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in publisher: "General Atomics, San Diego, CA United States"  
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The TITAN reversed-field-pinch fusion reactor study

Description: This report discusses research on the titan-1 fusion power core. The major topics covered are: titan-1 fusion-power-core engineering; titan-1 divertor engineering; titan-1 tritium systems; titan-1 safety design and radioactive-waste disposal; and titan-1 maintenance procedures.
Date: January 1, 1990
Partner: UNT Libraries Government Documents Department
open access

The TITAN reversed-field-pinch fusion reactor study

Description: This report discusses the following topics: overview of titan-2 design; titan-2 fusion-power-core engineering; titan-2 divertor engineering; titan-2 tritium systems; titan-2 safety design and radioactive-waste disposal; and titan-2 maintenance procedures.
Date: January 1, 1990
Partner: UNT Libraries Government Documents Department
open access

The TITAN reversed-field-pinch fusion reactor study

Description: This paper on titan plasma engineering contains papers on the following topics: reversed-field pinch as a fusion reactor; parametric systems studies; magnetics; burning-plasma simulations; plasma transient operations; current drive; and physics issues for compact RFP reactors.
Date: January 1, 1990
Partner: UNT Libraries Government Documents Department
open access

The Role of Shaping in Achieving High Performance in DIII-D

Description: Experiments to study the effect of plasma shape on performance show that the high performance levels characteristic of VH-mode plasmas are only obtained for high triangularity ({delta}). A characteristic difference in central heating efficiency is observed when high and low {delta} plasmas are compared. The authors find this difference to correlate well with the attainment of Mercier stability. The core plasma for the high {delta} cases achieves Mercier stability when q{sub 0} rises above a cri… more
Date: October 1, 1994
Creator: Lazarus, E. A.; Hyatt, A. W. & Osborne, T. H.
Partner: UNT Libraries Government Documents Department
open access

First-wall heat-flux measurements during ELMing H-mode plasma

Description: In this report we present measurements of the diverter heat flux in DIII-D for ELMing H-mode and radiative diverter conditions. In previous work we have examined heat flux profiles in lower single-null diverted plasmas and measured the scaling of the peak heat flux with plasma current and beam power. One problem with those results was our lack of good power accounting. This situation has been improved to better than 80--90% accountability with the installation of new bolometer arrays, and the o… more
Date: January 28, 1994
Creator: Lasnier, C. J.; Allen, S. L.; Hill, D. N.; Leonard, A. W. & Petrie, T. W.
Partner: UNT Libraries Government Documents Department
open access

Toward a design for the ITER plasma shape and stability control system

Description: A design strategy for an integrated shaping and stability control algorithm for ITER is described. This strategy exploits the natural multivariable nature of the system so that all poloidal field coils are used to simultaneously control all regulated plasma shape and position parameters. A nonrigid, flux-conserving linearized plasma response model is derived using a variational procedure analogous to the ideal MHD Extended Energy Principle. Initial results are presented for the non-rigid plasma… more
Date: July 1, 1994
Creator: Humphreys, D. A.; Leuer, J. A.; Kellman, A. G.; Haney, S. W.; Bulmer, R. H.; Pearlstein, L. D. et al.
Partner: UNT Libraries Government Documents Department
open access

Converter performance TFE Verification Program. Final test report

Description: This report details TFE Verification Program, the objective, of which is to demonstrate the technology readiness of a TFE suitable for use as the basic element in a thermionic reactor with electric power output in the 0.5 to 5.0 MW(e) range, and a full-power life of 7 years. The TFE Verification Program built directly on the technology and data base developed in the 1960s and early 1970s in an AEC/NASA program, and in the SP-100 program conducted in 1983, 1984 and 1985. In the SP-100 program, t… more
Date: March 1, 1994
Partner: UNT Libraries Government Documents Department
open access

Liquid metal cooled divertor for ARIES

Description: A liquid metal, Ga-cooled divertor design was completed for the double null ARIES-II divertor design. The design analysis indicated a surface heat flux removal capability of up to 15 MW/m{sup 2}, and its relative easy maintenance. Design issues of configuration, thermal hydraulics, thermal stresses, liquid metal loop and safety effects were evaluated. For coolant flow control, it was found that it is necessary to use some part of the blanket cooling ducts for the draining of liquid metal from t… more
Date: January 1, 1995
Creator: Muraviev, E.
Partner: UNT Libraries Government Documents Department
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