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in creator/contributor: "Trachsel, C."

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Impurity Control System for the STARFIRE Commercial Fusion Reactor

The STARFIRE impurity control system is based on a low-Z coated limiter/vacuum system which collects and pumps about 30% of the particle flux at the edge of the plasma. This pumping efficiency, when combined with about a 1.5-T additional margin in the toroidal magnetic field, is sufficient to maintain the steady-state helium concentration to approx. 10% while permitting a tritium burnup fraction at approx. 10%. In order to keep the heat load on the limiter to reasonable limits, about 80% of the… more

Date: January 1, 1979

Creator: Brooks, J. N.; Baker, C. C.; Stevens, H. C. & Trachsel, C. A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Coaxial Test Fixture and Pulsed Power Supply for Contact-Material Screening Tests

A coaxial test fixture and a pulsed power supply have been built to conduct high-current screening tests on candidate materials for contacts to be used in first wall connectors on fusion devices, particularly tokamaks. The fixture was operated with half-sine-wave pulses of less than or equal to 300 kA; it is designed for carrying currents of up to 600 kA for approximately 300 ms at a repetition rate of 1 pulse every 5 minutes. The fixture is built as a vacuum vessel and capable of testing speci… more

Date: January 1, 1983

Creator: Praeg, W. F.; McGhee, D. G.; Trachsel, C. A. & Zahn, H. S.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Starfire: Initial Conceptual Design of a Commercial Tokamak Power Plant

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.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

STARFIRE: A Conceptual Design of a Commercial Tokamak Power Plant. Paper IAEA-CN-39/E-1

STARFIRE is a conceptual design for a commercial tokamak power plant based on the deuterium/tritium/lithium fuel cycle. The emphasis of the study is on the simplicity of the engineering design, maintainability, lower electricity cost, and improved safety and environmental features. The reactor has a 7-m major radius and produces 1200 MW of electric power. STARFIRE operates in a steady-state mode with the plasma current driven by a lower hybrid rf system. The plasma purity control and exhaust sy… more

Date: January 1, 1980

Creator: Abdou, M. A.; Baker, C. C.; DeFreece, D.; Trachsel, C.; Graumann, D. & Kokoszenski, J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

First wall and blanket design for the STARFIRE commercial tokamak power reactor

The first wall and blanket design concepts being evaluated for the STARFIRE commercial tokamak reactor study are presented. The two concepts represent different approaches to the mechanical design of a tritium breeding blanket using the reference materials options. Each concept has a separate ferritic steel first wall cooled by heavy water (D/sub 2/O), and a ferritic steel blanket with solid lithium oxide breeder cooled by helium. A separate helium purge system is used in both concepts to extra… more

Date: January 1, 1979

Creator: Morgan, G. D.; Trachsel, C. A.; Cramer, B. A.; Bowers, D. A. & Smith, D. L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Overview of the STARFIRE Reference Commercial Tokamak Fusion Power Reactor Design

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: Article

Partner: UNT Libraries Government Documents Department

open access

Starfire: a commercial tokamak reactor. [Overview of major parameters]

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.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Lower-Hybrid Heating and Current Drive System for the STARFIRE Tokamak

STARFIRE is a commercial tokamak reactor which is designed to operate in a purely steady-state mode with the electron current maintained by momentum transfer from lower-hybrid waves launched from end-fire waveguide arrays. The rf system has been designed for consistency with plasma physics constraints, and its components have been selected with the goal of minimizing the electric power required to maintain the plasma current. The system has been analyzed in the thermal, electrical, magnetic, an… more

Date: January 1, 1980

Creator: Ehst, D. A.; Boley, C. D.; Evans, K., Jr.; Fuja, R.; Jung, J.; Trachsel, C. A. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Demonstration Tokamak Power Plant

A conceptual design for a tokamak demonstration power plant (DEMO) was developed. A large part of the study focused on examining the key issues and identifying the R and D needs for: (1) current drive for steady-state operation, (2) impurity control and exhaust, (3) tritium breeding blanket, and (4) reactor configuration and maintenance. Impurity control and exhaust will not be covered in this paper but is discussed in another paper in these proceedings, entitled Key Issues of FED/INTOR Impurit… more

Date: January 1, 1983

Creator: Abdou, M.; Baker, C.; Brooks, J.; Ehst, D.; Mattas, R.; Smith, D. L. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Engineering testing requirements in FED/INTOR

The FED/INTOR critical issues activity has addressed three key testing requirements that have the largest impact on the design, operation and cost of FED/INTOR. These are: (1) the total testing time (fluence) during the device lifetime, (2) the minimum number of back-to-back cycles, and (3) the neutron wall load (power density in the first wall/blanket). The testing program activities were structured into three tasks in order to define the benefits, and in some cases, costs and risks of these t… more

Date: October 1, 1982

Creator: Abdou, M. A.; Nygren, R. E.; Morgan, G. D.; Trachsel, C. A.; Wire, G.; Oppermann, E. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Conceptual Design of the INTOR First-Wall System

The design concept and performance characteristics of the first-wall design for the phase-1 INTOR (International Tokamak Reactor) study is described. The reference design consists of a water-cooled stainless steel panel. The major uncertainty regarding the performance of the bare stainless steel wall relates to the response of a thin-melt layer predicted to form on limited regions during a plasma disruption. A more-complex backup design, which incorporates radiatively cooled graphite tiles on t… more

Date: October 1, 1981

Creator: Smith, D. L.; Majumdar, S.; Mattas, R. F.; Turner, L.; Jung, J.; Abdou, M. A. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department