Neutral Beam Heating and Current Drive Systems PDF Download

Author: D. Stork
Publisher:
ISBN:
Category : Controlled fusion
Languages : en
Pages : 42

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Category :
Languages : en
Pages : 6

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A conceptual design has been developed for a reference current drive and heating system for a HARD (High Aspect Ratio Design) option for ITER. Twelve neutral beam modules, each rated at 1.3MeV and 9.2MW, perform plasma heating and current drive. An electron cyclotron system is used for initiating the plasma and for disruption control. An alternate system has been defined which is comprised of a lower hybrid and ion cyclotron system for heating and current drive, augmented by the same electron cyclotron system proposed for the reference system. 7 refs., 8 figs., 1 tab.

Author: C. Hume McClure
Publisher:
ISBN:
Category : Controlled fusion
Languages : en
Pages : 40

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Category :
Languages : en
Pages :

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High energy neutral beams provide a promising method of heating and driving current in steady-state tokamak fusion reactors. As an example, we have made a conceptual design of a neutral beam system for current drive on the International Thermonuclear Experimental Reactor (ITER). The system, based on electrostatic acceleration of D/sup /minus// ions, can deliver up to 100 MW of 1.6 MeV D° neutrals through three ports. Radiation protection is provided by locating sensitive beamline components 35 to 50 m from the reactor. In an application to a 3300 MW power reactor, a system delivering 120 MW of 2-2.4 MeV deuterium beams assisted by 21 MW of lower hybrid wave power drives 25 MA and provides an adequate plasma power gain (Q = 24) for a commercial fusion power plant. 8 refs., 1 fig., 2 tabs.

Author: Ronald Hemsworth
Publisher:
ISBN:
Category : Electronic books
Languages : en
Pages : 0

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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.

Author:
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Category :
Languages : en
Pages : 3

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The neutral beams are used to heat the plasma in the DIII-D tokamak, a fusion energy research experiment operated by General Atomics (GA) and funded by the Department of Energy (DOE). The experiment is dedicated to demonstrating noninductive current drive of high beta high temperature divertor plasma with good confinement. The neutral beam heating system for the DIII-D tokamak uses four MODCOMP Classic computers for data acquisition and control of the four beamlines. The Neutral Beam Software Upgrade project was launched in early 1990. The major goals were to upgrade the MAX IV operating system to the latest revision (K.1), use standard MODCOMP software (as much as possible), and to develop a very ''user friendly, '' versatile system. Accomplishing these goals required new software to be developed and modifications to existing applications software to make it compatible with the latest operating system. The custom operating system modules to handle the message service and interrupt handling were replaced by the standard MODCOMP Inter Task Communication (ITC) and interrupt routines that are part of the MAX IV operating system. The message service provides the mechanism for doing shot task sequencing (task scheduling). The interrupt routines are used to connect external interrupts to the system. The new software developed consists of a task dispatcher, screen manager, and interrupt tasks. The existing applications software had to be modified to be compatible with the MODCOMP ITC services and consists of the Modcomp Infinity Data Base Manager, a multi-user system, and menu-driven operating system interface routines using the Infinity Data Base Manager.

Author:
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Category :
Languages : en
Pages : 30

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This report contains a description of the neutral beam heating and current drive module Beams, that was developed at Georgia Tech for the SUPERCODE, the new systems and operations code for the ITER EDA. The NB module calculates profiles of the neutral beam deposition, fast ion pressure, beam heating power, and neutral beam driven current density. It also computes global parameters such as current drive efficiencies, beam shinethrough, fast beam ion beta, and the fusion power and neutron production due to beam-plasma interactions. The most important consideration during the development of this module was to make it compute normally fast without compromising physical accuracy. We believe that through careful selection of physical models and optimized coding, these conflicting requirements have been largely met. As a result, the SUPERCODE has now the ability to perform self-consistent calculations involving NB heating and current drive. This capability is very important for the study of sub-ignited, hybrid, or steady-state ITER and post-TFIR reactor operating scenarios. It is also the first time that a systems code has had such capabilities, usually found only in 1-1/2D plasma transport codes.

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Category :
Languages : en
Pages :

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Negative-ion-based neutral beam systems can perform multiple functions for fusion reactors, such as heating, current drive in tokamak reactors, and establishing and maintaining potential barriers in tandem mirror reactors. Practical systems operating continuously at the 200 keV, 1 MW level can be built using present-day technology. Ion sources have been demonstrated that produce D− beams with

Author: Weston M. Stacey
Publisher: John Wiley & Sons
ISBN: 9783527629329
Category : Science
Languages : en
Pages : 262

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This second edition of a popular textbook is thoroughly revised with around 25% new and updated content. It provides an introduction to both plasma physics and fusion technology at a level that can be understood by advanced undergraduates and graduate students in the physical sciences and related engineering disciplines. As such, the contents cover various plasma confinement concepts, the support technologies needed to confine the plasma, and the designs of ITER as well as future fusion reactors. With end of chapter problems for use in courses.

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Category :
Languages : en
Pages :

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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.