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Dispersions Of Uranium Carbides In Aluminum Plate Type Research Reactor Fuel Elements
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Book Synopsis Dispersions of Uranium Carbides in Aluminum Plate-type Research Reactor Fuel Elements by : W. C. Thurber
Download or read book Dispersions of Uranium Carbides in Aluminum Plate-type Research Reactor Fuel Elements written by W. C. Thurber and published by . This book was released on 1959 with total page 58 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis DISPERSIONS OF URANIUM CARBIDES IN ALUMINUM PLATE-TYPE RESEARCH REACTOR FUEL ELEMENTS. by :
Download or read book DISPERSIONS OF URANIUM CARBIDES IN ALUMINUM PLATE-TYPE RESEARCH REACTOR FUEL ELEMENTS. written by and published by . This book was released on 1959 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The technical feasibility of employing uranium carbide aluminun dispersions in aluminum-base research reactor fuel elements was investigated This study was motivated by the need to obtain higher uranium loadings in these fuel elements. Although toe MTR-type unit, containing a 13 18 wt% U-Al alloy is a proven reactor component, fabrication problems of considerable magnitude arise when attempts are made to increase the uranium investment in the alloy to more than 25 wt.%. Au approach to these fabrication difficulties is to select a compound with significantly higher density tban UAl4 or UAl3 compounds of the alloy system which when dispersed in aluminum powder, will reduce the volume occupied by the brittle, fissile phase. The uranium carbides, with densities ranging from 11.68 to 13.63 g/cm3), appear to be suited for this application and were selected for development as a fuel material for aluminum-base dispersions. Studies were conducted at 580 to 620 deg C to determine the chemical compatibility of carbides with aluminum in sub-size cold- pressed comparts as well as in full-size fabricated fuel plates. Procedures were also developed to prepare uranium carbides, homogernously disperse the compounds in aluminum, roll clad the dispersions to form composite plates, and braze the plates into fuel assemblies. Corrosion tests of the fuel material were conducted in 20 and 60 deg C water to determine the integrity of the fuel material in the event of sin inadventent cladding failure. In addition, specimens were prepared to evaluate penformance under extensive irradiation Prior to studying the uranium carbide-aluminum system, methods for preparing the carbides were investigated. Are melting uranium and carnon was satisfactory for obtaining small quantities of various carbides. Later, reaction of graphite with UO2 was successfully employed in the preparation of large quantities of UC2, Studies of the chemical compatibility of cold-pressed compacts containing 50 wt% uranium carbide dispersed in aluminum revealed a marked trend toward stebifity as the carbon content of the uranium carbide increased from 446 to 9.20% C. Severe volume increases occurred in monocarbide dispersions with attendant formation of large quantities of the uranium-allumnim inter-metallic compounds. Dicarbide dispersions, on the other band, exhibited negligible reaction with aluminum after extended periods at 580 and 620 deg C. However, it was demonstrated that hydrogen can promote a reaction in UC2-Al compacts. The hydrogen appears to reduce the UC2 to UC which can subsequently react with aluminum producing the previously noted deleterious effects. A growth study at 605 deg C of composite fuel plates containing 59 wt.% UC2 revealed insignificant changes within processing periods envisioned for fuel element processing. However, plate elongations as high as 2.5% were observed after 100 hr at this temperature. Severe blistering which occurred on fuel plates fabricated in the initial stages of the investigation was attributed to gaseous hydrocarbons, and the condition was ellminated by vacuum degasification of cold-pressed compacts. With the exception of the degasification requirement, procedures for manufacturing UC- bearing fuel elements were identical to those specified for the Geneva Conference Reactor fuel elements. Dispersions of uranium dicarbide corroded catastrophically in 20 and 60 deg C water, thus limiting the application of this material However, spocimens were prepared and insented in the MTR to evaluate the irradiation behavior of this fuel because of its potential application in onganic- cooled reactors. (auth).
Book Synopsis Dispersions of Uranium in Aluminum Plate-type Research Reactor Fuel Elements by : William Clarence Thurber
Download or read book Dispersions of Uranium in Aluminum Plate-type Research Reactor Fuel Elements written by William Clarence Thurber and published by . This book was released on 1959 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1973 with total page 1132 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1975-11 with total page 960 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Summaries of Fuels and Materials Development Programs by :
Download or read book Summaries of Fuels and Materials Development Programs written by and published by . This book was released on 1961 with total page 232 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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Download or read book BMI- written by and published by . This book was released on 1962 with total page 232 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Government-wide Index to Federal Research & Development Reports by :
Download or read book Government-wide Index to Federal Research & Development Reports written by and published by . This book was released on 1965-10 with total page 840 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Specifications and Procedures Used in Manufacturing U3O8-aluminum Dispersion Fuel Elements for Core I of the Puerto Rico Research Reactor by : W. J. Kucera
Download or read book Specifications and Procedures Used in Manufacturing U3O8-aluminum Dispersion Fuel Elements for Core I of the Puerto Rico Research Reactor written by W. J. Kucera and published by . This book was released on 1963 with total page 61 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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Book Synopsis Dispersion-fuel Nuclear Reactor Elements by : Андрей Григорьевич Самойлов
Download or read book Dispersion-fuel Nuclear Reactor Elements written by Андрей Григорьевич Самойлов and published by . This book was released on 1968 with total page 240 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Uranium Carbides, Nitrides, and Silicides by :
Download or read book Uranium Carbides, Nitrides, and Silicides written by and published by . This book was released on 1965 with total page 204 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Articles Published in Technical Journals, Reports Issued, Papers Presented at Scientific Meetings, Theses Completed, and Inventions Disclosed During 1959 by ORNL Staff Members by : Oak Ridge National Laboratory
Download or read book Articles Published in Technical Journals, Reports Issued, Papers Presented at Scientific Meetings, Theses Completed, and Inventions Disclosed During 1959 by ORNL Staff Members written by Oak Ridge National Laboratory and published by . This book was released on 1960 with total page 100 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Fuel Elements Conference written by and published by . This book was released on 1959 with total page 314 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Treatise on Powder Metallurgy by : Claus Guenther Goetzel
Download or read book Treatise on Powder Metallurgy written by Claus Guenther Goetzel and published by . This book was released on 1963 with total page 920 pages. Available in PDF, EPUB and Kindle. Book excerpt: