Download or read book Recovery of Plutonium from Irradiated Plutonium aluminum Alloy written by and published by . This book was released on 1962 with total page 24 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Recovery of Plutonium and Other Transuranium Elements from Irradiated Plutonium aluminum Alloy by Ion Exchange Methods written by R. E. Brooksbank and published by . This book was released on 1964 with total page 80 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Controlled Nitric Acid Dissolution of Aluminum plutonium Alloys written by Wallace W. Schulz and published by . This book was released on 1972 with total page 26 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Chloride Removal from Plutonium aluminum Alloy Dissolver Solution Prior to Purex Solvent Extraction written by and published by . This book was released on 1990 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Savannah River Plant (SRP), operated by E.I. du Pont de Nemours Co. for the United States Department of Energy, has successfully recovered plutonium from plutonium-aluminum alloy processed through the F-Canyon Separations facility. The alloy, produced at the Rocky Flats Plant, results from recovery of plutonium residues from spent chloride salts from pyrochemical processing. The alloy, termed scrub alloy'' or Rocky Flats scrub alloy'' (RFSA), contains up to 15 weight percent chloride impurity prior to mercuric ion catalyzed dissolution with fluoride-containing nitric acid. Solutions containing 850 to 3000 [mu]g/mL (parts per million) of chloride result. During subsequent Purex solvent extraction of this solution with 30% tri-n-butyl phosphate in normal paraffin diluent, chloride is rejected to the aqueous waste stream. This stream is eventually evaporated for waste treatment and acid recovery. Chloride concentrations in the product streams, subject to further processing, must be less than 100 [mu]g/mL to prevent excessive corrosion of equipment. This paper describes scrub alloy production at RFP, its dissolution and head end treatment to remove chloride, chloride values in subsequent processing streams including environmental discharges, and the turbidimetric analysis technique. 2 tabs.

Download or read book Extractive and Physical Metallurgy of Plutonium and Its Alloys written by Metallurgical Society of AIME. and published by . This book was released on 1960 with total page 332 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book PLUTONIUM 238 RECOVERY FROM IRRADIATED NEPTUNIUM TARGETS USING SOLVENT EXTRACTION written by Bruce Mincher and published by . This book was released on 2006 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The United States Department of Energy proposes to re-establish a domestic capability for producing plutonium-238 (238Pu) to fuel radioisotope power systems primarily in support of future space missions. A conceptual design report is currently being prepared for a new 238Pu, and neptunium-237 (237Np) target fabrication and processing facility tentatively to be built at the Idaho National Laboratory (INL) in the USA. The facility would be capable of producing at least 5 kg of 238Pu-oxide powder per year. Production of 238Pu requires fabrication of 237Np targets with subsequent irradiation in the existing Advanced Test Reactor (ATR) located at the INL. The targets are 237Np oxide dispersed in a compact of powdered aluminum and clad with aluminum metal. The 238Pu product is separated and purified from the residual 237Np, aluminum matrix, and fission products. The unconverted 237Np is also a valuable starting material and is separated, purified and recycled to the target fabrication process. The proposed baseline method for separating and purifying 238Pu and unconverted 237Np post irradiation is by anion exchange (IX). Separation of Pu from Np by IX was chosen as the baseline method because of the method's proven ability to produce a quality Pu product and because it is amenable to the relatively small scale, batch type production methods used (small batches of ~200g 238Pu are processed at a time). Multiple IX cycles are required involving substantial volumes of nitric acid and other process solutions which must be cleaned and recycled or disposed of as waste. Acid recycle requires rather large evaporator systems, including one contained in a hot cell for remote operation. Finally, the organic based anion exchange resins are rapidly degraded due to the high a-dose and associated heat production from 238Pu decay, and must be regularly replaced (and disposed of as waste). In summary, IX is time consuming, cumbersome, and requires substantial tankage to accommodate the process. The primary purpose of the preliminary study discussed here is to develop an alternative process flowsheet using well-known solvent extraction (SX) techniques based on decades of experience with PUREX processing of nuclear materials. Ultimately, this initial study will be used to determine if an SX approach would offer any significant processing advantages relative to the currently proposed anion exchange process.

Download or read book Reprocessing of Irradiated Fission Reactor Fuel and Breeding Materials written by and published by . This book was released on 1964 with total page 212 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Dissolution of Pu Al Alloy written by William C. Perkins and published by . This book was released on 1962 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book The Metallurgy of Nuclear Fuel written by V. S. Yemel'Yanov and published by Elsevier. This book was released on 2013-10-22 with total page 600 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Metallurgy of Nuclear Fuel: Properties and Principles of the Technology of Uranium, Thorium and Plutonium is a systematic analysis of the metallurgy of nuclear fuel, with emphasis on the physical, mechanical, and chemical properties as well as the technology of uranium, thorium, and plutonium, together with their alloys and compounds. The minerals and raw material sources of nuclear fuel are discussed, along with the principles of the technology of the raw material processing and the production of the principal compounds, and of the pure metals and alloys. Comprised of three parts, this volume begins with an introduction to the history of the discovery of uranium and its position in the periodic system; its use as a nuclear fuel; radioactivity and isotopic composition; alloys and compounds; and physical, mechanical, and chemical properties. The effect of mechanical and thermal treatment, thermal cycling and irradiation on the physicochemical properties of uranium is also examined. The next two sections are devoted to thorium and plutonium and includes chapters dealing with their uses, alloys and compounds, and methods of recovery and purification. This book is written for university students, but should also prove useful to young production engineers and scientific workers who are concerned with problems in the metallurgy of nuclear fuel.

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1975-11 with total page 698 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Recovery of Americium and Curium from an Irradiated Plutonium napkin ring written by Meir Givon and published by . This book was released on 1964 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Recovery of Plutonium from Incinerator Ash written by F. E. Butler and published by . This book was released on 1964 with total page 48 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Hearings on H R 2603 Department of Energy Authorization Legislation national Security Programs for Fiscal Year 1980 Before the Procurement and Military Nuclear Systems Subcommittee of the Committee on Armed Services House of Representatives Ninety sixth Congress First Session written by United States. Congress. House. Committee on Armed Services. Procurement and Military Nuclear Systems Subcommittee and published by . This book was released on 1979 with total page 1340 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Bibliography on Nuclear Reactor Fuel Reprocessing and Waste Disposal Fissionable material recovery written by T. F. Connolly and published by . This book was released on 1960 with total page 170 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Chemical Analyses of Plutonium and Plutonium Alloys written by Rose Kraft and published by . This book was released on 1962 with total page 112 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Plutonium Fuel Fabrication and Reprocessing for Fast Ceramic Reactors written by E. L. Zebroski and published by . This book was released on 1962 with total page 60 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1969 with total page 1508 pages. Available in PDF, EPUB and Kindle. Book excerpt: