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Approach to decision modeling for an ignition test reactor

Description: A comparison matrix decision model is applied to candidates for a D-T ignition tokamak (TNS), including assessment of semi-quantifiable or judgemental factors as well as quantitative ones. The results show that TNS is mission-sensitive with a choice implied between near-term achievability and reactor technology.
Date: September 30, 1977
Creator: Howland, H.R. & Varljen, T.C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Three novel tokamak plasma regimes in TFTR

Description: Aside from extending ''standard'' ohmic and neutral beam heating studies to advanced plasma parameters, TFTR has encountered a number of special plasma regimes that have the potential to shed new light on the physics of tokamak confinement and the optimal design of future D-T facilities: (1) High-powered, neutral beam heating at low plasma densities can maintain a highly reactive hot-ion population (with quasi-steady-state beam fueling and current drive) in a tokamak configuration of modest bul… more
Date: October 1, 1985
Creator: Furth, H.P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ORNL TNS program: microwave start-up of tokamak plasmas near electron cyclotron and upper hybrid resonances

Description: The scenario of toroidal plasma start-up with microwave initiation and heating near the electron cyclotron frequency is suggested and examined here. We assume microwave irradiation from the high field side and an anomalously large absorption of the extraordinary waves near the upper hybrid resonance. The dominant electron energy losses are assumed to be due to magnetic field curvature and parallel drifts, ionization of neutrals, cooling by ions, and radiation by low Z impurities. It is shown by… more
Date: December 1, 1977
Creator: Peng, Y. K. M. & Borowski, S. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Plasma engineering considerations for an ignition test reactor: The Next Step (TNS) beyond TFTR

Description: Plasma engineering studies were done to establish credible ranges of physics parameters to be integrated into the TNS study program. The following are reviewed: high ..beta.. equilibrium, high density, basic assumptions, zero-dimensional scaling, one-dimensional effects, equilibrium evolution, injection scenario, MHD stability limits, equilibrium fields and flexibility. (MHR)
Date: January 1, 1977
Creator: Peng, Y. K. M.; Callen, J. D.; Marcus, F. B.; McNally, J. R., Jr.; Mense, A. T.; Uckan, N. A. et al.
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Partner: UNT Libraries Government Documents Department
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Engineering design problems of TFTR

Description: Design of the TFTR poses special engineering problems as a result of constraints posed by the physics requirements of the fusion experiments. The ratio of plasma major and minor radii and the associated magnetic field strength required to achieve desired plasma conditions, the required confinement time, the two-component plasma concept, the complications of providing shielding from the 14 MeV neutrons and the necessity to control the inventory of tritium fuel, all constitute problems which, oft… more
Date: January 1, 1977
Creator: Lee, D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Configuration review of TFCX design options

Description: As part of the preconceptual design effort of the Tokamak Fusion Core Experiment (TFCX), several candidate design options have been explored in order to identify a preferred option that will be developed in further detail during the conceptual design phase of the TFCX program. The development of the TFCX concepts has been a collaborative effort between the Princeton Plasma Physics Laboratory (PPPL) and the Fusion Engineering Design Center (FEDC) with broad community input. The design options be… more
Date: January 1, 1984
Creator: Brown, T.G.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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TFTR initial operations

Description: The Tokamak Fusion Test Reactor (TFTR) has operated since December 1982 with ohmically heated plasmas. Routine operation with feedback control of plasma current, position, and density has been obtained for plasmas with I/sub p/ approx. = 800 kA, a = 68 cm, R = 250 cm, and B/sub t/ = 27 kG. A maximum plasma current of 1 MA was achieved with q approx. = 2.5. Energy confinement times of approx. 150 msec were measured for hydrogen and deuterium plasmas with anti n/sub e/ approx. = 2 x 10/sup 13/ cm… more
Date: November 1, 1983
Creator: Young, K.M.; Bell, M.; Blanchard, W.R.; Bretz, N.; Cecchi, J.; Coonrod, J. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Confinement studies in TFTR

Description: The paper describes the present (end of February 1985) status of the plasma confinement studies in the TFTR tokamak with emphasis on those with neutral beam injection (NBI). Recent improvements in the device capabilities have substantially extended operating parameters: B/sub T/ increased to 4.0 T, I/sub p/ to 2.0 MA, injection power (P/sub b/) to 5 MW with H/sup 0/ or D/sup 0/ beams anti n/sub e/ to 5 x 10/sup 19/ m/sup -3/, and Z/sub eff/ reduced to 1.4. With ohmic heating (OH) alone, the pre… more
Date: June 1, 1985
Creator: Murakami, M.; Arunasalam, V.; Bell, J. D.; Bell, M. G.; Bitter, M.; Blanchard, W. R. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Draft program plan for TNS: The Next Step after the Tokamak Fusion Test Reactor. Part II. R and D needs assessment

Description: The information contained in this document represents the brief but intensive efforts of the Oak Ridge TNS Program Team to answer the following questions: (1) Is there an adequate basis of R and D support for the TNS program as a central, ambitious goal for the fusion program. (2) What are the principal gaps in the current and projected R and D program. (3) What must be done to permit operation of TNS in the mid 1980s. The findings of our preliminary study provide these answers to the questions… more
Date: December 1, 1977
Creator: Roberts, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design of a fusion engineering test facility

Description: The fusion Engineering Test Facility (ETF) is being designed to provide for engineering testing capability in a program leading to the demonstration of fusion as a viable energy option. It will combine power-reactor-type components and subsystems into an integrated tokamak system and provide a test bed to test blanket modules in a fusion environment. Because of the uncertainties in impurity control two basic designs are being developed: a design with a bundle divertor (Design 1) and one with a … more
Date: January 1, 1980
Creator: Sager, P.H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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ISX objectives and physics

Description: The ISX-B program has achieved average beta values of 1.8% in a relatively clean plasma with neutral beam injection power greater than 10 times ohmic power input. Total beta has increased smoothly with beam power so far and exceeded theoretical limits with no indication that ballooning or any other instability is significantly increasing the energy loss rate.
Date: January 1, 1979
Creator: Mihalczo, J.T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Plasma engineering innovations for the ORNL TNS reactor

Description: Recent plasma engineering studies have ascertained a viable concept for The Next Step (TNS) reactor based on medium toroidal fields between 4 T and 7 T at the plasma center, plasma ..beta.. values up to 10 percent and averaged densities between 0.6 x 10/sup 14/ cm/sup -3/ and 2.5 x 10/sup 14/ cm/sup -3/. Plasma engineering innovations that can substantially reduce the size, cost, and complexity of the TNS reactor have been explored and are summarized. It is shown that the previously anticipated… more
Date: January 1, 1977
Creator: Peng, Y. K. M.; Houlberg, W. A.; Mense, A. T.; Rome, J. A. & Uckan, N. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Conceptual design summary for modifying Doublet III to a large dee-shaped configuration

Description: The Doublet III tokamak is to be reconfigured by replacing its indented (doublet) vacuum vessel with a larger one of a dee-shaped cross section. This change will permit significantly larger elongated plasmas than is presently possible and will allow higher plasma current (up to 5 MA) and anticipated longer confinement time. Reactor relevant values of stable beta and plasma pressure are predicted. This modification, while resulting in a significant change in capability, utilizes most of the exis… more
Date: May 1, 1983
Creator: Davis, L. G.; Gallix, R.; Luxon, J. L.; Mahdavi, M. A.; Puhn, F. A.; Rock, P. J. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Oak Ridge TNS Program: system description manual

Description: This document provides a systems description of the Reference Design for The Next Step (TNS) evolved at Oak Ridge National Laboratory (ORNL) during FY 1978. The description is presented on the basis of 24 individual device and facility systems. Additional information on these systems, the Reference Design, and the FY 1978 Oak Ridge TNS activities can be found in the associated technical memoranda, ORNL/TM-6720 and ORNL/TM-6722--ORNL/TM-6733.
Date: May 1, 1979
Creator: Reid, R. L.; Becraft, W. R.; Brown, T. G.; Peng, Y. K. M.; Sardella, C.; Shannon, T. E. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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System studies of compact ignition tokamaks

Description: The new Tokamak Systems Code, used to investigate Compact Ignition Tokamaks (CITs), can simultaneously vary many parameters, satisfy many constraints, and minimize or maximize a figure of merit. It is useful in comparing different CIT design configurations over wide regions of parameter space and determining a desired design point for more detailed physics and engineering analysis, as well as for performing sensitivity studies for physics or engineering issues. Operational windows in major radi… more
Date: August 1, 1987
Creator: Galambos, J. D.; Blackfield, D. T.; Peng, Y. K. M.; Reid, R. L.; Strickler, D. J. & Selcow, E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Overview of the STARFIRE Reference Commercial Tokamak Fusion Power Reactor Design

Description: The purpose of the STARFIRE study is to develop a design concept for a commercial tokamak fusion electric power plant based on the deuterium/tritium/lithium fuel cycle. The major features for STARFIRE include a steady-state operating mode based on a continuous rf lower-hybrid current drive and auxiliary heating, solid tritium breeder material, pressurized water cooling, limiter/vacuum system for impurity control and exhaust, high tritium burnup, superconducting EF coils outside the TF supercond… more
Date: January 1, 1980
Creator: Baker, C. C.; Abdou, M. A.; DeFreece, D. A.; Trachsel, C. A.; Graumann, D. & Barry, K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Survey of Modes and Their Effects in ORMAK, ISX-A, and ISX-B

Description: A comparison of some features of the three tokamaks is given. The ORMAK and ISX-A have ceased operation. The ISX-B has completed a checkout phase with studies of circular, ohmically heated plasmas in which it performed much like ISX-A. Shaped and injection heated plasmas are being studied. Diagnostics for mode structures were the usual Mirnov loops for approx.B/sub theta/ and collimated soft x-ray detectors for the internal fluctuations approx.X. The approx.X measurements on ISX-A, and thus far… more
Date: February 14, 1979
Creator: Dunlap, J. L.; Burris, R. D.; Harris, J. H.; Navarro, A. P. & Pare, V. K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Overview of the TIBER II (Tokamak Ignition/Burn Experimental Reactor) design

Description: The TIBER II Tokamak Ignition/Burn Experimental Reactor design is the result of efforts by numerous people and institutions, including many fusion laboratories, universities, and industries. While subsystems will be covered extensively in other reports, this overview will attempt to place the work in perspective. Major features of the design are compact size, low cost, and steady-state operation. These are achieved through plasma shaping and innovative features such as radiation tolerant magnet… more
Date: October 16, 1987
Creator: Henning, C. D. & Logan, B. G.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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STARFIRE: A Commercial Tokamak Reactor

Description: The STARFIRE Project was initiated in May 1979, with the goal of completing the design study by October 1980. The purpose of this paper is to present an overview of the major parameters and design features that have been tentatively selected for STARFIRE.
Date: January 1, 1979
Creator: Baker, C. C.; Abdou, M. A.; DeFreece, D. A.; Trachael, A. A.; Graumann, D. & Kokoszenski, J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Poloidal field coil and current distribution study for the Toroidal Fusion Core Experiment (TFCX). Draft

Description: The Toroidal Fusion Core Experiment (TFCX) is a proposed concept for an ignited, long-pulse, current-driven, ''next step'' tokamak device. The poloidal field (PF) coil configuration has major impact on the size and cost of a tokamak machine. The purpose of this trade study was to determine the achievable values of plasma triangularity and elongation consistent with mechanical configuration and plasma performance requirements. The study was made with three sets of PF coil configurations: (1) PF … more
Date: January 1, 1983
Creator: Srivastava, V. C.; Miller, J. & Strickler, D. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Design review of the INTOR mechanical configuration

Description: The INTOR conceptual design has been carried out by design teams working in the home countries with periodic workshop sessions in Vienna to review the ongoing work and to make decisions on the evolving design. The decisions taken at each workshop session were then incorporated into each national design activity, so that the four national design contributions would progressively converge toward a single design with increasingly greater detail. This paper defines the final INTOR configuration tha… more
Date: January 1, 1981
Creator: Brown, T.G.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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