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Author : Richard Hall Wiswall
Publisher :
ISBN 13 :
Total Pages : 14 pages
Book Rating : 4.:/5 (618 download)
Download or read book The Removal of Tritium from Fusion Reactor Blankets written by Richard Hall Wiswall and published by . This book was released on 1977 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Removal of Tritium from Fusion Reactor Blankets. Annual Report, FY 1977 written by and published by . This book was released on 1977 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The program is concerned with investigating the chemistry of those compounds and alloys of lithium which have acceptable physical and neutronic properties. In particular, information is needed on whether tritium can be removed rapidly, and how removal rates are affected by particle size, temperature, dose rate, etc.; how stable the solids are under long irradiation; and whether they are chemically compatible with the other materials that will be present in a blanket. The ultimate objective is to specify an optimum compound or alloy; to describe methods of synthesizing it and incorporating it, with or without diluents, into blanket modules; and to be able to predict its long-term behavior under operating conditions.
Author :
Publisher :
ISBN 13 :
Total Pages : 83 pages
Book Rating : 4.:/5 (786 download)
Download or read book A Study of Tritium Removal from Fusion Reactor Blankets of Molten Salt and Lithium-aluminum written by and published by . This book was released on 1964 with total page 83 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Study of Tritium Removal from Fusion Reactor Blankets of Molten Salt and Lithium--aluminum written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The sorption of tritium by molten lithium--bismuth (Li--Bi, approx. 15 at. % lithium) and solid equiatomic lithium--aluminum (Li--Al) was investigated experimentally to evaluate the potential applications of both materials in a controlled thermonuclear reactor. The Li--Bi alloy was proposed to countercurrently extract tritium from a molten salt (Li/sub 2/BeF/sub 4/) blanket. However, because of the low solubility (
Download or read book Studies of Fusion Reactor Blankets with Minimum Radioactive Inventory and with Tritium Breeding in Solid Lithium Compounds written by and published by . This book was released on 1973 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The feasibility of fusion reactor blankets with low residual activity is examined. Several designs are examined with regard to activation, tritium breeding ratio, mechanical design, tritium removal from the blanket, and thermal cycle efflciency. Using aluminum (SAP) as a structural material, it should be possible to build CTR blankets with ~10 curies/MW(e) of long-lived (half life one day or greater) residual activity (other than tritium), which is many orders of magnitude less than with Nb or stainless steel blankets. In the designs examined in this study, tritium is bred in -solid-lithium-containing materials, e.g., LiAl alloy, which have high-equilibrium tritium pressures. The tritium diffuses into either the helium-coolant stream, from which it is removed by absorption, or into the vacuum region between the first wall and plasma. Depending on processing methods and blanket parameters, the tritium blanket inventory should range from 102 to 103 curies/ MW(e). Tritium breeding ratios range from 0.9 to 1.5 depending on blanket design, while therrnal cycle efficiency is estimated to range from 35% to well over 40%, depending on design. Several module designs are developed in which helium-coolant exit temperatures are substantially above the operating temperature limit (~400 deg C) for the aluminum (SAP) structure. (auth).
Download or read book Some Preliminary Considerations of a Molten-salt Extraction Process to Remove Tritium from Liquid Lithium Fusion Reactor Blankets written by and published by . This book was released on 1974 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Tetsuo Tanabe
Publisher : Springer
ISBN 13 : 4431564608
Total Pages : 365 pages
Book Rating : 4.4/5 (315 download)
Download or read book Tritium: Fuel of Fusion Reactors written by Tetsuo Tanabe and published by Springer. This book was released on 2016-12-05 with total page 365 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book focuses on tritium as a fuel for fusion reactors and a next-generation energy source. Following an introduction of tritium as a hydrogen radioisotope, important issues involved in establishing safe and economical tritium fuel cycles including breeding for a fusion reactor are summarized; these include the handling of large amounts of tritium: confinement, leakage, contamination, permeation, regulation and tritium accountancy, and impacts on surrounding areas. Targeting and encouraging the students and technicians who will design and operate fusion reactors in the near future, this book offers a valuable resource on tritium science and technology.
Author : Stuart Green
Publisher :
ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (911 download)
Download or read book Estimation of Tritium Production in Fusion Reactor Blankets written by Stuart Green and published by . This book was released on 1988 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Joseph J. Costello
Publisher :
ISBN 13 :
Total Pages : 168 pages
Book Rating : 4.:/5 (89 download)
Download or read book Engineering and Heat Removal Considerations in Fusion Reactor Blanket Systems written by Joseph J. Costello and published by . This book was released on 1972 with total page 168 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 582 pages
Book Rating : 4.3/5 (91 download)
Download or read book Radiation Effects and Tritium Technology for Fusion Reactors written by and published by . This book was released on 1976 with total page 582 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Ernest F. Johnson
Publisher :
ISBN 13 :
Total Pages : 15 pages
Book Rating : 4.:/5 (713 download)
Download or read book Tritium Recovery from Fusion Reactor Blankets written by Ernest F. Johnson and published by . This book was released on 1969 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Patrick S. Spangler
Publisher :
ISBN 13 :
Total Pages : 180 pages
Book Rating : 4.:/5 (227 download)
Download or read book Fusion reactor blanket experiment written by Patrick S. Spangler and published by . This book was released on 1965 with total page 180 pages. Available in PDF, EPUB and Kindle. Book excerpt: The behavior of 1-14 Mev neutrons was measured in cylinders, 46 cm in diameter and 38 cm thick, to evaluate previous theoretical calculations on neutron economy and tritium production in proposed fusion reactor blankets. The cylinders were constructed from 0.5-inch graphite slabs and 1-inch layers of solid lithium-beryllium fluoride salt encased in aluminum pans. The neutron spectrum was measured with a series of threshold detectors: U-238(n, f), P-31(n, p), Fe-56(n, p), I-127(n, 2n), and F-19(n, 2n). The spectra in the graphite assemblies are characterized by a sharp peak near 14 Mev, with a smaller, broader peak at 3 Mev. Farther from the source, the 14-Mev peak is attenuated more than the 3-Mev peak. Adding 3-cm Mo to the base of the assembly shifts the 3-Mev peak to lower energies and increases its size at the expense of the 14Mev peak, because of the Mo-92(n,2n) reaction. Addition of the lithium-beryllium fluoride has no effect, because of the similarity in the scattering properties of the salt and the graphite. The removal of neutrons through the Li-6(n, t) reaction was not observed, because of the small size of the assembly and the low (1-3% isotopic content of Li-6 in the salt. Preliminary measurements indicate the feasibility of directly measuring the tritium produced in the assemblies by the Li-6(n, t) and Li-7(n, tn) reactions. (Author).
Author : Robert E. Buxbaum
Publisher :
ISBN 13 :
Total Pages : 312 pages
Book Rating : 4.:/5 (353 download)
Download or read book The Separation of Tritium from the Liquid Lithium Breeder-blanket of a Fusion Reactor written by Robert E. Buxbaum and published by . This book was released on 1982 with total page 312 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Analysis of In-situ Tritium Recovery from Solid Fusion-reactor Blankets written by and published by . This book was released on 1980 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The proposed concept for in-situ tritium recovery from the STARFIRE blanket involves circulation of a low pressure (approx. 0.05 MPa) helium through formed channels in the highly porous solid breeding material. Tritium generated within the grains must diffuse to the grain boundaries, migrate through the grain boundaries to the particle surface and then percolate through the packed bed to the helium purge channel. Highly porous .cap alpha.-LiAlO2 with a bimodal pore distribution is proposed for the breeding material to facilitate the tritium release.
Download or read book Development of Tritium Breeding Blankets for DT-burning Fusion Reactors written by and published by . This book was released on 1980 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This study examines the status of understanding of blanket tritium recovery and the performance of potentially viable tritium breeding materials under conditions anticipated in a DT-fueled fusion reactor environment. The existing physicochemical, thermophysical, and ceramographic data for candidate liquid and solid breeders are reviewed and appropriate operating conditions defined. It is shown that selection of a breeding material and an appropriate tritium recovery method can impose significant constraints upon blanket design, particularly when considerations of breeder/coolant/structure compatibility and temperature limitations are taken into account.
Author : Cheazone Hsu
Publisher :
ISBN 13 :
Total Pages : 368 pages
Book Rating : 4.3/5 (129 download)
Download or read book Permeation Membranes for Tritium Extraction from Liquid Metal Collants in Fusion Reactors written by Cheazone Hsu and published by . This book was released on 1987 with total page 368 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : F. Mannone
Publisher : Springer Science & Business Media
ISBN 13 : 9401119104
Total Pages : 241 pages
Book Rating : 4.4/5 (11 download)
Download or read book Safety in Tritium Handling Technology written by F. Mannone and published by Springer Science & Business Media. This book was released on 2012-12-06 with total page 241 pages. Available in PDF, EPUB and Kindle. Book excerpt: The use of tritium as a basic fuel material in a thermonuclear fusion reactor raises particular safety issues due to the combined effects of its physico chemical properties and radioactive nature. Furthermore the possibility of attaining further significant progresses in developing and demonstrating the feasibility of tritium burning devices relies on the handling of tritium macroquantities, say ten grammes, in a safe and reliable manner. It is also undoubted that, apart from technological constraints, any validation and exploitation of thermonuclear fusion as a source of energy will be strongly conditioned by the application of stringent operational and environmental safety criteria as it derives from norms of the modern legislation and public acceptance considerations. Even if the safe handling of tritium has already been demonstrated to be feasible on a full fuel cycle scale, it is unanimously recognized that further efforts are still to be concentrated on the improvement of current concepts and development of advanced technologies. Some of the areas requiring substantial additional efforts are plasma exhaust fuel c1ean-up, tritium pellet injection, processing of inert carrier gas, development of large free-oil pumps,tritlUm process analytics, development of large detritiation systems, beryllium-tritium interaction studies, tritium hold-up studies in getter beds, adsorbers and structural materials, tritium recovery from first wall, structural and breeder materials for minimizing tritiated waste arising,tritium storage technology, tritiated waste disposal technolo~y, methodology for routine tritium accountancy,etc . . Most of them are intrinsically related to the safety requirement of tritium technology.
