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Transactions of the American Nuclear Society | 1977

Liquid-wall boiler and moderator (BAM) for heavy ion-pellet fusion reactors

J.R. Powell; O. Lazareth; J.A. Fillo

Thick liquid wall blankets appear to be of great promise for heavy ion pellet fusion reactors. They avoid the severe problems of intense radiation and blast damage that would be encountered with solid blanket structures. The liquid wall material can be chosen so that its vapor pressure at the working temperature of the power cycle is well below the value at which it might interfere with the propagation of the heavy ion beam. The liquid wall can be arranged so that it does not contact any surrounding solid structure when the pellet explosion occurs, including the ends. The ends can be magnetically closed just before the pellet explosion, or a time phased flow can be used, which will leave a clear central zone into which the pellet is injected. Parametric analysis comparing three candidate liquid wall materials were carried out. The three materials were lithium, flibe, and lead (with a low concentration of disolved lithium). Lead appeared to be the best choice for the liquid wall, although any of the three should allow a practical reactor system. The parametric analyses examined the effects of pellet yield (0 to 10 GJ), pellet mass (3 g to 3 kg), liquid wall thickness (10 cm to 80 cm), vapor condensation time (0 to 10 milliseconds), degree of neutron moderation in the pellet (none to 100%), liquid wall chamber size (radius of 1.5 meters to 4 meters), Pb/Li/sup 6/ ratio (100 to 5,000), and thickness of graphite moderating zone behind the liquid wall.


Transactions of the American Nuclear Society | 1975

Minimum activity aluminum reference design

O.W. Lazareth; J.R. Powell; R. Benenati; J.A. Fillo; S. Majeski; T.V. Sheehan


Transactions of the American Nuclear Society | 1981

Results of parametric neutronic studies for high-temperature blankets with breeding

H. Makowitz; O. Lazareth; J.R. Powell; J.A. Fillo


Transactions of the American Nuclear Society | 1981

Fusion plasma control using TRAIL - a nondamageable limiter

J.A. Fillo; J.R. Powell; J.L. Usher; W.S. Yu


Transactions of the American Nuclear Society | 1980

HYFIRE blanket design

F.L. Horn; T.S. Botts; J.A. Fillo; O. Lazareth; H. Makowitz; J.R. Powell


Transactions of the American Nuclear Society | 1978

Thermal-hydraulic study of fusion-Synfuel blankets

F.L. Horn; O. Lazareth; J.A. Fillo; J.R. Powell


Transactions of the American Nuclear Society | 1978

NOEL: a no-external-leak blanket for fusion power reactors

J.R. Powell; H. Makowitz; W.S. Yu; J.A. Fillo


Transactions of the American Nuclear Society | 1977

Miniumum-activity aluminum blanket design for TFTR upgrade

J.A. Fillo; J.R. Powell; R. Benenati; H. Makowitz


Transactions of the American Nuclear Society | 1977

Catalyzed D-D and D-/sup 3/He fusion blanket designs

J.A. Fillo; J.R. Powell; O. Lazareth


Transactions of the American Nuclear Society | 1976

Graphite blanket heat transfer for an experimental power reactor

J.A. Fillo; R. Benenati; J.R. Powell

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