Blankets for Thermonuclear Reactors
Author | : C. J. Barton |
Publisher | : |
Total Pages | : 32 |
Release | : 1962 |
Genre | : Fusion reactors |
ISBN | : |
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Author | : C. J. Barton |
Publisher | : |
Total Pages | : 32 |
Release | : 1962 |
Genre | : Fusion reactors |
ISBN | : |
Author | : |
Publisher | : |
Total Pages | : |
Release | : 1958 |
Genre | : |
ISBN | : |
In all likelihood, a nuclear power economy based on D-T thermonuclear reactors would require efficient breeding of tritium in blankets around such machines. Some of the chemical aspects of tritium breeder blankets are discussed by application of the principle of electroneutrality. It is shown that the most interesting fertile materials are metallic Li and LiD, although there are no serious bars to the use of many other materials. If neutron multiplication be employed, it appears necessary to use elemental Be due to the extensive decomposition that will be encountered in Be compounds. (auth).
Author | : Laszlo N. Lontai |
Publisher | : |
Total Pages | : 106 |
Release | : 1965 |
Genre | : Nuclides |
ISBN | : |
The use of fissile nuclides in a fusion power reactor heat-extraction blanket is investigated from the point of view of tritium regeneration and power production. The existence of a stable, steady-state D-T plasma in a cylindrical configuration is postulated. Nuclear reaction rates are analyzed with the aid of theoretical methods and multigroup, multiregion computer codes developed by A.J. Impink, Jr. Codes developed by W.G. Homeyer were used to calculate nuclear heating rates. Optimization studies of several blanket configurations show that a blanket with a thin Mo first wall, a narrow, fused (LiF)2BeF2 first-wall coolant region, and about 50 cm 21% C and 79% fused (LiF-BeF2-UF4) primary attenuator region with 17 to 27 mole per cent (U238)F4 and about 50% Li6 enrichment is feasible and practical. The calculated tritium regeneration is adequate. The total heat recovery is approximately twice that in a nonfissile blanket; approximately 90% of the heat is liberated in the primary attenuator region. The heating rate in the first wall and in the coolant region is independent of the UF4 salt composition. The thermonuclear power limit is about 5 Mw/sq. m of neutron energy incident on the first wall. The performance of blankets with a UF4 fusedsalt coolant region was found to be marginal; fissioning metallic first-wall configurations are not feasible. (Author).
Author | : Keith W. Hoffman |
Publisher | : |
Total Pages | : 152 |
Release | : 1977 |
Genre | : |
ISBN | : |
Author | : Laszlo M. Lontai |
Publisher | : |
Total Pages | : |
Release | : 1963 |
Genre | : |
ISBN | : |
Author | : George I. Bell |
Publisher | : |
Total Pages | : 12 |
Release | : 1969 |
Genre | : Fusion reactors |
ISBN | : |
Author | : D. M. Gruen |
Publisher | : |
Total Pages | : 20 |
Release | : 1958 |
Genre | : Breeder reactors |
ISBN | : |
The use of fused lithium nitrate as a breeding material for thermonuclear reactors is proposed. Some of the properties of LiNO3 such as thermal stability, radiation stability, neutron reaction products, and corrosive effects are briefly considered. Further studies are suggested.
Author | : Joseph J. Costello |
Publisher | : |
Total Pages | : 168 |
Release | : 1972 |
Genre | : |
ISBN | : |
Author | : S. Förster |
Publisher | : |
Total Pages | : 17 |
Release | : 1971 |
Genre | : Fusion |
ISBN | : |
Author | : |
Publisher | : |
Total Pages | : |
Release | : 1972 |
Genre | : |
ISBN | : |