WorldWideScience

Sample records for promethium

  1. Physics of the missing atoms: technetium and promethium

    International Nuclear Information System (INIS)

    Aspden, H.

    1987-01-01

    Technetium (Z = 43) and promethium (Z = 61) are by far the least abundant of all atoms below the radioactive elements (Z = 84 onwards). Their scarcity confirms theoretical predictions emerging from a theory of the photon derived from synchronous lattice electrodynamics. This theory has given precise theoretical values for the fine-structure constant and the constant of gravitation G and is now shown in this paper to indicate resonant interactions between the vacuum lattice oscillations and technetium and promethium. In the case of promethium there is strong reason for believing that this atom can assume supergravitational or antigravitational properties, accounting for its scarcity. This paper not only adds support to the earlier theoretical work on the photon and gravitation, but suggests a research route that might lead to new technology based on controlled interactions with gravity fields

  2. 10 CFR 30.19 - Self-luminous products containing tritium, krypton-85, or promethium-147.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Self-luminous products containing tritium, krypton-85, or..., krypton-85, or promethium-147. (a) Except for persons who manufacture, process, produce, or initially transfer for sale or distribution self-luminous products containing tritium, krypton-85, or promethium-147...

  3. Techniques involved in the preparation of radioluminescent sources with promethium-147 and gaseous tritium radionuclides

    International Nuclear Information System (INIS)

    Seshadri, N.K.; Subramanian, T.K.; Ravi, S.; Mathew, K.M.; Chinnayan, C.

    2001-01-01

    Beta radiation emanating from promethium-147 and gaseous tritium in close proximity with zinc sulphide phosphor will provide self sustained light sources and are used for, nocturnal illumination of liquid crystal display digital watches and clocks, product advertisements, telephone numbers, exit signs etc. In this paper a procedure for activation of zinc sulphide phosphor with promethium-147 and development of gaseous tritium light sources with respect to thickness of phosphor coating and its effect on light output is described. A typical light source was constructed with promethium-147 activated zinc sulphide to find the overall efficiency of conversion of beta energy to visible light. (author)

  4. 10 CFR 32.22 - Self-luminous products containing tritium, krypton-85 or promethium-147: Requirements for license...

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Self-luminous products containing tritium, krypton-85 or... containing tritium, krypton-85 or promethium-147: Requirements for license to manufacture, process, produce... self-luminous products containing tritium, krypton-85, or promethium-147, or to initially transfer such...

  5. Strontium-90 and promethium-147 recovery

    International Nuclear Information System (INIS)

    Hoisington, J.E.; McDonell, W.R.

    1982-01-01

    Strontium-90 and promethium-147 are fission product radionuclides with potential for use as heat source materials in high reliability, non-interruptible power supplies. Interest has recently been expressed in their utilization for Department of Defense (DOD) applications. This memorandum summarizes the current inventories, the annual production rates, and the possible recovery of Sr-90 and Pm-147 from nuclear materials production operations at Hanford and Savannah River. Recovery of these isotopes from LWR spend fuel utilizing the Barnwell Nuclear Fuels Plant (BNFP) is also considered. Unit recovery costs at each site are provided

  6. A novel ion selective sensor for promethium determination

    International Nuclear Information System (INIS)

    Gupta, Vinod K.; Jain, Rajeev; Hamdan, A.J.; Agarwal, Shilpi; Bharti, Arvind K.

    2010-01-01

    This is a first promethium 145 ion-selective sensor based on the comparative study of two Schiff base ligands (X 1 and X 2 ) as neutral ionophores. Effect of various plasticizers: 2-nitrophenyloctylether (o-NPOE), dibutyl phosphonate (DBP), dioctylphthalate (DOP), tri-(2-ethylhexyl) phosphate (TEHP), dibutyl butylphosphonate (DBBP), chloronaphthalene (CN) and anion excluders: potassium tetrakis (p-chloropheny1) borate (KTpClPB), sodiumtetraphenylborate (NaTPB) and oleic acid (OA) have been studied. The membrane with a composition of ionophore (X 1 /X 2 ):KTpClPB:PVC:o-NPOE (w/w, %) in the ratio of 5:5:30:60 exhibited best performance. The best responsive membrane sensors (8 and 21) exhibited working concentration range of 4.5 x 10 -7 -1.0 x 10 -2 M and 3.5 x 10 -6 -1.0 x 10 -2 M with a detection limits of 3.2 x 10 -7 M and 2.3 x 10 -6 M and Nernstian slopes of 20.0 ± 0.5, 19.5 ± 0.5 mV decade -1 of activity, respectively. The sensor no. 8 works satisfactorily in partially non-aqueous media up to 10% (v/v) content of methanol, ethanol and acetonitrile. Analytical application of the proposed sensor has been demonstrated in determination of promethium (III) ions in spiked water samples.

  7. Method of fixing a luminous powder such as tritium-3 promethium-147 in a nuclear battery for wrist watches

    International Nuclear Information System (INIS)

    Atomachi, Tadaaki; Imai, Hiroshi.

    1969-01-01

    A method of adhering and fixing a luminous powder such as tritium-3 or promethium-147 onto a small semi-conductor element for use in nuclear batteries is disclosed in which a radio isotope such as tritium-3 or promethium-147 is coated onto the surface of a fluorescent material such as ZnS-Cu, CaS, (Ca, Sr)S, (Cd, Zn)S which is then suspended in a silver plating bath. A composite of silver and the luminous powder is electro-deposited onto the semi-conductor element. The deposited layer will not easily separate from the semi-conductor and long life is assured owing to the thickness of the layer. Small dimensions are obtainable without sacrificing capacity. (Owens, K.J.)

  8. Penetration of radionuclides across the skin. Rat age dependent promethium permeation through skin in vitro

    International Nuclear Information System (INIS)

    Kassai, Z.; Kassai, A.; Bauerova, K.; Koprda, V.; Harangozo, M.; Bendova, P.; Bujnova, A.

    2003-01-01

    The composition and the permeation properties of the skin are dependent on age. In the animal models for permation studies, age affects the mechanical as well as the permeation properties significantly. The time dependence of permeation of 147 Pm 3+ from aqueous solution was established by the animal skin model and the age dependence of promethium permeation through the skin was examined. The aim was to find the optimum rat skin age model for radionuclide permeation studies and to assess the relative importance of the main permeation pathways: transepidermal and transfollicular permeation. The skin from 5-day-old rats (5DR) was found to represent the optimum animal model to study transepidermal permeation of ions. The skin from 9-day-old rats (9DR) was selected to study transfollicular permeation of ions. Comparison of the permeated amounts of promethium through the skin without hairs (3 DR to 6 DR) and with hairs (7DR to 12DR) showed that the additional permation mode via follicles significantly contributed to the permeation rate and extent. (author)

  9. Synthesis and Preliminary Biological Evaluations of Fluorescent or 149Promethium Labeled Trastuzumab-Polyethylenimine

    Directory of Open Access Journals (Sweden)

    Jonathan Fitzsimmons

    2015-12-01

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

  10. Contribution to the penetration of radionuclides across the skin. Age dependence of promethium through rat skin in vitro

    International Nuclear Information System (INIS)

    Kassai, Z.; Koprda, V.; Harangozo, M.; Bendova, P.; Bauerova, K.

    2001-01-01

    In this paper: - the time dependence of permeation of 147 Pm 3+ from aqueous solution through animal skin model was studied; - the age dependence of promethium through the skin was proved; - the optimum biological model of human skin was selected, and - the relative importance of the main diffusion pathways for 147 Pm 3+ the diffusion across the intact skin and the diffusion through the hair channels was assessed. Concluding it can be said, that: -it was proved, that the 5-day-old rats (5DR) represents the optimum animal model to the human skin; - in the case of 8DR to 11DR the dominant route of 147 Pm 3+ penetration is along the follicles; - the permeation resistance of the skin depends on the thickness and mechanical properties of the skin. Comparing amounts of penetrated ions of promethium through the skin without hairs (3DR to 6DR) and through the skin with hairs, it was showed that the additional diffusion along hair's follicles pronounced with animal skin can be important also in case of human skin where hair density is many times lower than in used animal models. (authors)

  11. An experimental study of odd mass promethium isotopes using proton stripping and pickup reactions

    International Nuclear Information System (INIS)

    Straume, O.

    1979-11-01

    Odd Pm isotopes have been studied by one proton pick-up and stripping reactions. Spin assignment and spectroscopic factors have been obtained for a number of energy levels. In the stripping reactions, the relative cross-sections have been measured with an unusually high precision by the use of a target of natural neodymium. The spectroscopic strengths have been extracted using standard distorted wave methods. The nuclear structures of these promethium isotopes fall into three categories. The spherical approach seems valid for 143 Pm and 145 Pm and the deformed regime covers 151 Pm and 153 Pm, while 147 Pm and 149 Pm remain as transitional nuclei. (Auth.)

  12. Development of a diagnostic model for inhaled promethium-147 oxide. Animal studies

    International Nuclear Information System (INIS)

    Shipler, D.B.; Ballou, J.E.; Griffin, B.I.; Nelson, I.C.

    1976-01-01

    Rats and beagles were exposed by inhalation to an aerosol containing stable Sm 2 O 3 tagged with 145 Sm 2 O 3 and 143 Pm 2 O 3 . The animals were sacrificed at 0, 14 and 30 days post-exposure to compare the kinetics and translocation of 145 Sm and 143 Pm. Quantitative analysis for 145 Sm and 143 Pm in several tissues and excreta indicate that the two rare-earth elements were mobilized and distributed similarly by the rats and dogs. Results indicate that within the error of the measurement technique, samarium acts as a carrier for promethium. The data also indicate that activities measured in faecal samples could be used to predict lung burdens of 147 Pm. At activity levels and sintering temperatures employed in the rat exposures, there was sufficient activity in urine samples to permit its use as an indicator of lung burdens of 147 Pm. At activity levels and sintering temperatures employed in the dog exposures, this was not the case. (author)

  13. Development of a diagnostic model for inhaled promethium-147 oxide: animal studies

    International Nuclear Information System (INIS)

    Shipler, D.B.; Ballou, J.E.; Griffin, B.I.; Nelson, I.C.

    1975-01-01

    Rats and beagle dogs were exposed by inhalation to an aerosol containing stable Sm 2 O 3 tagged with 145 Sm 2 O 3 and 143 Pm 2 O 3 . The animals were sacrificed at 0, 14 and 30 days post-exposure to compare the kinetics and translocation of 145 Sm and 143 Pm. Quantitative analysis for 145 Sm and 143 Pm in several tissues and excreta indicate that the two rare earth elements were mobilized and distributed similarly by the rats and dogs. Results indicate that within the error of the measurement technique, samarium acts as a carrier for promethium. The data also indicate that activities measured in fecal samples could be used to predict lung burdens of 147 Pm. At activity levels and sintering temperatures employed in the rat exposures, there was sufficient activity in urine samples to permit its use as an indicator of lung burdens of 147 Pm. At activity levels and sintering temperatures employed in the dog exposures, this was not the case. (auth)

  14. The sequential separation of strontium-90, yttrium-90, promethium-147, and cerium-144 from urine and their subsequent estimation

    International Nuclear Information System (INIS)

    Kramer, G.H.; Davies, J.M.

    1981-04-01

    A method has been developed for separating low-level activities of the beta-emitting isotopes strontium-90, yttrium-90, promethium-147 and cerium-144 from urine and aqueous solutions. They are subsequently estimated by planchet or liquid scintillation counting. The radionuclides are separated from each other and from interfering elements by solvent extraction with HDEHP (di-2-ethylhexyl phosphoric acid) in n-heptane. It is possible to separate the elements with a minimum of cross-contamination by selecting appropriate pH's and solvent concentrations. Percentage recoveries for the radionuclides are: 90 Sr, 100 +- 12; 90 Y, 65 +- 4; 147 Pm, 90 +- 8; 144 Ce, 87 +- 11. The limits of detection are: 90 Sr, 0.6 pCi; 90 Y, 0.7 pCi; 147 Pm, 1.0 pCi; 144 Ce, 0.8 pCi. (author)

  15. Preparation of 147Pm metal and the determination of the melting point and phase transformation temperatures

    International Nuclear Information System (INIS)

    Angelini, P.; Adair, H.L.

    1976-07-01

    The promethium metal used in the determination of the melting point and phase transformation temperatures was prepared by reduction of promethium oxide with thorium metal at 1600 0 C and distilling the promethium metal into a quartz dome. The melting point and phase transformation temperatures of promethium metal were found to be 1042 +- 5 0 C and 890 +- 5 0 C, respectively. The ratio for the heat of the high-temperature transformation to the heat of fusion was determined to be 0.415

  16. Process for producing a self luminescent material

    Energy Technology Data Exchange (ETDEWEB)

    Abe, E

    1962-01-28

    A self luminescent material is produced by a process comprising applying a hydroxide or fluoride of promethium-147 suspended in a medium of paraffinic acid to the surface of a fluorescent body. Promethium-147 decays with a half-life of 2.6 years and emits beta-rays but not alpha- and gamma-rays so that it is suitable for manufacturing self luminescent materials. A chloride of promethium-147 cannot be employed because its structure is destroyed by acids. Although fluorides and hydroxides of promethium-147 are difficult to mix with the fluorescent body material, they become mixable when paraffinic acids containing from 12 to 20 carbon atoms, (for example, steric acid, palmitic acid and margaric acid) are used as a medium. In embodiments, the self luminescent materials are prepared by either neutralization of a promethium-147 chloride solution having a specific radioactivity of 1.2 c/cc. with an ammonium hydroxide solution to form gelatinous hydroxide, or the reaction of a promethium-147 chloride solution with H/sub 2/SiF/sub 6/ by heating at 80/sup 0/C to form a fluoride of promethium-147. The products have a specific radioactivity of 8 to 12 mc/g. These products are suspended in vehicles of polystyrene and methacrylic resin to produce the self luminescent coating materials. Tests show that the initical brightness is comparatively high, the decreasing rate of brightness is small, no blackening effects by alpha-rays occur and costs are low. The brightness of the coating containing promethium-147 is 82-85 after 5 days, 100-105 after 100 days and 82-92 after 180 days. With respect to the coating containing radium the values are 31-70 after 5 days, 28-49 after 100 days and 19-31 after 180 days.

  17. Inhaled /sup 147/Pm and/or total-body gamma radiation: Early mortality and morbidity in rats

    Energy Technology Data Exchange (ETDEWEB)

    Filipy, R.E.; Lauhala, K.E.; McGee, D.R.; Cannon, W.C.; Buschbom, R.L.; Decker, J.R.; Kuffel, E.G.; Park, J.F.; Ragan, H.A.; Yaniv, S.S.; Scott, B.R.

    1989-05-01

    Rats were given doses of /sup 60/Co gamma radiation and/or lung burdens of /sup 147/Pm (in fused aluminosilicate particles) within lethal ranges in an experiment to determine and compare morbidity and mortality responses for the radiation insults within 1 year after exposure. Radiation-induced morbidity was assessed by measuring changes in body weights, hematologic parameters, and pulmonary-function parameters. Acute mortality and morbidity from inhaled promethium were caused primarily by radiation pneumonitis and pulmonary fibrosis that occurred more than 53 days after exposure. Acute mortality and morbidity from total-body gamma irradiation occurred within 30 days of exposure and resulted from the bone-marrow radiation syndrome. Gamma radiation caused transient morbidity, reflected by immediately depressed blood cell levels and by reduced body weight gain in animals that survived the acute gamma radiation syndrome. Inhaled promethium caused a loss of body weight and diminished pulmonary function, but its only effect on blood cell levels was lymphocytopenia. Combined gamma irradiation and promethium lung burdens were synergistic, in that animals receiving both radiation insults had higher morbidity and mortality rates than would be predicted based on the effect of either kind of radiation alone. Promethium lung burdens enhanced the effect of gamma radiation in rats within the first 30 days of exposure, and gamma radiation enhanced the later effect of promethium lung burdens. 70 refs., 68 figs., 21 tabs.

  18. Preparation of 147Pm ceramic source core

    International Nuclear Information System (INIS)

    Mielcarski, M.

    1989-01-01

    Preparation of ceramic pellets containing fixed promethium-147 is described. Incorporation rate of 147 Pm into the ceramic material was determined. The leachability and vaporization of promethium from the obtained ceramics was investigated. The ceramic pellets prepared by the described procedure, mounted in special holders, can be applied as point sources in beta backscatter thickness gauges. (author)

  19. Raman spectra of Pm2O3, PmF3, PmCl3, PmBr3 and PmI3

    International Nuclear Information System (INIS)

    Wilmarth, W.R.; Peterson, J.R.

    1988-01-01

    Raman spectral data are presented for the sesquioxide and the trihalides (F, Cl, Br and I) of promethium. The Raman spectra of these lanthanide compounds are reported for the first time and are compared with those of the homologous lanthanide compounds. Tentative symmetry assignments have been made for the observed Raman-active bands based on factor group analysis of their respective crystal structures and comparisons with the assigned Raman spectra of other lanthanide compounds. The characteristic band patterns of the Raman phonon spectra have been found to be very useful in determining the crystal structure of the respective promethium compounds. (author)

  20. Use of Box-Wilson method for determination of optimum conditions for extraction some lanthanoids with amines

    International Nuclear Information System (INIS)

    Kopyrin, A.A.; Murashov, V.D.; Shvedov, V.P.

    1980-01-01

    The effect of DTPA, cerium and europium nitrates concentration in the range from 10 -1 -10 -6 M on extraction and separation of americium (3), cerium (3), prometium and europium 0.2 M with the solution of tri-n-octylamine nitrate in n-xylol of concentrated lithium nitrate solutions, is investigated. The method of Box-Wilson is used to determine the optimum conditions of separation of the above elements. The maximum values of separation factors are obtained for the following pairs: cerium(3)-americium(3) - 100, americium (3)-europium - 12, promethium-americium(3) - 35, cerium(3)-promethium - 30, cerium(3)-europium - 890 [ru

  1. Mass separation of rare-earth elements by a high-temperature thermal ion source coupled with a He-jet system

    International Nuclear Information System (INIS)

    Kawase, Y.; Okano, K.; Aoki, K.

    1987-01-01

    By using a high-temperature thermal ion source coupled to a He-jet system, neutron-rich isotopes of rare-earth elements such as cerium, praseodymium, neodymium and promethium produced by the thermal-neutron fission of /sup 235/U were ionized and successfully separated. The temperature dependence of the ionization efficiency has been measured and found to be explained qualitatively by the vapour pressure of the relevant elements. The characteristic temperature dependence of the ionization efficiency has been utilized for Z-identification of several isobars of rare-earth elements. The heaviest isotopes of neodymium and promethium, /sup 155/Nd and /sup 156/Pm, have recently been identified

  2. Public health implications of radioluminous materials

    International Nuclear Information System (INIS)

    Moghissi, A.A.; Carter, M.W.

    1975-07-01

    The safety, efficacy, and relative merits of radium, tritium, and promethium in radioluminous materials, particularly as used in the dial paint of timepieces and instruments, were evaluated. The reduced use of radium in recent years is reflected in estimates of the population dose for 1973--3600 person-rem from 24 million tritium watches versus 2500 person-rem from 8.4 million radium clocks. Had radium still been used in watches, the dose could have been significantly higher. No reliable data are available on the activity of promethium used for this purpose. Assuming a minimum dose of 6100 person-rem from all these radionuclides, an average of 0.03 mrem/year is estimated for the U.S. population. Because of the unavoidable radiation hazard, it is recommended that radium no longer be used in radioluminous materials. Furthermore, the 'frivolous' use of other radionuclides for this purpose should be discouraged

  3. State of the art of cardiac pacemaker technology

    International Nuclear Information System (INIS)

    Lambeck, R.

    1978-01-01

    The development of cardiac pacemakers from fixed-frequency to demand pacemakers is reviewed. The latter is described in more detail with regard to its energy sources and its design. The use of radioactive energy sources is illustrated by the example of 238 Pu and 147 promethium and a comparison of the two radiation sources. (AJ) 891 AJ [de

  4. Nuclear structure from radioactive decay

    International Nuclear Information System (INIS)

    Wood, J.L.

    1991-01-01

    This report discusses nuclear structure from radioactive decay of the following: Neutron-Deficient Iridium Isotopes; Neutron-Deficient Platinum Isotopes; Neutron-Deficient Gold Isotopes; Neutron-Deficient Mercury Isotopes; Neutron-Deficient Thallium Isotopes; Neutron-Deficient Lead Isotopes; Neutron-Deficient Samarium Isotopes; Neutron-Deficient Promethium Isotopes; Neutron-Deficient Neodymium Isotopes; and Neutron-Deficient Praseodymium Isotopes. Also discussed are Nuclear Systematics and Models

  5. 10 CFR 32.55 - Same: Quality assurance; prohibition of transfer.

    Science.gov (United States)

    2010-01-01

    ...; prohibition of transfer. (a) Each person licensed under § 32.53 shall visually inspect each device and shall... promethium-147. (b) Each person licensed under § 32.53 shall take a random sample of the size required by the... subject each unit in the sample to the following tests: (1) Each device shall be immersed in 30 inches of...

  6. Kinetics of promethium-147 in a simulated pond

    International Nuclear Information System (INIS)

    Shang Zhaorong

    1995-03-01

    The dynamic behaviour of 147 Pm in a simulated aquatic ecosystem which consists of water, soil and aquatic lives. The results are as follows: The accumulation of 147 Pm in the ecosystem can be expressed by an exponential function; the aquatic plants have the highest capacity of concentration of 147 Pm, they can be used as bio-monitors and cleaning agents of contamination of 147 Pm in water; the absorption of 147 Pm by cardio is few, and the most of it accumulates in bone; 147 Pm in soil has little penetrability, and about 80% of it accumulates within 1 cm of top soil. (10 refs., 1 fig., 5 tabs.)

  7. Installation for producing sealed radioactive sources; Installation de fabrication de sources radioactives scellees

    Energy Technology Data Exchange (ETDEWEB)

    Fradin, J; Hayoun, C [Commissariat a l' Energie Atomique, 91 - Saclay (France). Centre d' Etudes Nucleaires

    1969-07-01

    This installation has been designed and built for producing sealed sources of fission elements: caesium 137, strontium 90, promethium 147, ruthenium 106 and cerium 144 in particular. The installation consists of sealed and protected cells, each being assigned to a particular production. The safety and the operational reliability of the equipment are the principal considerations which have governed this work. The report describes the installation and, in particular, the apparatus used as well as the various control devices. In conclusion, a review as presented of six years operation. (authors) [French] Cette installation a ete concue et realisee pour effectuer des fabrications de sources scellees d'elements de fission: caesium 137 - strontium 90 - promethium 147 - ruthenium 106 - cerium 144 en particulier. L'installation est composee de cellules etanches et protegees, chacune d'elles etant affectee a une fabrication particuliere. La securite et la surete de fonctionnement de l'ensemble sont parmi les elements principaux qui ont guide l'etude. Le rapport decrit l'installation et plus particulierement l'appareillage utilise ainsi que les divers controles et commandes. Le bilan de fonctionnement apres 6 ans d'exploitation sert de conclusion. (auteurs)

  8. Installation for producing sealed radioactive sources; Installation de fabrication de sources radioactives scellees

    Energy Technology Data Exchange (ETDEWEB)

    Fradin, J.; Hayoun, C. [Commissariat a l' Energie Atomique, 91 - Saclay (France). Centre d' Etudes Nucleaires

    1969-07-01

    This installation has been designed and built for producing sealed sources of fission elements: caesium 137, strontium 90, promethium 147, ruthenium 106 and cerium 144 in particular. The installation consists of sealed and protected cells, each being assigned to a particular production. The safety and the operational reliability of the equipment are the principal considerations which have governed this work. The report describes the installation and, in particular, the apparatus used as well as the various control devices. In conclusion, a review as presented of six years operation. (authors) [French] Cette installation a ete concue et realisee pour effectuer des fabrications de sources scellees d'elements de fission: caesium 137 - strontium 90 - promethium 147 - ruthenium 106 - cerium 144 en particulier. L'installation est composee de cellules etanches et protegees, chacune d'elles etant affectee a une fabrication particuliere. La securite et la surete de fonctionnement de l'ensemble sont parmi les elements principaux qui ont guide l'etude. Le rapport decrit l'installation et plus particulierement l'appareillage utilise ainsi que les divers controles et commandes. Le bilan de fonctionnement apres 6 ans d'exploitation sert de conclusion. (auteurs)

  9. Identification of Radiation Sources in a Peacetime Environment

    Science.gov (United States)

    1998-04-01

    Radionuclides in Medicine, Research, and Industry (continued) Isotope Symbol Polonium - 210 Po- 210 Promethium-147 Pr-147 Radium-226 Ra-226 Selenium-75 Se...equip- ment seen in a nuclear medicine department or nuclear pharmacy, radia- tion therapy sources, industrial food irradiation facilities, and small... Food Irradiator 28 Commercial Irradiator Facility 28 Appendix 1. Commonly Used Radionuclides in Medicine, Research, and Industry 29 General

  10. Preparation, characterization and thermal behaviour study of 4-dimethyl amino benzal pyruvate of lanthanides (III) and yttrium (III) in solid state

    International Nuclear Information System (INIS)

    Miyano, M.H.

    1990-01-01

    Solid state compounds involving Ln and DMBP, where Ln trivalent lanthanides (except promethium) and yttrium; DMBP 4-dimethyl amino benzylidene pyruvate, were prepared by addition of ligand to the corresponding metal ions chlorides, both in aqueous solution. The precipitates were washed with distilled water and dried at 40 0 C in a forced circulation oven. Complexometry with EDTA, thermogravimetry (TG), differential thermal analysis (DTA), infra-red absorption and X-ray diffraction have been used in the study of these compounds. (author)

  11. Sorption and chromatographic techniques for processing liquid waste of nuclear fuel cycle

    International Nuclear Information System (INIS)

    Gelis, V.M.; Milyutin, V.V.; Chuveleva, E.A.; Maslova, G.B.; Kudryavtseva, S.P.; Firsova, L.A.; Kozlitin, E.A.

    2000-01-01

    In the spent nuclear fuel processing procedures the significant quantity of high level liquid waste containing long-lived high toxic radionuclides of cesium, strontium, promethium, americium, curium, etc. is generated. Separation of those radionuclides from the waste not merely simplifies the further safe waste handling but also reduces the waste processing operation costs due to the market value of certain individual radionuclide preparations. Recovery and separation of high grade pure long-lived radionuclide preparations is frequently performed by means of chromatographic techniques. (authors)

  12. Casualty Estimation for Nuclear and Radiological Weapons

    Science.gov (United States)

    2016-06-01

    rate 2.69 d β Metal Polonium - 210 210Po Static eliminators 138 d α Metal foil Radium-226 226Ra Brachytherapy - low dose rate 1600 y α Salt...Promethium-147 153Gd Gadolinium-153 169Yb Ytterbium-169 170Tm Thulium-170 192Ir Iridium-192 210Po Polonium - 210 226Ra Radium-226 238Pu Plutonium-238...Brussels: NATO, in development). iv present in a large food irradiator facility, and constitutes about 34.5 kg of 137Cs. To illustrate alternative

  13. Surface-ionization ion source designed for in-beam operation with the BEMS-2 isotope separator

    International Nuclear Information System (INIS)

    Bogdanov, D.D.; Voboril, J.; Demyanov, A.V.; Karnaukhov, V.A.; Petrov, L.A.

    1976-01-01

    A surface-ionization ion source designed to operate in combination with the BEMS-2 isotope separator in a heavy ion beam is described. The ion source is adjusted for the separation of rare-earth elements. The separation efficiency for 150 Dy is determined to be equal to about 20% at the ionizer temperature of 2600 deg K. The hold-up times for praseodymium, promethium and dysprosium in the ion source range from 5 to 10 sec at the ionizer temperature of 2500-2700 deg K

  14. Methods radiation protection data sheets for the use radionuclides in unsealed sources

    International Nuclear Information System (INIS)

    Anon.

    1999-01-01

    These radiation protection data sheets are devoted to responsible persons and employees of various laboratories or medical, pharmaceutical, university and industrial departments where radionuclides are handled as well as all the persons who attend to safety in this field. They contain the essential radiation protection data for the use of radionuclides in unsealed sources: physical characteristics, risk assessment, administrative procedures, recommendations, regulations and bibliography. This new series includes the following radionuclides: bromine 82, cobalt 58, cobalt 60, manganese 54, mercury 197, mercury 203, promethium 147, xenon 133 and ytterbium 169. (O.M.)

  15. New developments in the analysis and measurement of thicknesses by excitation of the fluorescent lines by means of β particles

    International Nuclear Information System (INIS)

    Martinelli, P.

    1960-01-01

    The process for analysing and measuring the thickness of deposits by β-X fluorescence which we have already described has undergone further development. The use of promethium-147 and krypton-85 sources makes it possible to reduce the background noise which is observed with strontium-90. We present the results obtained for various measurements of the thickness of metallic coatings and the continuous measurement of calcium and of iron in ore samples. We describe the tests carried out with a view to analysing the X-rays by means of a crystal. (author) [fr

  16. Calculation of entropy of liquid metals using acoustic measurements in the framework of the rigid sphere model

    International Nuclear Information System (INIS)

    Tekuchev, V.V.; Barashkov, B.I.; Rygalov, L.N.; Dolzhikov, Yu.S.

    2001-01-01

    For the first time one obtained the polytherms of ultrasound velocity for liquid high-melting metals within wide temperature range. In terms of the rigid sphere model on the basis of the acoustic data one calculated the entropy values for 34 liquid metals at the melting point. The average discrepancy of the calculated values of entropy with the published one constitutes 8.2%. With increase of metal valency the error increases from 2.8 up to 13%. In case of francium, radium, promethium, actinium, hafnium, polonium, rhenium one obtained data for the first time [ru

  17. Installation for producing sealed radioactive sources

    International Nuclear Information System (INIS)

    Fradin, J.; Hayoun, C.

    1969-01-01

    This installation has been designed and built for producing sealed sources of fission elements: caesium 137, strontium 90, promethium 147, ruthenium 106 and cerium 144 in particular. The installation consists of sealed and protected cells, each being assigned to a particular production. The safety and the operational reliability of the equipment are the principal considerations which have governed this work. The report describes the installation and, in particular, the apparatus used as well as the various control devices. In conclusion, a review as presented of six years operation. (authors) [fr

  18. A method for atomic spectroscopy of highly charged ions in the Pm isoelectronic sequence

    International Nuclear Information System (INIS)

    Andersson, Oe.

    1995-08-01

    The aim was to search for alkali-like spectra in the Promethium isoelectronic sequence. Pb 22+ ions were produced by means of an ECR-ion source and accelerated towards a target of He gas. Colliding with He atoms the Pb 22+ ions are likely to capture an electron, thus forming an excited Pm-like ion (Pb 21+ ). A 2 m grazing-incidence spectrometer was used for recording the spectra arising as the accelerated ions impinge on the target. No lines were recorded throughout the wavelength region where the spectrometer is sensitive. Further experiments are needed to make clear if this is due to experimental errors or not. 14 refs, 8 figs

  19. Closed N-shell alkali spectra

    International Nuclear Information System (INIS)

    Ellis, D.G.; Curtis, L.J.

    1982-01-01

    Term values and ionization potentials have been calculated for several ions in the promethium (N = 61) isoelectronic sequence. As the nuclear charge is increased, the ground configuration changes from 4f 13 5s 2 to 4f 14 5s giving the upper portion of the sequence an alkali-like character. According to our most recent Hartree-Fock calculations with first-order relativistic corrections, the ground term is 5s 2 S for Z > 77 (Ir XVII) and the first excited term is 5p 2 P 0 for Z > 84 (P 0 XXIV). Comparisons are made with calculations of Cowan in W XIV. The prospects for observation of these spectra in fast ion beams are discussed. (orig.)

  20. A method for atomic spectroscopy of highly charged ions in the Pm isoelectronic sequence

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, Oe

    1995-08-01

    The aim was to search for alkali-like spectra in the Promethium isoelectronic sequence. Pb{sup 22+} ions were produced by means of an ECR-ion source and accelerated towards a target of He gas. Colliding with He atoms the Pb{sup 22+} ions are likely to capture an electron, thus forming an excited Pm-like ion (Pb{sup 21+}). A 2 m grazing-incidence spectrometer was used for recording the spectra arising as the accelerated ions impinge on the target. No lines were recorded throughout the wavelength region where the spectrometer is sensitive. Further experiments are needed to make clear if this is due to experimental errors or not. 14 refs, 8 figs.

  1. Acoustic study of the characteristic temperature of metals

    International Nuclear Information System (INIS)

    Tekuchev, V.V.; Rygalov, L.N.; Ivanova, I.V.; Barashkov, B.I.

    2000-01-01

    The calculation of the Debye temperature for 64 metals, including Be, La, Mo, W, Os, Ni, Cd, In, Ta, U, Sc, Cs, Sr, Ce, Pr, Nd, Pm, Sm, Eu, Gd, Dy, Ho, Er, Yb, Lu, Th is carried out. The data on polonium and promethium are obtained for the first time. The calculation is performed with application of ultrasound velocity value at the melting temperature of the given metal. The average derivation of the calculational data on the Debye temperature from the published ones equals 12%. It is noted, that application of the acoustic method for determination of the characteristic temperature makes it possible to solve the wide range of theoretical and applied problems [ru

  2. Measurement of 147Pm in-vivo using phoswich detectors

    International Nuclear Information System (INIS)

    Johnson, J.R.

    1977-10-01

    Recently an individual was suspected of having inhaled significant amounts of the almost pure beta emitter, 147 Pm. Urine analysis confirmed that contaminations had occurred but these results could not be used to evaluate the amount of material deposited in the lungs because an acceptable model of promethium clearance from the lung to blood and hence to urine has not been developed. Therefore another method of evaluation, that of the measurement, using phoswich detectors, of the soft photons emitted by the deposited 147 Pm was used. This paper describes the calibrations and measurements that were done in order that an upper limit on the deposited activity, and hence limits for committed dose to the various organs, could be assigned. (author)

  3. Separation device of radio lanthanides (DISER)

    International Nuclear Information System (INIS)

    Vera T, A.L.; Monroy G, F.; Vazquez M, J.C.; Jimenez B, F.

    2008-01-01

    At the present time the cancer is one of the main causes of mortality in our country, therefore, its prevention, diagnostic and treatment is of vital importance for those health systems. The treatment of the cancer and other illnesses, starting from monoclonal antibodies, peptides, macro aggregates or marked aminoacids with beta particles emitting radioisotopes, it is an extremely promising field. The radioactive lanthanides: Promethium 149, Terbium 161, Holmium 166 and Lutetium 177 are beta emitting (β), which possess nuclear and chemical properties that have shown their feasibility like radioisotopes of radiotherapeutic use. However, these radioisotopes are not commercially available; to this respect, the Radioactive Materials Research Laboratory (LIMR) of the National Institute of Nuclear Research (ININ), it has developed the methodology of production of these radioisotopes and based on these works, there is designed, built and mounted the Radio lanthanides Separation Device (DISER) able to carry out the radioisotopes production in a routine way. This device is content in a cell that has an auxiliary air service, an extraction system and it is protected with a lead armor-plating of 10 cm. The DISER it is manual and easy of managing. The main function of this equipment is the radio lanthanides separation starting from the extractive chromatography by means of packed columns with a commercial resin (LnSPS) and recovered in the superior and inferior part by fiber glass. The DISER is composed by a main carrousel where the separation columns and the elution recipients are mounted. Also counts with an opening system of irradiation vials, port samples for columns and glass material. The present work presents a detailed description of the DISER, as well as its handling that allows to produce the radioisotopes Promethium-149, Terbium-161, Holmium-166 and Lutetium-177 starting from the separation of its parent elements Neodymium-149, Gadolinium-161, Dysprosium-166 and

  4. Separation device of radio lanthanides (DISER); Dispositivo de separacion de radiolantanidos (DISER)

    Energy Technology Data Exchange (ETDEWEB)

    Vera T, A.L. [FES-Zaragoza, UNAM, 09000 Mexico D.F. (Mexico); Monroy G, F.; Vazquez M, J.C.; Jimenez B, F. [ININ, 52750 La Marquesa, Estado de Mexico (Mexico)]. e-mail: veratrevino@hotmail.com

    2008-07-01

    At the present time the cancer is one of the main causes of mortality in our country, therefore, its prevention, diagnostic and treatment is of vital importance for those health systems. The treatment of the cancer and other illnesses, starting from monoclonal antibodies, peptides, macro aggregates or marked aminoacids with beta particles emitting radioisotopes, it is an extremely promising field. The radioactive lanthanides: Promethium 149, Terbium 161, Holmium 166 and Lutetium 177 are beta emitting ({beta}), which possess nuclear and chemical properties that have shown their feasibility like radioisotopes of radiotherapeutic use. However, these radioisotopes are not commercially available; to this respect, the Radioactive Materials Research Laboratory (LIMR) of the National Institute of Nuclear Research (ININ), it has developed the methodology of production of these radioisotopes and based on these works, there is designed, built and mounted the Radio lanthanides Separation Device (DISER) able to carry out the radioisotopes production in a routine way. This device is content in a cell that has an auxiliary air service, an extraction system and it is protected with a lead armor-plating of 10 cm. The DISER it is manual and easy of managing. The main function of this equipment is the radio lanthanides separation starting from the extractive chromatography by means of packed columns with a commercial resin (LnSPS) and recovered in the superior and inferior part by fiber glass. The DISER is composed by a main carrousel where the separation columns and the elution recipients are mounted. Also counts with an opening system of irradiation vials, port samples for columns and glass material. The present work presents a detailed description of the DISER, as well as its handling that allows to produce the radioisotopes Promethium-149, Terbium-161, Holmium-166 and Lutetium-177 starting from the separation of its parent elements Neodymium-149, Gadolinium-161, Dysprosium-166

  5. On the use of spectroscopic techniques to determine the crystal structure of compounds of the artificial f elements

    International Nuclear Information System (INIS)

    Peterson, J.R.

    1989-01-01

    For some time the author has been using solid state absorption spectrophotometry to identify the crystal structure of selected transuranium (5f) and promethium (4f) compounds, based on spectral-structural correlations in his data base. More recently he has shown that Raman phonon spectroscopy is also very useful in this regard. These spectral probes of structure have their specific advantages and disadvantages; however, both are applicable to the structural characterization of radioactive compounds and can provide data for interpretation faster and more reliably than the commonly used X-ray powder diffraction method. The experimental methods, examples from the growing data bases, successes and limitations of these spectral probes of crystal structure, and some useful applications to the study of f-element compounds under varying conditions of temperature and pressure are presented

  6. Radioactive rare earths from fallout for study of particle movement in the sea

    International Nuclear Information System (INIS)

    Sugihara, Thomas T.; Bowen, Vaughan T.

    1962-01-01

    As part of an extensive study of the distribution of long-lived radionuclides from fallout in the Atlantic Ocean, a large number of measurements of cerium-144 and promethium-147 concentration have been made. Comparison of these concentrations as they vary both horizontally and vertically, with simultaneously measured concentrations of strontium-90, indicates that the rare earths are generally depleted in surface water, by comparison with the nuclides known to be soluble. This observation, coupled with frequent observation of rare-earth enrichment at depth, leads us to postulate rapid vertical transport of rare earths by attachment to particles undergoing sedimentation. This is completely plausible in terms of the 'radiocolloid' behaviour generally observed for rare earths at sea-water pH. An attempt is made to interpret this study in the overall picture of the marine geochemistry of the trivalent cations, as well as to emphasize the unique and generally useful aspects of the fallout tracer experiment. (author) [fr

  7. Determination of stability constants of lanthanide complexes with tetracycline

    International Nuclear Information System (INIS)

    Saiki, Mitiko

    1975-01-01

    The stability constants of complexes compounds formed with tetracycline and lanthanides elements were determined for all lanthanides except promethium. The experimental procedure used was solvent extraction of the lanthanides labelled with their radioactive isotopes. It was shown that the formed complexes are mononuclear and that no hydroxo complexes or negatively charged complexes are formed in the experimental conditions of this work. Four methods of calculation were used for all complexes studied: the method of the average number of ligands, the method of limiting value, the method of two parameters and the method of weighted least squares. A comparison was made of the graphical methods with the method of least squares, showing the convenience of preceding least squares calculation by the graphical methods, in order to verify eventual mistakes of numerical data. It was shown the advantage of using radioisotopes of the elements for such a study, specially if the solvent extraction technique is used to-get the experimental data. (author)

  8. Dosimetry in single lung cells by means of microautoradiographic activity measurements

    International Nuclear Information System (INIS)

    Kraus, W.

    1976-01-01

    After inhalation of compounds containing promethium-147 in the lungs of mice most of the activity was deposited in the form of local concentrations (hotspots). By means of a special quantitative microautoradiographic method using stripping film ORWO K 105, measurements of the activity of single hotspots of about 10 -14 Ci were possible. A microphotometer with a variable measuring diaphragm was used for the determination of the density profile of the autoradiographic image in order to get hotspot depth within the biological specimen. To determine hotspot activity it was necessary to calibrate the film with a Pm-147 plane source. The systematic and random errors of the method are discussed in detail, giving a total error of +- 21% (SD) for one hotspot activity measurement. A few examples of biological results obtained by the method are given. Simple models were used to calculate doses absorbed in macrophage and alveolar cell nuclei from the measured activities. (author)

  9. Studies of photon spectra from a thallium-204 foil source as an aid to dosimetry and shielding

    CERN Document Server

    Francis, T M

    1976-01-01

    Beta ray foil sources incorporating nuclides such as thallium-204, promethium-147 and strontium-90 plus yttrium-90 ar increasingly used in industrial devices such as thickness gauges. These sources are so constructed that they give rise to complex photon spectra containing low energy Bremsstrahlung and X-rays characteristic of the constructional materials. The energy response of practical monitoring instruments is such that they are likely to underestimate the dose due to such spectra unless they are calibrated using appropriate spectra. This report describes a series of measurements carried out on a commercially available thallium-204 foil source and five commonly used shielding materials. The measurements made with a NaI(T1) spectrometer have been corrected for instrumental distortions to obtain the photon spectra in air. These spectra are presented and have been used to compute dose in air with the help of published data on mass energy-absorption coefficients. Also included in the report are data derived f...

  10. Results of submerged sediment core sampling and analysis on Par Pond, Pond C, and L Lake: July 1995

    International Nuclear Information System (INIS)

    Koch, J.W. II; Martin, F.D.; Friday, G.P.

    1996-06-01

    Sediment cores from shallow and deep water locations in Par Pond, Pond C, and L Lake were collected and analyzed in 1995 for radioactive and nonradioactive constituents. This core analysis was conducted to develop a defensible characterization of contaminants found in the sediments of Par Pond, Pond C, and L Lake. Mercury was the only nonradiological constituent with a nonestimated quantity that was detected above the U.S Environmental Protection Agency Region IV potential contaminants of concern screening criteria. It was detected at a depth of 0.3--0.6 meters (1.0--2.0 feet) at one location in L Lake. Cesium-137, promethium-146, plutonium-238, and zirconium-95 had significantly higher concentrations in Par Pond sediments than in sediments from the reference sites. Cobalt-60, cesium-137, plutonium-238, plutonium-239/240, and strontium-90 had significantly higher concentrations in L-Lake sediments than sediments from the reference sites

  11. Astronomy Matters for Chemistry Teachers

    Science.gov (United States)

    Huebner, Jay S.; Vergenz, Robert A.; Smith, Terry L.

    1996-11-01

    The purpose of this paper is to encourage more chemistry teachers to become familiar with some of the basic ideas described in typical introductory astronomy courses (1 - 9), including those about the origin of elements and forms of matter. These ideas would enrich chemistry courses and help resolve some basic misconceptions that are expressed in many introductory texts (10 - 16) and journal articles for chemistry teachers (17, 18). These misconceptions are typified by statements such as "we can classify all substances as either elements or compounds," and "nature has provided 92 elements out of which all matter is composed." If students accept these misconceptions, they could be deprived of (i) an appreciation of the history of elements and knowing that the elemental composition of the universe continues to evolve, (ii) knowing that of the first 92 elements in the periodic table, technetium and promethium do not occur naturally on Earth, and (iii) understanding that there are forms of matter other than elements and compounds. This paper briefly explores these ideas.

  12. The occurrence of primary pulmonary neoplasms in rats after inhalation of 147Pm in fused aluminosilicate particles

    International Nuclear Information System (INIS)

    Herbert, R.A.; Scott, B.R.; Hahn, F.F.; Newton, G.J.; Snipes, M.B.; Damon, E.G.; Boecker, B.B.

    1988-01-01

    To determine the biological response following low-energy, beta irradiation of the lung, F344/Crl rats were exposed to aerosols of promethium-147 in fused aluminosilicate particles and observed for their life spans. Radiation pneumonitis and pulmonary fibrosis caused the majority of deaths during the first year after exposure with cumulative doses to the lungs of 210 to 630 Gy. Primary pulmonary neoplasms were responsible for the majority of deaths that occurred beyond 1 yr after exposure and in rats receiving lower cumulative doses to the lung. Hemangiosarcomas and squamous cell carcinomas were the most prevalent pulmonary neoplasms. Three adenocarcinomas were found. The uncorrected crude incidence of primary lung tumors increased with increasing dose to the lung for cumulative doses less than 140 Gy. With higher doses, the incidence declined. Adjusting the data for competing risks eliminated the turnover in the dose-response curve. The times of onset of pulmonary tumors and median survival times were dose-dependent. Rats with higher accumulated radiation doses developed fatal lung tumors at earlier times after exposure. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

    Taherzadeh, M.

    1987-11-13

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

  14. Technology for recovery of by-products

    International Nuclear Information System (INIS)

    Van Tuy, H.H.

    1983-01-01

    Products of conventional nuclear fuel processing plants are uranium and plutonium, and any other recovered material is considered to be a by-product. Some by-products have been recovered from past nuclear fuel processing operations, either as a normal mode of operation or by special campaigns. Routing recovery over an extended period has been limited to neptunium, but extended campaigns were used at Hanford to recover strontium for radioisotope thermoelectric generators. Krypton is recovered at Idaho Chemical Processing Plant on a campaign basis, and isotope separation of krypton is done at Oak Ridge National Laboratory. Past campaigns at Hanford PUREX have recovered cesium, promethium, amercium, cerium, and technetium. Past by-product recovery efforts were usually severely constrained by the status of flowsheet development and availability of existing facilities at the time decisions wee made to recover the by-products. Additional processes were developed to accommodate other unit operations and in response to changes in waste management objectives or user requirements. Now an impressive variety of recovery technology is available for most potential by-products, with varying degrees of demonstration under conditions which satisfy today's environmental protection and waste management constraints

  15. New developments in the analysis and measurement of thicknesses by excitation of the fluorescent lines by means of {beta} particles; Nouveaux developpements de l'analyse et de la mesure des epaisseurs par excitation des raies de fluorescence au moyen de particules {beta}

    Energy Technology Data Exchange (ETDEWEB)

    Martinelli, P [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires; Seibel, G [Institut de Recherches de la Siderurgie, 78 - Saint-Germain-en-Laye (France)

    1960-07-01

    The process for analysing and measuring the thickness of deposits by {beta}-X fluorescence which we have already described has undergone further development. The use of promethium-147 and krypton-85 sources makes it possible to reduce the background noise which is observed with strontium-90. We present the results obtained for various measurements of the thickness of metallic coatings and the continuous measurement of calcium and of iron in ore samples. We describe the tests carried out with a view to analysing the X-rays by means of a crystal. (author) [French] Le procede d'analyse et de mesure des epaisseurs de depots par fluorescence {beta}-X que nous avons precedemment decrit a fait l'objet de nouveaux developpements. L'emploi de sources de prometheum-147 et de krypton-85 permet de reduire le bruit de fond que l'on observe avec le strontium-90. Nous dormons les resultats obtenus pour diverses mesures d'epaisseurs de depots metalliques et la mesure en continu du calcium et du fer dans les carottes de minerais. Nous decrivons les essais effectues en vue d'analyser le rayonnement X au moyen d'un cristal. (auteur)

  16. Return to the... past

    International Nuclear Information System (INIS)

    Ammerich, M.

    2009-01-01

    This article goes back over the incidents occurring during the summer 2008, that is to say the uranium release from the Socatri facility in the South of France. From this point, the purpose studies the radiological situation of the Camargue seashore; the levels of radioactivity are from 3 to thirty times higher than these ones expected in this area, but the natural radioactivity with thorium and uranium coming from the granitic massifs erosion brings an important part. It is difficult to make the part between human and natural contribution to ambient radioactivity. However, it appears that to limit the water consumption until the time of dilution played its part was absolutely necessary. Then, because it is question of water, the drinking water is tackled. Some mineral waters go over the recommended limits of doses. A last return to the past with the radioactive watches, but this time with actual watches that activate detection. Two watches contained promethium 147, 147 Pm is a beta emitter but also gamma emitter. To end, in Ireland and Great Britain, some fire detectors contain americium 241. In fact, this article constitutes a summary of different abnormalities around radioactivity. (N.C.)

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

    Science.gov (United States)

    Hedrick, James B.

    1997-01-01

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

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

    Science.gov (United States)

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

    2017-12-19

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

  19. Radiation sources and process

    International Nuclear Information System (INIS)

    Honious, H.B.; Janzow, E.F.; Malson, H.A.; Moyer, S.E.

    1980-01-01

    The invention relates to radiation sources comprising a substrate having an electrically-conductive non-radioactive metal surface, a layer of a metal radioactive isotope of the scandium group, which in addition to scandium, yttrium, lanthanum and actinium, includes all the lanthanide and actinide series of elements, with the actinide series usually being preferred because of the nature of the radioactive isotopes therein, particularly americium-241, curium-244, plutonium-238, californium-252 and promethium-147, and a non-radioactive bonding metal codeposited on the surface by electroplating the isotope and bonding metal from an electrolytic solution, the isotope being present in the layer in minor amount as compared to the bonding metal, and with or without a non-radioactive protective metal coating covering the isotoype and bonding metal on the surface, the coating being sufficiently thin to permit radiation to pass through the coating. The invention also relates to a process for providing radiation sources comprising codepositing a layer of the metal radioactive isotope with a non-radioactive bonding metal from an electrolytic solution in which the isotope is present in minor molar amount as compared to the bonding metal such that the codeposited layer contains a minor molar amount of the isotope compared to the bonding metal by electroplating on an electrically-conductive non-radioactive metal surface of a cathode substrate, and with or without depositing a nonradioactive protective metal coating over the isotope and bonding metal on the surface, the coating being sufficiently thin to permit radiation to pass through the coating

  20. New processing techniques for radioisotopes at Oak Ridge National Laboratory; Production de radioisotopes: nouvelles techniques employees au Laboratoire national d'Oak Ridge; Novye tekhnologicheskie metody polucheniya radioizotopov v Okridzhskoj natsional'noj laboratorii; Nuevos metodos de preparacion de radioisotopos aplicados en el Oak Ridge National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Butler, T A; Lamb, E; Rupp, A F [Oak Ridge National Laboratory, Oak Ridge, TN (United States)

    1962-01-15

    Recent developments in the radioisotope production programme at Oak Ridge National Laboratory include new processes and process improvements for the production of cerium-144, promethium-147, technetium-99 and strontium-90. Cerium-144 has been produced in kc quantities in a test run. A product recovery of more than 98% with a product purity of more than 99% was attained. The cerium was further processed to obtain pure cerium-144 oxide powder having an activity concentration of 235 c/g. The powder was pressed into pellets which were sintered to a dense ceramic form. Promethium-147 has been produced in kc quantities by a combination of precipitation and ion exchange techniques. A solvent extraction system for separating promethium- 147 from other rare earths has been tested on a tracer scale. Gram quantities of technetium-99 have been recovered from fission-product waste streams by a combination of precipitation and solvent extraction processes. The technetium product was produced with a chemical purity of more than 99.9% and radiochemical purity of more than 99.99%. The separation and purification of strontium-90 from gross contaminants by a continuous solvent-extraction flowsheet has been demonstrated on a tracer scale. Product quality of 98% strontium has been achieved from feed containing 95% inert calcium contaminant. The strontium-90 is further processed to form strontium titanate ceramic elements. (author) [French] Les faits recents a noter dans le programme de production de radioisotopes du laboratoire national d'Oak Ridge sont l'introduction de nouvelles methodes et l'amelioration des techniques existantes pour la production du eerium-144, du prometheum-147, du technetium-99 et du strontium-90. Le cerium-144 a ete obtenu en quantites de l'ordre du kilocurie, lors d'une experience. On a obtenu un taux d'extraction de plus de 98% et un produit d'une purete superieure a 99%. On a ensuite traite le cerium pour avoir de l'oxyde de cerium-144 pur en poudre ayant

  1. China's rare-earth industry

    Science.gov (United States)

    Tse, Pui-Kwan

    2011-01-01

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

  2. Intra-group separation of rare earths using new organic phosphorus ligands

    International Nuclear Information System (INIS)

    Hadic, Sanela

    2017-01-01

    Rare earth elements (REE) have unique magnetic, photophysical, and chemical properties and they are therefore used in numerous high-technology applications. However, to this day, the isolation of pure rare earths from primary and secondary raw materials is very challenging. In this work, the hydrometallurgical separation of neighboring rare earths (e.g., praseodymium/ neodymium) was optimized with novel selective extraction agents. The separation of rare earths (yttrium and all lanthanides except promethium) was investigated with fourteen new organophosphorus compounds. Oxygen-bearing phosphinic acids yielded good separation results for heavy rare earths (dysprosium to lutetium). For light rare earths (lanthanum to neodymium), particularly high separation factors were realized with synergistic systems containing an aromatic dithiophosphinic acid and a co-extractant, such as tris (2-ethylhexyl) phosphate (TEHP). Optimization studies of the latter extraction system revealed an extremely high separation factor (SF) of 4.21 between praseodymium and neodymium. Another focus of this work was to understand the extraction mechanism. With the aid of nuclear magnetic resonance spectroscopy ("1H-NMR) and time-resolved laser fluorescence spectroscopy (TRLFS), the complex stoichiometry of promising extraction systems was examined. Studies revealed a dependency between the selectivity for rare earths and the coordination number of the formed complexes. In addition, temperature-dependent extraction experiments were performed and thermodynamic data (ΔG, ΔH, and ΔS) determined. These data provided additional information about the origin of selectivity for neighboring rare earths. With regard to the industrial capability of the investigated extraction systems, the chemical durability of ligands was studied under process-relevant conditions. Qualitative and quantitative analytical methods (e.g., GC-MS) were used in long-term experiments to determine the ligand degradation. After

  3. Thermodynamic study on the complexation of Trivalent actinide and lanthanide cation by N-donor ligands in homogeneous conditions; Etude thermodynamique de la complexation des ions actinide (III) et lanthanide (III) par des ligands polyazotes en milieu homogene

    Energy Technology Data Exchange (ETDEWEB)

    Miguirditchian, M

    2004-07-01

    Polydentate N-donor ligands, alone or combined with a synergic acid, may selectively extract minor actinides(III) from lanthanide(III) ions, allowing to develop separation processes of long-live radioelements. The aim of the researches carried out during this thesis was to better understand the chemical mechanisms of the complexation of f-elements by Adptz, a tridentate N-donor ligand, in homogeneous conditions. A thermodynamic approach was retained in order to estimate, from an energetic point of view, the influence of the different contributions to the reaction, and to acquire a complete set of thermodynamic data on this reaction. First, the influence of the nature of the cation on the thermodynamics was considered. The stability constants of the 1/1 complexes were systematically determined by UV-visible spectrophotometry for every lanthanide ion (except promethium) and for yttrium in a mixed solvent methanol/water in volume proportions 75/25%. The thermodynamic parameters ({delta}H{sup 0} {delta}{sup S}) of complexation were estimated by the van't Hoff method and by micro-calorimetry. The trends of the variations across the lanthanide series are compared with similar studies. The same methods were applied to the study of three actinide(III) cations: plutonium, americium and curium. The comparison of these values with those obtained for the lanthanides highlights the increase of stability of these complexes by a factor of 20 in favor of the actinide cations. This gap is explained by a more exothermic reaction and is associated, in the data interpretation, to a higher covalency of the actinide(III)-nitrogen bond. Then, the influence of the change of solvent composition on the thermodynamic of complexation was studied. The thermodynamic parameters of the complexation of europium(III) by Adptz were determined for several fractions of methanol. The stability of the complex formed increases with the percentage of methanol in the mixed solvent, owing to an

  4. Intra-group separation of rare earths using new organic phosphorus ligands; Intragruppentrennung Seltener Erden mittels neuer phosphororganischer Liganden

    Energy Technology Data Exchange (ETDEWEB)

    Hadic, Sanela

    2017-10-01

    Rare earth elements (REE) have unique magnetic, photophysical, and chemical properties and they are therefore used in numerous high-technology applications. However, to this day, the isolation of pure rare earths from primary and secondary raw materials is very challenging. In this work, the hydrometallurgical separation of neighboring rare earths (e.g., praseodymium/ neodymium) was optimized with novel selective extraction agents. The separation of rare earths (yttrium and all lanthanides except promethium) was investigated with fourteen new organophosphorus compounds. Oxygen-bearing phosphinic acids yielded good separation results for heavy rare earths (dysprosium to lutetium). For light rare earths (lanthanum to neodymium), particularly high separation factors were realized with synergistic systems containing an aromatic dithiophosphinic acid and a co-extractant, such as tris (2-ethylhexyl) phosphate (TEHP). Optimization studies of the latter extraction system revealed an extremely high separation factor (SF) of 4.21 between praseodymium and neodymium. Another focus of this work was to understand the extraction mechanism. With the aid of nuclear magnetic resonance spectroscopy ({sup 1}H-NMR) and time-resolved laser fluorescence spectroscopy (TRLFS), the complex stoichiometry of promising extraction systems was examined. Studies revealed a dependency between the selectivity for rare earths and the coordination number of the formed complexes. In addition, temperature-dependent extraction experiments were performed and thermodynamic data (ΔG, ΔH, and ΔS) determined. These data provided additional information about the origin of selectivity for neighboring rare earths. With regard to the industrial capability of the investigated extraction systems, the chemical durability of ligands was studied under process-relevant conditions. Qualitative and quantitative analytical methods (e.g., GC-MS) were used in long-term experiments to determine the ligand degradation

  5. Advanced methodology to simulate boiling water reactor transient using coupled thermal-hydraulic/neutron-kinetic codes

    Energy Technology Data Exchange (ETDEWEB)

    Hartmann, Christoph Oliver

    2016-06-13

    Coupled Thermal-hydraulic/Neutron-kinetic (TH/NK) simulations of Boiling Water Reactor transients require well validated and accurate simulation tools. The generation of cross-section (XS) libraries, depending on the individual thermal-hydraulic state parameters, is of paramount importance for coupled simulations. Problem-dependent XS-sets for 3D core simulations are being generated mainly by well validated, fast running commercial and user-friendly lattice codes such as CASMO and HELIOS. In this dissertation a computational route, based on the lattice code SCALE6/TRITON, the cross-section interface GenPMAXS, the best-estimate thermal-hydraulic system code TRACE and the core simulator PARCS, for best-estimate simulations of Boiling Water (BWR) transients has been developed and validated. The computational route has been supplemented by a subsequent uncertainty and sensitivity study based on Monte Carlo sampling and propagation of the uncertainties of input parameters to the output (SUSA code). The analysis of a single BWR fuel assembly depletion problem with PARCS using SCALE/TRITON cross-sections has been shown a good agreement with the results obtained with CASMO cross-section sets. However, to compensate the deficiencies of the interface program GenPMAXS, PYTHON scripts had to be developed to incorporate missing data, as the yields of Iodine, Xenon and Promethium, into the cross-section-data sets (PMAXS-format) generated by GenPMAXS from the SCALE/TRITON output. The results of the depletion analysis of a full BWR core with PARCS have indicated the importance of considering history effects, adequate modeling of the reflector region and the control rods, as the PARCS simulations for depleted fuel and all control rods inserted (ARI) differs significantly at the fuel assembly top and bottom. Systematic investigations with the coupled codes TRACE/PARCS have been performed to analyse the core behaviour at different thermal conditions using nuclear data (XS

  6. Radioactive rare earths from fallout for study of particle movement in the sea; Etude du mouvement des particules dans la mer a l'aide de terres rares radioactives provenant de retombees; Ispol'zovanie osazhdayushchikhsya pri vypadenii radioaktivnykh redkikh zemel' dlya issledovaniya dvizheniya chastits v more; Estudio del movimiento de las particulas en el mar con ayuda de tierras raras radiactivas procedentes de las precipitaciones

    Energy Technology Data Exchange (ETDEWEB)

    Sugihara, Thomas T [Clark University, Worcester, MA (United States); Bowen, Vaughan T [Woods Hole Oceanographic Institution, Woods Hole, MA (United States)

    1962-01-15

    As part of an extensive study of the distribution of long-lived radionuclides from fallout in the Atlantic Ocean, a large number of measurements of cerium-144 and promethium-147 concentration have been made. Comparison of these concentrations as they vary both horizontally and vertically, with simultaneously measured concentrations of strontium-90, indicates that the rare earths are generally depleted in surface water, by comparison with the nuclides known to be soluble. This observation, coupled with frequent observation of rare-earth enrichment at depth, leads us to postulate rapid vertical transport of rare earths by attachment to particles undergoing sedimentation. This is completely plausible in terms of the 'radiocolloid' behaviour generally observed for rare earths at sea-water pH. An attempt is made to interpret this study in the overall picture of the marine geochemistry of the trivalent cations, as well as to emphasize the unique and generally useful aspects of the fallout tracer experiment. (author) [French] Dans le cadre d'une vaste etude sur la repartition dans l'Ocean Atlantique des radionuclides de longue periode provenant de retombees, on a procede a de nombreuses mesures de la concentration du cerium-144 et du prometheum- 147. En comprenant les variations horizontales et verticales de ces concentrations avec les concentrations, mesurees simultanement, du strontium-90, on constate que les terres rares sont en general moins abondantes en surface que les nuclides connus pour etre solubles. Cette observation, jointe au fait que l'on a souvent constate un enrichissement des eaux profondes en terres rares, amene les auteurs a considerer qu'il s'effectue im transport vertical rapide des terres rares, par adhesion aux particules qui subissent une sedimentation. Cette hypothese est entierement compatible avec le comportement que les terres rares ont generalement dans un milieu ayant le pH de l'eau de mer. Les auteurs du memoire essaient d

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