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Author : Wallace W. Schulz
Publisher :
ISBN 13 :
Total Pages : 26 pages
Book Rating : 4.3/5 (91 download)
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:
Author : William C. Perkins
Publisher :
ISBN 13 :
Total Pages : 16 pages
Book Rating : 4.3/5 (91 download)
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:
Author : William C. Perkins
Publisher :
ISBN 13 :
Total Pages : 16 pages
Book Rating : 4.3/5 (91 download)
Download or read book Dissolving Highly Irradiated Pu - Al Alloy written by William C. Perkins and published by . This book was released on 1964 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Dissolving Highly Irradiated Pu-Al Alloy written by and published by . This book was released on 1964 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The Nitric Acid Dissolution of Uranium-Aluminum Alloy in a Flooded Continuous Dissolver written by and published by . This book was released on 1954 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Extensive pilot plant studies of the mercury-catalyzed nitric acid dissolution of unirradiated 7.5% uranium--92.5% aluminum alloy slugs were carried out in tall-pipe, flooded, continuous dissolvers, In producing an acidic product containing 1.2M aluminum nitrate, dissolution rates as high as 15 kg of aluminum per day per square inch of cross section were achieved. Countercurrent flow of metal and acid has some advantages over concurrent flow, The large heat of reaction produced great volumes of steam in the dissolvers; the operational problems due to the resulting foam were best solved by the use of an over head reflux condenser to condense, partially or totally, the steam in the off-gas. Only minor quantities of solids were found in acidic product solutions. Extruded alloy dissolved abcut twice as fast as cast alloy, The metal dissolving rate was directly proportional to the 0.8 power of the nitric acid feed rate and tc the cube root of the mercuric ion (catalyst) concentration. The maximim dissolving rates occurred at feed acid concentrations of abcut 3M for cast slugs and 5M for extruded alloy, The system studied is inherently self-regulating in that a uniform product composition will normally be produced by feeding slugs, nitric acid, and catalyst at constant rates. The occasional minor rate adjustments are best accomplished by varying the catalyst concentration. Data and correlations developed are given. (auth).
Author : R. E. Brooksbank
Publisher :
ISBN 13 :
Total Pages : 80 pages
Book Rating : 4.3/5 (91 download)
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 Лекции по истории экономического быта Западной Европы written by and published by . This book was released on 1918 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Caustic Dissolution of Uranium-Aluminum Alloy written by and published by . This book was released on 1956 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Dissolution of Plutonium Metal in Sulfamic Acid at Elevated Temperatures written by and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The kinetics of the dissolution of plutonium metal in sulfamic acid at varying temperatures was determined. Hydrogen off-gas rates and plutonium concentrations were determined as functions of time for different dissolving conditions. Nominal 2.2 kg Pu buttons (surface area, 171 cm2) should yield solutions containing 190 to 260 g Pu/L and 3.3M sulfamate ion after a one-hour dissolving time at 70°C. Hydrogen off-gas rates were calculated to vary from a high of 2.7L of gaseous hydrogen per minute (STP) at the beginning of a dissolving cycle to 50 mL of hydrogen gas per minute at the end of a one-hour dissolving time. Sludge formation, which is a problem at ambient temperatures, does not occur at dissolving temperatures of 60 to 80°C. Dissolution curves suggest that the mechanism of dissolution changes at about 50 to 55°C. Below this temperature, a surface coating of plutonium hydride may form; above this temperature, plutonium metal appears to be converted directly to Pu/sup 3 +/. 13 figures, 1 table.
Download or read book Dissolution of Plutonium Metal in HNO/sub 3/-N/sub 2/H/sub 4/-KF. written by and published by . This book was released on 1983 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Plutonium metal dissolves in HNO/sub 3/-N/sub 2/H/sub 4/. HNO/sub 3/-KF solution to yield a Pu/sup 3 +/ solution without an accompanying precipitation of plutonium oxide solids. The reaction evolves less than 0.2 mole of gas per mole of plutonium dissolved; the gas contains only 3% H/sub 2/. About 10/sup -3/ moles of HN/sub 3/ are produced per mole of plutonium dissolved. Optimum conditions for dissolving both alpha-phase and delta-phase plutonium metal were developed. Possible applications are to the recovery of plutonium metal or the processing of irradiated plutonium metal and alloys.
Download or read book Electrolytic Dissolver for Plutonium Metal written by and published by . This book was released on 1971 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Laboratory tests have demonstrated that plutonium metal, as well as aluminum, stainless steel, Hastelloy C, and other alloys, can be electrolytically dissolved in nitric acid using the ''solution contact'' approach. Two sources of plutonium metal were evaluated, weapons' grade and a special reactor grade (42% 24°Pu, 12% 241Pu) from Savannah River, both yielding a dissolution rate of approximately one gram per ampere-hour. A current flow of 150 amperes was attained at 12 volts (limit of the power supply) and higher current should be possible at increased voltage. Since no fluoride was used in the actual dissolution, glass and 304 stainless steel components provided satisfactory performance. Preliminary investigations on the sludge formed (less than 1%) during electrolysis showed it to be soluble in a low fluoride-high nitric wash. The proposed electrolytic dissolver is recommended to replace the present metal dissolution process for the following reasons: (1) eliminates button sectioning--entire buttons are dissolved; (2) eliminates metal burning; (3) eliminates powder handling; (4) eliminates PuO2 dissolution; (5) reduces solids going to the recovery columns; (6) simple to operate; (7) relatively independent of plutonium metal source; (8) reduces operator time resulting in decreased cost and operator exposure; and (9) will directly dissolve many types of plutonium alloys and cladding materials.
Author :
Publisher :
ISBN 13 :
Total Pages : 5 pages
Book Rating : 4.:/5 (727 download)
Download or read book Mercury-Free Dissolution of Aluminum-Based Nuclear Material written by and published by . This book was released on 2003 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: Conditions were optimized for the first plant-scale dissolution of an aluminum-containing nuclear material without using mercury as a catalyst. This nuclear material was a homogeneous mixture of plutonium oxide and aluminum metal that had been compounded for use as the core matrix in Mark 42 nuclear fuel. Because this material had later failed plutonium distribution specifications, it was rejected for use in the fabrication of Mark 42 fuel tubes, and was stored at the Savannah River Site (SRS) awaiting disposition. This powder-like material was composed of a mixture of approximately 80 percent aluminum and 11 percent plutonium. Historically, aluminum-clad spent nuclear fuels [13] have been dissolved using a mercuric nitrate catalyst in a nitric acid (HNO3) solution to facilitate the dissolution of the bulk aluminum cladding. Developmental work at SRS indicated that the plutonium oxide/aluminum compounded matrix could be dissolved without mercury. Various mercury-free conditions were studied to evaluate the rate of dissolution of the Mark 42 compact material and to assess the corrosion rate to the stainless steel dissolver. The elimination of mercury from the dissolution process fit with waste minimization and industrial hygiene goals to reduce the use of mercury in the United States. The mercury-free dissolution technology was optimized for Mark 42 compact material in laboratory-scale tests, and successfully implemented at the plant.
Author :
Publisher :
ISBN 13 :
Total Pages : 24 pages
Book Rating : 4.3/5 (91 download)
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:
Author : Robert L. Andelin
Publisher :
ISBN 13 :
Total Pages : 48 pages
Book Rating : 4.3/5 (91 download)
Download or read book Status Report on Studies of Uranium-aluminum Alloy Dissolution to a DIBAN Dissolver Product written by Robert L. Andelin and published by . This book was released on 1957 with total page 48 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 13 pages
Book Rating : 4.:/5 (873 download)
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 Aluminum Target Dissolution in Support of the Pu-238 Program written by and published by . This book was released on 2014 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Selection of an aluminum alloy for target cladding affects post-irradiation target dissolution and separations. Recent tests with aluminum alloy 6061 yielded greater than expected precipitation in the caustic dissolution step, forming up to 10 wt.% solids of aluminum hydroxides and aluminosilicates. We present a study to maximize dissolution of aluminum metal alloy, along with silicon, magnesium, and copper impurities, through control of temperature, the rate of reagent addition, and incubation time. Aluminum phase transformations have been identified as a function of time and temperature, using X-ray diffraction. Solutions have been analyzed using wet chemical methods and X-ray fluorescence. These data have been compared with published calculations of aluminum phase diagrams. Temperature logging during the transients has been investigated as a means to generate kinetic and mass transport data on the dissolution process. Approaches are given to enhance the dissolution of aluminum and aluminosilicate phases in caustic solution.
Download or read book Dissolving Uranium Oxide--aluminum Fuel written by and published by . This book was released on 1973 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The dissolution of aluminum-clad uranium oxide-aluminum fuel was studied to provide basic data for dissolving this type of enriched uranium fuel at the Savannah River Plant. The studies also included the dissolution of a similar material prepared from scrap uranium oxides that were to be recycled through the solvent extraction process. The dissolving behavior of uranium oxide-aluminum core material is similar to that of U-Al alloy. Dissolving rates are rapid in HNO/sub 3/-Hg(NO/sub 3/)/sub 2/ solutions. Irradiation reduce s the dissolving rate and increases mechanical strength. A dissolution model for use in nuclear safety analyses is developed, . based on the observed dissolving characteristics. (auth).
