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Book THE ISOLATION AND PURIFICATION OF AMERICIUM

Download or read book THE ISOLATION AND PURIFICATION OF AMERICIUM written by and published by . This book was released on 1956 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book The Isolation of Americium 241 in 100 milligram Quantities from Large Amounts of Impurities

Download or read book The Isolation of Americium 241 in 100 milligram Quantities from Large Amounts of Impurities written by Fritz Weigel and published by . This book was released on 1957 with total page 36 pages. Available in PDF, EPUB and Kindle. Book excerpt: The preparation of pure americium samples on the order of 100 mg is described. The type of processing depends largely on the individual starting material. It is most strongly influenced by the presence of lanthanides, especially lanthanum itself, which are difficult to separate from the americium. The separation procedures used on five different starting materials are described, and the efficiency of some separation methods is discussed in view of personal experience.

Book The Isolation and Chemistry of Americium

Download or read book The Isolation and Chemistry of Americium written by Burris Bell Cunningham and published by . This book was released on 1948 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book A Method of Purification of Americium

Download or read book A Method of Purification of Americium written by Keiji Naito and published by . This book was released on 1959 with total page 26 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Ion Exchange Purification of Promethium 147 and Its Separation from Americium 241  with Diethylenetriaminepentaacetic Acid as the Eluant

Download or read book Ion Exchange Purification of Promethium 147 and Its Separation from Americium 241 with Diethylenetriaminepentaacetic Acid as the Eluant written by P. B. Orr and published by . This book was released on 1962 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Americium Purification by a Combined Anion Exchange and Bidentate Organophosphorus Solvent Extraction Process   Patent Application

Download or read book Americium Purification by a Combined Anion Exchange and Bidentate Organophosphorus Solvent Extraction Process Patent Application written by and published by . This book was released on 1981 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Americium is separated from mixtures containing plutonium, other actinides, and other non-lanthamide impurities, by a combined process of anion exchange resin sorption to remove plutonium, and a bidentate organophosphorus solvent extraction of americium of the anion exchange resin effluent. Dihexyl-N, N-diethylcarbamylmethylenephosphonate is a preferred solvent. The initial mixture may be subjected to a cation exchange operation to remove monovalent impurities. The process is especially effective when aluminum, zinc, lead, and copper are present in significant quantities in the original mixture.

Book The Chemistry of Americium

Download or read book The Chemistry of Americium written by Wallace W. Schulz and published by . This book was released on 1976 with total page 312 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book The First Isolation of Americium in the Form of Pure Compounds

Download or read book The First Isolation of Americium in the Form of Pure Compounds written by Burris Bell Cunningham and published by . This book was released on 1951 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Chemical Isolation of Am 240 and the Adsorption of Europium and Americium Using Silica Supported CMPO Calix 4 arenes

Download or read book Chemical Isolation of Am 240 and the Adsorption of Europium and Americium Using Silica Supported CMPO Calix 4 arenes written by Erin Marie Gantz May and published by . This book was released on 2016 with total page 149 pages. Available in PDF, EPUB and Kindle. Book excerpt: My dissertation is composed of two projects. The first area of study was the conclusion of a six-year project to determine the neutron-induced fission cross-section of Am-240. This cross-section is difficult to study due to the 50.8 hour half-life of Am-240 but is important for the evaluation of neutron signatures to establish the history of plutonium-containing materials. Such a study is relevant for the fields of nuclear stockpile stewardship and nuclear forensics. Prior to the study outlined here, much of the ground work for this determination had already been provided, including the identification of the Pu-242(p; 3n)Am-240 reaction for the production of approximately 100 nanograms of Am-240 and the development of a preliminary separation procedure to isolate the Am-240 from the unreacted Pu-242 and the undesirable fission and decay products generated from other reactions with the target. However, many variables in the separation procedure needed further investigation. Therefore, a series of column chromatography experiments was performed to determine which of the two previously designed procedures would provide the best purification of 240Am while minimizing the losses. Once the general outline of the procedure was determined, a collaboration with Idaho National Laboratory (INL) made it possible to further refine and test it. Of the four steps in the originally designed procedure, the final step was among the most difficult to accomplish as it involved the separation of the light trivalent lanthanides from americium. Americium/lanthanide separations are dificult due to their identical oxidation states and very similar ionic radii of americium and the lanthanides. The original step utilized a column composed of TEVA® extraction chromatography resin and a mobile phase composed of ammonium thiocyanate and formic acid. Due to the complexity of this procedure, several alternative procedures were tested at INL with the TRU® resin and a mixture of fission products more representative of those that would be found in the actual target. A gas pressurized extraction chromatography (GPEC) system was used to automate the separation and achieve greater resolution between the lanthanide and americium elution peaks. Ultimately, it was demonstrated that the original TEVA® resin procedure was more reliable than the TRU® resin procedure, however the TRU® GPEC experiments may be relevant for future target material separations. The culmination of this project was the testing of the first step of the procedure with one-tenth of the amount of Pu-242 that will be in the actual target. This experiment, in conjunction with the americium/lanthanide separation steps that were tested, prompted a re-evaluation and abbreviation of the overall separation procedure, decreasing the required number of total separation steps from four to two. Therefore, the purification of Am-240 could be accomplished much more quickly and easily than originally anticipated, making the determination of the neutron-induced fission cross-section of Am-240 more of a reasonable possibility in the future. Part II of my dissertation describes the investigation of the adsorption and complexation properties of silica-anchored carbamoylmethylphophine oxide (CMPO)-calix[4]arenes. In Part I, it was demonstrated that the difficulty encountered when separating trivalent lanthanides and actinides can be a severe impediment to accomplishing even fairly straightforward benchtop radiochemical procedures. Much greater motivation for developing new technologies to achieve this are encountered when considering the mixtures of trivalent actinides and lanthanides produced when irradiated nuclear fuel is reprocessed. CMPO, a ligand that binds indiscriminately with both the trivalent actinides and lanthanides, was attached to a calix[4]arene scaffold, which was then attached via two different methods to a silica surface. In previous studies, it has been shown that the CMPO-calix[4]arene has a greater affinity for americium than europium. The experiments in this work aimed to establish whether this relationship held for CMPO-calix[4]arenes anchored in two new ways to the silica surface. It was found that, for a very particular set of conditions - high salt concentration and an aqueous solution pH of 3 - that a CMPO-calix[4]arene very rigidly anchored to the surface of the silica displayed extremely high uptake for Eu(III)when sites outnumbered the number of Eu(III) atoms by at least 10 to 1. This was not found when the same material and conditions were tested with Am(III) nor when the more flexibly anchored CMPO-calix[4]arene material and conditions were tested, leading to the conclusion that both the aqueous solution conditions and the rigidity of the grafted site affect the affinity of the CMPO-calix[4]arene toward cations of interest. The optimization of the CMPO-calix[4]arene system could have been potentially useful for Part I of this dissertation for separating americium and the lanthanides, had it existed at the time, and could eventually be applied to the separation of trivalent actinides and lanthanides at the conclusion of nuclear fuel reprocessing. Part I and Part II contribute to two different areas of actinide/lanthanide separation research, with Part I focused on optimizing existing resin systems to achieve separation and Part II focused on testing new materials specifically intended for separating trivalent actinides and lanthanides. Part I shows that existing resin systems can be used to rapidly purify a very small amount of americium from much greater amounts of plutonium, the lanthanides, and other elements. Part II demonstrates that the affinity of a grafted CMPO-calix[4]arene site for either trivalent actinides or lanthanides can be tailored based on the rigidity of the grafting to the solid and the aqueous phase conditions. Separately, it is hoped that these studies can be applied to work focused on detailed actinide target material purification and new innovations in actinide/lanthanide separations, respectively. However, it is also hoped that, cumulatively, these studies contribute to a broader understanding of actinide and lanthanide interactions with ligands designed to effect their separation, both for benchtop laboratory separations and nuclear fuel reprocessing.

Book Americium Recovery and Purification at Rocky Flats

Download or read book Americium Recovery and Purification at Rocky Flats written by and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Americium processing at Rocky Flats Plant is described. The americium is recovered from plutonium metal by a pyrochemical process; the resulting molten salt extraction residues must be processed to recover americium. At present the process uses cation exchange with Dowex 50W-X8 resin, This work shows that a macroporous resin, BioRad AG MP-50, has 30 to 50% more capacity and better elution kinetics than Dowex 50W-X8. Two extraction methods, solvent extraction and extraction chromatography with an organophoshorus bidentate, are also described. Americium is effectively decontaminated from magnesium and aluminum, and recovered by these methods.

Book The Isolation of Americium 241

    Book Details:
  • Author : Atomic Energy Research Establishment (Harwell, England)
  • Publisher :
  • Release : 1955
  • ISBN :
  • Pages : 0 pages

Download or read book The Isolation of Americium 241 written by Atomic Energy Research Establishment (Harwell, England) and published by . This book was released on 1955 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Isolation and Propterties of Curium

Download or read book Isolation and Propterties of Curium written by and published by . This book was released on 1948 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The isolation of curium, element number 96, in relatively pure form has been accomplished. A method, involving a solvent extraction process, is given for the purification of americium from lanthanum and other ions. The discovery of a higher oxidation state of americium led to a method of separating americium from curium. Separation of the two elements was also accomplished by use of ion exchange resins. The details of the isolation of curium are given; the results of the spectrographic analysis, specific activity measurement, and calorimetric determination of half life showed the curium to be relatively pure. The absorption of light of various wave-lengths by an aqueous solution of Cm(III) is described, and some physical effects of the radiation from the curium are noted.

Book The Isolation and Properties of Curium

Download or read book The Isolation and Properties of Curium written by and published by . This book was released on 1948 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The isolation of curium, element number 96, in relatively pure form has been accomplished. A method, involving a solvent extraction process, is given for the purification of americium from lanthanum and other ions. The discovery of a higher oxidation state of americium led to a method of separating americium from curium. Separation of the two elements was also accomplished by use of ion exchange resins. The details of the isolation of curium are given; the results of the spectrographic analysis, specific activity measurement, and calorimetric determination of half life showed the curium to be relatively pure. The absorption of light of various wave-lengths by an aqueous solution of Cm(III) is described, and some physical effects of the radiation from the curium are noted.

Book Molten Salt Extraction of Americium from Molten Plutonium Metal

Download or read book Molten Salt Extraction of Americium from Molten Plutonium Metal written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The chemical basis for molten salt extraction separation of americium from plutonium is presented. The extraction factor relationship is used to quantify this liquid-liquid extraction (molten salt-molten metal) unit operation. The amount of salt required for an optimum process is an order of magnitude lower than the amount used previously in the production operation of the process.

Book THE FIRST ISOLATION OF AMERICIUM IN THE FORM OF PURE COMPOUNDS   THE SPECIFIC ALPHA ACTIVITY AND HALF LIFE OF Am241

Download or read book THE FIRST ISOLATION OF AMERICIUM IN THE FORM OF PURE COMPOUNDS THE SPECIFIC ALPHA ACTIVITY AND HALF LIFE OF Am241 written by and published by . This book was released on 1950 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The microgram scale isolation and preparation of pure compounds of americium is described. Data are presented to show that the alpha-half-life of the isotope Am241 is 490 ± 14 years. The absorption spectrum of Am(III) in 1M nitric acid in the range 3500-8000 mu is given. The wave lengths of 10 of the most prominent lines in the copper spark emission spectrum of americium are given to the nearest 0.01 Å. Evidence is presented to show that the potential for the Am(III)-Am(IV) couple in acid solution is more negative than -2v and that the potential for the Am(II)-Am(III) couple is more positive than +0.9v.