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Aspects of theta pinch power plant development

Description: An engineering conceptual design study of a fusion power plant based on the theta-pinch concept has recently been completed. This study presented a compatible design for ten major systems. Although the design appears viable, some systems need considerable development to show that they are completely feasible and credible. Interactions between systems prevent implementation of some obvious solutions to the individual problems. Design alternatives, development, and demonstrations, as well as fundamental research required on these systems to make a feasible theta-pinch power plant are discussed. (auth)
Date: January 1, 1973
Creator: Coultas, T.A. & Krakowski, R.A.
Partner: UNT Libraries Government Documents Department

Minimum activity blankets for commercial and experimental power reactors

Description: From 5th symposium on engineering problems of fusion research; Princeton, New Jersey, USA (6 Nov 1973). A new kind of tritium breeding blanket for fusion reactors is investigated. All components in the blanket are solid, including the lithium containing material, which eliminates problems of corrosion and materials compatibility. This permits the use of structural materials with very low neutron activation. A promising structural material is SAP, a pure aluminum strengthened by an Al/sub 2/O/sub 3/ dispersoid. Three types of blanket module designs are investigated in which the helium coolant exit temperature is substantially greater than the maximum operating temperature of SAP ( approximates 400 deg C). Exit temperatures range from 500 deg C to above 1000 deg C, while breeding ratios range from 0.9 to 1.5, depending on design. Structural stress is approximates 2000 psi, which is approximates -20% of failure stress. The bred tritium diffuses from the lithium alloy or compound (e.g., LiAl), which has a much higher tritium pressure than pure lithium, into the helium coolant stream from which it is recovered. Depending on processing rates, temperature, LiAl inventory, and the amount of scavenging by added H/sub 2/ , the tritium blanket inventory ranges from approximates 10/sup 5/ to 10/sup 6/ curies. Short lived activities, principall y /sup 24/Na (15 hour half life), decay to a negligible amount in a few days, leaving a long lived inventory of approximates 10/sup 4/ curies/100O MW(e) (principally /sup 26/Al (7.3 x 10/sup 5/ year half life)!. This material appears to present no problems of permanent waste disposal. Because of the very low inventory of long lived activities, blanket repair or replacement seems relatively simple. (auth)
Date: January 1, 1973
Creator: Powell, J.R.; Miles, F.T.; Aronson, A.; Winsche, W.E. & Bezler, P.
Partner: UNT Libraries Government Documents Department

Controlled thermonuclear research. Survey of applications of fusion power and technology to the chemical and materials processing industries. Bimonthly report No. 4, January--February 1974

Description: Current efforts are directed toward processes and markets which can utilize the energy forms from fusion reactors. A list is given that outlines various products and processes which are energy-intensive. The thermal reactions may utilize energy directly or indirectly. Directly indicates that the process gas is introduced into the blanket to obtain the required energy. Indirectly indicates that the process gas is heated by heat exchange with blanket coolant gas. The heat exchange may be accomplished by regenerative pebble-bed heaters, in which alternate beds are heated by reactor coolant gas (e.g., helium). By appropriate valving, the hot bed then gives up its stored heat to the process gas while the other bed is heated. (MOW)
Date: January 1, 1974
Creator: Steinberg, M.; Powell, J. & Beller, M.
Partner: UNT Libraries Government Documents Department

Analysis of the 50 kG toroidal field coil for high field ORMAK

Description: From 5th symposium on engineering problems of fusion research; Princeton, New Jersey, USA (6 Nov 1973). Due to space limitations on the windings, the power efficiencies of toroidal field coils for tokamak experiments are in general rather poor. Very substantial improvement can be achieved by using asymmetrical magnet coil designs. The results of mathematical analysis and electric-current-flow plotting for various types of asymmetrical coil designs are discussed, and numerical data of resistance measurements with the High-Field ORMAK prototype coil are given. (auth)
Date: January 1, 1973
Creator: Gauster, W.F. & Walstrom, P.L.
Partner: UNT Libraries Government Documents Department

Fluxes of charged and neutral particles from tokamaks

Description: From surface effects in controlled thermonuclear fusion devices and reactors meeting; Argonne, Illinois, USA (10 Jan 1974). A brief description of a tokamak is given and some related impurity problems are discudsed. The role of neutral particles and their influence on present and future experiments involving larger machines is described. Some experimental and theoretical data are shown. (MOW)
Date: January 1, 1973
Creator: Hogan, J.T. & Clarke, J.F.
Partner: UNT Libraries Government Documents Department