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Engineering aspects of the INTOR design

Description: The INTOR engineering design has been strongly influenced by considerations for assembly and maintenance. A maintenance philosophy was established at the outset of the conceptual design to insure that the tokamak configuration would be developed to accommodate maintenance requirements. The main features of the INTOR design are summarized in this paper with primary emphasis on the impact of maintenance considerations.
Date: January 1, 1981
Creator: Shannon, T.E.
Partner: UNT Libraries Government Documents Department
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STARFIRE-II studies. Summary. [Reactor parameters]

Description: The US Department of Energy's Office of Fusion Energy has initiated several studies during FY-1985 called Tokamak Power System Studies (TPSS). The TPSS is being carried out by several laboratories, universities and industry with the general objective of developing innovative physics and technology concepts to improve the commercial attractiveness of tokamak power reactors. The effort of Argonne National Laboratory, entitled STARFIRE-II, is an effort to update and improve STARFIRE, which was the… more
Date: January 1, 1985
Creator: Baker, C. C.; Brooks, J. N.; Ehst, D. A.; Smith, D. L. & Sze, D. K.
Partner: UNT Libraries Government Documents Department
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Engineering features of the INTOR conceptual design

Description: The INTOR engineering design has been strongly influenced by considerations for assembly and maintenance. A maintenance philosophy was established at the outset of the conceptual design to insure that the tokamak configuration would be developed to accommodate maintenance requirements. The main features of the INTOR design are summarized in this paper with primary emphasis on the impact of maintenance considerations.
Date: January 1, 1981
Creator: Shannon, T.E.
Partner: UNT Libraries Government Documents Department
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Systems code assessment of innovations, major design drivers, and minimum sizes of INTOR (International Tokamak Reactor) and ETR-like designs

Description: System studies of next-generation superconducting tokamaks are presented here. These studies include examining design changes suggested for the International Tokamak Reactor (INTOR) as a means of reducing the size and simplifying the device and assessing the impact of a series of more aggressive design assumptions suggested in recent Engineering Test Reactor (ETR) studies. Also, a set of candidate design points offering small machines (major radius = 4 m) with a relatively conservative mix of d… more
Date: October 1, 1987
Creator: Galambos, J. D.; Peng, Y. K. M.; Strickler, D. J. & Reid, R. L.
Partner: UNT Libraries Government Documents Department
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US tokamak research

Description: Current experiments on ISX-B, Alcator C, PDX, and PLT respectively address the four areas of principal concern in the development of a tokamak reactor: optimization of MHD-stability at high ..beta..-values; achievement of high n tau/sub E/; preservation of plasma purity; and development of effective techniques for achieving high plasma temperatures. The neutral-beam-heated ISX-B is the first tokamak device to have reached a ..beta..-level of approximately 3%, thus exploring - or even challengin… more
Date: October 1, 1979
Creator: Furth, H.P.
Partner: UNT Libraries Government Documents Department
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A short introduction to the status and motivation for reversed field pinch and compact toroid research

Description: Potential commercial fusion power systems must be acceptable from a safety and environmental standpoint. They must also promise to be competitive with other sources of energy (i.e., fossil, fission, etc.) when considered from the standpoint of the cost of electricity (COE) and the unit direst cost (UDC) in ($/kWe). These costs are affected by a host of factors including recirculating power, plant availability, construction time, capital cost etc., and are, thus, influenced by technological comp… more
Date: September 1, 1987
Creator: Dreicer, H.
Partner: UNT Libraries Government Documents Department
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The configuration development of the compact ignition tokamak (CIT) device

Description: The paper consists of viewgraphs discussing different component design options for the Compact Ignition Tokamak (CIT). The author concludes that a CIT device configuration has been established which meets physics requirements, performance margins and engineering component design needs. The baseline (R/sub 0/ = 1.75 meters) machine appears reasonable based on the analysis performed to date. (LSP)
Date: January 1, 1987
Creator: Brown, T.G.
Partner: UNT Libraries Government Documents Department
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Review of the ISX-B experimental program

Description: The ISX-B tokamak is a modestly sized device that is designed to explore questions closely related to the design of future tokamak devices, such as the Engineering Test Facility (ETF). The major program emphasis is on high-..beta.. plasma operation using neutral beams to heat plasmas with noncircular cross sections. In addition, substantial efforts are under way or planned in the areas of plasma-wall interactions, coated limiter studies, electron-cyclotron heating, ripple injection, impurity fl… more
Date: January 1, 1979
Creator: Saltmarsh, M.J.
Partner: UNT Libraries Government Documents Department
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Oak Ridge TNS Program: technical needs assessment

Description: This document highlights the technical requirements of the key subsystems of the Reference Design for The Next Step (TNS) and presents a preliminary assessment of the adequacy of the technical capabilities available to satisfy these requirements. Additional information on the Reference Design and the FY 1978 TNS Program activities can be found in the associated technical memoranda, ORNL/TM-6720, ORNL/TM-6721, and ORNL/TM-6723 - ORNL/TM-6733.
Date: August 1, 1979
Creator: Becraft, W.R.; Brown, T.G. & Reid, R.L.
Partner: UNT Libraries Government Documents Department
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Starfire: a commercial tokamak reactor. [Overview of major parameters]

Description: The basic objective of the STARFIRE Project is to develop a design concept for a commercial tokamak fusion electric power plant based on the deuterium/tritium/lithium fuel cycle. The key technical objective is to develop the best embodiment of the tokamak as a power reactor consistent with credible engineering solutions to design problems. Another key goal of the project is to give careful attention to the safety and environmental features of a commercial fusion reactor. The STARFIRE Project wa… more
Date: January 1, 1979
Creator: Baker, C. C.; Abdou, M. A.; Trachsel, C. A.; Graumann, D. & Kokoszenski, J.
Partner: UNT Libraries Government Documents Department
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Princeton Plasma Physics Laboratory annual report, October 1, 1982-September 30, 1983

Description: The Tokamak Fusion Test Reactor (TFTR) achieved first plasma at 3:05 a.m. on December 24, 1982. During the course of the year, the plasma current was raised to a maximum of 1 MA, and extensive confinement studies were carried out with ohmic-heated plasmas. The most important finding was that tokamak energy confinement time increases as the cube of the plasma size. The Princeton Large Torus (PLT) carried out a number of high-powered plasma-heating experiments in the ion cyclotron frequency range… more
Date: January 1, 1983
Creator: Phillips, C.A. (ed.)
Partner: UNT Libraries Government Documents Department
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Oak Ridge TNS Program: summary of FY 1978 activities

Description: The Next Step (TNS) represents the stage of fusion energy development in which the major emphasis is on engineering testing and demonstration. In this document, the activities of the Oak Ridge TNS Program for FY 1978 are described and summarized. The Reference Design that has evolved from these activities is described, its operating characteristics are examined, and project planning issues are considered. Major conclusions from the FY 1978 effort are stated.
Date: July 1, 1979
Creator: Steiner, D.; Becraft, W.R. & Brown, T.G.
Partner: UNT Libraries Government Documents Department
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Mechanical engineering aspects of TFTR

Description: This paper briefly presents the principles which characterize a tokamak and discusses the mechanical aspects of TFTR, particularly the toroidal field coils and the vacuum chamber, in the context of being key components common to all tokamaks. The mechanical loads on these items as well as other design requirements are considered and the solutions to these requirements as executed in TFTR are presented. Future technological developments beyond the scope of TFTR, which are necessary to bring the … more
Date: April 1, 1983
Creator: Citrolo, J.C.
Partner: UNT Libraries Government Documents Department
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Comparative analysis of INTOR-like designs: Status and preliminary results

Description: This document provides an interim status report on the INTOR tasks related to the critical analysis of INTOR-like designs. At the INTOR Workshop in December 1986, and updated at the INTOR related Specialists' Meeting in March 1987, a series of comparative analysis studies was established. Initial results were targeted for completion for the July INTOR meeting and final results completed for the November INTOR meeting. The goal of the analytic comparisons is to evaluate and determine the specifi… more
Date: July 1, 1987
Creator: Flanagan, C. A.; Galambos, J. D.; Peng, P. K. M.; Reid, R. L. & Strickler, D. J.
Partner: UNT Libraries Government Documents Department
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Mission statement for the Engineering Test Facility

Description: This Mission Statement defines the ETF activity during its operating life. The results of those operations must provide the data, knowledge, experience, and confidence to continue to the next steps beyond ETF in making fusion power a viable energy option. The results from the ETF mission (operations are assumed to start early in the 1990's) are to bridge the gap between the base of magnetic fusion knowledge at the start of operations and that reqired to design the EPR/DEMO devices.
Date: October 1, 1979
Partner: UNT Libraries Government Documents Department
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Starfire: Initial Conceptual Design of a Commercial Tokamak Power Plant

Description: The purpose of the study is to provide a mechanism for the US Department of Energy to further assess the commercial potential of tokamak magnetic confinement for power reactors. The initial reference parameters for a helium cooled option are summarized. This study is placing particular emphasis on utility requirements, safety and maintenance considerations.
Date: January 1, 1979
Creator: Baker, C. C.; Abdou, M. A.; DeFreece, D.; Trachsel, C.; Graumann, D. & Kokszenski, J.
Partner: UNT Libraries Government Documents Department
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Results of Systems Studies for the STARFIRE Commercial Tokamak

Description: Extensive system and tradeoff studies were performed to support the selection process for the major parameters and design features of the STARFIRE commercial reactor. With a thermal power of 3800 MW, a neutron wall load of 3.5 MW/m/sup 2/ results in a relatively small-size reactor without imposing excessive requirements on the first-wall cooling capability, maximum toroidal-magnetic field, and frequency of structural material requirements. This moderately high-wall load requires that the first-… more
Date: January 1, 1979
Creator: Abdou, M. A.; Ehst, D. A. & Waganer, L. M.
Partner: UNT Libraries Government Documents Department
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Princeton Plasma Physics Laboratory annual report, October 1, 1983-September 30, 1984

Description: Progress made during this reporting period is reported for each of the following areas: (1) principal parameters achieved in experimental devices, (2) TFTR, (3) PLT, (4) PBX, (5) S-1 Spheromak, (6) advanced concepts Torus-1, (7) x-ray laser studies, (8) theory, (9) tokamak modeling, (10) reactor studies, (11) spin-polarized fusion program, (12) tokamak fusion core experiment, and (13) engineering. (MOW)
Date: January 1, 1984
Creator: Phillips, C.A. (ed.)
Partner: UNT Libraries Government Documents Department
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Recent contributions to fusion reactor design and technology development

Description: The report contains a collection of 16 recent fusion technology papers on the STARFIRE Project, the study of alternate fusion fuel cycles, a maintainability study, magnet safety, neutral beam power supplies and pulsed superconducting magnets and energy transfer. This collection of papers contains contributions for Argonne National Laboratory, McDonnell Douglas Astronautics Company, General Atomic Company, The Ralph M. Parsons Company, the University of Illinois, and the University of Wisconsin.… more
Date: November 1, 1979
Partner: UNT Libraries Government Documents Department
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Princeton Plasma Physics Laboratory annual report, October 1, 1984-September 30, 1985

Description: Summaries of research progress during this period are given for the following areas: (1) TFTR, (2) PLT, (3) PBX, (4) S-1 Spheromak, (5) Advanced Concepts Torus-1, (6) x-ray laser studies, (7) theory, (8) tokamak modeling, (9) spin-polarization, and (10) ignition studies. (MOW)
Date: January 1, 1985
Creator: Phillips, C.A. (ed.)
Partner: UNT Libraries Government Documents Department
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Steady-state tokamak reactor with non-divertor impurity control: STARFIRE

Description: STARFIRE is a conceptual design study of a commercial tokamak fusion electric power plant. Particular emphasis has been placed on simplifying the reactor concept by developing design concepts to produce a steady-state tokamak with non-divertor impurity control and helium ash removal. The concepts of plasma current drive using lower hybrid rf waves and a limiter/vacuum system for reactor applications are described.
Date: January 1, 1980
Creator: Baker, C. C.
Partner: UNT Libraries Government Documents Department
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Oak Ridge TNS Program: a status report

Description: The Oak Ridge TNS activities have been directed at characterizing the design space between TFTR and EPR with a fundamental emphasis on higher beta plasma systems than previously projected, i.e., anti ..beta.. approximately 5 to 10% as compared to 1 to 3%. Based on the results of the FY 1977 System Studies, our activities this year are directed toward preconceptual design with particular emphasis placed on reducing the technological requirements through innovations in plasma engineering. Example… more
Date: January 1, 1978
Creator: Roberts, M
Partner: UNT Libraries Government Documents Department
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