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A Study Of Tritium Removal From Fusion Reactor Blankets Of Molten Salt And Lithium Aluminum
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Book Synopsis A Study of Tritium Removal from Fusion Reactor Blankets of Molten Salt and Lithium-aluminum by :
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:
Book Synopsis Study of Tritium Removal from Fusion Reactor Blankets of Molten Salt and Lithium--aluminum by :
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 (
Book Synopsis Some Preliminary Considerations of a Molten-salt Extraction Process to Remove Tritium from Liquid Lithium Fusion Reactor Blankets by :
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:
Book Synopsis Chemical Processing of Liquid Lithium Fusion Reactor Blankets by :
Download or read book Chemical Processing of Liquid Lithium Fusion Reactor Blankets written by and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A 50-gallon-capacity lithium loop constructed mostly from 304L stainless steel has been operated for over 6000 hours at temperatures in the range from 360 to 480°C. This facility, the Lithium Processing Test Loop (LPTL), is being used to develop processing and monitoring technology for liquid lithium fusion reactor blankets. Results of tests of a molten-salt extraction method for removing impurities from liquid lithium have yielded remarkably good distribution coefficients for several of the more common nonmetallic elements found in lithium systems. In particular, the equilibrium volumetric distribution coefficients, D/sub v/ (concentration per unit volume of impurity in salt/concentration per unit volume of impurity in lithium), for hydrogen, deuterium, nitrogen and carbon are approx. 3, approx. 4,> 10, approx. 2, respectively. Other studies conducted with a smaller loop system, the Lithium Mini-Test Loop (LMTL), have shown that zirconium getter-trapping can be effectively used to remove selected impurities from flowing lithium.
Book Synopsis Direct Lit Electrolysis In A Metallic Lithium Fusion Blanket by :
Download or read book Direct Lit Electrolysis In A Metallic Lithium Fusion Blanket written by and published by . This book was released on 2015 with total page 6 pages. Available in PDF, EPUB and Kindle. Book excerpt: A process that simplifies the extraction of tritium from molten lithium based breeding blankets was developed. The process is based on the direct electrolysis of lithium tritide using a ceramic Li ion conductor that replaces the molten salt extraction step. Extraction of tritium in the form of lithium tritide in the blankets/targets of fission/fusion reactors is critical in order to maintained low concentrations. This is needed to decrease the potential tritium permeation to the surroundings and large releases from unforeseen accident scenarios. Because of the high affinity of tritium for the blanket, extraction is complicated at the required low levels. This work identified, developed and tested the use of ceramic lithium ion conductors capable of recovering the hydrogen and deuterium thru an electrolysis step at high temperatures.
Book Synopsis The Removal of Tritium from Fusion Reactor Blankets by : Richard Hall Wiswall
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:
Book Synopsis Removal of Tritium from Fusion Reactor Blankets. Annual Report, FY 1977 by :
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.
Book Synopsis Proceedings of the Second Topical Meeting on the Technology of Controlled Nuclear Fusion by :
Download or read book Proceedings of the Second Topical Meeting on the Technology of Controlled Nuclear Fusion written by and published by . This book was released on 1976 with total page 370 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis ERDA Energy Research Abstracts by : United States. Energy Research and Development Administration
Download or read book ERDA Energy Research Abstracts written by United States. Energy Research and Development Administration and published by . This book was released on 1976-05 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Recovery of Tritium from a Liquid Lithium Blanket by :
Download or read book Recovery of Tritium from a Liquid Lithium Blanket written by and published by . This book was released on 1981 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The sorption of tritium on yttrium from liquid lithium and the subsequent release of tritium from yttrium by thermal regeneration of the metal sorbent were investigated to study such a tritium-recovery process for a fusion reactor blanket of liquid lithium. Recent static sorption experiments have shown the effects of lithium temperature and possible impurities on the sorption of tritium. Diffusivity data, obtained from previous tritium recovery experiments, were evaluated to show the importance of the yttrium surface condition in controlling the release of tritium.
Book Synopsis Direct LiT Electrolysis in a Metallic Fusion Blanket by :
Download or read book Direct LiT Electrolysis in a Metallic Fusion Blanket written by and published by . This book was released on 2016 with total page 7 pages. Available in PDF, EPUB and Kindle. Book excerpt: A process that simplifies the extraction of tritium from molten lithium based breeding blankets was developed. The process is based on the direct electrolysis of lithium tritide using a ceramic Li ion conductor that replaces the molten salt extraction step. Extraction of tritium in the form of lithium tritide in the blankets/targets of fusion/fission reactors is critical in order to maintain low concentrations. This is needed to decrease the potential tritium permeation to the surroundings and large releases from unforeseen accident scenarios. Extraction is complicated due to required low tritium concentration limits and because of the high affinity of tritium for the blanket. This work identified, developed and tested the use of ceramic lithium ion conductors capable of recovering hydrogen and deuterium through an electrolysis step at high temperatures.
Author :United States. Energy Research and Development Administration. Technical Information Center Publisher : ISBN 13 : Total Pages :982 pages Book Rating :4.3/5 (129 download)
Book Synopsis ERDA Energy Research Abstracts by : United States. Energy Research and Development Administration. Technical Information Center
Download or read book ERDA Energy Research Abstracts written by United States. Energy Research and Development Administration. Technical Information Center and published by . This book was released on 1977 with total page 982 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Energy Research Abstracts written by and published by . This book was released on 1988 with total page 1684 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis ERDA Research Abstracts by : United States. Energy Research and Development Administration
Download or read book ERDA Research Abstracts written by United States. Energy Research and Development Administration and published by . This book was released on 1976 with total page 716 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book ERDA Energy Research Abstracts written by and published by . This book was released on 1977 with total page 724 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Proceedings of the Second Topical Meeting on the Technology of Controlled Nuclear Fusion, September 21-23, 1976, Richland, Washington by :
Download or read book Proceedings of the Second Topical Meeting on the Technology of Controlled Nuclear Fusion, September 21-23, 1976, Richland, Washington written by and published by . This book was released on 1976 with total page 836 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Fusion Energy Update written by and published by . This book was released on 1986 with total page 100 pages. Available in PDF, EPUB and Kindle. Book excerpt: