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Sample records for actinium

  1. Extraction of actinium with di-(2-ethylhexyl)phosphoric acid from hydrochloric and nitric acid solutions

    The extraction of actinium with HDEHP from Cl- and NO3- systems has been investigated. It was found that extraction of actinium from HCl solutions is much better than from HNO3 solutions. Stability constants of actinium complexes Ac(X-)+2 with Cl- and NO3- ligands were determined. Our results show that the actinium formed less stable complexes with Cl- than with NO3- ligands. 5 refs., 3 figs., 1 tab. (author)

  2. The sorption of polonium, actinium and protactinium onto geological materials

    This paper describes a combined experimental and modeling program of generic sorption studies to increase confidence in the performance assessment for a potential high-level radioactive waste repository in Japan. The sorption of polonium, actinium and protactinium onto geological materials has been investigated. Sorption of these radioelements onto bentonite, tuff and granodiorite from equilibrated de-ionized water was studied under reducing conditions at room temperature. In addition, the sorption of actinium and protactinium was investigated at 60 C. Thermodynamic chemical modeling was carried out to aid interpretation of the results

  3. Separation of Actinium 227 from the uranium minerals

    The purpose of this work was to separate Actinium 227, whose content is 18%, from the mineral carnotite found in Gomez Chihuahua mountain range in Mexico. The mineral before processing is is pre-concentrated and passed, first through anionic exchange resins, later the eluate obtained is passed through cationic resins. The resins were 20-50 MESH QOWEX and 100-200 MESH 50 X 8-20 in some cased 200-400 MESH AG 50W-X8, 1X8 in other cases. The eluates from the ionic exchange were electrodeposited on stainless steel polished disc cathode and platinum electrode as anode; under a current ODF 10mA for 2.5 to 5 hours and of 100mA for .5 of an hour. it was possible to identify the Actinium 227 by means of its descendents, TH-227 and RA-223, through alpha spectroscopy. Due to the radiochemical purity which the electro deposits were obtained the Actinium 227 was low and was not quantitatively determined. A large majority of the members of the natural radioactive series 3 were identified and even alpha energies reported in the literature with very low percentages of non-identified emissions were observed. We conclude that a more precise study is needed concerning ionic exchange and electrodeposit to obtain an Actinium 227 of radiochemical purity. (Author)

  4. Spectroscopic and computational investigation of actinium coordination chemistry.

    Ferrier, Maryline G; Batista, Enrique R; Berg, John M; Birnbaum, Eva R; Cross, Justin N; Engle, Jonathan W; La Pierre, Henry S; Kozimor, Stosh A; Lezama Pacheco, Juan S; Stein, Benjamin W; Stieber, S Chantal E; Wilson, Justin J

    2016-01-01

    Actinium-225 is a promising isotope for targeted-α therapy. Unfortunately, progress in developing chelators for medicinal applications has been hindered by a limited understanding of actinium chemistry. This knowledge gap is primarily associated with handling actinium, as it is highly radioactive and in short supply. Hence, Ac(III) reactivity is often inferred from the lanthanides and minor actinides (that is, Am, Cm), with limited success. Here we overcome these challenges and characterize actinium in HCl solutions using X-ray absorption spectroscopy and molecular dynamics density functional theory. The Ac-Cl and Ac-OH2O distances are measured to be 2.95(3) and 2.59(3) Å, respectively. The X-ray absorption spectroscopy comparisons between Ac(III) and Am(III) in HCl solutions indicate Ac(III) coordinates more inner-sphere Cl(1-) ligands (3.2±1.1) than Am(III) (0.8±0.3). These results imply diverse reactivity for the +3 actinides and highlight the unexpected and unique Ac(III) chemical behaviour. PMID:27531582

  5. Discovery of the actinium, thorium, protactinium, and uranium isotopes

    Fry, C; Thoennessen, M

    2012-01-01

    Currently, 31 actinium, 31 thorium, 28 protactinium, and 23 uranium isotopes have so far been observed; the discovery of these isotopes is discussed. For each isotope a brief summary of the first refereed publication, including the production and identification method, is presented.

  6. Production of high-purity radium-223 from legacy actinium-beryllium neutron sources.

    Soderquist, Chuck Z; McNamara, Bruce K; Fisher, Darrell R

    2012-07-01

    Radium-223 is a short-lived alpha-particle-emitting radionuclide with potential applications in cancer treatment. Research to develop new radiopharmaceuticals employing (223)Ra has been hindered by poor availability due to the small quantities of parent actinium-227 available world-wide. The purpose of this study was to develop innovative and cost-effective methods to obtain high-purity (223)Ra from (227)Ac. We obtained (227)Ac from two surplus actinium-beryllium neutron generators. We retrieved the actinium/beryllium buttons from the sources and dissolved them in a sulfuric-nitric acid solution. A crude actinium solid was recovered from the solution by coprecipitation with thorium fluoride, leaving beryllium in solution. The crude actinium was purified to provide about 40 milligrams of actinium nitrate using anion exchange in methanol-water-nitric acid solution. The purified actinium was then used to generate high-purity (223)Ra. We extracted (223)Ra using anion exchange in a methanol-water-nitric acid solution. After the radium was separated, actinium and thorium were then eluted from the column and dried for interim storage. This single-pass separation produces high purity, carrier-free (223)Ra product, and does not disturb the (227)Ac/(227)Th equilibrium. A high purity, carrier-free (227)Th was also obtained from the actinium using a similar anion exchange in nitric acid. These methods enable efficient production of (223)Ra for research and new alpha-emitter radiopharmaceutical development. PMID:22697483

  7. Radium, thorium, and actinium extraction from seawater using an improved manganese-oxide-coated fiber

    Laboratory experiments were conducted to determine the efficiency with which improved manganese-oxide-coated acrylic fibers extract radium, thorium, and actinium from seawater. Tests were made using surface seawater spiked with 227Ac, 227Th and 223Ra. For sample volumes of approximately 30 liters and flow rates up to 0.5 liters per minute, radium and actinium are removed quantitatively. Approximately 80-95% of the thorium is removed under these same conditions. (Auth.)

  8. Production of Actinium-225 via High Energy Proton Induced Spallation of Thorium-232

    The science of cancer research is currently expanding its use of alpha particle emitting radioisotopes. Coupled with the discovery and proliferation of molecular species that seek out and attach to tumors, new therapy and diagnostics are being developed to enhance the treatment of cancer and other diseases. This latest technology is commonly referred to as Alpha Immunotherapy (AIT). Actinium-225/Bismuth-213 is a parent/daughter alpha-emitting radioisotope pair that is highly sought after because of the potential for treating numerous diseases and its ability to be chemically compatible with many known and widely used carrier molecules (such as monoclonal antibodies and proteins/peptides). Unfortunately, the worldwide supply of actinium-225 is limited to about 1,000mCi annually and most of that is currently spoken for, thus limiting the ability of this radioisotope pair to enter into research and subsequently clinical trials. The route proposed herein utilizes high energy protons to produce actinium-225 via spallation of a thorium-232 target. As part of previous R and D efforts carried out at Argonne National Laboratory recently in support of the proposed US FRIB facility, it was shown that a very effective production mechanism for actinium-225 is spallation of thorium-232 by high energy proton beams. The base-line simulation for the production rate of actinium-225 by this reaction mechanism is 8E12 atoms per second at 200 MeV proton beam energy with 50 g/cm2 thorium target and 100 kW beam power. An irradiation of one actinium-225 half-life (10 days) produces ∼100 Ci of actinium-225. For a given beam current the reaction cross section increases slightly with energy to about 400 MeV and then decreases slightly for beam energies in the several GeV regime. The object of this effort is to refine the simulations at proton beam energies of 400 MeV and above up to about 8 GeV. Once completed, the simulations will be experimentally verified using 400 MeV and 8 GeV protons

  9. Production of Actinium-225 via High Energy Proton Induced Spallation of Thorium-232

    Harvey, James T.; Nolen, Jerry; Vandergrift, George; Gomes, Itacil; Kroc, Tom; Horwitz, Phil; McAlister, Dan; Bowers, Del; Sullivan, Vivian; Greene, John

    2011-12-30

    The science of cancer research is currently expanding its use of alpha particle emitting radioisotopes. Coupled with the discovery and proliferation of molecular species that seek out and attach to tumors, new therapy and diagnostics are being developed to enhance the treatment of cancer and other diseases. This latest technology is commonly referred to as Alpha Immunotherapy (AIT). Actinium-225/Bismuth-213 is a parent/daughter alpha-emitting radioisotope pair that is highly sought after because of the potential for treating numerous diseases and its ability to be chemically compatible with many known and widely used carrier molecules (such as monoclonal antibodies and proteins/peptides). Unfortunately, the worldwide supply of actinium-225 is limited to about 1,000mCi annually and most of that is currently spoken for, thus limiting the ability of this radioisotope pair to enter into research and subsequently clinical trials. The route proposed herein utilizes high energy protons to produce actinium-225 via spallation of a thorium-232 target. As part of previous R and D efforts carried out at Argonne National Laboratory recently in support of the proposed US FRIB facility, it was shown that a very effective production mechanism for actinium-225 is spallation of thorium-232 by high energy proton beams. The base-line simulation for the production rate of actinium-225 by this reaction mechanism is 8E12 atoms per second at 200 MeV proton beam energy with 50 g/cm2 thorium target and 100 kW beam power. An irradiation of one actinium-225 half-life (10 days) produces {approx}100 Ci of actinium-225. For a given beam current the reaction cross section increases slightly with energy to about 400 MeV and then decreases slightly for beam energies in the several GeV regime. The object of this effort is to refine the simulations at proton beam energies of 400 MeV and above up to about 8 GeV. Once completed, the simulations will be experimentally verified using 400 MeV and 8 Ge

  10. Neutron-Induced Fission of Actinium-227, Protactinium-231 and Neptunium-237: Mass Distribution

    Results of radiochemical studies on the mass distribution in the neutron-induced fission of actinium-227, protactinium-231 and neptunium-237 have been presented. This work has been carried out as part of a programme to determine the mass distribution in the fission of heavy elements as a function of Z and A. All irradiations have been carried out in the core of the swimming-pool type reactor APSARA with cadmium shielding wherever necessary. Relative yields of several fission product nuclides have been obtained by a method involving a comparison of the fission product activities from the respective targets with those formed from uranium-235 simultaneously irradiated. Thermal-neutron fission yields of uranium-235 have been assumed. These results indicate a predominantly asymmetric mass distribution in all the three cases, and also a distinct though small symmetric peak in the case of actinium-227. (author)

  11. A new method for the determination of low-level actinium-227 in geological samples

    We developed a new method for the determination of 227Ac in geological samples. The method uses extraction chromatographic techniques and alpha-spectrometry and is applicable for a range of natural matrices. Here we report on the procedure and results of the analysis of water (fresh and seawater) and rock samples. Water samples were acidified and rock samples underwent total dissolution via acid leaching. A DGA (N,N,N',N'-tetra-n-octyldiglycolamide) extraction chromatographic column was used for the separation of actinium. The actinium fraction was prepared for alpha spectrometric measurement via cerium fluoride micro-precipitation. Recoveries of actinium in water samples were 80 ± 8 % (number of analyses n = 14) and in rock samples 70 ± 12 % (n = 30). The minimum detectable activities (MDA) were 0.017-0.5 Bq kg-1 for both matrices. Rock sample 227Ac activities ranged from 0.17 to 8.3 Bq kg-1 and water sample activities ranged from below MDA values to 14 Bq kg-1of 227Ac. From the analysis of several standard rock and water samples with the method we found very good agreement between our results and certified values. (author)

  12. Analysis of the gamma spectra of the uranium, actinium, and thorium decay series

    Momeni, M.H.

    1981-09-01

    This report describes the identification of radionuclides in the uranium, actinium, and thorium series by analysis of gamma spectra in the energy range of 40 to 1400 keV. Energies and absolute efficiencies for each gamma line were measured by means of a high-resolution germanium detector and compared with those in the literature. A gamma spectroscopy method, which utilizes an on-line computer for deconvolution of spectra, search and identification of each line, and estimation of activity for each radionuclide, was used to analyze soil and uranium tailings, and ore.

  13. Analysis of the gamma spectra of the uranium, actinium, and thorium decay series

    This report describes the identification of radionuclides in the uranium, actinium, and thorium series by analysis of gamma spectra in the energy range of 40 to 1400 keV. Energies and absolute efficiencies for each gamma line were measured by means of a high-resolution germanium detector and compared with those in the literature. A gamma spectroscopy method, which utilizes an on-line computer for deconvolution of spectra, search and identification of each line, and estimation of activity for each radionuclide, was used to analyze soil and uranium tailings, and ore

  14. In-source laser spectroscopy developments at TRILIS—towards spectroscopy on actinium and scandium

    Resonance Ionization Laser Ion Sources (RILIS) have become a versatile tool for production and study of exotic nuclides at Isotope Separator On-Line (ISOL) facilities such as ISAC at TRIUMF. The recent development and addition of a grating tuned spectroscopy laser to the TRIUMF RILIS solid state laser system allows for wide range spectral scans to investigate atomic structures on short lived isotopes, e.g., those from the element actinium, produced in uranium targets at ISAC. In addition, development of new and improved laser ionization schemes for rare isotope production at ISAC is ongoing. Here spectroscopic studies on bound states, Rydberg states and autoionizing (AI) resonances on scandium using the existing off-line capabilities are reported. These results allowed to identify a suitable ionization scheme for scandium via excitation into an autoionizing state at 58,104 cm − 1 which has subsequently been used for ionization of on-line produced exotic scandium isotopes.

  15. Developments towards in-gas-jet laser spectroscopy studies of actinium isotopes at LISOL

    Raeder, S.; Bastin, B.; Block, M.; Creemers, P.; Delahaye, P.; Ferrer, R.; Fléchard, X.; Franchoo, S.; Ghys, L.; Gaffney, L. P.; Granados, C.; Heinke, R.; Hijazi, L.; Huyse, M.; Kron, T.; Kudryavtsev, Yu.; Laatiaoui, M.; Lecesne, N.; Luton, F.; Moore, I. D.; Martinez, Y.; Mogilevskiy, E.; Naubereit, P.; Piot, J.; Rothe, S.; Savajols, H.; Sels, S.; Sonnenschein, V.; Traykov, E.; Van Beveren, C.; Van den Bergh, P.; Van Duppen, P.; Wendt, K.; Zadvornaya, A.

    2016-06-01

    To study exotic nuclides at the borders of stability with laser ionization and spectroscopy techniques, highest efficiencies in combination with a high spectral resolution are required. These usually opposing requirements are reconciled by applying the in-gas-laser ionization and spectroscopy (IGLIS) technique in the supersonic gas jet produced by a de Laval nozzle installed at the exit of the stopping gas cell. Carrying out laser ionization in the low-temperature and low density supersonic gas jet eliminates pressure broadening, which will significantly improve the spectral resolution. This article presents the required modifications at the Leuven Isotope Separator On-Line (LISOL) facility that are needed for the first on-line studies of in-gas-jet laser spectroscopy. Different geometries for the gas outlet and extraction ion guides have been tested for their performance regarding the acceptance of laser ionized species as well as for their differential pumping capacities. The specifications and performance of the temporarily installed high repetition rate laser system, including a narrow bandwidth injection-locked Ti:sapphire laser, are discussed and first preliminary results on neutron-deficient actinium isotopes are presented indicating the high capability of this novel technique.

  16. Groundwater seepage from the Ranger uranium mine tailings dam: radioisotopes of radium, thorium and actinium. Supervising Scientist report 106

    Monitoring of bores near the Ranger uranium mine tailings dam has revealed deterioration in water quality in several bores since 1983. In a group of bores to the north of the dam, increases have been observed of up to 500 times for sulphate concentrations and of up to 5 times for 226Ra concentrations. Results are presented here of measurements of members of the uranium, thorium and actinium decay series in borewater samples collected between 1985 and 1993. In particular, measurements of all four naturally-occurring radium isotopes have been used in an investigation of the mechanism of radium concentration changes. For the most seepage-affected bores the major findings of the study include: 228Ra/226Ra 223Ra /226Ra and 224Ra/228Ra ratios all increased over the course of the study; barium concentrations show high seasonal variability, being lower in November than May, but strontium concentrations show a steady increase with time. Calculations show that the groundwater is probably saturated with respect to barite but not with respect to celestite or anglesite; sulphide concentrations are low in comparison with sulphate, and are higher in November than in May; and 227Ac concentrations have increased with time, but do not account for the high 223Ra/226Ra ratios. It is concluded on the basis of these observations that increases in Ra isotope concentrations observed in a number of seepage-affected bores arise from increases in salinity leading to desorption of radium from adsorption sites in the vicinity of the bore rather by direct transport of radium from the tailings. Increased salinity is also causing the observed increases in 227Ac and strontium concentrations, while formation of a barite solid phase in the groundwater is causing the removal of some radium from solution. This is the cause of the increasing radium isotope ratios noted above

  17. Reflection asymmetry in odd-A and odd-odd actinium nuclei

    Theoretical calculations and measurements indicate that octupole correlations are at a maximum in the ground states of the odd-proton nuclei Ac and Pa. It has been expected that odd-odd nuclei should have even larger amount of octupole-octupole correlations. We have recently made measurements on the structure of 224Ac. Although spin and parity assignments could not be made, two bands starting at 354.1 and 360.0 keV have properties characteristic of reflection asymmetric shape. These two bands have very similar rotational constants and also similar alpha decay rates, which suggest similarity between the wavefunctions of these bands. These signatures provide evidence for octupole correlations in these nuclides

  18. Bestimmung der Ionisationsenergie von Actinium und Ultraspurenanalyse von Plutonium mit resonanter Ionisationsmassenspektrometrie (RIMS)

    Waldek, Achim Marcus

    2001-01-01

    ZusammenfassungDie Resonanzionisationsmassenspektrometrie (RIMS) verbindet hohe Elementselektivität mit guter Nachweiseffizienz. Aufgrund dieser Eigenschaften ist die Methode für Ultraspurenanalyse und Untersuchungen an seltenen oder schwer handhabbaren Elementen gut geeignet. Für RIMS werden neutrale Atome mit monochromatischem Laserlicht ein- oder mehrfach resonant auf energetisch hoch liegende Niveaus angeregt und anschließend durch einen weiteren Laserstrahl oder durch ein elektrisches Fe...

  19. Radium-228 analysis of natural waters by Cherenkov counting of Actinium-228

    The activities of 228Ra in natural waters were determined by the Cherenkov counting of the daughter nuclide 228Ac. The radium was pre-concentrated on MnO2 and the radium purified via ion exchange and, after a 2-day period of incubation to allow for secular equilibrium between the parent-daughter 228Ra(228Ac), the daughter nuclide 228Ac was isolated by ion exchange according to the method of Nour et al. [2004. Radium-228 determination of natural waters via concentration on manganese dioxide and separation using Diphonix ion exchange resin. Appl. Radiat. Isot. 61, 1173-1178]. The Cherenkov photons produced by 228Ac were counted directly without the addition of any scintillation reagents. The optimum Cherenkov counting window, sample volume, and vial type were determined experimentally to achieve optimum Cherenkov photon detection efficiency and lowest background count rates. An optimum detection efficiency of 10.9±0.1% was measured for 228Ac by Cherenkov counting with a very low Cherenkov photon background of 0.317±0.013 cpm. The addition of sodium salicylate into the sample counting vial at a concentration of 0.1 g/mL yielded a more than 3-fold increase in the Cherenkov detection efficiency of 228Ac to 38%. Tests of the Cherenkov counting technique were conducted with several water standards of known activity and the results obtained compared closely with a conventional liquid scintillation counting technique. The advantages and disadvantages of Cherenkov counting compared to liquid scintillation counting methods are discussed. Advantages include much lower Cherenkov background count rates and consequently lower minimal detectable activities for 228Ra and no need for expensive environmentally unfriendly liquid scintillation cocktails. The disadvantages of the Cherenkov counting method include the need to measure 228Ac Cherenkov photon detection efficiency and optimum Cherenkov counting volume, which are not at all required when liquid scintillation analysis is used

  20. Linear free energy relationship applied to trivalent cations with lanthanum and actinium oxide and hydroxide structure

    Linear free energy relationships for trivalent cations with crystalline M2O3 and, M(OH)3 phases of lanthanides and actinides were developed from known thermodynamic properties of the aqueous trivalent cations, modifying the Sverjensky and Molling equation. The linear free energy relationship for trivalent cations is as ΔGf,MvX0=aMvXΔGn,M3+0+bMvX+βMvXrM3+, where the coefficients aMvX, bMvX, and βMvX characterize a particular structural family of MvX, rM3+ is the ionic radius of M3+ cation, ΔGf,MvX0 is the standard Gibbs free energy of formation of MvX and ΔGn,M3+0 is the standard non-solvation free energy of the cation. The coefficients for the oxide family are: aMvX=0.2705, bMvX=-1984.75 (kJ/mol), and βMvX=197.24 (kJ/molnm). The coefficients for the hydroxide family are: aMvX=0.1587, bMvX=-1474.09 (kJ/mol), and βMvX=791.70 (kJ/molnm).

  1. Actinium: A RESTful Runtime Container for Scriptable Internet of Things Applications

    Kovatsch, Matthias; Lanter, Martin; Duquennoy, Simon

    2012-01-01

    Programming Internet of Things (IoT) applications is challenging because developers have to be knowledgeable in various technical domains, from low-power networking, over embedded operating systems, to distributed algorithms. Hence, it will be challenging to find enough experts to provide software for the vast number of expected devices, which must also be scalable and particularly safe due to the connection to the physical world. To remedy this situation, we propose an architecture that pr...

  2. New method for large scale production of medically applicable Actinium-225 and Radium-223

    Alpha-emitters (211At, 212Bi, 213Bi, 223Ra, 225Ac) are promising for targeted radiotherapy of cancer. Only two alpha decays near a cell membrane result in 50% death of cancer cell and only a single decay inside the cell is required for this. 225Ac may be used either directly or as a mother radionuclide in 213Bi isotope generator. Production of 225Ac is provided by three main suppliers - Institute for Transuranium Elements in Germany, Oak Ridge National Laboratory in USA and Institute of Physics and Power Engineering in Obninsk, Russia. The current worldwide production of 225Ac is approximately 1.7 Ci per year that corresponds to only 100-200 patients that could be treated annually. The common approach for 225Ac production is separation from mother 229Th or irradiation of 226Ra with protons in a cyclotron. Both the methods have some practical limitations to be applied routinely. 225Ac can be also produced by irradiation of natural thorium with medium energy protons . Cumulative cross sections of 225Ac, 227Ac, 227Th, 228Th formations have been obtained recently. Thorium targets (1-9 g) were irradiated by 114-91 MeV proton beam (1-50 μA) at INR linear accelerator. After dissolution in 8 M HNO3 + 0.004 M HF thorium was removed by double LLX by HDEHP in toluene (1:1). Ac and REE were pre-concentrated and separated from Ra and most fission products by DGA-Resin (Triskem). After washing out by 0.01 M HNO3 Ac was separated from REE by TRU Resin (Triskem) in 3 M HNO3 media. About 6 mCi 225Ac were separated in hot cell with chemical yield 85%. The method may be upscaled for production of Ci amounts of the radionuclide. The main impurity is 227Ac (0.1% at the EOB) but it does not hinder 225Ac from being used for medical 225Ac/213Bi generators. (author)

  3. Synthesis of chelating agents for actinium 225 complexation and its application in radioimmunotherapy

    Immunotherapy with radiolabeled antibodies should allow fairly specific targeting of certain cancers. However, iodine 131 may not be the best isotope for tumor therapy because of its limited specific activity, low beta-energy, relatively long half life and strong gamma emission. Another approach to improve therapeutic efficacy is the use of replacement isotopes with better physical properties. Chelator that can hold radio-metals with high stability under physiological conditions are essential to avoid excessive damage to non-target cells; Moreover, the development of new bifunctional chelating agents is essential for this purpose. Accordingly, our efforts have been directed, for several years, to the synthesis of original chelating agents likely to form stable complexes in vivo with the numerous potential candidates for such applications. Therefore, we have developed a new simple and efficient synthesis pathway of 2-(4-iso-thio-cyanate-benzyl)-1,4,7,10,13,16- hexa-aza-cyclo-hexadecane- 1,4,7,10,13,16-hexa-acetic acid, though functionalized on the cycle by a termination allowed coupling to an antibody or any other biological substance such as a hapten. (author)

  4. Purification of selenium from thorium, uranium, radium, actinium and potassium impurities for low background measurements

    A technique of selenium purification from 232Th, 238U, 226,228Ra, 227Ac and 40K was developed. This technique is simple to perform and employs a minimum number of highly pure reagents (bidistilled water, nitric acid). Operations carried out during purification (elution, evaporation) practically exclude losses of the target product (chemical yields of Se > 99%). A test purification of 100 g of selenium was carried out using this technique. The efficiency of this technique was confirmed by low background gamma spectrometry of the purified selenium sample. Distribution coefficients of Th, U, Ra and Ac on DOWEX 50W- x 8 cation-exchange resin at different concentrations of selenium and nitric acid were experimentally determinated. Instrumental neutron activation analysis of bidistilled water, deionized water and nitric acid was performed. (orig.)

  5. Purification of selenium from thorium, uranium, radium, actinium and potassium impurities for low background measurements

    Rakhimov, A.V. [Joint Institute for Nuclear Research (JINR), Dubna (Russian Federation); Uzbek Academy of Sciences, Tashkent (Uzbekistan). Inst. of Nuclear Physics (INP AS RUz); Warot, G. [CEA-CNRS, Modane (France). Laboratoire Souterrain de Modane (LSM); Karaivanov, D.V. [Joint Institute for Nuclear Research (JINR), Dubna (Russian Federation); Institute for Nuclear Research and Nuclear Energy (INRNE), Sofia (Bulgaria); Kochetov, O.I.; Lebedev, N.A.; Filosofov, D.V. [Joint Institute for Nuclear Research (JINR), Dubna (Russian Federation); Mukhamedshina, N.M.; Sadikov, I.I. [Uzbek Academy of Sciences, Tashkent (Uzbekistan). Inst. of Nuclear Physics (INP AS RUz)

    2013-07-01

    A technique of selenium purification from {sup 232}Th, {sup 238}U, {sup 226,228}Ra, {sup 227}Ac and {sup 40}K was developed. This technique is simple to perform and employs a minimum number of highly pure reagents (bidistilled water, nitric acid). Operations carried out during purification (elution, evaporation) practically exclude losses of the target product (chemical yields of Se > 99%). A test purification of 100 g of selenium was carried out using this technique. The efficiency of this technique was confirmed by low background gamma spectrometry of the purified selenium sample. Distribution coefficients of Th, U, Ra and Ac on DOWEX 50W- x 8 cation-exchange resin at different concentrations of selenium and nitric acid were experimentally determinated. Instrumental neutron activation analysis of bidistilled water, deionized water and nitric acid was performed. (orig.)

  6. Purification of radium-226 for the manufacturing of actinium-225 in a cyclotron for alpha-immunotherapy; Radium-Aufreinigung zur Herstellung von Actinium-225 am Zyklotron fuer die Alpha-Immuntherapie

    Marx, Sebastian Markus

    2014-09-23

    The thesis describes the development of methods for the purification of Ra-226. The objective was to obtain the radionuclide in the quality that is needed to be used as starting material in the manufacturing process for Ac-225 via proton-irradiated Ra-226. The radionuclide has been gained efficiently out of huge excesses of impurities. The high purity of the obtained radium affords its use as staring material in a pharmaceutical manufacturing process.

  7. Renal uptake of bismuth-213 and its contribution to kidney radiation dose following administration of actinium-225-labeled antibody

    Schwartz, J; O' Donoghue, J A; Humm, J L [Department of Medical Physics, Memorial Sloan-Kettering Cancer Center, 1275 York Avenue, New York, NY 10065 (United States); Jaggi, J S [Bristol-Myers Squibb, Plainsboro, NJ (United States); Ruan, S; Larson, S M [Nuclear Medicine Service Department of Radiology, Memorial Sloan-Kettering Cancer Center, 1275 York Avenue, New York, NY 10065 (United States); McDevitt, M; Scheinberg, D A, E-mail: schwarj1@mskcc.org [Molecular Pharmacology and Chemistry, Sloan-Kettering Institute, 1275 York Avenue, New York, NY 10065 (United States)

    2011-02-07

    Clinical therapeutic studies using {sup 225}Ac-labeled antibodies have begun. Of major concern is renal toxicity that may result from the three alpha-emitting progeny generated following the decay of {sup 225}Ac. The purpose of this study was to determine the amount of {sup 225}Ac and non-equilibrium progeny in the mouse kidney after the injection of {sup 225}Ac-huM195 antibody and examine the dosimetric consequences. Groups of mice were sacrificed at 24, 96 and 144 h after injection with {sup 225}Ac-huM195 antibody and kidneys excised. One kidney was used for gamma ray spectroscopic measurements by a high-purity germanium (HPGe) detector. The second kidney was used to generate frozen tissue sections which were examined by digital autoradiography (DAR). Two measurements were performed on each kidney specimen: (1) immediately post-resection and (2) after sufficient time for any non-equilibrium excess {sup 213}Bi to decay completely. Comparison of these measurements enabled estimation of the amount of excess {sup 213}Bi reaching the kidney ({gamma}-ray spectroscopy) and its sub-regional distribution (DAR). The average absorbed dose to whole kidney, determined by spectroscopy, was 0.77 (SD 0.21) Gy kBq{sup -1}, of which 0.46 (SD 0.16) Gy kBq{sup -1} (i.e. 60%) was due to non-equilibrium excess {sup 213}Bi. The relative contributions to renal cortex and medulla were determined by DAR. The estimated dose to the cortex from non-equilibrium excess {sup 213}Bi (0.31 (SD 0.11) Gy kBq{sup -1}) represented {approx}46% of the total. For the medulla the dose contribution from excess {sup 213}Bi (0.81 (SD 0.28) Gy kBq{sup -1}) was {approx}80% of the total. Based on these estimates, for human patients we project a kidney-absorbed dose of 0.28 Gy MBq{sup -1} following administration of {sup 225}Ac-huM195 with non-equilibrium excess {sup 213}Bi responsible for approximately 60% of the total. Methods to reduce renal accumulation of radioactive progeny appear to be necessary for the success of {sup 225}Ac radioimmunotherapy.

  8. Purification of radium-226 for the manufacturing of actinium-225 in a cyclotron for alpha-immunotherapy

    The thesis describes the development of methods for the purification of Ra-226. The objective was to obtain the radionuclide in the quality that is needed to be used as starting material in the manufacturing process for Ac-225 via proton-irradiated Ra-226. The radionuclide has been gained efficiently out of huge excesses of impurities. The high purity of the obtained radium affords its use as staring material in a pharmaceutical manufacturing process.

  9. Distribution of trace elements in land plants and botanical taxonomy with special reference to rare earth elements and actinium

    Distribution profiles of trace elements in land plants were studied by neutron activation analysis and radioactivity measurements without activation. Number of botanical samples analyzed were more than three thousand in which more than three hundred botanical species were included. New accumulator plants of Co, Cr, Zn, Cd, rare earth elements, Ac, U, etc., were found. Capabilities of accumulating trace elements can be related to the botanical taxonomy. Discussions are given from view points of inorganic chemistry as well as from botanical physiology

  10. Study on laser atomic spectroscopy

    Laser atomic spectroscopic study on actinium element has been performed in many areas of spectroscopy. The study on characteristic of atomic vapor has been proceeded for copper atom and the spatial density distribution of copper vapor is measured. This experimental data has been compared with the theoretically calculated data. In spectroscopic experiment, the first and second excited states for actinium element are identified and the most efficient ionization scheme for actinium element is identified. In addition, the corrosion problem for filament material due to the heating of the actinium element has been studied. (Author)

  11. Removal of actinium from europium for the determination of specific radioactivity of ultra low-level Eu-152 in a sample exposed to atomic-bomb neutrons in Nagasaki

    Measurements of specific radioactivities of residual neutron-induced radionuclides such as 152Eu and 60Co have been carried out to check the validity of a series of computer calculations employed for the atomic-bomb neutron dosimetry in Hiroshima (exposed to uranium bomb) and Nagasaki (exposed to plutonium bomb). The use of these nuclides for atomic-bomb neutron dosimetry, however, has been limited by the following difficulties: (1) today, these radionuclides are found only at extremely low concentrations in materials exposed to the atomic-bomb and (2) the neutrons that induced these radionuclides were thermal and epithermal, while the neutron dose received in Hiroshima and Nagasaki is attributable to fast neutrons. In order to overcome the first difficulty, we established a chemical procedure to extract Eu and Co from materials exposed to the atomic-bomb, and the chemical procedure has been successful for the materials exposed to atomic-bomb within 1400 m in slant distance from the explosion point. As for Nagasaki, materials exposed in the distances farther than 1200 m have never been subjected to the measurement of residual neutron-induced radionuclides. In this work, determination of specific radioactivity of 152Eu (half-life: 13.542 y) in a sample exposed to Nagasaki atomic-bomb at a distant place from the explosion point was undertaken. But, because of radioactive decay during this ∝60 years since 1945 and long distance from the explosion point, the present specific radioactivity of 152Eu in the sample is extremely low (estimated to be ∝3 x 10-4 Bq-152Eu/mg-Eu), and a serious problem is interferences from daughters of 227Ac (half-life: 21.8 y) in the measurement of ultra low-level radioactivity of 152Eu. Hence, our chemical procedure to obtain Eu-enriched counting source should be improved, and much attention is being denoted to removal of Ac from Eu. (orig.)

  12. Generator method of 225Ac production without a carrier for nuclear medicine

    The two-steps isotope generator scheme of 225Ac production from 229Th has been developed. The first step is used for separation of thorium, actinium, radium and daughter decay products (DDP), and removals of parent radionuclide. The second step provides additional separation of actinium from traces of radium and DDP, and conversion of actinium in the nitrate form. The chosen solutions provide optimal conditions for carry out of process. The yield of the 225Ac was 99.9% at minimal losses of parent 229Th (less than 0.1%)

  13. I. The metabolic properties of plutonium and allied materials

    Hamilton, J.G.

    1948-05-24

    This report on the metabolic properties of plutonium and related radioactive materials presents experimental information in the following areas: radioautographic studies; tracer studies (with tables of accumulation in tissues) of actinium, radio-zirconium, technetium, radio-rubidium, radio-germanium, beryllium, and cadmium; decontamination and bone metabolism studies; and radio-chemical isolation.

  14. Sorption studies of radioelements on geological materials

    Batch sorption experiments have been carried out to study the sorption of uranium, technetium, curium, neptunium, actinium, protactinium, polonium, americium and plutonium onto bentonite, granodiorite and tuff. Mathematical modelling using the HARPHRQ program and the HATCHES database was carried out to predict the speciation of uranium and technetium in the equilibrated seawater, and neptunium, americium and plutonium in the rock equilibrated water. Review of the literature for thermodynamic data for curium, actinium, protactinium and polonium was carried out. Where sufficient data were available, predictions of the speciation and solubility were made. This report is a summary report of the experimental work conducted by AEA Technology during April 1991-March 1998, and the main results have been presented at Material Research Society Symposium Proceedings and published as proceedings of them. (author)

  15. Investigation for determining the retention properties of rock over the ASSE II mine for dissolved radionuclides

    For a model consideration of groundwater movement and the associated transport of dissolved substance in deep groundwater, the retention properties of the ASSE II mine for radionuclides dissolved in water were determined. A series of properties of rocks were examined and described for this purpose. Apart from the chemical, mineralogical and petrophysical characteristics of the rocks, the retention was determined by 3 different methods and stated in the form of distribution coefficients for specific elements. A comparison of the results of vibration and diffusion experiments gave good agreement, while the results in through column experiments only reached the same order of magnitude after an expensive determination with the aid of a place concentration distribution. The distribution coefficients for the elements carbon, selenium, strontium, technetium, iodine, caesium, lead, radium, actinium, proto-actinium, uranium, neptunium, plutonium, americium and curium are listed and collected for model rock packages. (orig./HP)

  16. Sorption studies of radioelements on geological materials

    Berry, J. A; 油井 三和; 北村 暁

    2007-01-01

    Batch sorption experiments have been carried out to study the sorption of uranium, technetium, curium, neptunium, actinium, protactinium, polonium, americium and plutonium onto bentonite, granodiorite and tuff. Mathematical modelling using the HARPHRQ program and the HATCHES database was carried out to predict the speciation of uranium and technetium in the equilibrated seawater, and neptunium, americium and plutonium in the rock equilibrated water. Review of the literature for thermodynamic ...

  17. Purification of cerium, neodymium and gadolinium for low background experiments

    Boiko R.S.; Barabash A.S.; Belli P.; Bernabei R.; Cappella F.; Cerulli R.; Danevich F.A.; Incicchitti A.; Laubenstein M.; Mokina V.M.; Nisi S.; Poda D.V.; Polischuk O.G.; Tretyak V.I.

    2014-01-01

    Cerium, neodymium and gadolinium contain double beta active isotopes. The most interesting are 150Nd and 160Gd (promising for 0ν2β search), 136Ce (2β+ candidate with one of the highest Q2β). The main problem of compounds containing lanthanide elements is their high radioactive contamination by uranium, radium, actinium and thorium. The new generation 2β experiments require development of methods for a deep purification of lanthanides from the radioactive elements. A combination of physical an...

  18. LASL experience in decontamination of the environment

    This discussion represents one part of a major effort in soil decontamination at the Los Alamos site. A contaminated industrial waste line in the Los Alamos townsite was removed, and a plutonium incineration facility, and a filter building contaminated with actinium-227 were dismantled. The former plutonium handling facility has been decontaminated, and canyons and an old firing site contaminated with strontium-90 have been surveyed

  19. Study of the origin of elements of the uranium-235 family observed in excess in the vicinity of the experimental nuclear EL4 reactor under dismantling. Lessons got at this day and conclusions; Etude de l'origine des elements de la famille de l'uranium-235 observes en exces dans les environs du reacteur nucleaire experimental EL4 en cours de demantelement. Enseignements retires a ce jour et conclusion

    NONE

    2007-07-01

    This study resumes the discovery of an excess of actinium 227 found around by EL4 nuclear reactor actually in dismantling. The search for the origin of this excess revealed a real inquiry of investigation during three years. Because a nuclear reactor existed in this area a particular attention will have concerned this region. The doubt became the line of conduct to find the answer to the human or natural origin of this excess. Finally and against any evidence, it appears that the origin of this phenomenon was natural, consequence of the particular local geology. The detail of the different investigations is given: search of a possible correlation with the composition of elevations constituent of lanes, search (and underlining) of new sites in the surroundings of the Rusquec pond and the Plouenez station, study of the atmospheric deposits under winds of the nuclear power plant and in the east direction, search of a possible relationship with the gaseous effluents of the nuclear power plant in the past, historical study of radioactive effluents releases in the fifty last years by the analysis of the sedimentary deposits in the Saint-Herbiot reservoir, search of a possible correlation between the excess of actinium 227 and the nuclear power plant activity; search of a possible correlation with a human activity without any relationship with the nuclear activities, search of a correlation with the underground waters, search of a correlation with the geological context, collect of information on the possible transfers in direction of the food chain, determination of the radiological composition of the underground waters ( not perturbed by human activity), search of the cause of an excess of actinium 227 in the old channel of liquid effluents release of the nuclear power plant. The results are given and discussed. And contrary to all expectations the origin of the excess of actinium 227 is completely natural. (N.C.)

  20. The discoveries of uranium 237 and symmetric fission — From the archival papers of Nishina and Kimura

    IKEDA, Nagao

    2011-01-01

    Shortly before the Second World War time, Nishina reported on a series of prominent nuclear physical and radiochemical studies in collaboration with Kimura. They artificially produced 231Th, a member of the natural actinium series of nuclides, by bombarding thorium with fast neutrons. This resulted in the discovery of 237U, a new isotope of uranium, by bombarding uranium with fast neutrons, and confirmed that 237U disintegrates into element 93 with a mass number of 237. They also identified t...

  1. History of the unraveling of the natural decay series

    Milestones in the subject of radioactivity, which were important to the unraveling of natural decay series, have been identified and described. The interplay between all these issues is very complex, and some aspects of the development of the uranium series is discussed as an example, the thorium and actinium series evolved in a similar way from research by many of the same people. All three series as understood in 1913 are compared with their present-day representation. (orig.)

  2. History of the unraveling of the natural decay series

    Milestones in the subject of radioactivity, which were important to the unraveling of natural decay series, have been identified and described. The interplay between all these issues is very complex, and some aspects of the development of the uranium series is discussed as an example, the thorium and actinium series evolved in a similar way from research by many of the same people. All three series as understood in 1913 are compared with their present-day representation. (author)

  3. System for recovery of daughter isotopes from a source material

    Tranter, Troy J [Idaho Falls, ID; Todd, Terry A [Aberdeen, ID; Lewis, Leroy C [Idaho Falls, ID; Henscheid, Joseph P [Idaho Falls, ID

    2009-08-04

    A method of separating isotopes from a mixture containing at least two isotopes in a solution is disclosed. A first isotope is precipitated and is collected from the solution. A daughter isotope is generated and collected from the first isotope. The invention includes a method of producing an actinium-225/bismuth-213 product from a material containing thorium-229 and thorium-232. A solution is formed containing nitric acid and the material containing thorium-229 and thorium-232, and iodate is added to form a thorium iodate precipitate. A supernatant is separated from the thorium iodate precipitate and a second volume of nitric acid is added to the thorium iodate precipitate. The thorium iodate precipitate is stored and a decay product comprising actinium-225 and bismuth-213 is generated in the second volume of nitric acid, which is then separated from the thorium iodate precipitate, filtered, and treated using at least one chromatographic procedure. A system for producing an actinium-225/bismuth-213 product is also disclosed.

  4. Behaviour of uranium series radionuclides in surface water (Crouzille, Limousin). Geochemical implications

    Understanding natural radionuclides behaviour in surface water is a required step to achieve uranium mine rehabilitation and preserve water quality. The first objective of this thesis is to determine which are the radionuclides sources in a drinking water reservoir. The second objective is to improve the knowledge about the behaviour of uranium series radionuclides, especially actinium. The investigated site is a brook (Sagnes, Limousin, France) which floods a peat bog contaminated by a former uranium mine and which empties into the Crouzille lake. It allows studying radionuclides transport in surface water and radionuclides retention through organic substance or water reservoir. Radionuclides distribution in particulate, colloidal and dissolved phases is determined thanks to ultra-filtrations. Gamma spectrometry allows measuring almost all natural radionuclides with only two counting stages. However, low activities of 235U series radionuclides impose the use of very low background well-type Ge detectors, such as those of the Underground Laboratory of Modane (France). Firstly, this study shows that no or few radionuclides are released by the Sagnes peat bog, although its radioactivity is important. Secondly, it provides details on the behaviour of uranium series radionuclides in surface water. More specifically, it provides the first indications of actinium solubility in surface water. Actinium's behaviour is very close to uranium's even if it is a little less soluble. (author)

  5. DISSOLVED CONCENTRATION LIMITS OF RADIOACTIVE ELEMENTS

    P. Bernot

    2005-07-13

    The purpose of this study is to evaluate dissolved concentration limits (also referred to as solubility limits) of elements with radioactive isotopes under probable repository conditions, based on geochemical modeling calculations using geochemical modeling tools, thermodynamic databases, field measurements, and laboratory experiments. The scope of this activity is to predict dissolved concentrations or solubility limits for elements with radioactive isotopes (actinium, americium, carbon, cesium, iodine, lead, neptunium, plutonium, protactinium, radium, strontium, technetium, thorium, and uranium) relevant to calculated dose. Model outputs for uranium, plutonium, neptunium, thorium, americium, and protactinium are provided in the form of tabulated functions with pH and log fCO{sub 2} as independent variables, plus one or more uncertainty terms. The solubility limits for the remaining elements are either in the form of distributions or single values. Even though selection of an appropriate set of radionuclides documented in Radionuclide Screening (BSC 2002 [DIRS 160059]) includes actinium, transport of Ac is not modeled in the total system performance assessment for the license application (TSPA-LA) model because of its extremely short half-life. Actinium dose is calculated in the TSPA-LA by assuming secular equilibrium with {sup 231}Pa (Section 6.10); therefore, Ac is not analyzed in this report. The output data from this report are fundamental inputs for TSPA-LA used to determine the estimated release of these elements from waste packages and the engineered barrier system. Consistent modeling approaches and environmental conditions were used to develop solubility models for the actinides discussed in this report. These models cover broad ranges of environmental conditions so they are applicable to both waste packages and the invert. Uncertainties from thermodynamic data, water chemistry, temperature variation, and activity coefficients have been quantified or

  6. DISSOLVED CONCENTRATION LIMITS OF RADIOACTIVE ELEMENTS

    The purpose of this study is to evaluate dissolved concentration limits (also referred to as solubility limits) of elements with radioactive isotopes under probable repository conditions, based on geochemical modeling calculations using geochemical modeling tools, thermodynamic databases, field measurements, and laboratory experiments. The scope of this activity is to predict dissolved concentrations or solubility limits for elements with radioactive isotopes (actinium, americium, carbon, cesium, iodine, lead, neptunium, plutonium, protactinium, radium, strontium, technetium, thorium, and uranium) relevant to calculated dose. Model outputs for uranium, plutonium, neptunium, thorium, americium, and protactinium are provided in the form of tabulated functions with pH and log fCO2 as independent variables, plus one or more uncertainty terms. The solubility limits for the remaining elements are either in the form of distributions or single values. Even though selection of an appropriate set of radionuclides documented in Radionuclide Screening (BSC 2002 [DIRS 160059]) includes actinium, transport of Ac is not modeled in the total system performance assessment for the license application (TSPA-LA) model because of its extremely short half-life. Actinium dose is calculated in the TSPA-LA by assuming secular equilibrium with 231Pa (Section 6.10); therefore, Ac is not analyzed in this report. The output data from this report are fundamental inputs for TSPA-LA used to determine the estimated release of these elements from waste packages and the engineered barrier system. Consistent modeling approaches and environmental conditions were used to develop solubility models for the actinides discussed in this report. These models cover broad ranges of environmental conditions so they are applicable to both waste packages and the invert. Uncertainties from thermodynamic data, water chemistry, temperature variation, and activity coefficients have been quantified or otherwise

  7. Detection of rare earth elements in Powder River Basin sub-bituminous coal ash using laser-induced breakdown spectroscopy (LIBS)

    Tran, Phuoc [National Energy Technology Lab. (NETL), Pittsburgh, PA, (United State; Mcintyre, Dustin [National Energy Technology Lab. (NETL), Pittsburgh, PA, (United State

    2015-10-01

    We reported our preliminary results on the use of laser-induced breakdown spectroscopy to analyze the rare earth elements contained in ash samples from Powder River Basin sub-bituminous coal (PRB-coal). We have identified many elements in the lanthanide series (cerium, europium, holmium, lanthanum, lutetium, praseodymium, promethium, samarium, terbium, ytterbium) and some elements in the actinide series (actinium, thorium, uranium, plutonium, berkelium, californium) in the ash samples. In addition, various metals were also seen to present in the ash samples

  8. The identification of soil radionuclides in the area of Puspiptek and surrounding

    The area of PUSPIPTEK and the surrounding are potentially exposed by radionuclides, because the operation of the nuclear research plant. The PPTN Serpong was operated long than 10 years, therefore soil radioactivity need to evaluate. The determination of radioactivity in the soil samples which be taken from research location using gamma spectrometry on June-August. The result of the research identified natural radionuclides K-40; Thorium decay series Ac-228, Bi-212, Pb-212, Tl-208, Ra-224 and Rn-220; Uranium decay series Bi-214, Pa-234, Pb-214 and Actinium decay series Bi-211, Po-211. There are no identification radionuclides produce from the activation of PPTN Serpong

  9. An aerial radiological survey of the Sandia National Laboratories and surrounding area

    A team from the Remote Sensing Laboratory conducted an aerial radiological survey of the area surrounding the Sandia National Laboratories and Kirtland Air Force Base in Albuquerque, New Mexico, during March and April 1993. The survey team measured the terrestrial gamma radiation at the site to determine the levels of natural and man-made radiation. This survey includes the areas covered by a previous survey in 1981. The results of the aerial survey show a background exposure rate which varies between 5 and 18 μR/h plus an approximate 6 μR/h contribution from cosmic rays. The major radioactive isotopes found in this survey were: potassium-40, thallium-208, bismuth-214, and actinium-228, which are all naturally-occurring isotopes, and cobalt-60, cesium-137, and excess amounts of thallium-208 and actinium-228, which are due to human actions in the survey area. In regions away from man-made activity, the exposure rates inferred from this survey's gamma ray measurements agree almost exactly with the exposure rates inferred from the 1981 survey. In addition to the aerial measurements, another survey team conducted in situ and soil sample radiation measurements at three sites within the survey perimeter. These ground-based measurements agree with the aerial measurements within ± 5%

  10. Mixed valency of the RE and Ac ions in solid states

    Full text: This review is devoted to consideration of the methods and results of the theoretical and experimental investigations of the electronic state of the rare earths and actinium ions in the separate compound. The methods of the high resolution X ray spectroscopy were used for our consideration. Energy of the X ray lines of the rare earths and actinium ions in free state and solid states was study carefully. Valency shifts of X Ray lines under change of electronic state of nf - ions in different oxide, fluoride and chloride compounds were determined for K -, L- and M - lines for these ions with accuracy near 10 -100 MeV. We studied the electronic state of nf- ions which is changed from '+2' to '+4' and determined the concentration of ions in different electronic state. Relative error for theoretical energy of the most lines for HFP - approach in comparison with experiment is less than 0.5%, and deviation for concentration is less than 5%

  11. A study of uranium and thorium migration at the Koongarra uranium deposit with application to actinide transport from nuclear waste repositories

    One way to gain confidence in modelling possible radionuclide releases is to study natural systems which are similar to components of the multibarrier waste repository. Several such analogues are currently under study and these provide useful data about radionuclide behaviour in the natural environment. One such system is the Koongarra uranium deposit in the Northern Territory. In this dissertation, the migration of actinides, primarily uranium and thorium, has been studied as an analogue for the behaviour of transuranics in the far-field of a waste repository. The major findings of this study are: 1. the main process retarding uranium migration in the dispersion fan at Koongarra is sorption, which suppresses dissolved uranium concentrations well below solubility limits, with ferrihydrite being a major sorbing phase; 2. thorium is extremely immobile, with very low dissolved concentrations and corresponding high distribution ratios for 230Th. Overall, it is estimated that colloids are relatively unimportant in Koongarra groundwater. Uranium migrates mostly as dissolved species, whereas thorium and actinium are mostly adsorbed to larger, relatively immobile particles and the stationary phase. However, of the small amount of 230Th that passes through a 1μm filter, a significant proportion is associated with colloidal particles. Actinium appears to be slightly more mobile than thorium and is associated with colloids to a greater extent, although generally present in low concentrations. These results support the possibility of colloidal transport of trivalent and tetravalent actinides in the vicinity of a nuclear waste repository. 112 refs., 23 tabs., 32 figs

  12. Purification of cerium, neodymium and gadolinium for low background experiments

    Boiko R.S.

    2014-01-01

    Full Text Available Cerium, neodymium and gadolinium contain double beta active isotopes. The most interesting are 150Nd and 160Gd (promising for 0ν2β search, 136Ce (2β+ candidate with one of the highest Q2β. The main problem of compounds containing lanthanide elements is their high radioactive contamination by uranium, radium, actinium and thorium. The new generation 2β experiments require development of methods for a deep purification of lanthanides from the radioactive elements. A combination of physical and chemical methods was applied to purify cerium, neodymium and gadolinium. Liquid-liquid extraction technique was used to remove traces of Th and U from neodymium, gadolinium and for purification of cerium from Th, U, Ra and K. Co-precipitation and recrystallization methods were utilized for further reduction of the impurities. The radioactive contamination of the samples before and after the purification was tested by using ultra-low-background HPGe gamma spectrometry. As a result of the purification procedure the radioactive contamination of gadolinium oxide (a similar purification efficiency was reached also with cerium and neodymium oxides was decreased from 0.12 Bq/kg to 0.007 Bq/kg in 228Th, from 0.04 Bq/kg to <0.006 Bq/kg in 226Ra, and from 0.9 Bq/kg to 0.04 Bq/kg in 40K. The purification methods are much less efficient for chemically very similar radioactive elements like actinium, lanthanum and lutetium.

  13. The Technological Enhancement of Normally Occurring Radioactive Materials in Red Mud due to the Production of Alumina

    Maurice O. Miller

    2016-01-01

    Full Text Available This study investigates the level of technological enhancement of normally occurring radioactive materials (TENORM in the red mud waste due to the production of alumina in Jamaica. Technological enhancements factors (TEF were determined for the uranium, thorium, actinium series, their progenies, and the nonseries potassium-40 using gamma spectrometry. The study concluded that bauxite production technologically enhances the uranium progenies Th-234, Pb-214, Bi-214, and Pa-234 and the thorium-232 progenies Ac-228, Pb-212, and Bi-212 in red mud. The actinium series was technologically enhanced, but K-40 and the thorium daughter, Tl-208, were reduced. The spectrometric comparison of Tl-208 (at 510 keV was unexpected since its other photopeaks at 583 keV, 934 keV, and 968 keV were markedly different. An explanation for this anomaly is discussed. An explanation regarding the process of accumulation and fractionation of organically derived phosphate deposits and potassium-feldspar is offered to explain the spectrometric differences between the alumina product and its waste material, red mud.

  14. Low background counting of 222Rn, 220Rn and 219Rn with electrostatic counters

    Mong, Brian; EXO-200 Collaboration; nEXO Collaboration

    2014-09-01

    The radon counting technique based on electrostatic precipitation of progenies in gas followed by alpha spectroscopy has been applied to support the material selection programs of low background, neutrino and dark matter experiments with emphasis on EXO. An array of 8 counters operated by Laurentian University at SNOLAB and the Waste Isolation Pilot Plant have reached the sensitivity of 10 atoms/day in the uranium, thorium and actinium chains. Hardware improvements are underway to further increase the capacity and sensitivity in support of nEXO. The radon counting technique based on electrostatic precipitation of progenies in gas followed by alpha spectroscopy has been applied to support the material selection programs of low background, neutrino and dark matter experiments with emphasis on EXO. An array of 8 counters operated by Laurentian University at SNOLAB and the Waste Isolation Pilot Plant have reached the sensitivity of 10 atoms/day in the uranium, thorium and actinium chains. Hardware improvements are underway to further increase the capacity and sensitivity in support of nEXO. Supported by NSERC Project Grants ``Search for Double Beta Decay with EXO.''

  15. Purification of cerium, neodymium and gadolinium for low background experiments

    Boiko, R. S.; Barabash, A. S.; Belli, P.; Bernabei, R.; Cappella, F.; Cerulli, R.; Danevich, F. A.; Incicchitti, A.; Laubenstein, M.; Mokina, V. M.; Nisi, S.; Poda, D. V.; Polischuk, O. G.; Tretyak, V. I.

    2014-01-01

    Cerium, neodymium and gadolinium contain double beta active isotopes. The most interesting are 150Nd and 160Gd (promising for 0ν2β search), 136Ce (2β+ candidate with one of the highest Q2β). The main problem of compounds containing lanthanide elements is their high radioactive contamination by uranium, radium, actinium and thorium. The new generation 2β experiments require development of methods for a deep purification of lanthanides from the radioactive elements. A combination of physical and chemical methods was applied to purify cerium, neodymium and gadolinium. Liquid-liquid extraction technique was used to remove traces of Th and U from neodymium, gadolinium and for purification of cerium from Th, U, Ra and K. Co-precipitation and recrystallization methods were utilized for further reduction of the impurities. The radioactive contamination of the samples before and after the purification was tested by using ultra-low-background HPGe gamma spectrometry. As a result of the purification procedure the radioactive contamination of gadolinium oxide (a similar purification efficiency was reached also with cerium and neodymium oxides) was decreased from 0.12 Bq/kg to 0.007 Bq/kg in 228Th, from 0.04 Bq/kg to <0.006 Bq/kg in 226Ra, and from 0.9 Bq/kg to 0.04 Bq/kg in 40K. The purification methods are much less efficient for chemically very similar radioactive elements like actinium, lanthanum and lutetium.

  16. Purification system of gram-amount neptunium using anion exchange chromatography

    To develop a purification system of gram-amount neptunium using anion exchange chromatography, adsorption elution of excess amount of actinium in 6M HNO3 aqueous solution was studied using thorium and uranium tracer. The partition coefficient (Kd) of Th (IV) decreased from Kd=99.1 of tracer to Kd=44.0, 5% load. By decreasing the partition coefficient, we can wash until 30 Vs under the purification conditions of 1% load and 95% recovery. The retention volume of U (IV) was about 300 Vs, a large value. The partition coefficient of Np (IV) may be larger than it and the large amount of washable eluting solution may be obtained. Washing of impurity of 3d transition metal and actinide (VI) can be done until 20Vs. With washing of 150Vs, impurity of alkali earth metal, metals (III) and platinum group metals decreased less than 0.1%. (S.Y.)

  17. A francium-223 reservoir source

    By improving and accelerating a method which had been earlier tried for caesium-rubidium separation on a cellulose column, i.e. elution with 2N HCl-equilibrated phenol, the author succeeded in obtaining consecutive and quasi-selective elutions of francium-223, starting with actinium-227 fixed at the top of a small cellulose column to which ZrO2 had been added. The francium-223, rapidly eluted under pressure, is extracted by water while the phenol is extracted by ether; it can easily be cleared of any residual traces of radioactive contaminants (thallium-207, radium-223, thorium-227) by two consecutive BaSO4 precipitations. The preparation of a Fr223 solution (HCl-H2SO4) requires approximately 20 min; the time noted for Fr223 was closer to 22 than to 21 min. (author)

  18. Radionuclide interactions with marine sediments

    A critical review of the literature on the subject of the interactions of radionuclides with marine sediments has been carried out. On the basis of the information available, an attempt has been made to give ranges and 'best estimates' for the distribution ratios between seawater and sediments. These estimates have been based on an understanding of the sediment seawater system and the porewater chemistry and mineralogy. Field measurements, laboratory measurements and estimates based on stable-element geochemical data are all taken into account. Laboratory measurements include distribution-ratio and diffusion-coefficient determinations. The elements reviewed are carbon, chlorine, calcium, nickel, selenium, strontium, zirconium, niobium, technetium, tin, iodine, caesium, lead, radium, actinium, thorium, protactinium, uranium, neptunium, plutonium, americium and curium. (author)

  19. Formerly utilized MED/AEC sites Remedial Action Program. Radiological survey of the St. Louis Airport Storage Site, St. Louis, Missouri. Final report

    Results of two radiological surveys of the St. Louis-Lambert Airport property, formerly known as the Airport Storage Site, St. Louis, Missouri, are presented. Uranium- and radium-bearing waste materials were stored from the 1940's to the late 1960's in this area. The surveys included direct measurements of beta-gamma radiation; determination of uranium, actinium, and radium concentrations in soil samples and from bore holes; determination of radionuclide concentrations in groundwater and surface water; measurement of radon flux from the ground surface; and measurements of 222Rn in air near the site. Results indicate that some offsite drainage pathways are becoming contaminated, probably by runoff from the site; no migration of 222Rn from the site was observed

  20. JAEA thermodynamic database for performance assessment of geological disposal of high-level and TRU wastes. Refinement of thermodynamic data for trivalent actinoids and samarium

    Within the scope of the JAEA thermodynamic database project for performance assessment of geological disposal of high-level radioactive and TRU wastes, the refinement of the thermodynamic data for the inorganic compounds and complexes of trivalent actinoids (actinium(III), plutonium(III), americium(III) and curium(III)) and samarium(III) was carried out. Refinement of thermodynamic data for these elements was based on the thermodynamic database for americium published by the Nuclear Energy Agency in the Organisation for Economic Co-operation and Development (OECD/NEA). Based on the similarity of chemical properties among trivalent actinoids and samarium, complementary thermodynamic data for their species expected under the geological disposal conditions were selected to complete the thermodynamic data set for the performance assessment of geological disposal of radioactive wastes. (author)

  1. Theoretical Study on Properties of New Isotope 265Bh

    2006-01-01

    The properties of nuclei belonging to the newly observed α-decay chain starting from 265Bh have been studied. The axially deformed relativistic mean-field calculation with the force NL-Z2 has been performed in the blockedBCS approximation. Some ground state properties such as binding energies, deformations, spins, and parities, as well as Q-values of the α-decay for this decay chain have been calculated and compared with known experimental data. Good agreement is found. The single-particle spectrum of the nucleus 265 Bh is studied and some new magic numbers are found,while the magnitudes of the shell gaps in superheavy nuclei are much smaller than those of nuclei before the actinium region, and the Fermi surfaces are close to the continuum. Thus the superheavy nuclei are usually not stable. The The methods which give good agreement with the data are selected.

  2. Proposed training program for construction personnel involved in remedial action work at sites contaminated by naturally occurring radionuclides

    Many sites used during the early days of the US atomic energy program are contaminated with radionuclides of the primordial decay chains (uranium, thorium, and actinium series). This contamination consists of residues resulting from refining and processing uranium and thorium. Preparation of these sites for release to unrestricted private use will involve the assistance of construction workers, many of whom have limited knowledge of the hazards associated with radioactive materials. Therefore, there is a need to educate these workers in the fundamentals of radioactive material handling to minimize exposures and possible spread of contamination. This training should disseminate relevant information at an appropriate educational level and should instill a cautious, common-sense attitude toward the handling of radioactive materials. The training should emphasize basic information concerning environmental radiation within a context of relative risk. A multi-media format, including colorful visual aids, demonstration, and discussion, should be used to maximize motivation and retention. A detailed, proposed training program design is presented

  3. Origin of elements of the Uranium-235 family observed in the Ellez river near the EL-4 experimental nuclear reactor in dismantling (Monts d'Arree- Finistere department); Origine des elements de la famille de l'uranium-235 observes dans la riviere Ellez a proximite du reacteur nucleaire experimental EL4 en cours de demantelement (Mont d'Arree - departement du Finistere). Resultats et premiers constats annee 2006

    NONE

    2006-07-01

    In a previous study which concerned the catchment basin of the harbour of Brest, the A.C.R.O. put in evidence a marking by artificial radioelements around the power plant of Brennilis which can be imputed without ambiguities to the nuclear installation. It also put in evidence abnormalities concerning the natural radioactivity which justifies this new study. In the area of the Monts d'Arree, actinium 227 ({sup 227}Ac), non born by its ascendents which are {sup 235}U and {sup 231}Pa is observed. This phenomenon is characterized by mass activities superior to these ones of {sup 235}U and able to reach these ones of {sup 238}U. Its presence corresponds with the drainage of the Ellez river since the former channel of radioactive effluents releases from the nuclear power plant EL-4 up to the reservoir Saint-Herblot situated 6 km downstream. The strongest values of radioactivity are registered near the disused power plant, at this place a relationship exists between the level of actinium 227 and this one of the artificial radioactivity as it exists a relationship with the decay products of radon exhaled from the subsoil ({sup 210}Pb). But its presence is not limited to a part of the Ellez river, it is equally observed in terrestrial medium, in places in priori not influenced by the direct liquid effluents of the power plant. This place is situated at more than 4 km and without any connection with the Ellez waters. At this stage of the study, it is not possible to answer with certainty the question of the origin of this phenomenon. A new reorientation is considered indispensable to clarify definitively the origin of this unknown phenomenon in the scientific publications and the environmental monitoring. (N.C.)

  4. origin of elements of the Uranium-235 family observed in the Ellez river near the EL-4 experimental nuclear reactor in dismantling (Monts d'Arree- Finistere department)

    In a previous study which concerned the catchment basin of the harbour of Brest, the A.C.R.O. put in evidence a marking by artificial radioelements around the power plant of Brennilis which can be imputed without ambiguities to the nuclear installation. It also put in evidence abnormalities concerning the natural radioactivity which justifies this new study. In the area of the Monts d'Arree, actinium 227 (227Ac), non born by its ascendents which are 235U and 231Pa is observed. This phenomenon is characterized by mass activities superior to these ones of 235U and able to reach these ones of 238U. Its presence corresponds with the drainage of the Ellez river since the former channel of radioactive effluents releases from the nuclear power plant EL-4 up to the reservoir Saint-Herblot situated 6 km downstream. The strongest values of radioactivity are registered near the disused power plant, at this place a relationship exists between the level of actinium 227 and this one of the artificial radioactivity as it exists a relationship with the decay products of radon exhaled from the subsoil (210Pb). But its presence is not limited to a part of the Ellez river, it is equally observed in terrestrial medium, in places in priori not influenced by the direct liquid effluents of the power plant. This place is situated at more than 4 km and without any connection with the Ellez waters. At this stage of the study, it is not possible to answer with certainty the question of the origin of this phenomenon. A new reorientation is considered indispensable to clarify definitively the origin of this unknown phenomenon in the scientific publications and the environmental monitoring. (N.C.)

  5. Physical Measurements and Clinical Findings of Persons with Radium Burdens

    Results of physical measurements and some clinical findings of persons with radium burdens are reported and discussed. Ten workers of the dial painting industry, two chemists, who have been working for between 10 and 20 yr in the radium- industry, one technician, who has been- working for over 20 yr with high-emanation radium preparations and one person with high radium intake of rather unknown history were measured in a whole-body counter for evaluation of the body burdens of radium-226 and radium-228+ actinium-228. In some cases the radon concentration of expired air was also measured. For four of the measured persons the radium-226 burden is of the order of the maximum permissible amount (MPA : 10-7 c) or more. In one case the burden amounts to more than three times the MPA, (3.4 x 10-7 c), in another case to more than 100 times the MPA (160 x 10-7 c). In one case the radium-228 + actinium-228 burden exceeds the MPA (6 x 10-8 c in bone). The measured radon concentrations in the expired air were used to calculate the excretion rate of radon. The average was 67%. Clinical findings with some of the measured persons are related to the measured body burdens. The patient with the high body burden of 160 x 10-7 c radium-226 shows heavy bone changes leading to spontaneous bone fractures. The blood picture shows a decrease in the number of erythrocytes and a low haemoglobin content but puncture of the sternum indicates normal haematopoiesis. It seems that the low number of erythrocytes is caused by chronic nephropathia, the reason for which might be an additional intake of uranium because.uranium was found in the urine by gamma spectroscopy. The results are discussed with respect to the MPA of radium-226 recommended by the International Commission on Radiological Protection. (author)

  6. Minor Actinide Burning in Thermal Reactors. A Report by the Working Party on Scientific Issues of Reactor Systems

    The actinides (or actinoids) are those elements in the periodic table from actinium upwards. Uranium (U) and plutonium (Pu) are two of the principal elements in nuclear fuel that could be classed as major actinides. The minor actinides are normally taken to be the triad of neptunium (Np), americium (Am) and curium (Cm). The combined masses of the remaining actinides (i.e. actinium, thorium, protactinium, berkelium, californium, einsteinium and fermium) are small enough to be regarded as very minor trace contaminants in nuclear fuel. Those elements above uranium in the periodic table are known collectively as the transuranics (TRUs). The operation of a nuclear reactor produces large quantities of irradiated fuel (sometimes referred to as spent fuel), which is either stored prior to eventual deep geological disposal or reprocessed to enable actinide recycling. A modern light water reactor (LWR) of 1 GWe capacity will typically discharge about 20-25 tonnes of irradiated fuel per year of operation. About 93-94% of the mass of uranium oxide irradiated fuel is comprised of uranium (mostly 238U), with about 4-5% fission products and ∼1% plutonium. About 0.1-0.2% of the mass is comprised of neptunium, americium and curium. These latter elements accumulate in nuclear fuel because of neutron captures, and they contribute significantly to decay heat loading and neutron output, as well as to the overall radio-toxic hazard of spent fuel. Although the total minor actinide mass is relatively small - approximately 20-25 kg per year from a 1 GWe LWR - it has a disproportionate impact on spent fuel disposal, and thus the longstanding interest in transmuting these actinides either by fission (to fission products) or neutron capture in order to reduce their impact on the back end of the fuel cycle. The combined masses of the trace actinides actinium, thorium, protactinium, berkelium and californium in irradiated LWR fuel are only about 2 parts per billion, which is far too low for

  7. TRASH TO TREASURE: CONVERTING COLD WAR LEGACY WASTE INTO WEAPONS AGAINST CANCER

    As part of its commitment to clean up Cold War legacy sites, the U.S. Department of Energy (DOE) has initiated an exciting and unique project to dispose of its inventory of uranium-233 (233U) stored at Oak Ridge National Laboratory (ORNL), and extract isotopes that show great promise in the treatment of deadly cancers. In addition to increasing the supply of potentially useful medical isotopes, the project will rid DOE of a nuclear concern and cut surveillance and security costs. For more than 30 years, DOE's ORNL has stored over 1,200 containers of fissile 233U, originally produced for several defense-related projects, including a pilot study that looked at using 233U as a commercial reactor fuel. This uranium, designated as special nuclear material, requires expensive security, safety, and environmental controls. It has been stored at an ORNL facility, Building 3019A, that dates back to the Manhattan Project. Down-blending the material to a safer form, rather than continuing to store it, will eliminate a $15 million a year financial liability for the DOE and increase the supply of medical isotopes by 5,700 percent. During the down-blending process, thorium-229 (229Th) will be extracted. The thorium will then be used to extract actinium-225 (225Ac), which will ultimately supply its progeny, bismuth-213 (213Bi), for on-going cancer research. The research includes Phase II clinical trials for the treatment of acute myelogenous leukemia at Sloan-Kettering Memorial Cancer Center in New York, as well as other serious cancers of the lungs, pancreas, and kidneys using a technique known as alpha-particle radioimmunotherapy. Alpha-particle radioimmunotherapy is based on the emission of alpha particles by radionuclides. 213Bi is attached to a monoclonal antibody that targets specific cells. The bismuth then delivers a high-powered but short-range radiation dose, effectively killing the cancerous cells but sparing the surrounding tissue. Production of the actinium and

  8. TRASH TO TREASURE: CONVERTING COLD WAR LEGACY WASTE INTO WEAPONS AGAINST CANCER

    Nicholas, R.G.; Lacy, N.H.; Butz, T.R.; Brandon, N.E.

    2004-10-06

    As part of its commitment to clean up Cold War legacy sites, the U.S. Department of Energy (DOE) has initiated an exciting and unique project to dispose of its inventory of uranium-233 (233U) stored at Oak Ridge National Laboratory (ORNL), and extract isotopes that show great promise in the treatment of deadly cancers. In addition to increasing the supply of potentially useful medical isotopes, the project will rid DOE of a nuclear concern and cut surveillance and security costs. For more than 30 years, DOE's ORNL has stored over 1,200 containers of fissile 233U, originally produced for several defense-related projects, including a pilot study that looked at using 233U as a commercial reactor fuel. This uranium, designated as special nuclear material, requires expensive security, safety, and environmental controls. It has been stored at an ORNL facility, Building 3019A, that dates back to the Manhattan Project. Down-blending the material to a safer form, rather than continuing to store it, will eliminate a $15 million a year financial liability for the DOE and increase the supply of medical isotopes by 5,700 percent. During the down-blending process, thorium-229 (229Th) will be extracted. The thorium will then be used to extract actinium-225 (225Ac), which will ultimately supply its progeny, bismuth-213 (213Bi), for on-going cancer research. The research includes Phase II clinical trials for the treatment of acute myelogenous leukemia at Sloan-Kettering Memorial Cancer Center in New York, as well as other serious cancers of the lungs, pancreas, and kidneys using a technique known as alpha-particle radioimmunotherapy. Alpha-particle radioimmunotherapy is based on the emission of alpha particles by radionuclides. 213Bi is attached to a monoclonal antibody that targets specific cells. The bismuth then delivers a high-powered but short-range radiation dose, effectively killing the cancerous cells but sparing the surrounding tissue. Production of the actinium and

  9. DISSOLVED CONCENTRATION LIMITS OF RADIOACTIVE ELEMENTS

    NA

    2004-11-22

    The purpose of this study is to evaluate dissolved concentration limits (also referred to as solubility limits) of elements with radioactive isotopes under probable repository conditions, based on geochemical modeling calculations using geochemical modeling tools, thermodynamic databases, field measurements, and laboratory experiments. The scope of this modeling activity is to predict dissolved concentrations or solubility limits for 14 elements with radioactive isotopes (actinium, americium, carbon, cesium, iodine, lead, neptunium, plutonium, protactinium, radium, strontium, technetium, thorium, and uranium) important to calculated dose. Model outputs for uranium, plutonium, neptunium, thorium, americium, and protactinium are in the form of tabulated functions with pH and log (line integral) CO{sub 2} as independent variables, plus one or more uncertainty terms. The solubility limits for the remaining elements are either in the form of distributions or single values. The output data from this report are fundamental inputs for Total System Performance Assessment for the License Application (TSPA-LA) to determine the estimated release of these elements from waste packages and the engineered barrier system. Consistent modeling approaches and environmental conditions were used to develop solubility models for all of the actinides. These models cover broad ranges of environmental conditions so that they are applicable to both waste packages and the invert. Uncertainties from thermodynamic data, water chemistry, temperature variation, and activity coefficients have been quantified or otherwise addressed.

  10. Formerly utilized MED/AEC sites remedial action program. Radiological survey of the E. I. Du Pont de Nemours and Co. , Deepwater, New Jersey. Final report

    None

    1978-12-01

    The results of a radiological survey of the E. I. Du Pont Company, Deepwater, New Jersey, are presented in this report. During the 1940's this site was used for development of a process for the conversion of uranium oxide to produce uranium tetrafluoride and small quantities of uranium metal. The survey included measurements of the following: residual alpha and beta--gamma contamination levels, both fixed and transferable, in the one remaining uranium tetrafluoride operations building; external gamma radiation levels at 1 m above the surface inside this building and at outdoor locations where radioactive materials were handled; radon and radon daughter concentrations in the air in the operations building; uranium, radium, actinium, and thorium concentrations in soil and water on and near the site; and the airborne concentrations of uranium, thorium, and radium in the operations building. Elevated concentrations of uranium were found in residues from the operations building and in some surface and subsurface soil samples. Alpha and beta--gamma contamination levels in some areas of the operations building were above the limits of current federal guidelines set for the release of property for unrestricted use. 18 figures, 11 tables.

  11. Geological disposal: security and R and D. Security of 'second draft for R and D of geological disposal'

    The second draft for R and D of geological disposal (second draft) was arranged in 1999. The idea of security of geological disposal in the second draft is explained. The evaluation results of the uncertainty analysis and an example of evaluation of the effect of separation nuclear transmutation on the geological disposal are shown. The construction of strong engineered barrier is a basic idea of geological disposal system. Three processes such as isolation, engineering countermeasures and safety evaluation are carried out for the security of geological disposal. The security of geological environment for a long time of 12 sites in Japan was studied by data. Provability of production and enforcement of engineered barrier were confirmed by trial of over pack, tests and the present and future technologies developed. By using the conditions of reference case in the second draft, the evaluation results of dose effects in the two cases: 1) 90 to 99% Cs and Sr removed from HLW (High Level radioactive Waste) and 2) high stripping ratio of actinium series are explained. (S.Y.)

  12. Selective Decontamination Effect of Metal Ions in Soil Using Supercritical CO{sub 2} and TBP Complex

    Park, Jihye; Park, Kwangheon; Jung, Wonyoung [Kyunghee Univ., Yongin (Korea, Republic of)

    2014-10-15

    Decontamination of soil pollution is difficult because the type of contamination largely depends on the characteristics of the pollutant and the area. Also, existing soil decontamination methods generate large quantities of secondary waste and additional process costs. For this reason, new decontamination methods are always under active investigation. A method involving the use of supercritical carbon dioxide with excellent permeability in place of chemical solvents is currently being studied. Unlike other heavy metals in fission products, uranium is used as fuel, and must be handled carefully. Therefore, in this paper, we studied a supercritical carbon dioxide method for decontaminating heavy metal ions in soil using tri-n-butyl phosphate(TBP), which is well known as a ligand for the extraction of metal ions of actinium. We investigated the decontamination effect of heavy metal ions in the soil using TBP-HNO{sub 3} Complex and supercritical carbon dioxide. The study results showed that when heavy metals in soil are extracted using supercritical carbon dioxide, the extraction efficiency is different according to the type of pollutant metal ions in the soil. When TBP-HNO{sub 3} Complex is used with an extractant, uranium extraction is very effective, but lithium, strontium, and cesium extraction is not effective. Therefore, in the case of a mixture of uranium and other metals such as lithium, strontium, cesium, and so on in soil contaminated by fission product leaks from nuclear power plants, we can selectively decontaminate uranium with supercritical carbon dioxide and TBP-HNO{sub 3} Complex.

  13. Tumor immunotargeting using innovative radionuclides.

    Kraeber-Bodéré, Françoise; Rousseau, Caroline; Bodet-Milin, Caroline; Mathieu, Cédric; Guérard, François; Frampas, Eric; Carlier, Thomas; Chouin, Nicolas; Haddad, Ferid; Chatal, Jean-François; Faivre-Chauvet, Alain; Chérel, Michel; Barbet, Jacques

    2015-01-01

    This paper reviews some aspects and recent developments in the use of antibodies to target radionuclides for tumor imaging and therapy. While radiolabeled antibodies have been considered for many years in this context, only a few have reached the level of routine clinical use. However, alternative radionuclides, with more appropriate physical properties, such as lutetium-177 or copper-67, as well as alpha-emitting radionuclides, including astatine-211, bismuth-213, actinium-225, and others are currently reviving hopes in cancer treatments, both in hematological diseases and solid tumors. At the same time, PET imaging, with short-lived radionuclides, such as gallium-68, fluorine-18 or copper-64, or long half-life ones, particularly iodine-124 and zirconium-89 now offers new perspectives in immuno-specific phenotype tumor imaging. New antibody analogues and pretargeting strategies have also considerably improved the performances of tumor immunotargeting and completely renewed the interest in these approaches for imaging and therapy by providing theranostics, companion diagnostics and news tools to make personalized medicine a reality. PMID:25679452

  14. Tumor Immunotargeting Using Innovative Radionuclides

    Françoise Kraeber-Bodéré

    2015-02-01

    Full Text Available This paper reviews some aspects and recent developments in the use of antibodies to target radionuclides for tumor imaging and therapy. While radiolabeled antibodies have been considered for many years in this context, only a few have reached the level of routine clinical use. However, alternative radionuclides, with more appropriate physical properties, such as lutetium-177 or copper-67, as well as alpha-emitting radionuclides, including astatine-211, bismuth-213, actinium-225, and others are currently reviving hopes in cancer treatments, both in hematological diseases and solid tumors. At the same time, PET imaging, with short-lived radionuclides, such as gallium-68, fluorine-18 or copper-64, or long half-life ones, particularly iodine-124 and zirconium-89 now offers new perspectives in immuno-specific phenotype tumor imaging. New antibody analogues and pretargeting strategies have also considerably improved the performances of tumor immunotargeting and completely renewed the interest in these approaches for imaging and therapy by providing theranostics, companion diagnostics and news tools to make personalized medicine a reality.

  15. Purification of lanthanides for double beta decay experiments

    Polischuk, O. G.; Barabash, A. S.; Belli, P.; Bernabei, R.; Boiko, R. S.; Cappella, F.; Cerulli, R.; Danevich, F. A.; Incicchitti, A.; Laubenstein, M.; Mokina, V. M.; Nisi, S.; Poda, D. V.; Tretyak, V. I.

    2013-08-01

    There are several potentially double beta active isotopes among the lanthanide elements. However, even high purity grade lanthanide compounds contain 238U, 226Ra and 232,228Th typically on the level of ˜ (0.1 - 1) Bq/kg. The liquid-liquid extraction technique was used to remove traces of U, Ra and Th from CeO2, Nd2O3 and Gd2O3. The radioactive contamination of the samples before and after the purification was tested by using ultra-low-background HPGe γ spectrometry at the underground Gran Sasso National Laboratories of the INFN (Italy). After the purification the radioactive contamination of gadolinium oxide by Ra and Th was decreased at least one order of magnitude. The efficiency of the approach to purify cerium oxide from Ra was on same level, while the radioactive contamination of neodymium sample before and after the purification is below the sensitivity of analytical methods. The purification method is much less efficient for chemically very similar radioactive elements like lanthanum, lutetium and actinium. R&D of the methods to remove the pollutions with improved efficiency is in progress.

  16. Radionuclides in coastal swampland soils in South Australia - An unusual distribution?

    A plant processing uranium ore was constructed during the 1950's on coastal swamplands at Port Pirie, South Australia, with tailings and chemical residues stored in clay-lined dams on site. Environmental soil samples collected recently from this area showed an unusual radionuclide distribution which suggested possible contamination from the former uranium plant nearby. On subsequent investigation it appears this distribution is a general property of swampland soils. The concentration of uranium in these soils is significantly greater (2-10 times) than that of its decay products, with an observed range of uranium concentrations from 50 to 300 Bq/kg. In contrast, 'normal' soils in South Australia contain between 5 and 60 Bq/kg, with decay products close to secular equilibrium. In addition, actinium (and its parent, protactinium) occur in sediments in greater concentration than expected - 6 to 36 Bq/kg compared with a 'normal soil' range of 0.2 to 3 Bq/kg. Results obtained suggest: organic residues in the sediments play a major part in the concentration of radionuclides; and the probable source of radionuclides is sea-water. These observations are consistent with results of other workers who examined the incorporation of stable trace metals into coastal swampland sediments in South Australia. Representative data are presented and discussed

  17. Study of Thorium Utilization in a Large Scale Sodium Cooled Fast Reactor

    The breeding performance of 232Th in fast reactor is better than 238U, since the capture cross section of 232Th is slightly higher than 238U under the fast neutron spectrum. There are much less fission neutrons in the blanket, so the proportion of neutron with energy above 6MeV (the threshold energy of (n,2n) reaction of 232Th) is very small. Therefore, the 233U produced in fast reactor blanket would have high purity. In this paper, an large scale fast reactor core was taken as the reference core for 232Th utilization study. In the calculation results, the whole capability of 233U production is about 443kg/(GWe•a) in the blanket; at the end of the first cycle (160EFPD), the 233U production per unit mass of 232Th is about 10.71g/(kgTh), and the weight fraction of 232U in actinium is less than 0.019%. It is an attractive technology option to produce 233U in the blanket. (author)

  18. A Critical Review of Alpha Radionuclide Therapy-How to Deal with Recoiling Daughters?

    de Kruijff, Robin M; Wolterbeek, Hubert T; Denkova, Antonia G

    2015-01-01

    This review presents an overview of the successes and challenges currently faced in alpha radionuclide therapy. Alpha particles have an advantage in killing tumour cells as compared to beta or gamma radiation due to their short penetration depth and high linear energy transfer (LET). Touching briefly on the clinical successes of radionuclides emitting only one alpha particle, the main focus of this article lies on those alpha-emitting radionuclides with multiple alpha-emitting daughters in their decay chain. While having the advantage of longer half-lives, the recoiled daughters of radionuclides like 224Ra (radium), 223Ra, and 225Ac (actinium) can do significant damage to healthy tissue when not retained at the tumour site. Three different approaches to deal with this problem are discussed: encapsulation in a nano-carrier, fast uptake of the alpha emitting radionuclides in tumour cells, and local administration. Each approach has been shown to have its advantages and disadvantages, but when larger activities need to be used clinically, nano-carriers appear to be the most promising solution for reducing toxic effects, provided there is no accumulation in healthy tissue. PMID:26066613

  19. A Critical Review of Alpha Radionuclide Therapy—How to Deal with Recoiling Daughters?

    de Kruijff, Robin M.; Wolterbeek, Hubert T.; Denkova, Antonia G.

    2015-01-01

    This review presents an overview of the successes and challenges currently faced in alpha radionuclide therapy. Alpha particles have an advantage in killing tumour cells as compared to beta or gamma radiation due to their short penetration depth and high linear energy transfer (LET). Touching briefly on the clinical successes of radionuclides emitting only one alpha particle, the main focus of this article lies on those alpha-emitting radionuclides with multiple alpha-emitting daughters in their decay chain. While having the advantage of longer half-lives, the recoiled daughters of radionuclides like 224Ra (radium), 223Ra, and 225Ac (actinium) can do significant damage to healthy tissue when not retained at the tumour site. Three different approaches to deal with this problem are discussed: encapsulation in a nano-carrier, fast uptake of the alpha emitting radionuclides in tumour cells, and local administration. Each approach has been shown to have its advantages and disadvantages, but when larger activities need to be used clinically, nano-carriers appear to be the most promising solution for reducing toxic effects, provided there is no accumulation in healthy tissue. PMID:26066613

  20. A Critical Review of Alpha Radionuclide Therapy—How to Deal with Recoiling Daughters?

    Robin M. de Kruijff

    2015-06-01

    Full Text Available This review presents an overview of the successes and challenges currently faced in alpha radionuclide therapy. Alpha particles have an advantage in killing tumour cells as compared to beta or gamma radiation due to their short penetration depth and high linear energy transfer (LET. Touching briefly on the clinical successes of radionuclides emitting only one alpha particle, the main focus of this article lies on those alpha-emitting radionuclides with multiple alpha-emitting daughters in their decay chain. While having the advantage of longer half-lives, the recoiled daughters of radionuclides like 224Ra (radium, 223Ra, and 225Ac (actinium can do significant damage to healthy tissue when not retained at the tumour site. Three different approaches to deal with this problem are discussed: encapsulation in a nano-carrier, fast uptake of the alpha emitting radionuclides in tumour cells, and local administration. Each approach has been shown to have its advantages and disadvantages, but when larger activities need to be used clinically, nano-carriers appear to be the most promising solution for reducing toxic effects, provided there is no accumulation in healthy tissue.

  1. Background radiation and individual dosimetry in the coastal area of Tamil Nadu (India)

    South coast of India is known as the high-level background radiation area (HBRA) mainly due to beach sands that contain natural radionuclides as components of the mineral monazite. The rich deposit of monazite is unevenly distributed along the coastal belt of Tamil Nadu and Kerala. An HBRA site that laid in 2x7 m along the sea was found in the beach of Chinnavillai, Tamil Nadu, where the maximum ambient dose equivalent reached as high as 162.7 mSv y-1. From the sands collected at the HBRA spot, the high-purity germanium semi-conductor detector identified six nuclides of thorium series, four nuclides of uranium series and two nuclides belonging to actinium series. The highest radioactivity observed was 43.7 Bq g-1 of Th-228. The individual dose of five inhabitants in Chinnavillai, as measured by the radiophotoluminescence glass dosimetry system, demonstrated the average dose of 7.17 mSv y-1 ranging from 2.79 to 14.17 mSv y-1. (authors)

  2. Emanations and 'induced' radioactivity: from mystery to (mis)use

    The natural Rn isotopes were discovered within the period 1899-1902 and at that time referred to as emanations because they came out (emanated) of sources/materials containing actinium, thorium and radium, respectively. The (somewhat mysterious) emanations appeared to disintegrate into radioactive decay products which by depositing at solid surfaces gave rise to 'induced' radioactivity i.e. radioactive substances with various half-lives. Following the discovery of the emanations the volume of the research involving them and their disintegration products grew steeply. The identity of a number of these radioactive products was soon established. Radium emanation was soon used as a source of RaD (210Pb) to be applied as an 'indicator' (radiotracer) for lead in a study on the solubility of lead sulphide and lead chromate. Moreover, radium and its emanation were introduced into the medical practice. Inhaling radon and drinking radon-containing water became an accepted medicinal use (or misuse?) of that gas. Shortly after the turn of the century, the healing (?) action of natural springs (spas) was attributed to their radium emanation, i.e. radon. Bathing in radioactive spring water and drinking it became very popular. Even today, bathing in radon-containing water is still a common medical treatment in Jachymov, Czech Republic. (author)

  3. Liquid Scintillation Counting of Environmental Radioisotopes: A Review of the Impact of Background Reduction

    Douglas, Matthew; Bernacki, Bruce E.; Erchinger, Jennifer L.; Finn, Erin C.; Fuller, Erin S.; Hoppe, Eric W.; Keillor, Martin E.; Morley, Shannon M.; Mullen, Crystal A.; Orrell, John L.; Panisko, Mark E.; Warren, Glen A.; Wright, Michael E.

    2016-03-09

    Liquid scintillation counting (LSC) is a versatile and commonplace method for radiometric measurement of charged particle emitting radionuclides. The LSC method provides utility in a range of environmental science applications including hydrological studies of water transport, anthropogenic releases of radionuclides into the environment, and vertical mixing rates within oceans. Instrumental measurement background is one limiting factor of radiometric measurement sensitivity. As part of the development of a custom low background LSC system located in a shallow underground laboratory at Pacific Northwest National Laboratory, a number of measurement applications of LSC have been considered and are summarized here. The focus is on determining which aspects of such measurements would gain the greatest benefit from the reduction of LSC backgrounds by a factor of 10-100 relative to values reported in the literature. Examples of benefits include lowering the minimum detectable activity, reducing the sample size required, and shortening the elapsed timeline of the processing and analysis sequence. In particular tritium, strontium, and actinium isotopes are examined as these isotopes cover a range of requirements related to the LSC measurement method (e.g., 3H: low energy; Sr: spectral deconvolution; Ac: alpha/beta discrimination).

  4. Development of an Ultra-Low Background Liquid Scintillation Counter for Trace Level Analysis

    Erchinger, Jennifer L.; Orrell, John L.; Aalseth, Craig E.; Bernacki, Bruce E.; Douglas, Matthew; Finn, Erin C.; Fuller, Erin S.; Keillor, Martin E.; Morley, Shannon M.; Mullen, Crystal A.; Panisko, Mark E.; Shaff, Sarah M.; Warren, Glen A.; Wright, Michael E.

    2015-09-01

    Low-level liquid scintillation counting (LSC) has been established as one of the radiation detection techniques useful in elucidating environmental processes and environmental monitoring around nuclear facilities. The Ultra-Low Background Liquid Scintillation Counter (ULB-LSC) under construction in the Shallow Underground Laboratory at Pacific Northwest National Laboratory aims to further reduce the MDAs and/or required sample processing. Through layers of passive shielding in conjunction with an active veto and 30 meters water equivalent overburden, the background reduction is expected to be 10 to 100 times below typical analytic low-background liquid scintillation systems. Simulations have shown an expected background of around 14 counts per day. A novel approach to the light collection will use a coated hollow light guide cut into the inner copper shielding. Demonstration LSC measurements will show low-energy detection, spectral deconvolution, and alpha/beta discrimination capabilities, from trials with standards of tritium, strontium-90, and actinium-227, respectively. An overview of the system design and expected demonstration measurements will emphasize the potential applications of the ULB-LSC in environmental monitoring for treaty verification, reach-back sample analysis, and facility inspections.

  5. Enhanced radioactivity due to natural oil and gas production and related radiological problems

    Within the scope of a research contract, the following aspects are considered: External radiation exposure at production sites; internal radiation exposures during cleaning operations such as removing of scale by sand blasting; problems of waste disposal; internal radiation exposure due to radon inhalation by consumers; the origin of the high radium content of brines from oil and gas fields. Enhanced dose rates up to 50 μSv/h have been found at the external surface of saltwater tanks, but 72% of the 160 sites investigated did not show any increase above the natural background. Brines from gas contained radium-226 up to 286 Bq/1 and scale up to 1 kBq/g. In brines and scale from oil fields radium-228 was usually the dominating radionuclide. Some samples contained significant amounts of lead-210 and even actinium-227, too, but practically no uranium or thorium. The radon-222 concentrations in natural gas samples varied between 0.004 and 4 Bq/l with an average value of 0.6 Bq/l. Related radiological problems are discussed. (orig./HP)

  6. Neutron measurements with miniature fission chambers

    This report analyses the use and qualification of miniature fission chambers for two types of neutron measurements: 1) relative measurements in nuclear power reactors, or nuclear irradiation reactors. We consider the problem of burnable fissile material in detectors, under important neutron exposures and conclude on recommending the use of regenerating neutron detectors. 2) Measurements of integral physical parameters in experimental reactors. This method has been applied to measurements of fission rates in detectors with strong alpha-rays emitter deposits in order to establish standard tables of physical parameters. It has been used in particular for detectors including very radioactive actinium series. After a discussion of the instrumentation choice and data processing, specific to each measurements, we provide results on: 1) the technological and neutron behaviour of regenerating miniature fission chambers, in the swimming pool reactor 'TRITON', under a neutron exposure of 7.1020 n cm-2 and a gamma-rays exposure of 1,5.1011 rads about. The fissile material is 235U and the fertile material 234U. 2) The integral measurements of effective cross sections for 241Am and 238Pu in the experimental reactor 'MINERVE' use for study of problems of fast neutron reactors

  7. Quantification of radionuclide transfer in terrestrial and freshwater environments: A summary

    Exposure may occur as a result of incidental releases and discharges from all stages of the nuclear fuel cycle. This includes uranium mines, fuel fabrication facilities, reactors, reprocessing plants and low, intermediate and high level radioactive waste repository sites. Each of these releases involves mainly fission and neutron activation products as well as actinides. Uranium mining and fuel fabrication also involve radionuclides of the uranium, actinium and thorium decay series. In addition, some industries such as mineral sands production and processing, phosphate ore processing, coal burning and oil and gas production can generate naturally occurring radioactive materials (NORMs) as waste. Other sources of human exposure include nuclear weapon testing and radiation accidents or incidents. Any radiological assessments are based on an analysis of radionuclide transport patterns and processes governing radionuclide behaviour in the environment. Therefore, it is an aim of the IAEA to support Member States to enhance their capability for evaluating radionuclide transport, geochemical and biochemical enrichment, and radiation effects on human beings and other biota

  8. Study of Soil Decontamination Method Using Supercritical Carbon Dioxide and TBP

    The result of this study means that we have a possible new method for cheap and less wasteful nuclear waste decontamination. When severe accidents such as the incident at the Fukushima nuclear site occur, the soil near the power plant is contaminated with fission products or the activation metal structure of the power plant. The soil pollution form depends on the environment and soil characteristics of the contaminated areas. Thus, a- single-decontamination method is not effective for site cleanup. In addition, some soil decontamination methods are expensive and large amounts of secondary waste are generated. Therefore, we need new soil decontamination methods. In this study, instead of using a conventional solvent method that generates secondary waste, supercritical carbon dioxide was used to remove metal ions from the soil. Supercritical carbon dioxide is known for good permeation characteristics. We expect that we will reduce the cost of soil pollution management. Supercritical carbon dioxide can decontaminate soil easily, as it has the ability to penetrate even narrow gaps with very good moisture permeability. We used TBP, which is a known for extractant of actinium metal. TBP is usually used for uranium and strontium extraction. Using TBP-HNO3 complex and supercritical carbon dioxide, we did extraction experiments for several heavy metals in contaminated soil

  9. Selective Decontamination Effect of Metal Ions in Soil Using Supercritical CO2 and TBP Complex

    Decontamination of soil pollution is difficult because the type of contamination largely depends on the characteristics of the pollutant and the area. Also, existing soil decontamination methods generate large quantities of secondary waste and additional process costs. For this reason, new decontamination methods are always under active investigation. A method involving the use of supercritical carbon dioxide with excellent permeability in place of chemical solvents is currently being studied. Unlike other heavy metals in fission products, uranium is used as fuel, and must be handled carefully. Therefore, in this paper, we studied a supercritical carbon dioxide method for decontaminating heavy metal ions in soil using tri-n-butyl phosphate(TBP), which is well known as a ligand for the extraction of metal ions of actinium. We investigated the decontamination effect of heavy metal ions in the soil using TBP-HNO3 Complex and supercritical carbon dioxide. The study results showed that when heavy metals in soil are extracted using supercritical carbon dioxide, the extraction efficiency is different according to the type of pollutant metal ions in the soil. When TBP-HNO3 Complex is used with an extractant, uranium extraction is very effective, but lithium, strontium, and cesium extraction is not effective. Therefore, in the case of a mixture of uranium and other metals such as lithium, strontium, cesium, and so on in soil contaminated by fission product leaks from nuclear power plants, we can selectively decontaminate uranium with supercritical carbon dioxide and TBP-HNO3 Complex

  10. Exposure to radioactive aerosols in mining and milling operations: the importance of 227Ac and 231Pa

    'Full-Text:' 227Ac (half-life of 21.8 y) is the daughter or 231Pa; a beta emitter and parent of a subseries with five short-lived alpha-emitters. 231Pa (half-life of 3.27x104 y) is an alpha-emitter of the actinium series, the decay chain of 235U. As daughters of this uranium isotope they are thought to be unimportant as a radiological hazard, despite the fact that their ALI values for ingestion and inhalation are the lowest of any other radionuclide. Both nuclides can be considered as being in secular equilibrium with uranium in most geological media and so the mass concentration of 231Pa is the same of the 226Ra and that of 227Ac is the same of the 210Pa, to mention only two radionuclides of radiological concern. It is shown in this paper that if 231Pa and 227Ac are considered in the evaluations of dose commitments incurred by inhalation of aerosols in mining and milling operations, the results can be 70% higher than those calculated by the methodology of ICRP Publication 47. (author)

  11. Radium-228 determination of natural waters via concentration on manganese dioxide and separation using Diphonix ion exchange resin

    The objective of this work was to establish a new procedure for 228Ra determination of natural waters via preconcentration of radium on MnO2 and separation of its daughter, 228Ac, using Diphonix ion exchange resin. Following removal of potential interferences via passage through an initial Diphonix Resin column, the first daughter of 228Ra, 228Ac, is isolated by chromatographic separation via a second Diphonix column. A holding time of >30 h for 228Ac ingrowth in between the two column separations ensures secular equilibrium. Barium-133 is used as a yield tracer. Actinium-228 is eluted from the second Diphonix Resin with 5 ml 1 M 1-Hydroxyethane-1,1-diphosphonic acid (HEDPA) and quantified by addition of scintillation cocktail and LSC counting. Radium (and 133Ba) from the load and rinse solutions from the 2nd Diphonix column may be prepared for alpha spectrometry (for determination of 223Ra, 224Ra, and 226Ra) by BaSO4 microprecipitation and filtration. Decontamination tests indicate that U, Th, and Ra series nuclides do not interfere with these measurements, although high contents of 90Sr (90Y) require additional treatment for accurate measurement of 228Ra. Addition of stable Sr as a 'hold back' carrier during the initial MnO2 preconcentration step was shown to remove most 90Sr interference

  12. Soil and river sediments radionuclides monitoring at Aramar Experimental Center: an historical overview

    In order to evaluate possible effects to the environment resulting from the implementation of the Centro Tecnologico da Marinha - Centro Experimental Aramar (CTMSP-CEA) at Ipero in Sao Paulo state, Brazil, which came into operation in 1989, an Environmental Monitoring Program (PMA) was established in October, 1987. One of the aims of this program is to monitor the soil and river sediments radionuclides levels at CEA and beyond its boundary. The utilization of statistical tools to evaluate the results of radiometric environmental monitoring is a procedure required by National Nuclear Energy Commission (CNEN). The box plot is a simple statistical tool for displaying data. The central tendency and dispersion of the results as well as the observation of unusual results (outliers) in the dataset are easily visualized. Control chart is a graph that maps data and provides a picture of how a process is performing over time. A control chart always has a central line for the mean, an upper line for the upper control limit and a lower line for the lower control limit. Box plots and control charts were used to visualize the annual amount of natural uranium, lead-214, actinium-228 and lead-212 in soil and river sediment detected between 1987 and 2011, considering the measurements of all monitored places each year. This historical observation shows that, in average, the results obtained are below than the 1987-1988 levels (CEA's pre-operational) or below than the backgrounds radionuclides values. (author)

  13. Theoretical Study on Properties of New Isotope 265Bh

    The properties of nuclei belonging to the newly observed α-decay chain starting from 265Bh have been studied. The axially deformed relativistic mean-field calculation with the force NL-Z2 has been performed in the blocked BCS approximation. Some ground state properties such as binding energies, deformations, spins, and parities, as well as Q-values of the α-decay for this decay chain have been calculated and compared with known experimental data. Good agreement is found. The single-particle spectrum of the nucleus 265Bh is studied and some new magic numbers are found, while the magnitudes of the shell gaps in superheavy nuclei are much smaller than those of nuclei before the actinium region, and the Fermi surfaces are close to the continuum. Thus the superheavy nuclei are usually not stable. The α-decay lifetimes in the 265Bh decay chain are evaluated by different formulae, and compared with experimental data. The methods which give good agreement with the data are selected.

  14. Workplace monitoring and related health hazard evaluation in South African mining and mineral processing industries by application of nuclear and related analytical techniques

    The South African Government notice R 849 (23 April 1994) requires application to the South African Council for Nuclear Safety (CNS) for a nuclear licence if materials are dealt with that contain more than 0,2 but less than 1 Becquerel per gram of any radionuclide of the natural uranium, thorium and actinium decay series. If the material is to be used in the construction of buildings the application should have been made before 1 April 1996, otherwise before 31 March 1999. The first phase of the monitoring programme assesses the observed radioactivity levels of waste products and the possible radiological impact on people working on site and living in the direct environment of the operational site. Information has been obtained on the radionuclide content and elemental composition of the various sources of the coal, waste ash, ash related products, crusher materials and effluent water. Except for the effluent and coal samples all other materials showed activity levels for one or more nuclides above the 0,2 Bq/g but not exceeding the 1 Bq/g level. Accordingly a first order assessment of the possible radiological impact on workers and the public has been performed for water consumption and dust inhalation. Actual dust concentrations recorded at various sites within the operational area are used to evaluate the yearly dose to workers. (author)

  15. Purification of lanthanides for double beta decay experiments

    Polischuk, O. G. [Institute for Nuclear Research, MSP 03680 Kyiv, Ukraine and INFN, Section of Rome, La Sapienza, I-00185 Rome (Italy); Barabash, A. S. [Institute of Theoretical and Experimental Physics, 117259 Moscow (Russian Federation); Belli, P. [INFN, Section of Rome Tor Vergata, I-00133 Rome (Italy); Bernabei, R. [INFN, Section of Rome Tor Vergata, I-00133 Rome, Italy and Department of Physics, University of Rome Tor Vergata, I-00133 Rome (Italy); Boiko, R. S.; Danevich, F. A.; Mokina, V. M.; Poda, D. V.; Tretyak, V. I. [Institute for Nuclear Research, MSP 03680 Kyiv (Ukraine); Cappella, F.; Incicchitti, A. [INFN, Section of Rome La Sapienza, I-00185 Rome, Italy and Department of Physics, University of Rome La Sapienza, I-00185 Rome (Italy); Cerulli, R.; Laubenstein, M.; Nisi, S. [INFN, Gran Sasso National Laboratories, I-67100 Assergi (Aq) (Italy)

    2013-08-08

    There are several potentially double beta active isotopes among the lanthanide elements. However, even high purity grade lanthanide compounds contain {sup 238}U, {sup 226}Ra and {sup 232,228}Th typically on the level of ∼ (0.1 - 1) Bq/kg. The liquid-liquid extraction technique was used to remove traces of U, Ra and Th from CeO{sub 2}, Nd{sub 2}O{sub 3} and Gd{sub 2}O{sub 3}. The radioactive contamination of the samples before and after the purification was tested by using ultra-low-background HPGe γ spectrometry at the underground Gran Sasso National Laboratories of the INFN (Italy). After the purification the radioactive contamination of gadolinium oxide by Ra and Th was decreased at least one order of magnitude. The efficiency of the approach to purify cerium oxide from Ra was on same level, while the radioactive contamination of neodymium sample before and after the purification is below the sensitivity of analytical methods. The purification method is much less efficient for chemically very similar radioactive elements like lanthanum, lutetium and actinium. R and D of the methods to remove the pollutions with improved efficiency is in progress.

  16. Astatine-211 Pathway from Radiochemistry to Clinical Investigation

    Particularly in clinical settings where tumour burden is low and cancers are located in close proximity to essential normal tissue structures, α-particle emitting radionuclides can offer significant advantages for targeted radionuclide therapy. One of the first alpha emitters to be evaluated for this purpose is the 7.2-h half-life radiohalogen Astatine-211 (211At). From a commercialization-potential perspective 211At, is less appealing than the longer half-life alpha particle emitters Radium-223, Actinium-225 and Thorium-227, which have become the focus of many laboratories. However, if methods for providing a better supply of 211At could be developed, this alpha emitter would be the radionuclide of choice for many potential therapeutic applications. With regard to the production of 211At, this can be readily be accomplished by bombarding natural bismuth targets with 28−29.5 MeV alpha particles via the 209Bi(α,2n)211At reaction. The goal is to utilize an alpha particle beam energy that provides the required balance for maximizing 211At production while minimizing creation of 210At, which is problematic because of its 138.4-day half life alpha-particle emitting daughter, 210Po. For most intended clinical applications, alpha particle beam energy of about 29 MeV offers the best compromise between maximizing yield and providing 211At with sufficient radionuclidic purity for clinical use. Clinically relevant levels of 211At have been produced at several institutions using both internal and external cyclotron targets

  17. Selective alpha-particle mediated depletion of tumor vasculature with vascular normalization.

    Jaspreet Singh Jaggi

    Full Text Available BACKGROUND: Abnormal regulation of angiogenesis in tumors results in the formation of vessels that are necessary for tumor growth, but compromised in structure and function. Abnormal tumor vasculature impairs oxygen and drug delivery and results in radiotherapy and chemotherapy resistance, respectively. Alpha particles are extraordinarily potent, short-ranged radiations with geometry uniquely suitable for selectively killing neovasculature. METHODOLOGY AND PRINCIPAL FINDINGS: Actinium-225 ((225Ac-E4G10, an alpha-emitting antibody construct reactive with the unengaged form of vascular endothelial cadherin, is capable of potent, selective killing of tumor neovascular endothelium and late endothelial progenitors in bone-marrow and blood. No specific normal-tissue uptake of E4G10 was seen by imaging or post-mortem biodistribution studies in mice. In a mouse-model of prostatic carcinoma, (225Ac-E4G10 treatment resulted in inhibition of tumor growth, lower serum prostate specific antigen level and markedly prolonged survival, which was further enhanced by subsequent administration of paclitaxel. Immunohistochemistry revealed lower vessel density and enhanced tumor cell apoptosis in (225Ac-E4G10 treated tumors. Additionally, the residual tumor vasculature appeared normalized as evident by enhanced pericyte coverage following (225Ac-E4G10 therapy. However, no toxicity was observed in vascularized normal organs following (225Ac-E4G10 therapy. CONCLUSIONS: The data suggest that alpha-particle immunotherapy to neovasculature, alone or in combination with sequential chemotherapy, is an effective approach to cancer therapy.

  18. Determination of radium in water

    These detailed work instructions (DWIs) are tailored for the analysis of radium-226 and radium-228 in drinking water supplies from ground water and surface water sources and composites derived from them. The instructions have been adapted from several sources, including a draft EPA method. One objective was to minimize the generation of mixed wastes. Quantitative determinations of actinium-228 are made at 911 keV. The minimum detection level (MDL) for the gamma spectrometric measurements at this energy vary with matrix, volume, geometry, detector, background, and counting statistics. The range of MDL's for current detectors is 0.07 to 0.5 Bq/sample. Quantitative determinations of radium-226 are made by counting the high energy alpha particles which radium-226 progeny emit using liquid scintillation counting (LSC). The minimum detectable activity (MDA) is 3.8 E-3 Bq/sample. The maximum concentration which may be counted on available instruments without dilution is about 2 E + 5 Bq/sample. Typically, this determination of radium in a 2 L sample has a yield of 80%. If radium-228 is determined using a 16 h count after 50 h grow-in, the typical MDL is 1 E-9 to 8 E-9 μCi/mL (1 to 8 pCi/L). If radium-226 is determined using a 2.5 h count after 150 h grow-in, the typical MDA is about 1 E-10 μCi/mL (0. 1 pCi/L)

  19. Determination of radium in water

    Hohorst, F.A.; Huntley, M.W.; Hartenstein, S.D.

    1995-10-01

    These detailed work instructions (DWIs) are tailored for the analysis of radium-226 and radium-228 in drinking water supplies from ground water and surface water sources and composites derived from them. The instructions have been adapted from several sources, including a draft EPA method. One objective was to minimize the generation of mixed wastes. Quantitative determinations of actinium-228 are made at 911 keV. The minimum detection level (MDL) for the gamma spectrometric measurements at this energy vary with matrix, volume, geometry, detector, background, and counting statistics. The range of MDL`s for current detectors is 0.07 to 0.5 Bq/sample. Quantitative determinations of radium-226 are made by counting the high energy alpha particles which radium-226 progeny emit using liquid scintillation counting (LSC). The minimum detectable activity (MDA) is 3.8 E-3 Bq/sample. The maximum concentration which may be counted on available instruments without dilution is about 2 E + 5 Bq/sample. Typically, this determination of radium in a 2 L sample has a yield of 80%. If radium-228 is determined using a 16 h count after 50 h grow-in, the typical MDL is 1 E-9 to 8 E-9 {mu}Ci/mL (1 to 8 pCi/L). If radium-226 is determined using a 2.5 h count after 150 h grow-in, the typical MDA is about 1 E-10 {mu}Ci/mL (0. 1 pCi/L).

  20. The Properties of Trilaurylmethylammonium Nitrate as an Extractant for Trivalent Actinides. RCN Report

    The concept of the group of the actinide elements as a f-type transition series within the periodic system was first launched by G.T. Seaborg in 1944]. In this transition series the filling up of the 5 f electron shell would cause a close similarity with the lanthanide series. This proved to be a very fruitful hypothesis in the prediction of the properties of the new elements americium and curium that soon were discovered. The new hypothesis necessitated a shift of the accepted ideas concerning the place of the elements thorium, protactinium and uranium in the periodic table. In fact, the chemistry of these elements had never been considered to be so closely parallel to that of the lanthanides. On the contrary, the trend in the stability of the oxidation states had been interpreted to indicate that these elements would belong to group IVA, VA and VIA respectively. It is undeniable that there are marked differences in oxidation states between the lanthanide elements and the first six elements of the actinide series. However, physical and chemical investigations both of the newly discovered elements and the elements actinium to uranium disclosed many resemblances with the lanthanides that had not been noticed before in this group. The actinide elements - and more in particular the transuranium elements - have been the subject of a number of monographs covering the discovery, the synthesis, the systematics, the chemistry, and (or) the nuclear properties of these elements. It is for this reason that the scope of the following sections in this chapter will be limited to a summary of the chemistry in sofar as it is relevant to the investigations described in the following chapters, viz., the properties of the elements in aqueous systems and more in particular in those systems containing nitrate ions

  1. Alpha Emitting Radionuclides and Radiopharmaceuticals for Therapy

    Today, cancer treatments mainly rely on surgery or external beam radiation to remove or destroy bulky tumors. Chemotherapy is given when tumours cannot be removed or when dissemination is suspected. However, these approaches cannot permanently treat all cancers and relapse occurs in up to 50% of the patients’ population. Radioimmunotherapy (RIT) and peptide receptor radionuclide therapy (PRRT) are effective against some disseminated and metastatic diseases, although they are rarely curative. Most preclinical and clinical developments in this field have involved electron-emitting radionuclides, particularly iodine-131, yttrium-90 and lutetium-177. The large range of the electrons emitted by these radionuclides reduces their efficacy against very small tumour cell clusters or isolated tumour cells present in residual disease and in many haematological tumours (leukaemia, myeloma). The range of alpha particles in biological tissues is very short, less than 0.1 mm, which makes alpha emitters theoretically ideal for treatment of such isolated tumour cells or micro-clusters of malignant cells. Thus, over the last decade, a growing interest for the use of alpha-emitting radionuclides has emerged. Research on targeted alpha therapy (TAT) began years ago in Nantes through cooperation between Subatech, a nuclear physics laboratory, CRCNA, a cancer research centre with a nuclear oncology team and ITU (Karlsruhe, Germany). CD138 was demonstrated as a potential target antigen for Multiple Myeloma, which is a target of huge clinical interest particularly suited for TAT because of the disseminated nature of the disease consisting primarily of isolated cells and small clusters of tumour cells mainly localized in the bone marrow. Thus anti-CD138 antibodies were labelled with bismuth-213 from actinium-225/bismuth-213 generators provided by ITU and used to target multiple myeloma cells. In vitro studies showed cell cycle arrest, synergism with chemotherapy and very little induction

  2. Radiological analysis of environmental samples in some points of the coast of the Gulf of Mexico and Coast of Quintana Roo, Mexico

    Full text: We describe in this paper the results obtained by the project 'Radiological analysis of environmental samples in some points of the coast of the Gulf of Mexico and coast of Quintana Roo, Mexico'. The purpose of the study is to identify and quantify the natural and anthropogenic radionuclides present from sediments, sand and seawater from several sites located along the coast of the Gulf of Mexico and the Caribean Sea. The samples are analysed in a Canberra Multichannel analyzer system for gamma spectrometry, equipped with a detector of hyper pure germanium and a Genie 2000 software, in the 'Laboratory of Radiological Analysis of Environmental Samples', belonging to the Physics Department, Faculty of Sciences, National Autonomous University of Mexico (UNAM). The geographic sites were samples were taken include the states of Tamaulipas, Veracruz, Tabasco, Campeche, Yucatan and Quintana Roo. The results of this studies will be published at the end of the project and we hope they will be useful for the national health and industrial sectors. Until now we have identified and measured the presence of natural radionuclides such as Potassium-40 (K-40), Bismuth 212 (Bi-212), Lead-212 (Pb-212), Bismuth-214 (Bi-214), Lead-214 (Pb-214), Radium-226 (Ra-226), Actinium 228 (Ac-228), Uranium-235 (U-235), as well as some anthropogenic radionuclides found near the Laguna Verde Nuclear Power Plant. The project is scheduled to last for three years, finishing in 2009. At its ending we shall be able to present conclusions and identify some tendencies, in connection with the background and possible radioactive contamination of the studied zones. This project takes place under the auspice of the 'Program of Support to Projects of Research and Technological Innovation' of the National Autonomous University of Mexico. (author)

  3. The effects of actinide separation on the radiological consequences of disposal of high-level radioactive waste on the ocean bed

    One option in the management of high-level radioactive wastes is to separate the actinides prior to vitrification and disposal. This option is examined in the context of disposal of high-level wastes on the deep ocean bed. The initial quantity of waste corresponds to the generation of 1000 GW(e)y of nuclear energy, and the actinide-separation process is assumed to remove 99% of all elements of atomic number greater than that of actinium. The models used to describe the dispersion of activity from a single disposal site on the bed of the Atlantic Ocean represent both local dispersion and long-term mixing. Collective doses and doses to individuals are calculated for six potential pathways: ingestion of fish, crustacea, molluscs, plankton and seaweed, and external irradiation from contaminated beach sediments. The period from 400 to 1,000,000 years after disposal is considered. The potential radiological impact from disposal of high-level waste without separation of actinides on the ocean bed arises from the actinides; isotopes of americium, neptunium and plutonium give the highest doses. Actinide separation would reduce these doses in proportion to the effectiveness of the separation process, until doses become determined by fission products rather than actinides: the achievable dose reduction would be a factor of approximately a hundred, or less for certain pathways. This reduction applies only to doses to the public from waste disposal: no account was taken of doses arising from the separation process itself or from the management of the separated actinides. The results of the assessment are contrasted with those of similar studies based on toxicity indices. Major deficiencies are identified in the use of toxicity indices as a basis for decision-making. (author)

  4. An aerial radiological survey of the Nevada Test Site

    A team from the Remote Sensing Laboratory conducted an aerial radiological survey of the US Department of Energy's Nevada Test Site including three neighboring areas during August and September 1994. The survey team measured the terrestrial gamma radiation at the Nevada Test Site to determine the levels of natural and man-made radiation. This survey included the areas covered by previous surveys conducted from 1962 through 1993. The results of the aerial survey showed a terrestrial background exposure rate that varied from less than 6 microroentgens per hour (mR/h) to 50 mR/h plus a cosmic-ray contribution that varied from 4.5 mR/h at an elevation of 900 meters (3,000 feet) to 8.5 mR/h at 2,400 meters (8,000 feet). In addition to the principal gamma-emitting, naturally occurring isotopes (potassium-40, thallium-208, bismuth-214, and actinium-228), the man-made radioactive isotopes found in this survey were cobalt-60, cesium-137, europium-152, protactinium-234m an indicator of depleted uranium, and americium-241, which are due to human actions in the survey area. Individual, site-wide plots of gross terrestrial exposure rate, man-made exposure rate, and americium-241 activity (approximating the distribution of all transuranic material) are presented. In addition, expanded plots of individual areas exhibiting these man-made contaminations are given. A comparison is made between the data from this survey and previous aerial radiological surveys of the Nevada Test Site. Some previous ground-based measurements are discussed and related to the aerial data. In regions away from man-made activity, the exposure rates inferred from the gamma-ray measurements collected during this survey agreed very well with the exposure rates inferred from previous aerial surveys

  5. Leaching of uranyl-silica complexes from the host metapelite rock favoring high radon activity of subsoil air: case of Castanar cave (Spain)

    Castanar cave is a subterranean site with an outstanding natural environmental radioactivity. The maintaining of high radon activity of cave air and the detection of spatially anomalies of this gas in some cave emplacements, suggests that some natural geochemical processes are involved on the mobilization of radioactivity sources to cave environment, other than a simple exhalation of radon from the host-rock. The host rocks are interlaid dolostone-metapelite beds with radioactive nuclides of the three actinium, thorium and uranium decay series. In situ measurements on the spatial distribution of radioactivity, uranyl group's luminescence and radon gas concentrations inside cave were main focus of this work to model lixiviation and deposition mechanisms of radioactive elements from the host rock to the karstic system. In addition, collected micro-samples were also analyzed by a multi-approach suite of analytical techniques: inductively coupled plasma mass spectrometry, environmental scanning electron microscopy with an attached X-ray energy dispersive system and spectral cathodoluminescence detector, thermoluminescence, Raman spectroscopy, X-ray diffraction, differential-thermal and thermogravimetry analysis, Alpha-spectrometry and Gamma-spectrometry techniques. The host metapelitic beds contain Zr(Hf)-Th(U)-Ti-P-REE phases such as zircon, xenotime-(Y), monazite-(Ce, La) and poly-metallic mineralization veins of hydrothermal origin. Carbonated host beds and speleothems show frequently chemical elements leaked from the upper host rock masses. The weathering leakage processes are favored by the existence of pyrite and limonite in the dolostone masses. The cave exhibits under UV lamps abundant hydrous silica-uranyl coatings covering carbonated speleothems with radionuclides of 238U natural decay series. The long-lived radio-nuclides of the radium radioactive decay chain are responsible of the continuous regeneration of radon gas inside cave. The experimental work was

  6. Alpha-emitting isotopes and chromium in a coastal California aquifer

    Densmore, Jill N.; Izbicki, John A.; Murtaugh, Joseph M.; Swarzenski, Peter W.; Bullen, Thomas D.

    2014-01-01

    The unadjusted 72-h gross alpha activities in water from two wells completed in marine and alluvial deposits in a coastal southern California aquifer 40 km north of San Diego were 15 and 25 picoCuries per liter (pCi/L). Although activities were below the Maximum Contaminant Level (MCL) of 15 pCi/L, when adjusted for uranium activity; there is concern that new wells in the area may exceed MCLs, or that future regulations may limit water use from the wells. Coupled well-bore flow and depth-dependent water-quality data collected from the wells in 2011 (with analyses for isotopes within the uranium, actinium, and thorium decay-chains) show gross alpha activity in marine deposits is associated with decay of naturally-occurring 238U and its daughter 234U. Radon activities in marine deposits were as high as 2230 pCi/L. In contrast, gross alpha activities in overlying alluvium within the Piedra de Lumbre watershed, eroded from the nearby San Onofre Hills, were associated with decay of 232Th, including its daughter 224Ra. Radon activities in alluvium from Piedra de Lumbre of 450 pCi/L were lower than in marine deposits. Chromium VI concentrations in marine deposits were less than the California MCL of 10 μg/L (effective July 1, 2014) but δ53Cr compositions were near zero and within reported ranges for anthropogenic chromium. Alluvial deposits from the nearby Las Flores watershed, which drains a larger area having diverse geology, has low alpha activities and chromium as a result of geologic and geochemical conditions and may be more promising for future water-supply development.

  7. Natural radiation exposure occurring at handling, storage and disposal of natural radioactive materials; Strahlenbelastung bei Umgang, Lagerung und Abfallhaltung von natuerlicher Radioaktivitaet in Rohstoffen

    Brunner, Peter [Innsbruck Univ. (Austria). Inst. fuer Analytische Chemie und Radiochemie

    2009-07-01

    Processing certain raw materials containing natural radioactive isotopes (e.g. U-238, Th-232 or K- 40) into products such as glas, abrasives, grinding materials or electrodes used for gasshielded tungsten-arc welding also leads to certain concentrations of industrial waste containing natural radioactive materials. Such industrial waste does not necessarily contain natural radioactive substances in concentrations exceeding the highest possible levels but nevertheless in significantly measurable quantities. This, however, frequently leads to confusion bordering on irritation by entities processing such substances as well as the general public, since they tend to believe natural radioactive substances in unobjectable concentration to cause similar or identical - health - consequences as man made radioactive substances in detrimental concentration. Radioactive materials may be incorporated intentionally or unintentionally into the product as main or additional ingredients. The recent Austrian Regulation on Natural Radioactive Materials (NatStrSchV 2008) is applicable for entities processing substances containing high levels of natural Uranium or Thorium e.g. abrasives used with high-pressure-liquid-cutting or at sandblasting. However, if the quantities used do not exceed 1500 Kg per entity the aforesaid Regulation does not apply. Furthermore aforesaid Regulation applies to operations producing - among others - residue substances containing higher doses of Uranium or Thorium (in various shapes) as well as decay products thereof. Isotopes of the Uranium-Radium decay-chain, isotopes of the Thorium-Actinium decay-chain as well as primordial K-40 are being analyzed using gammaspectroscopy. The abovementioned Regulation stipulates that if substances or residues do show an activity concentration not exceeding 1 Bq/g per radionuclid of the decay-chains of Uranium or Thorium it may be deducted that the effective dose concerning occupational radiation exposition of 1 mSv per

  8. Report for General Research July 10 to October 2, 1950 (Supporting Research Volume)

    Haring, M M

    1950-11-06

    The efficient prosecution of the research and process development on polonium, radium, actinium, waste disposal, and alpha-neutron sources requires the use of a wide variety of instrumental techniques such as: alpha, beta, gamma, and neutron counters and survey meters; emission, absorption, and mass spectroscopy: x-ray and electron diffraction; microbalances; and calorimeters. The complex and kaleidoscopic aspects of our research program require; (1) The application of standard instruments and techniques to a variety of problems; (2) The development of new techniques for the use of standard instruments; and (3) The development of new or improved Instruments. The sum of the above three categories constitutes the field of supporting research. The amplifier for counting pulses of wide dynamic range which was developed for counting beta particles in the presence of alphas has operated so satisfactorily that it has been decided to attempt to adopt it for neutron counting. Substantial improvement at medium counting rates has already been obtained but results at high counting rates are not as satisfactory. The development of a survey meter for monitoring fast neutrons has been under way for sometime. The attainment of higher efficiency has been attempted by the use of a dual-chambered counter tube. The tube operates with a filling of methane gas at two atmospheres pressure. The achievement of leak-proof seals and highest purity methane has been under investigation as their necessity has been indicated by tests. The development of a scintillation counter for surveying and measuring low levels of alpha activity has been continued. Recent efforts have been directed towards determining the correct voltages to be applied to the photomultiplier tube in order to operate under optimum conditions. Recent tests of the coincidence counter to detect scintillations in water containing alpha-active waste material have indicated the necessity of obtaining photomultiplier tubes with low

  9. Radiological survey of the Mallinckrodt Chemical Works, St. Louis, Missouri

    Goldsmith, W A; Leggett, R W; Haywood, F F

    1981-12-01

    The results of a radiological survey of part of the Mallinckrodt Chemical Works (former Destrehan and Broadway Street plants), St. Louis, Missouri, are presented. During the period 1942 through 1957, this site was used for various projects involving the production of purified uranium from pitchblende concentrates. The survey included measurements of the following: residual alpha and beta-gamma contamination levels in the existing buildings that were used in the uranium projects; external gamma radiation levels at 1 m above the surface in these buildings and outdoors around these buildings; radon and radon daughter concentrations in the air in these buildings; uranium, radium, actinium, and thorium concentrations in surface and subsurface soil on the site; concentrations of radionuclides in water and sediment found in drains both inside and outside the buildings; and concentrations of radionuclides in ground and surface water on the site and in river water taken near the site. Alpha and beta-gamma contamination levels inside and outside some of the buildings were above limits set by current federal guidelines concerning the release of property for unrestricted use. Elevated external gamma radiation levels were measured at some outdoor locations and in some of the buildings. Licensable concentrations of uranium were found in soil at some places, and the concentration of uranium in a water sample taken from a core hole between Buildings 100 and 101 was in excess of limits set by current federal standards. Radon and radon daughter concentrations in three buildings were in excess of current federal guidelines for nonoccupational radiation exposure.

  10. Track 8: health and radiological applications. Isotopes and radiation: general. 3. Extraction of 229Th from 233U for Medical Research Applications

    the handling of 233U. After separation, the thorium is transferred to the ORNL Radiochemical Development Laboratory (RDL) for decay and periodic extraction of actinium. The safety basis for the RMAL has recently been upgraded to allow the processing of batches containing up to 500 g of 233U. The 233U from Mound Laboratories was delivered in 20 packages, each containing 232U contamination ranges from 2 to 16 ppm. Individual packages of uranium oxide are transferred from the RDF to the RMAL, the package is opened, and the quantity of uranium is verified. The uranium oxide is dissolved in nitric acid, and the solution is adjusted to 8 M. The solution is passed over a Bio-Rad 1x4 anion exchange column at a rate of ∼5 ml/ min. Thorium and plutonium load on the column; uranium, radium, and actinium pass through. The column is washed with 8 M nitric acid to remove residual uranium. Thorium is then eluted from the resin with 0.1 M nitric acid. This solution, typically containing ∼4 mCi of 229Th, is transferred to the RDL for further purification and is then added to the existing thorium inventory. The uranium and acid wash solutions are combined and evaporated to 3O8 by heating in air to 800 deg. C. The oxide is sampled, weighed, packaged, and returned to storage in the RDF. In fiscal year 2000, the process was set up and two small batches of uranium, with 2 ppm 232U, were processed. Because of the low dose associated with this material and to allow refinements to the process, these initial batches were processed in a glove box. The process performed well, with more than 90% recovery of thorium. Just over 5 mCi of 229Th was added to the inventory. Funding already provided for fiscal year 2001 will allow the extraction of another 30 mCi of 229Th; if additional funding can be identified, a total of nearly 70 mCi can be separated by the end of the fiscal year. With this additional thorium, and with other improvements to the actinium extraction facilities at the RDL, the

  11. TINGKAT KANDUNGAN UNSUR RADIOAKTIF AIR SUNGAI AYUNG DI DENPASAR BALI

    Dewa Nyoman Alit Ardana

    2012-11-01

    Full Text Available Ayung river is one of the longest rivers in Bali. The upstream of the river is in regency of Bangli, Badung, Buleleng, Tabananand downstream is located in Padang Galak beach, East Denpasar Sub-regency. As the sample of the study, the water of the river wastaken from the stream entering the city of Denpasar. The sample was taken in five different points and for each point was taken twice. Thefirst was taken at 5 p.m, and the second was at 6 a.m. This study aims at finding out the rate of radioactive content of Ayung river water inthe city of Denpasar.The water sample was analyzed in Radiometry Analysis Group of Radiation Physics and environmental research centre andNuclear Technique Development, Jalan Taman Sari 71 Bandung – 40132. The process of counting was conducted in this place in order toknow the rate of the element activities and then identification of elements contens in the sample. The result of the counting and identifyingwas compered with standard grade of radioactivity in the area.The element of identification result and the amount of activity rate found showed that the element were natural radioactiveelements, the content: 40K (Kalium-40, 234Th (Thorium-234, 233Th (Thorium-233, 228Ac (Actinium-288, 114mIn (Indium-114m. Thehighest activity of radioactive elements in each sample point: in E2 point content element 40K with the activity 2.08 Bq/lt, in point A1 234Thwith the activity 16.34 Bq/lt, in point E1 containts 233Th with activity 598.29 Bq/lt, in point E1 and E2 contain 228Ac with the activity939.63 Bq/lt. The height of activity value of the counting and identifying elements was still under the rate of the highest level.The result of the study showed that radioactive elements 40K had the tendency of increasing radioactivity. The same thinghappened to 233Th at the peak of energi 185.00 keV. The content of its radioactive tends to exist in each point of sample point and theactivity tends to increase. Though the rate of

  12. Termination of Safeguards on ULWBR Material

    Ivan R. Thomas; Ernest L. Laible

    2008-07-01

    The Department of Energy (DOE), Office of Environmental Management, has approved the disposition of 31 metric tons of Unirradiated Light Water Breeder Reactor (ULWBR) material in canisters stored within dry wells of the Underground Fuel Storage Facility at the Idaho Nuclear Technology and Engineering Center (INTEC). This unirradiated material consists primarily of ceramic pellets of thorium oxide in stainless steel cladding, but it also contains 300 kilograms of uranium that is 98 wt% U-233. The ULWBR material was not processed at the INTEC because it was incompatible with prior chemical separation schemes. Other economical recovery options have not been identified, and expressions of interest for consolidating the material with existing projects at other DOE sites have not been received. The U-233 could be used for producing the medical isotope Actinium-225, but the proof-of-principle demonstration and follow-on pilot program have not been developed to the point of requiring production quantities of U-233. Consequently, the selected disposition of the ULWBR material was burial as Low Level Waste at the Nevada Test Site (NTS), which required terminating safeguards controls for the contained Category II quantity of Attractiveness Level D special nuclear material (SNM). The requested termination followed the twelve point evaluation criteria of the Historical Defense Program Discard Guidance and included a security analysis for evaluating the risks of theft, diversion, and radiological sabotage associated with the material. Continuity of knowledge in the book inventory was assured by documenting that the original shipper’s measurements accurately reflected the quantities of materials received and that the ULWBR materials had remained under adequate physical protection and had been subject to periodic physical inventories. The method selected for substantiating the book values as the basis for terminating safeguards was the nondestructive assay used during physical

  13. Natural and manmade radionuclides in the environment

    Human beings are constantly exposed to ionizing radiations in nature. These natural background radiations have both terrestrial and extraterrestrial origin. The extraterrestrial radiation is largely due to cosmic rays. Earth's atmosphere is continuously bombarded with high energy cosmic rays which originate from our own cosmos. The primary interaction of high energy cosmic rays with the atmosphere produces a number of secondary radiations in the form of neutrons and protons of various energies which in turn produce a variety of radionuclides through nuclear reactions with nitrogen, oxygen and other nuclei in atmosphere and through other processes. In addition, sub-atomic particles like mesons, muons and electrons are also produced. The radiation dose rate in India at sea level due to cosmic rays is 32 nGy h-1. The naturally occurring terrestrial radionuclides can be divided into those that occur singly and those that are components of the three chains of radioactive series namely, the Uranium series, the Thorium series and the Actinium series. Among the singly occurring radionuclides Potassium-40 with half life of 1.3x109 years is the most prominent and is widely distributed in rocks and soil. 40K is fairly abundant, forming about 0.012% of' total potassium, and is widely distributed in environmental matrix and it is an essential element for most life forms. Uranium-238 and Thorium 232 and their daughters generate the bulk of natural ionising radiation in our environment. Uranium-238 is the head of a series of 15 principal radionuclides, It is the most abundant (99.28%) isotope of natural uranium and is found in all rocks and soil in varied concentration. The radionuclide 238U decays through 234U and 230Th to 226Ra, which has a relatively long half life of 1628 years. 226Ra and its daughter products constitute an important part of natural radiation exposure. About 98% of the external dose from uranium series is delivered by 226Ra and its daughter products

  14. Imaging and treating tumor vasculature with targeted radiolabeled carbon nanotubes

    Alessandro Ruggiero

    2010-09-01

    imaging. Near-infrared three-dimensional fluorescent-mediated tomography was used to image the LS174T tumor model, collect antibody-alone PK data, and calculate the number of copies of VE-cad epitope per cell. All of these studies were performed as a single administration of construct and were found to be safe and well tolerated by the murine model. These data have implications that support further imaging and radiotherapy studies using a SWCNT-based platform and focusing on the tumor vessels as the target.Keywords: actinium-225 (225Ac, zirconium-89 (89Zr, angiogenesis, vascular endothelial-cadherin, radioimmunotherapy (RIT, radioimmunoPET

  15. Use of gamma-ray spectrometry for analysis of Uranium isotopic composition in soil of Iran

    The use of depleted uranium (DU) in various weaponry and ammunition during the Iraq war in April, 2003 caused serious concern in Iran over possible uranium contamination of the Iran environment and consequently long health effect. After a shell explosion, uranium is discharged by the fire in the air in the form of oxidized particles and can be dispersed within a radius of several kilometers. Gamma-ray spectrometry was used to determine uranium concentration in soil samples collected from 8 sites in Iranian sectors of Iraq border. All soil samples were dried ,gently grounded and passed through a 2 mm sieve. Three hundred grams of each sample were placed in plastic container and sealed for at least 20 days to allow equilibrium in uranium, thorium and actinium series. Gamma-ray intensities were measured with 40% HPGe (CANBERRA) detector. The detector was shielded by 10 cm lead on all sides with cadmium-copper in inner sides. The system is equipped with software for data acquisition and analyzing. The counting time was 6x104 seconds and background spectra were also collected for the same period of time. The concentrations of 238U assessed from 63.3 keV and 92.4 keV emission of its first daughter nuclide, 234Th. To assess the isotopic ratio of 238U/235 U, secular equilibrium was ensured and the concentration of 235U under the 186 keV was deduced. The 226Ra was determined through the 295 keV and 352 keV gamma-rays of 214Pb. The concentrations of 238U and activity ratio of 238U/235U is given. The average of measurement activity ratio is 21,very close to the value of 21.5 for natural uranium, while the activity ratio of DU can be as high as 76.9. The 238U activity ranges within typically accepted levels from 14-33 Bq kg-1, while the typical range given by UNSCEAR (1988) for different soil samples is 10 to 50 Bq kg-1. The analysis of eight surface soil samples of Iranian sites of Iraq border, showed that uranium isotopes are in their natural abundances

  16. Alpha-emitting isotopes and chromium in a coastal California aquifer

    Highlights: • Alluvium in Piedra de Lumbre basin higher radionuclides likely from natural Th. • Natural uranium decay-chain isotopes, including Ra, present in marine deposits. • Marine deposits also contain low concentrations of chromium. • Radionuclides and chromium concentrations lower in alluvium in the Las Flores basin. - Abstract: The unadjusted 72-h gross alpha activities in water from two wells completed in marine and alluvial deposits in a coastal southern California aquifer 40 km north of San Diego were 15 and 25 picoCuries per liter (pCi/L). Although activities were below the Maximum Contaminant Level (MCL) of 15 pCi/L, when adjusted for uranium activity; there is concern that new wells in the area may exceed MCLs, or that future regulations may limit water use from the wells. Coupled well-bore flow and depth-dependent water-quality data collected from the wells in 2011 (with analyses for isotopes within the uranium, actinium, and thorium decay-chains) show gross alpha activity in marine deposits is associated with decay of naturally-occurring 238U and its daughter 234U. Radon activities in marine deposits were as high as 2230 pCi/L. In contrast, gross alpha activities in overlying alluvium within the Piedra de Lumbre watershed, eroded from the nearby San Onofre Hills, were associated with decay of 232Th, including its daughter 224Ra. Radon activities in alluvium from Piedra de Lumbre of 450 pCi/L were lower than in marine deposits. Chromium VI concentrations in marine deposits were less than the California MCL of 10 μg/L (effective July 1, 2014) but δ53Cr compositions were near zero and within reported ranges for anthropogenic chromium. Alluvial deposits from the nearby Las Flores watershed, which drains a larger area having diverse geology, has low alpha activities and chromium as a result of geologic and geochemical conditions and may be more promising for future water-supply development

  17. Study of the production of residual evaporation nuclei issued from the spallation reaction of uranium-238 by 1 GeV protons

    The spallation reaction by high energy protons is one of the envisaged nuclear reactions for production of exotic nuclei. We have measured the production of more than 300 different evaporation residues issued by the spallation reaction of Uranium-238 by 1 GeV protons. We used the reverse kinematics technique in order to produce the relativistic nuclei and therefore to be able to detect those nuclides within a very short time, shorter in most cases than the radioactive disintegration period. The achieved nuclear charge and mass resolution are excellent. They allow a good accuracy on the values of the measured cross-sections (10 to 15%). We have observed for the first time the nuclide Actinium-235 obtained consequently to the loss of 3 protons by the projectile. The measured isotopic distribution are strongly influenced by the mechanism of fission which leads to a strong reduction of the production of the heavy neutron deficient isotopes. We have compared our results to some other measurements achieved with radio-chemical methods at a similar energy. We observed a systematic disagreement of about 40%. Some comparison with the available systematics show that those are presently not able to reproduce the data with a reasonable precision. We could also measure the recoil momentum distribution for each studied isotopes. We show that Goldhaber's model agrees very well with the experiment in case. of 'cold' channels where the evaporation of particles never occurs. On the other hand, when the produced pre-fragment is excited the data show that Goldhaber's model does not reproduce.the data showing the limitation of such an approach. We finally tried to reproduce the measurement of evaporation residue cross-section thanks to the coupling of intra-nuclear cascade and statistical evaporation codes. The influence of the fission process is rather important is the system p+U; we therefore had to account for the dynamical aspect of the fission. We also showed the determinant role

  18. DNA double strand breaks as predictor of efficacy of the alpha-particle emitter Ac-225 and the electron emitter Lu-177 for somatostatin receptor targeted radiotherapy.

    Franziska Graf

    Full Text Available RATIONALE: Key biologic effects of the alpha-particle emitter Actinium-225 in comparison to the beta-particle emitter Lutetium-177 labeled somatostatin-analogue DOTATOC in vitro and in vivo were studied to evaluate the significance of γH2AX-foci formation. METHODS: To determine the relative biological effectiveness (RBE between the two isotopes (as - biological consequence of different ionisation-densities along a particle-track, somatostatin expressing AR42J cells were incubated with Ac-225-DOTATOC and Lu-177-DOTATOC up to 48 h and viability was analyzed using the MTT assay. DNA double strand breaks (DSB were quantified by immunofluorescence staining of γH2AX-foci. Cell cycle was analyzed by flow cytometry. In vivo uptake of both radiolabeled somatostatin-analogues into subcutaneously growing AR42J tumors and the number of cells displaying γH2AX-foci were measured. Therapeutic efficacy was assayed by monitoring tumor growth after treatment with activities estimated from in vitro cytotoxicity. RESULTS: Ac-225-DOTATOC resulted in ED50 values of 14 kBq/ml after 48 h, whereas Lu-177-DOTATOC displayed ED50 values of 10 MBq/ml. The number of DSB grew with increasing concentration of Ac-225-DOTATOC and similarly with Lu-177-DOTATOC when applying a factor of 700-fold higher activity compared to Ac-225. Already 24 h after incubation with 2.5-10 kBq/ml, Ac-225-DOTATOC cell-cycle studies showed up to a 60% increase in the percentage of tumor cells in G2/M phase. After 72 h an apoptotic subG1 peak was also detectable. Tumor uptake for both radio peptides at 48 h was identical (7.5%ID/g, though the overall number of cells with γH2AX-foci was higher in tumors treated with 48 kBq Ac-225-DOTATOC compared to tumors treated with 30 MBq Lu-177-DOTATOC (35% vs. 21%. Tumors with a volume of 0.34 ml reached delayed exponential tumor growth after 25 days (44 kBq Ac-225-DOTATOC and after 21 days (34 MBq Lu-177-DOTATOC. CONCLUSION: γH2AX-foci formation, triggered

  19. The discovery of plutonium reorganized the periodic table and aided the discovery of new elements

    The modern Periodic Table derives principally from the work of the great Russian scientist Dimitri Mendeleev, who in 1869 enunciated a 'periodic law' that the properties of the elements are a periodic function of their atomic weights, and arranged the 65 known elements in a 'periodic table'. Fundamentally, every column in the main body of the Periodic Table is a grouping of elements that display similar chemical and physical behavior. Similar properties are therefore exhibited by elements with widely different mass. Chemical periodicity is central to the study of chemistry, and no other generalization comes close to its ability to systematize and rationalize known chemical facts. With the development of atomic theory, and an understanding of the electronic structure of atoms, chemical periodicity and the periodic table now find their natural explanation in the electronic structure of atoms. Moving from left to right along any row, the elements are arranged sequentially according to nuclear charge (the atomic number). Electrons counter balance that nuclear charge, hence each successive element has one more electron in its configuration. The electron configuration, or distribution of electrons among atomic orbitals, may be determined by application of the Pauli principle (paired spin in the same orbital) and the aufbau principle (which outlines the order of filling of electrons into shells of orbitals - s, p, d, f, etc.) such that in a given atom, no two electrons may have all four quantum numbers identical. In 1939, only three elements were known to be heavier than actinium: thorium, protactinium, and uranium. All three exhibited variable oxidation states and a complex chemistry. Thorium, protactinium and uranium were assumed to be d-transition metals and were placed in the Periodic Table under hafnium, tantalum, and tungsten, respectively. By 1940, McMillan and Abelson bombarded uranium atoms with slow neutrons and successfully identified atoms of element 93, which

  20. The discovery of plutonium reorganized the periodic table and aided the discovery of new elements

    Clark, David L [Los Alamos National Laboratory

    2009-01-01

    The modern Periodic Table derives principally from the work of the great Russian scientist Dimitri Mendeleev, who in 1869 enunciated a 'periodic law' that the properties of the elements are a periodic function of their atomic weights, and arranged the 65 known elements in a 'periodic table'. Fundamentally, every column in the main body of the Periodic Table is a grouping of elements that display similar chemical and physical behavior. Similar properties are therefore exhibited by elements with widely different mass. Chemical periodicity is central to the study of chemistry, and no other generalization comes close to its ability to systematize and rationalize known chemical facts. With the development of atomic theory, and an understanding of the electronic structure of atoms, chemical periodicity and the periodic table now find their natural explanation in the electronic structure of atoms. Moving from left to right along any row, the elements are arranged sequentially according to nuclear charge (the atomic number). Electrons counter balance that nuclear charge, hence each successive element has one more electron in its configuration. The electron configuration, or distribution of electrons among atomic orbitals, may be determined by application of the Pauli principle (paired spin in the same orbital) and the aufbau principle (which outlines the order of filling of electrons into shells of orbitals - s, p, d, f, etc.) such that in a given atom, no two electrons may have all four quantum numbers identical. In 1939, only three elements were known to be heavier than actinium: thorium, protactinium, and uranium. All three exhibited variable oxidation states and a complex chemistry. Thorium, protactinium and uranium were assumed to be d-transition metals and were placed in the Periodic Table under hafnium, tantalum, and tungsten, respectively. By 1940, McMillan and Abelson bombarded uranium atoms with slow neutrons and successfully identified atoms

  1. New production in the South China Sea

    CAI; Pinghe

    2002-01-01

    [1]Dugdale, R. C., Goering, J. J., Uptake of new and regenerated nitrogen in primary productivity, Limnology and Oceanog-raphy, 1967, 12: 196-206.[2]Eppley, R. W., Peterson, B. J., Particulate organic matter flux and planktonic new production in the deep ocean, Nature, 1979, 282: 677-680.[3]Allen, C. B., Kanda, J., Laws, E. A., New production and photosynthetic rates within and outside a cyclonic mesoscale eddy in the North Pacific Subtropical gyre, Deep-Sea Research Ⅱ, 1996, 43(6): 917-936.[4]Jenkins, W. J., Tritium-helium dating in the Sargasso Sea: A measurement of oxygen utilization rates, Nature, 1977, 196: 291-292.[5]Spitzer, W. S., Jenkins, W. J., Rates of vertical mixing, gas exchange and new production: Estimates from seasonal gas cy-cle in the upper ocean near Bermuda, Journal of Marine Research, 1989, 47: 169-196.[6]Sarmiento, J. L., Thiele, G., Key, R. M. et al., Oxygen and nitrate new production and remineralization in the North At-lantic Subtropical Gyre, Journal of Geophysical Research, 1990, 95: 18303-18315.[7]Ku, T. L., Luo, S., Kusakabe, M. et al., 228Ra-derived nutrient budgets in upper equatorial Pacific and the role of "new" silicate in limiting productivity, Deep-Sea Research II, 1995, 42(2/3): 479-497.[8]Wheeler, P. A., Rates of nitrate assimilation at the equator during the US-JGOFS spring time series: Estimates of new pro-duction, EOS, Transactions, American Geophysical Union, 1992, 73: 281.[9]Huang, Y., Xie, Y., Chen, M. et al., Distribution feature of 228Ra in surface seawater of the Nansha sea area, in Isotopes Marine Chemistry of Nansha Islands Waters (in Chinese), Beijing: Ocean Press, 1996, 70-78.[10]Reid, D. F., Key, R. M., Schink, D., Radium, thorium and actinium extraction from seawater using an improved manga-nese-oxide-coated fiber, Earth and Planetary Science Letters, 1979, 43: 223-226.[11]Shi, W., Qiu, X., Huang, Y., Distribution of dissolved 226Ra in the Jiulongjiang-Xiamen bay

  2. Production of rare earth polishing powders in Russia

    in a suspension; polishing powder Ftoropol with addition of fluorine and higher contents of cerium dioxide (at least 70% by mass) that has a higher polishing ability and is attrition-proof, used for high-speed treatment of optical lenses, mirrors, TV screens and eyeglasses. The rare earth polishing powders made in Russia possess the following physico-chemical properties and performance characteristics; cerium dioxide content in solid REE solution - 50-90% by mass; F-ion content (in Ftoropol powder) - 8-14% by mass; non-REE content of sodium, calcium, strontium and iron impurities - at most 0.1% by mass of each element; natural radionuclide content of thorium, uranium, actinium, potassium-40 series, total standard specific activity - 0.45-0.85 Bq/g; - average particle size, 2.0-3.5 μm; density - 6.3-6.8 g/cm3; pH of aqueous extract, 6-7; sedimentary stability - 10-20 minutes; polishing ability - 45-60 mg per 31 minutes (for polishing resin); abrasive inclusions - none. The report gives analysis of the. Russian powders compared against the best world analogues such as Cerox (Rhone Poulenc Company, France), Regipol (London and Scandinavian Division Chemical Company, England), etc. The analysis results imply, that the chief characteristics (granulometric composition, polishing ability and service life) of the Russian samples do not yield to the best foreign analogues, and in some properties (radionuclide content, sedimentary stability and scratching inclusions quantity) even surpass them

  3. Estimates of tidal mixing in the Indonesian archipelago from multidisciplinary INDOMIX in-situ data

    Koch-Larrouy, Ariane; Atmadipoera, Agus; van Beek, Pieter; Madec, Gurvan; Aucan, Jérôme; Lyard, Florent; Grelet, Jacques; Souhaut, Marc

    2015-12-01

    The Indonesian Mixing program (INDOMIX) was designed to quantify the very strong mixing that transforms Pacific waters into isohaline Indonesian Waters in the Indonesian archipelago. The turbulent dissipation rates and associated mixing were estimated and analyzed using a multidisciplinary approach that combines physical and geochemical in-situ observations: (1) direct measurements of the dissipation using a microstructure profiler, (2) use of density-based fine-scale methods applied to CTD and XCTD data, and (3) study of the vertical distribution of natural radionuclides (radium isotopes and actinium-227). Data were collected at five contrasting stations within the Indonesian archipelago, found above energetic straits or in relatively quiescent large basins. Strong instabilities, inversions of the density profiles and a very strong water mass transformation were observed. A wide range of dissipation values were obtained (between [10-10, 10-4] W kg-1) with spots of higher dissipation in the ocean interior correlated with a strong internal tide signal. Both the fine-scale and micro-scale methods allow us to identify very strong energy dissipation levels above the straits, ranging between [10-7, 10-4] W kg-1, in contrast to lower values at stations further away from the generation sites. The dissipation for the station located in the center of the Halmahera Sea ([10-9, 10-8] W kg-1) is stronger than for the Banda station ([10-11, 10-10] W kg-1), which is even further away from the generation sites. The three approaches agree relatively well and provide vertical eddy diffusivities values ranging between 5×10-4 and 5×10-1 m2 s-1, except in the Banda Sea where values are similar to the ones found in the open ocean (10-6 m2 s-1). CTD and XCTD profilers (deployed between stations) give estimates of dissipation all along the transit. It is found that enhanced mixing occurs preferentially above rough topography, such as in the Ombai Strait, the Halmahera Sea's northern

  4. Applications of High Intensity Proton Accelerators

    Raja, Rajendran; Mishra, Shekhar

    2010-06-01

    collider and neutrino factory - summary of working group 2 / J. Galambos, R. Garoby and S. Geer -- Prospects for a very high power CW SRF linac / R. A. Rimmer -- Indian accelerator program for ADS applications / V. C. Sahni and P. Singh -- Ion accelerator activities at VECC (particularly, operating at low temperature) / R. K. Bhandari -- Chinese efforts in high intensity proton accelerators / S. Fu, J. Wang and S. Fang -- ADSR activity in the UK / R. J. Barlow -- ADS development in Japan / K. Kikuchi -- Project-X, SRF, and very large power stations / C. M. Ankenbrandt, R. P. Johnson and M. Popovic -- Power production and ADS / R. Raja -- Experimental neutron source facility based on accelerator driven system / Y. Gohar -- Transmutation mission / W. S. Yang -- Safety performance and issues / J. E. Cahalan -- Spallation target design for accelerator-driven systems / Y. Gohar -- Design considerations for accelerator transmutation of waste system / W. S. Yang -- Japan ADS program / T. Sasa -- Overview of members states' and IAEA activities in the field of Accelerator Driven Systems (ADS) / A. Stanculescu -- Linac for ADS applications - accelerator technologies / R. W. Garnett and R. L. Sheffield -- SRF linacs and accelerator driven sub-critical systems - summary working groups 3 & 4 / J. Delayen -- Production of Actinium-225 via high energy proton induced spallation of Thorium-232 / J. Harvey ... [et al.] -- Search for the electric dipole moment of Radium-225 / R. J. Holt, Z.-T. Lu and R. Mueller -- SRF linac and material science and medicine - summary of working group 5 / J. Nolen, E. Pitcher and H. Kirk.

  5. Application of lanthanide ions doped in different glasses

    The transfer of optical excitation energy from one ion/molecule to another ion/molecule has proved to be of potential importance in industrial application as well as research. Rare earth elements (RE) although not as rare as some of them occur more prevalently then other well known material (e.g. silver, tin, tungsten) are special group of elements of the periodic table comprising lanthanide series (from lanthanum to lutetium) and actinide series (from actinium to lawrencium). Most of the actinides are highly radioactive hence their uses are limited. Fluorescence is the particular optical property of lanthanide (RE) ions. The narrow absorption and emission lines exhibited by the RE ions in crystals, glasses and solutions have always made these ions attractive as sensitive probes of solids and liquid state and also makes them useful in laser technology, CRT displays, UV to visible converters and optical communications etc. In recent years there has been a special interest to study the properties and applications of rare earth doped in glasses. Lanthanide ions in glasses play an important role, especially by retaining their emission capabilities, in the host matrix. Glass as a dielectric material plays an important role in science and industry. Its chemical, physical and particular optical properties make it suitable for applications such as opto-electronic materials, laboratory equipment, laser gain media, etc. Photoluminescence from rare earth doped glasses are of major interest in the research area of optoelectronic device applications like phosphors, display monitors, lasers and amplifiers for communication systems. Now a days, development of optical devices based on rare-earth ions doped materials is one of the interesting fields of research. Rare earth doped glasses are widely used as laser materials, optical amplifiers, optical memory devices, magneto-optical devices, medical lasers, eye safe lasers, flat panel displays, fluorescent lamps, white LED's etc

  6. 饲粮不同粗蛋白质水平对育肥羔羊小肠氨基酸流量及吸收率的影响%Effects of Different Dietary Crude Protein Levels on Amino Acid Flows and Absorbability in Small Intestine of Growing Lambs

    牛露; 尹华; 郑猛; 甘麦邻; 陈傲东; 刘晨黎; 陈道富; 高巍

    2016-01-01

    This experiment was conducted to compare the effects of different dietary crude protein ( CP) levels on amino acid ( AA) flows and absorbability in small intestine of growing lambs. Three Kazakh male lambs [(30.0±3.7) kg of body weight] fitted with permanent ruminal, duodenal and ileal fistulas were selected. A 3×3 Latin square design was adopted. Dietary CP levels of different treatments were 11. 00%, 12. 00% and 13.00%, respectively; the pretest lasted for 10 days, and the test lasted for 10 days. A dual-phase marker sys-tem with lithium-chromium ethylenediamine tetra-acetate ( LiCr-EDTA ) and ytterbium-actinium ( Yb-Ac ) as liquid-phase and particulate-phase digesta flow makers was adopted to measure small intestinal digesta flows, respectively. The results showed as follows:the intake, apparent digestibility and retention of nitrogen were in-creased with increasing level of dietary CP, and 13% treatment was significantly higher than 11% treatment ( P0.05) . Although intestinal true digesta flows and amino acid absorbability were not signifi-cantly affected by the increasing dietary CP level ( P>0.05) , but the flows of nitrogen and total amino acids, as well as absorption rates of essential amino acids, such as arginine, hisitidine and lysine, were numerically increased. The results indicate that increasing dietary CP level has the potential to improve digestibility, intesti-nal digesta flows and amino acid absorption rate.%本研究旨在比较饲粮不同粗蛋白质( CP)水平对育肥羔羊小肠氨基酸( AA)流量及吸收率的影响。选用体重(30.0±3.7) kg,安装有瘤胃、十二指肠近端和回肠末端瘘管的3只哈萨克羊公羔为试验动物,采用3×3拉丁方试验设计,各处理饲粮CP水平分别为11.00%、12.00%和13.00%;预试期10 d,正试期10 d。采用镱锕( Yb-Ac)、锂铬乙二胺四乙酸( LiCr-EDTA)分别作为消化道固相和液相食糜标记物测定小肠食糜流量。结果表明:提高饲粮CP水平可