Download or read book Dissolution of Neptunium and Plutonium Oxides Using a Catalyzed Electrolytic Process written by TD. Hylton and published by . This book was released on 2004 with total page 39 pages. Available in PDF, EPUB and Kindle. Book excerpt: This report discusses the scoping study performed to evaluate the use of a catalyzed electrolytic process for dissolving {sup 237}Np oxide targets that had been irradiated to produce {sup 238}Pu oxide. Historically, these compounds have been difficult to dissolve, and complete dissolution was obtained only by adding hydrofluoric acid to the nitric acid solvent. The presence of fluoride in the mixture is undesired because the fluoride ions are corrosive to tank and piping systems and the fluoride ions cause interferences in the spectrophotometric analyses. The goal is to find a dissolution method that will eliminate these issues and that can be incorporated into a processing system to support the domestic production and purification of {sup 238}Pu. This study evaluated the potential of cerium(IV) ions, a strong oxidant, to attack and dissolve the oxide compounds. In the dissolution process, the cerium(IV) ions are reduced to cerium(III) ions, which are not oxidants. Therefore, an electrolytic process was incorporated to continuously convert cerium(III) ions back to cerium(IV) ions so that they can dissolve more of the oxide compounds. This study showed that the neptunium and plutonium oxides were successfully dissolved and that more development work should be performed to optimize the procedure.
Download or read book Catalyzed Electrolytic Plutonium Oxide Dissolution CEPOD written by and published by . This book was released on 1990 with total page 37 pages. Available in PDF, EPUB and Kindle. Book excerpt: Catalyzed Electrolytic Plutonium Oxide Dissolution (CEPOD) was first demonstrated at PNL in early 1974 in work funded by EXXON Corporation. That work was aimed at dissolution of Pu-containing residues remaining in mixed-oxide reactor fuels dissolution and was first publicly disclosed in 1981. The process dissolves PuO2 in an anolyte containing small (catalytic) amounts of elements that form kinetically fast, strongly oxidizing ions. These are continuously regenerated at the anode. Catalysts used, in their oxidized form, include Ag{sup 2+}, Ce{sup 4+}, Co{sup 3+}, and AmO2{sup 2+}. This paper reviews the chemistry involved in CEPOD and the results of its application to the dissolution of the Pu content of a variety of PuO2-containing materials such as off-standard oxide, fuels dissolution residues, incinerator ash, contaminated soils, and other scrapes or wastes. Results are presented for both laboratory-scale and plant-scale dissolvers. Spin-off applications such as decontamination of metallic surfaces and destruction of organics are discussed. 27 refs., 14 figs.
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 Development of the CEPOD Process for Dissolving Plutonium Oxide and Leaching Plutonium from Scrap Or Wastes Catalyzed Electrochemical Plutonium Oxide Dissolution CEPOD written by and published by . This book was released on with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Laboratory-scale dissolving tests have demonstrated that PuO2, fired at temperatures between 950 and 1700°C, can be dissolved at 25 to 35°C to concentrations exceeding 100 g Pu/L in an electrochemical dissolver using silver ion as a redox catalyst. The dissolution rates are 2 to 5 times faster than the rates obtained using the current process (12 M HNO3-0.18 M HF at 90°C) and the corrosive fluoride ion is avoided. 4 refs., 5 figs., 1 tab.
Download or read book Apparatus and Process for the Electrolytic Reduction of Uranium and Plutonium Oxides written by and published by . This book was released on 1991 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: An apparatus and process for reducing uranium and/or plutonium oxides to produce a solid, high-purity metal. The apparatus is an electrolyte cell consisting of a first container, and a smaller second container within the first container. An electrolyte fills both containers, the level of the electrolyte in the first container being above the top of the second container so that the electrolyte can be circulated between the containers. The anode is positioned in the first container while the cathode is located in the second container. Means are provided for passing an inert gas into the electrolyte near the lower end of the anode to sparge the electrolyte and to remove gases which form on the anode during the reduction operation. Means are also provided for mixing and stirring the electrolyte in the first container to solubilize the metal oxide in the electrolyte and to transport the electrolyte containing dissolved oxide into contact with the cathode in the second container. The cell is operated at a temperature below the melting temperature of the metal product so that the metal forms as a solid on the cathode.
Download or read book Plutonium Oxide Dissolution written by and published by . This book was released on 1992 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: Several processing options for dissolving plutonium oxide (PuO[sub 2]) from high-fired materials have been studied. The scoping studies performed on these options were focused on PuO[sub 2] typically generated by burning plutonium metal and PuO[sub 2] produced during incineration of alpha contaminated waste. At least two processing options remain applicable for dissolving high-fired PuO[sub 2] in canyon dissolvers. The options involve solid solution formation of PuO[sub 2] With uranium oxide (UO[sub 2]) and alloying incinerator ash with aluminum. An oxidative dissolution process involving nitric acid solutions containing a strong oxidizing agent, such as cerium (IV), was neither proven nor rejected. This uncertainty was due to difficulty in regenerating cerium (IV) ions during dissolution. However, recent work on silver-catalyzed dissolution of PuO[sub 2] with persulfate has demonstrated that persulfate ions regenerate silver (II). Use of persulfate to regenerate cerium (IV) or bismuth (V) ions during dissolution of PuO[sub 2] materials may warrant further study.
Download or read book Dissolution of Neptunium Oxide in Unirradiated Mark 53 Targets written by and published by . This book was released on 2002 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: Nine unirradiated Mark 53 targets currently stored at the K-Reactor must be dissolved to allow recovery of the neptunium content. The Mark 53 targets are an aluminum clad, neptunium oxide (NpO2)/aluminum metal cermet used for the production of plutonium-238. The targets will be dissolved in H-Canyon and blended with solutions generated from routine fuel dissolutions for purification by solvent extraction. The increased neptunium concentration should not have a significant effect on the neptunium decontamination factor achieved by the 1st cycle of solvent extraction; however, the neptunium content of the uranium product (1CU) will likely increase in proportion to the increase in the neptunium feed concentration. The recovered neptunium will be combined with the existing inventory of neptunium solution currently stored in H-Canyon. The combined inventory will undergo subsequent purification and conversion to an oxide for shipment to the Oak Ridge National Laboratory where plutonium- 238 will be manufactured using the High Flux Isotope Reactor.
Download or read book A Kinetic Study of Plutonium Dioxide Dissolution in Hydrochloric Acid Using Iron II as an Electron Transfer Catalyst written by and published by . This book was released on 2006 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Effective dissolution of plutonium dioxide has traditionally been accomplished by contact with strong nitric acid containing a small amount of fluoride at temperatures of [approximately] 100 C. In spite of these aggressive conditions, PuO[sub 2] dissolution is sometimes incomplete requiring additional contact with the solvent. This work focused on an alternative to conventional dissolution in nitric acid where an electron transfer catalyst, Fe(II), was used in hydrochloric acid. Cyclic voltammetry was employed as an in-situ analytical technique for monitoring the dissolution reaction rate. The plutonium oxide selected for this study was decomposed plutonium oxalate with> 95% of the material having a particle diameter (
Download or read book Dissolution of Plutonium Oxide written by G.F. Molen and published by . This book was released on 1967 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Characterization of Neptunium and Plutonium in Manganese Oxide Solids Formed from Permanganate Reduction During Simulant Radioactive Waste Treatment written by M. C. Duff and published by . This book was released on 2003 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: Nearly 34 million gallons of high-level waste (HLW, the radioactive waste product associated with the dissolution of spent nuclear fuel rods for the recovery of weapons grade materials) await disposition at the Savannah River Site (SRS). The current design for the Salt Waste Processing Facility at the SRS includes use of monosodium titanate (MST) to remove and concentrate the strontium (Sr) and actinides [uranium, plutonium (Pu) and neptunium (Np)] from HLW salt solutions. However, the River Protection Program (RPP) at the Hanford Site in Washington State proposes use of potassium permanganate addition for Sr and actinide removal from RPP HLW. Recent studies at the SRS indicate sodium permanganate treatment holds promise for use in the decontamination of Sr and actinides in SRS HLW.
Download or read book Reactor Fuel Processing written by and published by . This book was released on 1963 with total page 726 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Investigation of the Electrolytic Dissolution of Plutonium written by Robert P. DeGrazio and published by . This book was released on 1978 with total page 6 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Dissolution of High fired Plutonium Oxide written by and published by . This book was released on 1973 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Method for Dissolving Plutonium Oxide with HI and Separating Plutonium written by and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: PuO.sub. 2 -containing solids, particularly residues from incomplete HNO.sub. 3 dissolution of irradiated nuclear fuels, are dissolved in aqueous HI. The resulting solution is evaporated to dryness and the solids are dissolved in HNO.sub. 3 for further chemical reprocessing. Alternatively, the HI solution containing dissolved Pu values, can be contacted with a cation exchange resin causing the Pu values to load the resin. The Pu values are selectively eluted from the resin with more concentrated HI.
Download or read book Nuclear Wastes written by National Research Council and published by National Academies Press. This book was released on 1996-02-23 with total page 590 pages. Available in PDF, EPUB and Kindle. Book excerpt: Disposal of radioactive waste from nuclear weapons production and power generation has caused public outcry and political consternation. Nuclear Wastes presents a critical review of some waste management and disposal alternatives to the current national policy of direct disposal of light water reactor spent fuel. The book offers clearcut conclusions for what the nation should do today and what solutions should be explored for tomorrow. The committee examines the currently used "once-through" fuel cycle versus different alternatives of separations and transmutation technology systems, by which hazardous radionuclides are converted to nuclides that are either stable or radioactive with short half-lives. The volume provides detailed findings and conclusions about the status and feasibility of plutonium extraction and more advanced separations technologies, as well as three principal transmutation concepts for commercial reactor spent fuel. The book discusses nuclear proliferation; the U.S. nuclear regulatory structure; issues of health, safety and transportation; the proposed sale of electrical energy as a means of paying for the transmutation system; and other key issues.
Download or read book Transuranium Elements written by Lester R. Morss and published by . This book was released on 1992 with total page 600 pages. Available in PDF, EPUB and Kindle. Book excerpt: Papers from an international symposium to commemorate the discovery of transuranium elements, held at the 200th ACS National Meeting in Washington, DC, August 1990. Many of the pioneers of transuranium research in the 1940s present papers in a section devoted to historical viewpoints. Contemporary research is addressed with articles in the areas of: spectroscopy, photophysics, and photochemistry; chemistry; separations and thermodynamics; nuclear physics and chemistry; materials physics; materials chemistry; and analytical/chemistry. Acidic paper. Annotation copyrighted by Book News, Inc., Portland, OR
Download or read book Energy Research Abstracts written by and published by . This book was released on 1992 with total page 752 pages. Available in PDF, EPUB and Kindle. Book excerpt:
