Sample records for promethium

  1. Chromatographic extraction with di(2-ethylhexyl)orthophosphoric acid for production and purification of promethium-147

    DOEpatents

    Boll, Rose A [Knoxville, TN; Mirzadeh, Saed [Knoxville, TN

    2008-10-14

    A method of producing and purifying promethium-147 including the steps of: irradiating a target material including neodymium-146 with neutrons to produce promethium-147 within the irradiated target material; dissolving the irradiated target material to form an acidic solution; loading the acidic solution onto a chromatographic separation apparatus containing HDEHP; and eluting the apparatus to chromatographically separate the promethium-147 from the neodymium-146.

  2. THE RARE EARTH ELEMENTS THULIUM AND PROMETHIUM BECOME TECHNICALLY VALUABLE

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Kogan, B.I.

    1957-01-01

    A survey of non-Slavic (mainly American) literature on thulium and promethium is given. Their preparation, propenties, and uses are considered. Thulium is used in flow detection, and promethium is used in miniature batteries. 20 references. (TCO)

  3. 10 CFR 32.22 - Self-luminous products containing tritium, krypton-85 or promethium-147: Requirements for license...

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... promethium-147: Requirements for license to manufacture, process, produce, or initially transfer. 32.22 Section 32.22 Energy NUCLEAR REGULATORY COMMISSION SPECIFIC DOMESTIC LICENSES TO MANUFACTURE OR TRANSFER... containing tritium, krypton-85 or promethium-147: Requirements for license to manufacture, process, produce...

  4. SEPARATION OF AMERICIUM FROM PROMETHIUM

    DOEpatents

    Pressly, R.E.

    1959-07-01

    Promethium-147 is separated from americium in acidic aqueous solution by adding fluosilicic acid to the solution, heating the solution to form a promethium precipitate and separating the precipitate from solution. The precipitate is then re-dissolved by ihe addition of boric acid and nitric acid, and re-precipitated by the addition of fluosilicic acid. This procedure is repeated six or more times to obtain a relatively americium-free promeihium precipitate. Americium may be separately recovered from the supernatant liquids. This process is applicable to the recovery of promethium from fission-product solutions which have been allowed to decay for a period of two to four years.

  5. Sparkle/AM1 Parameters for the Modeling of Samarium(III) and Promethium(III) Complexes.

    PubMed

    Freire, Ricardo O; da Costa, Nivan B; Rocha, Gerd B; Simas, Alfredo M

    2006-01-01

    The Sparkle/AM1 model is extended to samarium(III) and promethium(III) complexes. A set of 15 structures of high crystallographic quality (R factor < 0.05 Å), with ligands chosen to be representative of all samarium complexes in the Cambridge Crystallographic Database 2004, CSD, with nitrogen or oxygen directly bonded to the samarium ion, was used as a training set. In the validation procedure, we used a set of 42 other complexes, also of high crystallographic quality. The results show that this parametrization for the Sm(III) ion is similar in accuracy to the previous parametrizations for Eu(III), Gd(III), and Tb(III). On the other hand, promethium is an artificial radioactive element with no stable isotope. So far, there are no promethium complex crystallographic structures in CSD. To circumvent this, we confirmed our previous result that RHF/STO-3G/ECP, with the MWB effective core potential (ECP), appears to be the most efficient ab initio model chemistry in terms of coordination polyhedron crystallographic geometry predictions from isolated lanthanide complex ion calculations. We thus generated a set of 15 RHF/STO-3G/ECP promethium complex structures with ligands chosen to be representative of complexes available in the CSD for all other trivalent lanthanide cations, with nitrogen or oxygen directly bonded to the lanthanide ion. For the 42 samarium(III) complexes and 15 promethium(III) complexes considered, the Sparkle/AM1 unsigned mean error, for all interatomic distances between the Ln(III) ion and the ligand atoms of the first sphere of coordination, is 0.07 and 0.06 Å, respectively, a level of accuracy comparable to present day ab initio/ECP geometries, while being hundreds of times faster.

  6. 10 CFR 30.72 - Schedule C-Quantities of radioactive materials requiring consideration of the need for an...

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... Molybdenum-99 .01 30,000 Neptunium-237 .001 2 Nickel-63 .01 20,000 Niobium-94 .01 300 Phosphorus-32 .5 100 Phosphorus-33 .5 1,000 Polonium-210 .01 10 Potassium-42 .01 9,000 Promethium-145 .01 4,000 Promethium-147 .01...

  7. 10 CFR 30.72 - Schedule C-Quantities of radioactive materials requiring consideration of the need for an...

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... Molybdenum-99 .01 30,000 Neptunium-237 .001 2 Nickel-63 .01 20,000 Niobium-94 .01 300 Phosphorus-32 .5 100 Phosphorus-33 .5 1,000 Polonium-210 .01 10 Potassium-42 .01 9,000 Promethium-145 .01 4,000 Promethium-147 .01...

  8. 10 CFR 32.22 - Self-luminous products containing tritium, krypton-85 or promethium-147: Requirements for license...

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... promethium-147: Requirements for license to manufacture, process, produce, or initially transfer. 32.22 Section 32.22 Energy NUCLEAR REGULATORY COMMISSION SPECIFIC DOMESTIC LICENSES TO MANUFACTURE OR TRANSFER..., or initially transfer. (a) An application for a specific license to manufacture, process, or produce...

  9. Synthesis and preliminary biological evaluations of fluorescent or 149Promethium labeled Trastuzumab-polyethylenimine

    DOE PAGES

    Fitzsimmons, Jonathan; Nayak, Tapan; Cutler, Cathy; ...

    2015-12-30

    Radioimmunotherapy utilize a targeting antibody coupled to a therapeutic isotope to target and treat a tumor or disease. In this study we examine the synthesis and cell binding of a polymer scaffold containing a radiotherapeutic isotope and a targeting antibody. Methods: The multistep synthesis of a fluorescent or 149Promethium-labeled Trastuzumab-polyethyleneimine (PEI), Trastuzumab, or PEI is described. In vitro uptake, internalization and/or the binding affinity to the Her2/neu expressing human breast adenocarcinoma SKBr3 cells was investigated with the labeled compounds. Fluorescent-labeled Trastuzumab-PEI was internalized more into cells at 2 and 18 h than fluorescent-labeled Trastuzumab or PEI. The fluorescent-labeled Trastuzumab wasmore » concentrated on the cell surface at 2 and 18 h and the labeled PEI had minimal uptake. DOTA-PEI was prepared and contained an average of 16 chelates per PEI; the compound was radio-labeled with 149Promethium and conjugated to Trastuzumab. The purified 149Pm-DOTA-PEI-Trastuzumab had a radiochemical purity of 96.7% and a specific activity of 0.118 TBq/g. The compound demonstrated a dissociation constant for the Her2/neu receptor of 20.30 ± 6.91 nM. In conclusion, the results indicate the DOTA-PEI-Trastuzumab compound has potential as a targeted therapeutic carrier, and future in vivo studies should be performed.« less

  10. 10 CFR 20.2206 - Reports of individual monitoring.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... quantitites: Radionuclide Quantity of radionuclide 1 in curies Cesium-137 1 Cobalt-60 1 Gold-198 100 Iodine-131 1 Iridium-192 10 Krypton-85 1,000 Promethium-147 10 Techetium-99m 1,000 1 The Commission may...

  11. 10 CFR 20.2206 - Reports of individual monitoring.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... quantitites: Radionuclide Quantity of radionuclide 1 in curies Cesium-137 1 Cobalt-60 1 Gold-198 100 Iodine-131 1 Iridium-192 10 Krypton-85 1,000 Promethium-147 10 Techetium-99m 1,000 1 The Commission may...

  12. 10 CFR 32.22 - Self-luminous products containing tritium, krypton-85 or promethium-147: Requirements for license...

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... exceed 10 square centimeters, and the method of measurement. (vii) Degree of access of human beings to... product. (iv) Solubility in water and body fluids of the forms of the byproduct material identified in...

  13. 10 CFR 30.15 - Certain items containing byproduct material.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... electrical currents. (9) Ionizing radiation measuring instruments containing, for purposes of internal... material and not exceeding the following specified levels of radiation: (i) 25 millicuries of tritium per... considered as part of the dial), (vii) The levels of radiation from hands and dials containing promethium 147...

  14. Comparative biokinetics of trivalent radionuclides with similar ionic dimensions: promethium-147, curium-242 and americium-241.

    PubMed

    Priest, N D

    2007-09-01

    Data on the distribution and redistribution patterns in the laboratory rat of three trivalent elements with a similar ionic radius have been compared. This showed that these distributions for the two ions with the same ionic radius (111 pm), i.e., those of promethium (a lanthanoid) and curium (an actinoid), were indistinguishable and that americium, with a slightly larger ion size (111.5 pm), behaved similarly. The results are consistent with the suggestion that ion size is the only important factor controlling the deposition and redistribution patterns of trivalent lanthanoids and actinoids in rats. The result is important because it suggests that the same radiological protection dosimetry models should be used for trivalent actinoids and lanthanoids, that human volunteer data generated for lanthanoid isotopes can be used to predict the behavior of actinoids with the same ion size, and that appropriate pairs of beta-particle-emitting lanthanoid and alpha-particle-emitting actinoids could be used to study the relative toxicity of alpha and beta particles in experimental animals.

  15. 10 CFR 32.53 - Luminous safety devices for use in aircraft: Requirements for license to manufacture, assemble...

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... maximum quantity of tritium or promethium-147 in each device; (2) Details of construction and design; (3... information, including experimental studies and tests, required by the Commission to facilitate a... direct physical contact by any person with it; (3) The device is so designed that it cannot easily be...

  16. 10 CFR 32.53 - Luminous safety devices for use in aircraft: Requirements for license to manufacture, assemble...

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... maximum quantity of tritium or promethium-147 in each device; (2) Details of construction and design; (3... information, including experimental studies and tests, required by the Commission to facilitate a... direct physical contact by any person with it; (3) The device is so designed that it cannot easily be...

  17. Rare Earths; The Fraternal Fifteen (Rev.)

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Gschneidner, Jr., Karl A.

    1966-01-01

    Rare earths are a set of 15 elements: lanthanum, cerium, praseodymium, neodymium, promethium, samarium, europium, gadolinium, terbium, dysprosium, holmium, erbium, thulium, ytterbium and lutetium. They are not rare and not earths; they are metals and quite abundant. They are studied to develop commercial products which are beneficial to mankind, and because some rare earths are important to fission products.

  18. HAZARDS SUMMARY REPORT FOR A TWO WATT PROMETHIUM-147 FUELED THERMOELECTRIC GENERATOR

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    None

    1959-06-01

    Discussions are included of the APU design, vehicle integration, Pm/sup 147/ properties, shielding requirements, hazards design criteria, statistical analysis for impact, and radiation protection. The use of Pm/sup 147/ makes possible the fabrication of an auxiliary power unit which has applications for low power space missions of <10 watts (electrical). (B.O.G.)

  19. 10 CFR 32.53 - Luminous safety devices for use in aircraft: Requirements for license to manufacture, assemble...

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... maximum quantity of tritium or promethium-147 in each device; (2) Details of construction and design; (3... experimental studies and tests, required by the Commission to facilitate a determination of the safety of the... contact by any person with it; (3) The device is so designed that it cannot easily be disassembled; and (4...

  20. 10 CFR 32.53 - Luminous safety devices for use in aircraft: Requirements for license to manufacture, assemble...

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... maximum quantity of tritium or promethium-147 in each device; (2) Details of construction and design; (3... experimental studies and tests, required by the Commission to facilitate a determination of the safety of the... contact by any person with it; (3) The device is so designed that it cannot easily be disassembled; and (4...

  1. 10 CFR 32.53 - Luminous safety devices for use in aircraft: Requirements for license to manufacture, assemble...

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... maximum quantity of tritium or promethium-147 in each device; (2) Details of construction and design; (3... experimental studies and tests, required by the Commission to facilitate a determination of the safety of the... contact by any person with it; (3) The device is so designed that it cannot easily be disassembled; and (4...

  2. Identification of Radiation Sources in a Peacetime Environment

    DTIC Science & Technology

    1998-04-01

    Radionuclides in Medicine, Research, and Industry (continued) Isotope Symbol Polonium - 210 Po- 210 Promethium-147 Pr-147 Radium-226 Ra-226 Selenium-75 Se...Defense Intelligence Document Prepared by: Epidemiology and Environmental Health Division Armed Forces Medical Intelligence Center Defense...1811-1-96, May 1996, which should be destroyed. 2 I o % m > 1 >* This product responds to U.S. Army Center for Health Promotion and

  3. Experimental determination of water activity for binary aqueous cerium(III) ionic solutions: application to an assessment of the predictive capability of the binding mean spherical approximation model.

    PubMed

    Ruas, Alexandre; Simonin, Jean-Pierre; Turq, Pierre; Moisy, Philippe

    2005-12-08

    This work is aimed at a description of the thermodynamic properties of actinide salt solutions at high concentration. The predictive capability of the binding mean spherical approximation (BIMSA) theory to describe the thermodynamic properties of electrolytes is assessed in the case of aqueous solutions of lanthanide(III) nitrate and chloride salts. Osmotic coefficients of cerium(III) nitrate and chloride were calculated from other lanthanide(III) salts properties. In parallel, concentrated binary solutions of cerium nitrate were prepared in order to measure experimentally its water activity and density as a function of concentration, at 25 degrees C. Water activities of several binary solutions of cerium chloride were also measured to check existing data on this salt. Then, the properties of cerium chloride and cerium nitrate solutions were compared within the BIMSA model. Osmotic coefficient values for promethium nitrate and promethium chloride given by this theory are proposed. Finally, water activity measurements were made to examine the fact that the ternary system Ce(NO3)3/HNO3/H2O and the quaternary system Ce(NO3)3/HNO3/N2H5NO3/H2O may be regarded as "simple solutions" (in the sense of Zdanovskii and Mikulin).

  4. Promethium-147 capacitor.

    PubMed

    Kavetskiy, A; Yakubova, G; Lin, Q; Chan, D; Yousaf, S M; Bower, K; Robertson, J D; Garnov, A; Meier, D

    2009-06-01

    Beta particle surface fluxes for tritium, Ni-63, Pm-147, and Sr-90 sources were calculated in this work. High current density was experimentally achieved from Pm-147 oxide in silica-titana glass. A 96 GBq (2.6 Ci) Pm-147 4pi-source with flux efficiency greater than 50% was used for constructing a direct charge capacitor with a polyimide coated collector and vacuum as electrical insulation. The capacitor connected to high resistance (TOmega) loads produced up to 35 kV. Overall conversion efficiency was over 10% (on optimal load).

  5. Effect of lanthanides on the aromatic system of benzoic acid

    NASA Astrophysics Data System (ADS)

    Lewandowski, Włlodzimierz

    1983-08-01

    The stucture of lanthanide complexes with benzoic acid was investigated by IR and UV absorption spectra. To determine the effect of metal coordination on the aromatic system of benzoic acid, IR spectra of Ln(OBz) 3 (Ln is a lanthanide except promethium; BzO is benzoic acid radical) were compared with ligand and sodium benzoate spectra. Also, changes in frequency and relative intensity of the ? bands in the 1600-1400 cm -1 region, were analyzed in terms of the atomic number of lanthanides. It is shown that lanthanides disturb the aromatic system of the benzoate ligand less than sodium. This effect is discussed in terms of the bonds formed.

  6. Blast-wave density measurements

    NASA Astrophysics Data System (ADS)

    Ritzel, D. V.

    Applications of a densitometer to obtain time-resolved data on the total density in blast-wave flows are described. A beta-source (promethium-147) is separated by a gap from a scintillator and a photomultiplier tube (PMT). Attenuation of the radiation beam by the passing blast wave is due to the total density in the gap volume during the wave passage. Signal conditioning and filtering methods permit the system to output linearized data. Results are provided from use of the system to monitor blast waves emitted by detonation of a 10.7 m diameter fiberglass sphere containing 609 tons of ammonium nitrate/fuel oil at a 50.6 m height. Blast wave density data are provided for peak overpressure levels of 245, 172 and 70 kPa and distances of 183, 201 and 314 m from ground zero. Data resolution was of high enough quality to encourage efforts to discriminate dust and gasdynamic phenomena within passing blast waves.

  7. Silicon Carbide Radioisotope Batteries

    NASA Technical Reports Server (NTRS)

    Rybicki, George C.

    2005-01-01

    The substantial radiation resistance and large bandgap of SiC semiconductor materials makes them an attractive candidate for application in a high efficiency, long life radioisotope battery. To evaluate their potential in this application, simulated batteries were constructed using SiC diodes and the alpha particle emitter Americium Am-241 or the beta particle emitter Promethium Pm-147. The Am-241 based battery showed high initial power output and an initial conversion efficiency of approximately 16%, but the power output decayed 52% in 500 hours due to radiation damage. In contrast the Pm-147 based battery showed a similar power output level and an initial conversion efficiency of approximately 0.6%, but no degradation was observed in 500 hours. However, the Pm-147 battery required approximately 1000 times the particle fluence as the Am-242 battery to achieve a similar power output. The advantages and disadvantages of each type of battery and suggestions for future improvements will be discussed.

  8. Si--Au Schottky barrier nuclear battery

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Tse, Anthony N.

    1972-11-01

    A long-life, high-power-density, high-reliability, compact microwatt battery is needed in many applications. In the field of medicine, for example, such a battery could power an artificial pacemaker which would greatly extend the residence time of the device. Various alternatives are analyzed and discussed. Betavoltaic conversion systems with Si-Au Schottky barrier cells coupled with 147Pm metal foil were selected for investigation. Characterization experiments were performed to obtain optimized silicon resistivity and promethium metal foil thickness. Radiation dose rates were measured and the safety aspects of the battery were analyzed. A prototype battery was assembled and tested. The economics of the batterymore » were demonstrated for special applications. It is concluded that a microwatt nuclear battery can be built with a conversion efficiency of 1 to 2%, a power density of 60 to 300 pW/cm 3 depending on the power level, and a useful life of 5 to 10 years. Further research areas are recommended.« less

  9. Antibacterial, Antifungal and Nematicidal Activities of Rare Earth Ions.

    PubMed

    Wakabayashi, Tokumitsu; Ymamoto, Ayumi; Kazaana, Akira; Nakano, Yuta; Nojiri, Yui; Kashiwazaki, Moeko

    2016-12-01

    Despite the name, rare earth elements are relatively abundant in soil. Therefore, these elements might interact with biosphere during the history of life. In this study, we have examined the effect of rare earth ions on the growth of bacteria, fungi and soil nematode. All rare earth ions, except radioactive promethium that we have not tested, showed antibacterial and antifungal activities comparable to that of copper ions, which is widely used as antibacterial metals in our daily life. Rare earth ions also have nematicidal activities as they strongly perturb the embryonic development of the nematode, Caenorhabditis elegans. Interestingly, the nematicidal activity increased with increasing atomic number of lanthanide ions. Since the rare earth ions did not show high toxicity to the human lymphoblastoid cell line or even stimulate the growth of the cultured cells at 1 mM, it raised the possibility that we can substitute rare earth elements for the antibacterial metals usually used because of their safety.

  10. Plasma separation process. Betacell (BCELL) code, user's manual

    NASA Astrophysics Data System (ADS)

    Taherzadeh, M.

    1987-11-01

    The emergence of clearly defined applications for (small or large) amounts of long-life and reliable power sources has given the design and production of betavoltaic systems a new life. Moreover, because of the availability of the Plasma Separation Program, (PSP) at TRW, it is now possible to separate the most desirable radioisotopes for betacell power generating devices. A computer code, named BCELL, has been developed to model the betavoltaic concept by utilizing the available up-to-date source/cell parameters. In this program, attempts have been made to determine the betacell energy device maximum efficiency, degradation due to the emitting source radiation and source/cell lifetime power reduction processes. Additionally, comparison is made between the Schottky and PN junction devices for betacell battery design purposes. Certain computer code runs have been made to determine the JV distribution function and the upper limit of the betacell generated power for specified energy sources. A Ni beta emitting radioisotope was used for the energy source and certain semiconductors were used for the converter subsystem of the betacell system. Some results for a Promethium source are also given here for comparison.

  11. Plasma Separation Process: Betacell (BCELL) code: User's manual. [Bipolar barrier junction

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Taherzadeh, M.

    1987-11-13

    The emergence of clearly defined applications for (small or large) amounts of long-life and reliable power sources has given the design and production of betavoltaic systems a new life. Moreover, because of the availability of the plasma separation program, (PSP) at TRW, it is now possible to separate the most desirable radioisotopes for betacell power generating devices. A computer code, named BCELL, has been developed to model the betavoltaic concept by utilizing the available up-to-date source/cell parameters. In this program, attempts have been made to determine the betacell energy device maximum efficiency, degradation due to the emitting source radiation andmore » source/cell lifetime power reduction processes. Additionally, comparison is made between the Schottky and PN junction devices for betacell battery design purposes. Certain computer code runs have been made to determine the JV distribution function and the upper limit of the betacell generated power for specified energy sources. A Ni beta emitting radioisotope was used for the energy source and certain semiconductors were used for the converter subsystem of the betacell system. Some results for a Promethium source are also given here for comparison. 16 refs.« less

  12. Rare-earth metal prices in the USA ca. 1960 to 1994

    USGS Publications Warehouse

    Hedrick, James B.

    1997-01-01

    Rare-earth metal prices were compiled from the late 1950s and early 1960s through 1994. Although commercial demand for rare-earth metals began in 1908, as the alloy mischmetal, commercial quantities of a wide range of individual rare-earth metals were not available until the late 1950s. The discovery of a large, high-grade rare-earth deposit at Mountain Pass. CA, USA, in 1949, was significant because it led to the production of commercial quantities or rare-earth elements that reduced prices and encouraged wider application of the materials. The availability of ore from Mountain Pass, and other large rare-earth deposits, especially those in Australia and China, has provided the world with abundant resources for rare-earth metal production. This availability, coupled with improved technology from Government and private-sector metallurgical research, has resulted in substantial decreases in rare-earth metal prices since the late 1950s and early 1960s. Price series for the individual rare-earth metals (except promethium) are quoted on a kilogram basis from the late 1950s and early 1960s through 1994. Prices are given in US dollars on an actual and constant dollar basis. Industrial and economic factors affecting prices during this time period are examined.

  13. Rare-earth metal prices in the USA ca. 1960 to 1994

    USGS Publications Warehouse

    Hedrick, J.B.

    1997-01-01

    Rare-earth metal prices were compiled from the late 1950s and early 1960s through 1994. Although commercial demand for rare-earth metals began in 1908, as the alloy mischmetal, commercial quantities of a wide range of individual rare-earth metals were not available until the late 1950s. The discovery of a large, high-grade rare-earth deposit at Mountain Pass, CA, USA, in 1949, was significant because it led to the production of commercial quantities of rare-earth elements that reduced prices and encouraged wider application of the materials. The availability of ore from Mountain Pass, and other large rare-earth deposits, especially those in Australia and China, has provided the world with abundant resources for rare-earth metal production. This availability, coupled with improved technology from Government and private-sector metallurgical research, has resulted in substantial decreases in rare-earth metal prices since the late 1950s and early 1960s. Price series for the individual rare-earth metals (except promethium) are quoted on a kilogram basis from the late 1950s and early 1960s through 1994. Prices are given in US dollars on an actual and constant dollar basis. Industrial and economic factors affecting prices during this time period are examined.

  14. Strategic Materials in the Automobile: A Comprehensive Assessment of Strategic and Minor Metals Use in Passenger Cars and Light Trucks.

    PubMed

    Field, Frank R; Wallington, Timothy J; Everson, Mark; Kirchain, Randolph E

    2017-12-19

    A comprehensive component-level assessment of several strategic and minor metals (SaMMs), including copper, manganese, magnesium, nickel, tin, niobium, light rare earth elements (LREEs; lanthanum, cerium, praseodymium, neodymium, promethium, and samarium), cobalt, silver, tungsten, heavy rare earth elements (yttrium, europium, gadolinium, terbium, dysprosium, holmium, erbium, thulium, ytterbium, and lutetium), and gold, use in the 2013 model year Ford Fiesta, Focus, Fusion, and F-150 is presented. Representative material contents in cars and light-duty trucks are estimated using comprehensive, component-level data reported by suppliers. Statistical methods are used to accommodate possible errors within the database and provide estimate bounds. Results indicate that there is a high degree of variability in SaMM use and that SaMMs are concentrated in electrical, drivetrain, and suspension subsystems. Results suggest that trucks contain greater amounts of aluminum, nickel, niobium, and silver and significantly greater amounts of magnesium, manganese, gold, and LREEs. We find tin and tungsten use in automobiles to be 3-5 times higher than reported by previous studies which have focused on automotive electronics. Automotive use of strategic and minor metals is substantial, with 2013 vehicle production in the United States, Canada, EU15, and Japan alone accounting for approximately 20% of global production of Mg and Ta and approximately 5% of Al, Cu, and Sn. The data and analysis provide researchers, recyclers, and decision-makers additional insight into the vehicle content of strategic and minor metals of current interest.

  15. The Effects of Trivalent Lanthanide Cationization on the Electron Transfer Dissociation of Acidic Fibrinopeptide B and its Analogs

    NASA Astrophysics Data System (ADS)

    Commodore, Juliette J.; Cassady, Carolyn J.

    2016-09-01

    Electrospray ionization (ESI) on mixtures of acidic fibrinopeptide B and two peptide analogs with trivalent lanthanide salts generates [M + Met + H]4+, [M + Met]3+, and [M + Met -H]2+, where M = peptide and Met = metal (except radioactive promethium). These ions undergo extensive and highly efficient electron transfer dissociation (ETD) to form metallated and non-metallated c- and z-ions. All metal adducted product ions contain at least two acidic sites, which suggest attachment of the lanthanide cation at the side chains of one or more acidic residues. The three peptides undergo similar fragmentation. ETD on [M + Met + H]4+ leads to cleavage at every residue; the presence of both a metal ion and an extra proton is very effective in promoting sequence-informative fragmentation. Backbone dissociation of [M + Met]3+ is also extensive, although cleavage does not always occur between adjacent glutamic acid residues. For [M + Met - H ]2+, a more limited range of product ions form. All lanthanide metal peptide complexes display similar fragmentation except for europium (Eu). ETD on [M + Eu - H]2+ and [M + Eu]3+ yields a limited amount of peptide backbone cleavage; however, [M + Eu + H]4+ dissociates extensively with cleavage at every residue. With the exception of the results for Eu(III), metallated peptide ion formation by ESI, ETD fragmentation efficiencies, and product ion formation are unaffected by the identity of the lanthanide cation. Adduction with trivalent lanthanide metal ions is a promising tool for sequence analysis of acidic peptides by ETD.

  16. THE USE OF QUENCHING IN A LIQUID SCINTILLATION COUNTER FOR QUANTITATIVE ANALYSIS

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Foster, G.V.

    1963-01-01

    Quenching was used to quantitatively determine the amonnt of quenching agent present. A sealed promethium147 source was prepared to be used for the count rate determinations. Two methods to determine the amount of quenching agent present in a sample were developed. One method related the count rate of a sample containing a quenching agent to the amount of quenching agent present. Calibration curves were plotted using both color and chemical quenchers. The quenching agents used were: F.D.C. Orange No. 2, F.D.C. Yellow No. 3, F.D.C. Yellow No. 4, Scarlet Red, acetone, benzaldehyde, and carbon tetrachloride. the color quenchers gave amore » linear-relationship, while the chemical quenchers gave a non-linear relationship. Quantities of the color quenchers between about 0.008 mg and 0.100 mg can be determined with an error less than 5%. The calibration curves were found to be usable over a long period of time. The other method related the change in the ratio of the count rates in two voltage windows to the amount of quenching agent present. The quenchers mentioned above were used. Calibration curves were plotted for both the color and chemical quenchers. The relationships of ratio versus amount of quencher were non-linear in each case. It was shown that the reproducibility of the count rate and the ratio was independent of the amount of quencher present but was dependent on the count rate. At count rates above 10,000 counts per minute the reproducibility was better than 1%. (TCO)« less

  17. New reversed phase-high performance liquid chromatographic method for selective separation of yttrium from all rare earth elements employing nitrilotriacetate complexes in anion exchange mode.

    PubMed

    Dybczyński, Rajmund S; Kulisa, Krzysztof; Pyszynska, Marta; Bojanowska-Czajka, Anna

    2015-03-20

    Separation of Y from other rare earth elements (REE) is difficult because of similarity of its ionic radius to ionic radii of Tb, Dy and Ho. In the new RP-HPLC system with C18 column, tetra-n-butyl ammonium hydroxide (TBAOH) as an ion interaction reagent (IIR), nitrilotriacetic acid (NTA) as a complexing agent at pH=2.8-3.5, and post column derivatization with Arsenazo III, yttrium is eluted in the region of light REE, between Nd and Sm and is base line separated from Nd and Sm and even from promethium. Simple model employing literature data on complex formation of REE with NTA and based on anion exchange mechanism was developed to foresee the order of elution of individual REE. The model correctly predicted that lanthanides up to Tb will be eluted in the order of increasing Atomic Number (At.No.) but all heavier REE will show smaller retention factors than Tb. Concurrent UV/VIS detection at 658nm and the use of radioactive tracers together with γ-ray spectrometric measurements made possible to establish an unique elution order of elution of REE: La, Ce, Pr, Nd, Pm, Y, Sm, Er, Ho, Tm, Yb, Eu, Lu, Dy+Gd, Tb, Sc. The real place of Y however, in this elution series differs from that predicted by the model (Y between Sm and Eu). The method described in this work enables selective separation of Y from La, Ce, Pr, Nd, Pm, Sm and all heavier REE treated as a group. Copyright © 2015 Elsevier B.V. All rights reserved.

  18. China's rare-earth industry

    USGS Publications Warehouse

    Tse, Pui-Kwan

    2011-01-01

    Introduction China's dominant position as the producer of over 95 percent of the world output of rare-earth minerals and rapid increases in the consumption of rare earths owing to the emergence of new clean-energy and defense-related technologies, combined with China's decisions to restrict exports of rare earths, have resulted in heightened concerns about the future availability of rare earths. As a result, industrial countries such as Japan, the United States, and countries of the European Union face tighter supplies and higher prices for rare earths. This paper briefly reviews China's rare-earth production, consumption, and reserves and the important policies and regulations regarding the production and trade of rare earths, including recently announced export quotas. The 15 lanthanide elements-lanthanum, cerium, praseodymium, neodymium, promethium, samarium, europium, gadolinium, terbium, dysprosium, holmium, erbium, thulium, ytterbium, and lutetium (atomic numbers 57-71)-were originally known as the rare earths from their occurrence in oxides mixtures. Recently, some researchers have included two other elements-scandium and yttrium-in their discussion of rare earths. Yttrium (atomic number 39), which lies above lanthanum in transition group III of the periodic table and has a similar 3+ ion with a noble gas core, has both atomic and ionic radii similar in size to those of terbium and dysprosium and is generally found in nature with lanthanides. Scandium (atomic number 21) has a smaller ionic radius than yttrium and the lanthanides, and its chemical behavior is intermediate between that of aluminum and the lanthanides. It is found in nature with the lanthanides and yttrium. Rare earths are used widely in high-technology and clean-energy products because they impart special properties of magnetism, luminescence, and strength. Rare earths are also used in weapon systems to obtain the same properties.

  19. The space experiment CERASP: Definition of a space-suited radiation source and growth conditions for human cells

    NASA Astrophysics Data System (ADS)

    Hellweg, Christine E.; Baumstark-Khan, Christa; Spitta, Luis; Thelen, Melanie; Arenz, Andrea; Franz, Markus; Schulze-Varnholt, Dirk; Berger, Thomas; Reitz, Günther

    The combined action of ionizing radiation and microgravity will continue to influence future space missions, with special risks for astronauts on the Moon surface or for long duration missions to Mars. It has been estimated that on a 3-year mission to Mars about 3% of the bodies' cell nuclei would have been hit by one iron ion with the consequence that nuclear DNA will be heavily damaged. There is increasing evidence that basic cellular functions are sensitive not only to radiation but also to microgravity. DNA repair studies in space on bacteria, yeast cells and human fibroblasts, which were irradiated before, flight, gave contradictory results: from inhibition of repair by microgravity to enhancement, whereas others did not detect any influence of microgravity on repair. The space experiment CERASP (CEllular Responses to RAdiation in SPace) to be performed at the International Space Station (ISS) is aimed to supply basic information on the cellular response in microgravity to radiation applied during flight. It makes use of a recombinant human cell line as reporter for cellular signal transduction modulation by genotoxic environmental conditions. The main biological endpoints under investigation will be gene activation based on enhanced green fluorescent protein (EGFP, originally isolated from the bioluminescent jellyfish Aequorea victoria) expression controlled by a DNA damage-dependent promoter element which reflects the activity of the nuclear factor kappa B (NF- κB) pathway. The NF- κB family of proteins plays a major role in the inflammatory and immune response, cell proliferation and differentiation, anti-apoptosis and tumorgenesis. For radiation exposure during space flight a radiation source has been constructed as damage accumulation by cosmic radiation will certainly be insufficient for analysis. The space experiment specific hardware consists of a specially designed radiation source made up of the β-emitter promethium-147, combined with a miniaturized culture vessel and a seeding apparatus. With this prototype hardware, the requirements of CERASP can be fulfilled with cells growing on the polytetrafluoroethylene foil. The radiation source can be enveloped with additional titanium foils for safety issues. The results from the preparatory experimental phase clearly show that the Pm-147 radiation source meets the requirements for the space experiment CERASP.

  20. The German ISS-experiment Cellular Responses to Radiation in Space (CERASP): The effects of single and combined space flight conditions on mammalian cells

    NASA Astrophysics Data System (ADS)

    Hellweg, C. E.; Thelen, M.; Arenz, A.; Baumstark-Khan, C.

    The combined action of ionizing radiation and microgravity will continue to influence future manned space missions, with special risks for astronauts on the Moon surface or for long duration missions to Mars. There is increasing evidence that basic cellular functions are sensitive not only to radiation but also to microgravity. Previous space flight experiments gave contradictory results: from inhibition of DNA repair by microgravity to enhancement, whereas others did not detect any influence of microgravity on repair. At the Radiation Biology Department of the German Aerospace Center (DLR), recombinant bacterial and mammalian cell systems were developed as reporters for cellular signal transduction modulation by genotoxic environmental conditions. The space experiment “Cellular Responses to Radiation in Space” (CERASP) to be performed at the International Space Station (ISS) will make use of such reporter cell lines thereby supplying basic information on the cellular response to radiation applied in microgravity. One of the biological endpoints will be survival reflected by radiation-dependent reduction of constitutive expression of the enhanced variant of green fluorescent protein (EGFP). A second end-point will be gene activation by space flight conditions in mammalian cells, based on fluorescent promoter reporter systems using the destabilized d2EGFP variant. The promoter element to be investigated reflects the activity of the nuclear factor kappa B (NF-κB) pathway. The NF-κB family of proteins plays a major role in the inflammatory and immune response, cell proliferation and differentiation, apoptosis and tumor genesis. Results obtained with X-rays and accelerated heavy ions produced at the French heavy ion accelerator GANIL imply that densely ionizing radiation has a stronger potential to activate NF-κB dependent gene expression than sparsely ionizing radiation. The correlation of NF-κB activation to negative regulation of apoptosis could favor survival of cells with damaged DNA. A third endpoint to be examined will be DNA damage induced by combined exposure to radiation and microgravity and its repair. In the current work, preparatory experiments for the space experiment CERASP were performed. For radiation exposure on the ISS, an artificial radiation source is necessary since long-term exposure to cosmic radiation of frozen cells for damage accumulation will not be feasible. The biological activity of the designated space radiation source, the β-emitter promethium-147, was evaluated. Different shielding scenarios according to the experiment and safety requirements were evaluated. As growth surface for the human embryonic kidney cells, polytetrafluoroethylene and polyolefin foils were tested. For protection issues, the shielding effect of titanium foils was evaluated. With the prototype Pm-147 radiation source, the requirements of CERASP can be fulfilled with cells growing on the polytetrafluoroethylene foil and titanium foils for safety issues. In this setting, β-rays activated NF-κB-dependent reporter gene expression in human embryonic kidney cells. Regarding cell survival and NF-κB activation, the Pm-147 radiation source meets the requirements of the space experiment CERASP.

  1. A comprehensive dose reconstruction methodology for former rocketdyne/atomics international radiation workers.

    PubMed

    Boice, John D; Leggett, Richard W; Ellis, Elizabeth Dupree; Wallace, Phillip W; Mumma, Michael; Cohen, Sarah S; Brill, A Bertrand; Chadda, Bandana; Boecker, Bruce B; Yoder, R Craig; Eckerman, Keith F

    2006-05-01

    Incomplete radiation exposure histories, inadequate treatment of internally deposited radionuclides, and failure to account for neutron exposures can be important uncertainties in epidemiologic studies of radiation workers. Organ-specific doses from lifetime occupational exposures and radionuclide intakes were estimated for an epidemiologic study of 5,801 Rocketdyne/Atomics International (AI) radiation workers engaged in nuclear technologies between 1948 and 1999. The entire workforce of 46,970 Rocketdyne/AI employees was identified from 35,042 Kardex work histories cards, 26,136 electronic personnel listings, and 14,189 radiation folders containing individual exposure histories. To obtain prior and subsequent occupational exposure information, the roster of all workers was matched against nationwide dosimetry files from the Department of Energy, the Nuclear Regulatory Commission, the Landauer dosimetry company, the U.S. Army, and the U.S. Air Force. Dosimetry files of other worker studies were also accessed. Computation of organ doses from radionuclide intakes was complicated by the diversity of bioassay data collected over a 40-y period (urine and fecal samples, lung counts, whole-body counts, nasal smears, and wound and incident reports) and the variety of radionuclides with documented intake including isotopes of uranium, plutonium, americium, calcium, cesium, cerium, zirconium, thorium, polonium, promethium, iodine, zinc, strontium, and hydrogen (tritium). Over 30,000 individual bioassay measurements, recorded on 11 different bioassay forms, were abstracted. The bioassay data were evaluated using ICRP biokinetic models recommended in current or upcoming ICRP documents (modified for one inhaled material to reflect site-specific information) to estimate annual doses for 16 organs or tissues taking into account time of exposure, type of radionuclide, and excretion patterns. Detailed internal exposure scenarios were developed and annual internal doses were derived on a case-by-case basis for workers with committed equivalent doses indicated by screening criteria to be greater than 10 mSv to the organ with the highest internal dose. Overall, 5,801 workers were monitored for radiation at Rocketdyne/AI: 5,743 for external exposure and 2,232 for internal intakes of radionuclides; 41,169 workers were not monitored for radiation. The mean cumulative external dose based on Rocketdyne/AI records alone was 10.0 mSv, and the dose distribution was highly skewed with most workers experiencing low cumulative doses and only a few with high doses (maximum 500 mSv). Only 45 workers received greater than 200 mSv while employed at Rocketdyne/AI. However, nearly 32% (or 1,833) of the Rocketdyne/AI workers had been monitored for radiation at other nuclear facilities and incorporation of these doses increased the mean dose to 13.5 mSv (maximum 1,005 mSv) and the number of workers with >200 mSv to 69. For a small number of workers (n=292), lung doses from internal radionuclide intakes were relatively high (mean 106 mSv; maximum 3,560 mSv) and increased the overall population mean dose to 19.0 mSv and the number of workers with lung dose>200 mSv to 109. Nearly 10% of the radiation workers (584) were monitored for neutron exposures (mean 1.2 mSv) at Rocketdyne/AI, and another 2% were monitored for neutron exposures elsewhere. Interestingly, 1,477 workers not monitored for radiation at Rocketdyne/AI (3.6%) were found to have worn dosimeters at other nuclear facilities (mean external dose of 2.6 mSv, maximum 188 mSv). Without considering all sources of occupational exposure, an incorrect characterization of worker exposure would have occurred with the potential to bias epidemiologic results. For these pioneering workers in the nuclear industry, 26.5% of their total occupational dose (collective dose) was received at other facilities both prior to and after employment at Rocketdyne/AI. In addition, a small number of workers monitored for internal radionuclides contributed disproportionately to the number of workers with high lung doses. Although nearly 12% of radiation workers had been monitored for neutron exposures during their career, the cumulative dose levels were small in comparison with other external and internal exposure. Risk estimates based on nuclear worker data must be interpreted cautiously if internally deposited radionuclides and occupational doses received elsewhere are not considered.

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