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Development of Neutral Beams for Fusion Plasma Heating

Development of Neutral Beams for Fusion Plasma Heating PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description
A state-of-the-art account of neutral beam technology at the LBL/LLNL and ORNL facilities is given with emphasis on positive-ion-based systems. The advances made in the last few years are elaborated and problem areas are identified. The ORNL program has successfully completed the neutral injection systems for PLT, ISX-B, and most recently, PDX and the ISX-B upgrade. All of these are high current (60 to 100 A), medium energy (40 to 50 keV) systems. This program is also engaged in the development of a reactor-grade advanced positive ion system (150 to 200 kV/100 A/5 to 10 s) and a multimegawatt, long pulse (30 s) heating system for ISX-C. In a joint program, LBL and LLNL are developing and testing neutral beam injection systems based on the acceleration of positive ions for application in the 80- to 160-keV range on MFTF-B, D-III, TFTR/TFM, ETF, MNS, etc. A conceptual design of a 160-keV injection system for the German ZEPHYR project is in progress at LBL/LLNL and independently at ORNL. The laboratories are also engaged in the development of negative-ion-based systems for future applications at higher energies.

Development of Neutral Beams for Fusion Plasma Heating

Development of Neutral Beams for Fusion Plasma Heating PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description
A state-of-the-art account of neutral beam technology at the LBL/LLNL and ORNL facilities is given with emphasis on positive-ion-based systems. The advances made in the last few years are elaborated and problem areas are identified. The ORNL program has successfully completed the neutral injection systems for PLT, ISX-B, and most recently, PDX and the ISX-B upgrade. All of these are high current (60 to 100 A), medium energy (40 to 50 keV) systems. This program is also engaged in the development of a reactor-grade advanced positive ion system (150 to 200 kV/100 A/5 to 10 s) and a multimegawatt, long pulse (30 s) heating system for ISX-C. In a joint program, LBL and LLNL are developing and testing neutral beam injection systems based on the acceleration of positive ions for application in the 80- to 160-keV range on MFTF-B, D-III, TFTR/TFM, ETF, MNS, etc. A conceptual design of a 160-keV injection system for the German ZEPHYR project is in progress at LBL/LLNL and independently at ORNL. The laboratories are also engaged in the development of negative-ion-based systems for future applications at higher energies.

Research, Design, and Development Needed to Realise a Neutral Beam Injection System for a Fusion Reactor

Research, Design, and Development Needed to Realise a Neutral Beam Injection System for a Fusion Reactor PDF Author: Ronald Hemsworth
Publisher:
ISBN:
Category : Electronic books
Languages : en
Pages : 0

Book Description
The ion temperature in the plasma in a fusion reactor must be sufficiently high that the fusion reaction (probably between D+ and T+) will need to be high to ensure that the reaction rate is as high as is required. The plasma will be heated by the energetic alpha particle created in the fusion reaction, but it is widely accepted that additional (externally supplied) heating will also be required to ensure a sustained ,Äúburn,Äù and, perhaps, to control the reaction rate. A reactor based on the tokamak confinement system requires a toroidal current to flow in the plasma. Most of that current will be created by the ,Äúbootstrap,Äù effect, but an external method of driving current in the poloidal centre of the plasma is needed as the bootstrap current will be low, or zero in that region. Neutral beam injection is an efficient heating mechanism and it has the current drive efficiency required in a reactor. In this chapter the R&D required for an NBI system for a reactor, is considered against the background of the ITER NBI system design as the ITER beam energy and operating environment are reactor relevant. In addition the elements requiring most development are identified.

Value Engineering, an Approach to Optimizing Neutral Beam Heating Cost and Performance

Value Engineering, an Approach to Optimizing Neutral Beam Heating Cost and Performance PDF Author: C. Hume McClure
Publisher:
ISBN:
Category : Controlled fusion
Languages : en
Pages : 44

Book Description


Fusion power by magnetic confinement, program plan

Fusion power by magnetic confinement, program plan PDF Author: United States. Energy Research and Development Administration. Division of Magnetic Fusion Energy
Publisher:
ISBN:
Category :
Languages : en
Pages : 262

Book Description


Fusion Energy Update

Fusion Energy Update PDF Author:
Publisher:
ISBN:
Category : Controlled fusion
Languages : en
Pages : 364

Book Description


1980 Department of Energy Authorization

1980 Department of Energy Authorization PDF Author: United States. Congress. House. Committee on Science and Technology
Publisher:
ISBN:
Category :
Languages : en
Pages : 1492

Book Description


The Recent Development of the EAST Neutral Beam Injector*Supported by the National Magnetic Confinement Fusion Science Program of China Under Grant No 2013GB101001

The Recent Development of the EAST Neutral Beam Injector*Supported by the National Magnetic Confinement Fusion Science Program of China Under Grant No 2013GB101001 PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description
Abstract : Neutral beam injection has been recognized as one of the most effective means for plasma heating. According to the research plan of the EAST physics experiment, two sets of neutral beam injectors (4–8 MW, 10–100 s) were built and operated in 2014. We present the development of the EAST neutral beam injector (NBI) and the latest experiment results obtained on the test-stand about operation of ion source, beam extraction, and measurement of key parameters. Those results show that all targets reach or almost reach the design targets. All these lay a solid foundation for the achievement of plasma heating and current drive for EAST in 2014.

Fusion Plasma Analysis

Fusion Plasma Analysis PDF Author: Weston M. Stacey
Publisher: John Wiley & Sons
ISBN:
Category : Science
Languages : en
Pages : 408

Book Description
Deals with the physics of magnetically-confined fusion plasmas. Plasma physics is treated as an element in the development of fusion power, with important technological constraints and interactions being included in the analysis. Development of the material starts from the first principles and is carried through to an engineering physics formulation that can be applied to the analysis of fusion reactor plasmas.

Plasma Physics for Nuclear Fusion

Plasma Physics for Nuclear Fusion PDF Author: Kenrō Miyamoto
Publisher: MIT Press (MA)
ISBN:
Category : Science
Languages : en
Pages : 664

Book Description
The original English-language edition of this work appeared in 1979. Since then researchers around the world have made slow but steady progress toward the realization of sustained, controlled nuclear fusion. This new edition has been updated to review the important contributions of the past decade. The final chapter, "Confinement of High-Temperature Plasmas, " has been rewritten entirely to include the recent results of confinement in several types of devices and advances the under standing of wave heating. Miyamoto's approach is unique in encompassing Western, Soviet, and Japanese research in the fusion field. The book's 16 chapters are grouped into four major subject areas. Chapters in the first part develop the fundamentals of plasma physics and present the conditions of nuclear fusion reactions; those in the next two parts provide a magnetohydrodynamic description of plasmas and explain wave phenomena and instabilities by means of a kinetic model. Concluding chapters take up the problems of heating, diagnostics, and confinement. Specific topics include the Lawson condition; Boltzmann and Vlasov equations; plasma equilibrium; magnetohydrodynamic instabilities; waves in cold and hot plasmas; microinstabilities; fast neutral beam injection and wave heating; and diagnostics using microwaves, lasers, and energy analyzers. Plasma confinement in tokamaks and stellarators, multipole fields, mirrors, and cusps, as well as inertial confinement, are reviewed. Kenro Miyamoto, is Professor of Physics at the University of Tokyo.

Fusion Power by Magnetic Confinement

Fusion Power by Magnetic Confinement PDF Author: United States. Energy Research and Development Administration. Division of Magnetic Fusion Energy
Publisher:
ISBN:
Category : Controlled fusion
Languages : en
Pages : 52

Book Description