Fontenay-aux-RosesnFrascati Tokamak and Plasma Focus Experiments: Design InformationnProgress Report No. 1 on the Design Considerations for a Low-Power Experimental Mirror Fusion ReactornBlanket-Cooling Optimization for the Princeton Fusion Flower ReactornEntry-Region Effects on Lithium Flow and Pressure Drop in Fusion-Reactor BlanketsnCooling of Controlled Thermonuclear Fusion Reactors of Toroidal ConfigurationsnLithium Cooling for a Low-Beta Tokamak ReactornPotential Use of GERT IIlz Computer Simulation Techniques in the Analysis of Funding StrategiesnThe Scyllac MHD Feedback SystemnAn Engineering Study of the Electrical Design of a 1000-Megawatt Direct Converter for Mirror ReactorsnSome Features of the Environmental Impact of a Fusion-Reactor Power PlantnApplication of Fast Breeder Experience to Fusion-Blanket StudiesnPreliminary Conceptual Design of a Tokamak ReactornModeling and Optimization of a Conceptual Thermonuclear Fusion Reactor SystemnSurvey of Thermonuclear Reactor ParametersnA Simplified Parametric Study of Tokamak Fusion ReactorsnPotential Merits of Circulating Helium-3 in a D—D Fusion Reactor BlanketnLaser CTR Systems StudiesnEstimation of Impurity Radiation Loss from Fusion-Reactor PlasmasnNecessary Conditions for Steady-State Operation of Controlled Fusion ExperimentsnStaged Theta Pinches with Implosion HeatingnFusion Engineering at the Los Alamos Scientific LaboratorynBreak-Even Criteria for a Pulsed D-T ReactornMagnets for Open-Ended Fusion ReactorsnDiscrete-Ordinates Neutronic Analysis of a Reference Theta-Pinch ReactornNeutron-Flux Spectra at LAMPF for CTR Radiation-Damage StudiesnNeutronic Analysis of a Tritium-Production Integral ExperimentnFusion —Fission Hybrids: A Subcritical Thermal Fission Lattice for a D—T Fusion ReactornNeutron and Gamma Heating Rates in Fusion Reactor BlanketsnCalculation of Fusion Spectrum in GraphitenVariational Methods for CTR Blanket StudiesnSolubilities and Diffusivities of Hydrogen Isotopes in Niobium, Niobium—Zirconium Alloys, and Vanadium at High TemperaturesnRadiation Effects in Graphite in Relation to Its Role in Fusion ReactorsnElevated-Temperature Fatigue Characteristics of Helium-Implanted Stainless SteelnEffects of Heat Treatments on the Superconducting Critical Current Densities of Multifilamentary Nb3Sn wiresnComparative Study of Blistering in Nb, V, and V-20% Ti

著录项

  • 作者

    E. Linn Draper;

  • 作者单位
  • 年度 1974
  • 页码 1-1058
  • 总页数 1058
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 工业技术;
  • 关键词

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