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Sample records for mo tc ru

  1. Metal-metal bonding and aromaticity in [M2(NHCHNH)3]2 (μ-E)2 (E = O, S; M = Nb, Mo, Tc, Ru, Rh).

    Science.gov (United States)

    Yan, Xiuli; Meng, Lingpeng; Sun, Zheng; Li, Xiaoyan

    2016-02-01

    The nature of M-M bonding and aromaticity of [M2(NHCHNH)3]2(μ-E)2 (E = O, S; M = Nb, Mo, Tc, Ru, Rh) was investigated using atoms in molecules (AIM) theory, electron localization function (ELF), natural bond orbital (NBO) and molecular orbital analysis. These analyses led to the following main conclusions: in [M2(NHCHNH)3]2(μ-E)2 (E = O, S; M = Nb, Mo, Tc, Ru, Rh), the Nb-Nb, Ru-Ru, and Rh-Rh bonds belong to "metallic" bonds, whereas Mo-Mo and Tc-Tc drifted toward the "dative" side; all these bonds are partially covalent in character. The Nb-Nb, Mo-Mo, and Tc-Tc bonds are stronger than Ru-Ru and Rh-Rh bonds. The M-M bonds in [M2(NHCHNH)3]2(μ-S)2 are stronger than those in [M2(NHCHNH)3]2(μ-O)2 for M = Nb, Mo, Tc, and Ru. The NICS(1)ZZ values show that all of the studied molecules, except [Ru2(NHCHNH)3]2(μ-O)2, are aromaticity molecules. O-bridged compounds have more aromaticity than S-bridged compounds. Graphical Abstract Left Molecular graph, and right electron localization function (ELF) isosurface of [M2(NHCHNH)3]2(μ-E)2(E = O, S; M = Nb, Mo, Tc, Ru, Rh).

  2. Radionuclidic contamination of 99Mo, 131I and 103Ru in the eluate of 99Mo-99mTc chromatographic generator: comparision on fission produced 99Mo from RPC, Nordio and ARI

    International Nuclear Information System (INIS)

    Soenarjo, Sunarhadijoso; Gunawan, Adang Hardi

    1996-01-01

    The 99 Mo- 99m Tc Chromatographic generators is the most popular system to provide 99m Tc medical radioisotope. Radioisotope Production Centre (RPC)- BATAN has routinely produced the generator loaded with 99 Mo prepared by 235 U fission. By using fission produced 99 Mo, the resulting 99m Tc is potentially contaminated by other fission products which are difficult to eliminate completely. In order to study the characteristic of the generator and radionuclidic impurity pattern of the 99m Tc eluates, an evaluation of gamma spectrometric determination has been carried out. The bulk solutions of 99 Mo produced by RPC BATAN (Indonesia), Nordion (Canada) and ARI (Australia) were loaded to generators manufactured between July 1993 to May 1994. The saline-eluate 99m Tc, in a total volume of 10 ml each, was subjected to gamma spectrometric determination. The radiation of 99m Tc was eliminated by lead shield of 0.6913 cm thickness. The 99m Tc yield fluctuation from 28 generators indicated that the characteristics of the generator columns were very good. The 99m Tc eluates were consistently contaminated by 99 Mo, 131 I and 103 Ru, although the contamination level in all cases did not exceed the maximum permissible levels. The fluctuation of radionuclidic impurities were probably caused by variation in the irradiation parameter or by variation in the 99 Mo separation methods. (author), 23 refs, 1 tab, 3 figs

  3. Quality assurance of Mo-99/Tc-99m radionuclide generators

    Science.gov (United States)

    Uzunov, Nikolay; Yordanova, Galina; Salim, Seniha; Stancheva, Natalya; Mineva, Vanya; Meléndez-Alafort, Laura; Rosato, Antonio

    2018-03-01

    Gamma-ray spectrometry analyses of the radionuclide content of eluate from two Mo-99/Tc-99m radionuclide generators POLTECHNET have been performed. The relative activities of 99Mo 103Ru and 131I radioisotopes with respect to the activity of 99mTc at different time intervals after the primary pertechnetate elution of the generators have been analyzed. The relative activities of the isotopes were determined and compared to the radionuclidic purity requirements for 99mTc.

  4. Use of 99mTc from a commercial 99Mo/9mTc generator as yield tracer for the determination of 99Tc at low levels

    DEFF Research Database (Denmark)

    Hou, Xiaolin; Jensen, Mikael; Nielsen, Sven Poul

    2007-01-01

    The concentrations of Tc-99 and impurity radionuclides in the Tc-99m tracer solution obtained from a commercial Mo-99/Tc-99m generator were measured by gamma spectrometry and liquid scintillation counting. Mo-99 and Ru-103 were found in the Tc-99m eluate. A simple separation using two extra alumina...... cartridges was investigated to purify the eluate to obtain a suitable Tc-99m tracer with low Tc-99 concentration. The activity ratio of Tc-99/Tc-99m in the prepared Tc-99m solution is lower than 15 x 10(-9), which is higher than the theoretical ratio of less than 10 x 10(-9). The possible reason is discussed....... The Tc-99 in the 20 kBq spiked Tc-99m tracer was found to be less than 0.3mBq, which is lower than the detection limit of the radiometric method used for environmental samples. The purified Tc-99m eluate is used as yield tracer for the determination of low levels of Tc-99 in environmental samples. (c...

  5. 99Mo production for using in the nuclear medicine in 99mTc generators

    International Nuclear Information System (INIS)

    Kurenkov, N.V.; Chuvilin, D.Yu.

    1999-01-01

    The review of methods and advanced technologies for obtaining 99 Mo in nuclear reactors is presented. The 99 Mo isotope is used for preparing the 99m Tc generators, widely applied in nuclear medicine. The reactor method for obtaining 99 Mo is based on the 98 Mo(n, γ) 99 Mo radiation capture reaction and 235 U fission reaction under the effect of the 235 U (n, f) 99 Mo reaction. The results of studies on obtaining 99 Mo on the charged particles accelerators, mainly, on the proton beam and under the effect of photonuclear reaction is also described. The data on the 99 Mo real consumption and forecast for its application in different regions of the world from 1994 up to 2006 are presented [ru

  6. Altered [99mTc]Tc-MDP biodistribution from neutron activation sourced 99Mo.

    Science.gov (United States)

    Demeter, Sandor; Szweda, Roman; Patterson, Judy; Grigoryan, Marine

    2018-01-01

    Given potential worldwide shortages of fission sourced 99 Mo/ 99m Tc medical isotopes there is increasing interest in alternate production strategies. A neutron activated 99 Mo source was utilized in a single center phase III open label study comparing 99m Tc, as 99m Tc Methylene Diphosphonate ([ 99m Tc]Tc-MDP), obtained from solvent generator separation of neutron activation produced 99 Mo, versus nuclear reactor produced 99 Mo (e.g., fission sourced) in oncology patients for which an [ 99m Tc]Tc-MDP bone scan would normally have been indicated. Despite the investigational [ 99m Tc]Tc-MDP passing all standard, and above standard of care, quality assurance tests, which would normally be sufficient to allow human administration, there was altered biodistribution which could lead to erroneous clinical interpretation. The cause of the altered biodistribution remains unknown and requires further research.

  7. Study of methodologies for quality control of 99Mo used in 99Mo/99mTc generators

    International Nuclear Information System (INIS)

    Said, Daphne de Souza

    2016-01-01

    99m Tc is the most used radionuclide in nuclear medicine. In Brazil, the 99 Mo/ 99m Tc generators are exclusively produced by Radiopharmacy Center at IPEN-CNEN/ SP, by importing 99 Mo from different suppliers. 99 Mo (t 1/2 = 66 h) is a fission product of 235 U and it can have radionuclidic impurities that are prejudicial for human health. For safe use of generators, it is necessary to perform the evaluation of 99 Mo by quality control tests in order to assess if 99 Mo complies with the specifications. The European Pharmacopoeia (EP) presents a monograph for evaluation of the quality of the [ 99 Mo] solution as sodium molybdate,that is used as raw material for 99 Mo/ 99m Tc generators production, including specification parameters (identification, radiochemical purity and radionuclidic purity), analysis methods and limits. However, it has been observed difficulties on the execution and implementation of these methods by the generators producers, with a few literature about this subject, probably due to complexity of the proposed methods. In this work, many quality control parameters of 99 Mo described in the EP monograph were evaluated. Separation methods for 99M o from its radionuclidic impurities by solid phase extraction (SPE) and TLC were studied. After SPE separation, the quantification of metals by ICP-OES to evaluate the percentage of retention of Mo and the percentage of recovery of Ru, Te and Sr using different types of cartridges were proposed, replacing radiotracers use. It was observed that the specific type of SPE cartridge recommended by the EP for separation of 99 Mo presented low recoveries for Ru, compared to other available anion exchange SPE cartridges. 99 Mo samples from different worldwide suppliers were analyzed. It was observed that quantification of 103 Ru in 99 Mo samples with decay time higher than 4 weeks is possible. An alternative method for separation of 131 I from 99 Mo showed promising results by TLC. The quantification of beta and

  8. Density of states in Mo-Ru amorphous alloys

    International Nuclear Information System (INIS)

    Miyakawa, W.

    1985-01-01

    The density of states is calculated for several compositions of amorphous Mo 1-x Ru x . In order to simulate amorphous clusters, the structures (atomic positions) utilized in the calculations were built from a small dense randomly packed unit of hard spheres with periodic boundary conditions. The density of states is calculated from a tight-binding Hamiltonian with hopping integrals parametrized in terms of the ddσ, ddΠ and ddδ molecular integrals. The results for pure Mo and pure Ru, compared in the canonical band aproximation, agree well with the literature. For binary alloys, the comparison of the calculated density of states with the rigid band aproximation results indicates that a more complex approach than the rigid band model must be used, even when the two atoms have similar bands, with band centers at nearly the same energy. The results also indicate that there is no relation between the peak in the superconducting critical temperature as a function of the number of valence eletrons per atom (e/a) in the region near Mo(e/a=6) and the peak of the density of states at the Fermi level in the same region, as has been sugested by some authors. (Author) [pt

  9. Results of regular study on radionuclidic purity of sup(99m)Tc obtained from 99Mo-sup(99m)Tc generators

    International Nuclear Information System (INIS)

    Vlcek, J.; Rohacek, J.; Husak, V.

    1979-01-01

    A total of 39 sup(99m)Tc eluates obtained from 9 99 Mo-sup(99m)Tc generators delivered by The Radiochemical Centre Amersham during one year was studied with regard to their radionuclide purity. Using a Ge(Li) spectrometer the contaminants 60 Co, 103 Ru, 131 I, 134 Cs, 140 La and 188 Re were found in sup(99m)Tc-eluates with average levels ranging from 2.9 x 10 -3 to 2.8 x 10 -1 per cent of sup(99m)Tc activity. The additional total body absorbed dose caused by these contaminants, as calculated from their average content in sup(99m)Tc eluates, was less than 1% of the dose due to sup(99m)Tc pertechnetate. (orig.) 891 MG/orig. 892 CS [de

  10. Successful labeling of 99mTc-MDP using 99mTc separated from 99Mo produced by 100Mo(n,2n)99Mo

    International Nuclear Information System (INIS)

    Nagai, Yasuki; Hatsukawa, Yuichi; Kin, Tadahiro; Hashimoto, Kazuyuki; Motoishi, Shoji; Konno, Chikara; Ochiai, Kentaro; Takakura, Kosuke; Sato, Yuichi; Sato, Norihito; Ohta, Akio; Yamabayashi, Hisamichi; Tanase, Masakazu; Fujisaki, Saburo; Kawauchi, Yukimasa; Teranaka, Tomoyuki; Takeuchi, Nobuhiro; Igarashi, Takashi

    2011-01-01

    We have for the first time succeeded in separating 99m Tc from a MoO 3 sample irradiated with accelerator neutrons free from any radioactive impurities and in formulating 99m Tc-methylene diphosphonate ( 99 mTc-MDP). 99 Mo, the mother nuclide of 99m Tc, was produced by the 100 Mo(n,2n) 99 Mo reaction using about 14 MeV neutrons provided by the 3 H(d,n) 4 He reaction at the Fusion Neutronics Source of Japan Atomic Energy Agency. The 99m Tc was separated from 99 Mo by sublimation and its radionuclide purity was confirmed to be higher than 99.99% by γ-spectroscopy. The labeling efficiency of 99m Tc-MDP was shown to be higher than 99% by thin-layer chromatography. These values exceed the United States Pharmacopeia requirements for a fission product, 99 Mo. Consequently, a 99m Tc radiopharmaceutical preparation formed by using the mentioned 99 Mo can be a promising substitute for the fission product 99 Mo, which is currently produced using a highly enriched uranium target in aging research reactors. A longstanding problem to ensure a reliable and constant supply of 99 Mo in Japan can be partially mitigated. (author)

  11. Tc Generator Development: Up-to-Date Tc Recovery Technologies for Increasing the Effectiveness of Mo Utilisation

    Directory of Open Access Journals (Sweden)

    Van So Le

    2014-01-01

    Full Text Available A review on the Mo sources available today and on the Tc generators developed up to date for increasing the effectiveness of Mo utilisation is performed in the format of detailed description of the features and technical performance of the technological groups of the Mo production and Tc recovery. The latest results of the endeavour in this field are also surveyed in regard of the technical solution for overcoming the shortage of Mo supply. The technological topics are grouped and discussed in a way to reflect the similarity in the technological process of each group. The following groups are included in this review which are high specific activity Mo: the current issues of production, the efforts of more effective utilisation, and the high specific activity Mo-based Tc generator and Tc concentration units; low specific activity Mo: the Mo production based on neutron capture and accelerators and the direct production of Tc and the methods of increasing the specific activity of Mo using Szilard-Chalmers reaction and high electric power isotopic separator; up-to-date technologies of Tc recovery from low specific activity Mo: the solvent extraction-based Tc generator, the sublimation methods for Mo/Tc separation, the electrochemical method for Tc recovery, and the column chromatographic methods for Tc recovery. Besides the traditional Tc-generator systems, the integrated Tc generator systems (Tc generator column combined with postelution purification/concentration unit are discussed with the format of process diagram and picture of real generator systems. These systems are the technetium selective sorbent column-based generators, the high Mo-loading capacity column-based integrated Tc generator systems which include the saline-eluted generator systems, and the nonsaline aqueous and organic solvent eluent-eluted generator systems using high Mo-loading capacity molybdategel and recently developed sorbent columns. Tc concentration methods used in the

  12. Robust ultra-thin RuMo alloy film as a seedless Cu diffusion barrier

    International Nuclear Information System (INIS)

    Hsu, Kuo-Chung; Perng, Dung-Ching; Wang, Yi-Chun

    2012-01-01

    Highlights: ► A 5 nm-thick Mo added Ru film has been investigated as a Cu diffusion barrier layer. ► RuMo film provides over 175 °C improvement in thermal stability than that of pure Ru layer. ► The 5 nm-thick RuMo film shows excellent barrier performance against Cu diffusion upon 725 °C. - Abstract: This study investigated the properties of 5 nm-thick RuMo film as a Cu diffusion barrier. The sheet resistance variation and X-ray diffraction patterns show that the RuMo alloy film has excellent barrier performance and that it is stable upon annealing at 725 °C against Cu. The transmission electron microscopy micrograph and diffraction patterns show that the RuMo film is an amorphous-like structure, whereas pure Ru film is a nano-crystalline structure. The elements’ depth profiles, analyzed by X-ray photoelectron spectroscopy, indicate no inter-diffusion behavior between the Cu and Si layer, even annealing at 700 °C. Lower leakage current has been achieved from the Cu/barrier/insulator/Si test structure using RuMo film as the barrier layer. A 5 nm ultrathin RuMo film provided two orders of magnitude improvement in leakage current and also exhibited a 175 °C improvement in thermal stability than that of the pure Ru film. It is a potential candidate as a seedless Cu diffusion barrier for advanced Cu interconnects.

  13. Determination of 99Mo contamination in 99mTc elute obtained from 99Mo/99mTc- generator

    International Nuclear Information System (INIS)

    Momennezhad, M.; Zakavi, S. R.; Sadeghi, R.

    2010-01-01

    99m Tc is a widely used radioisotope in nuclear medicine centers which is obtained by elution from Mo-99/Tc-99m generators. Usually the generators are either supplied by the Iran Atomic Energy Agency or by private companies from foreign countries. In this study we have measured 99 Mo contamination in 99m Tc elute from different generators in a period of one year. Materials and Methods: The radionuclide impurity of the 99m Tc elute were studied in two types of radionuclide generators (A: produced in Iran and B: Imported from other country). In-vitro measurements were performed using dose calibrator. Direct measurements were made, using a standard canister at the time of milking of the generators and also in Subsequent hours after milking. Results: The results showed a mean of 99 Mo impurity in generators A and B to be 0.00932±0.0043 and 0.0170±0.0127 respectively. Although the results showed that the 99 Mo contamination in 99 mTc elute was lesser than the maximum accepted activity limit of 0.015%, the difference in these two types may reflect different methods of productions of generator, as well as the quality control procedures. Conclusion: The mean of 99 Mo contamination in generators produced in Iran Atomic Energy Organization was lesser than generators imported from foreign origin.

  14. Spent 99Mo/99mTc generator as an economical source of 99Mo

    International Nuclear Information System (INIS)

    El-Kolaly, M.T.

    1990-01-01

    An improved method for utilization and purification of 99 Mo from spent 90 Mo/ 99m Tc generators has been described. After washing the generator with saline to remove the generated 99m Tc, followed by 2 mL 5 M NaOH containing a few drops of H 2 O 2 , the 99 Mo was quantitatively eluted from the generator with 5 mL 5 M NaOH. The alkaline eluate containing 99 Mo was contaminated with partially dissolved alumina. In the present method, an anion-exchange resin Dowex 1 x 8 column was used for purification of 99 Mo from the contaminating alumina. The resultant 99 Mo was of high purity and contained 3+ /mL 99 Mo solution, as estimated by atomic absorption. (author)

  15. Separation and determination of 103Ru in samples of fission 99Mo

    International Nuclear Information System (INIS)

    Aghazarian, V.P.; Duran, Adrian P.; Mondino, Angel V.

    2003-01-01

    In Argentina 99 Mo is produced in the RA-3 reactor at the Ezeiza Atomic Center (CAE), by irradiation of miniplates of Al/U (90% 235 U) alloy. The 99 Mo separation is carried out at the Fission Radioisotopes Production Plant. Quality control is important to assure the quality of molybdenum that is produced in CAE. A new method to purify and on line quantify 103 Ru as an impurity present in 99 Mo samples was developed. This procedure is based in the RuO 4 volatilization and its dissolution in NaOH 6M. This is necessary due to the fact that 103 Ru cannot be detected in presence of high activities of 99 Mo without previous separation. This method allows a quantitative, specific, efficient, fast and reproducible separation of 103 Ru from 99 Mo. (author)

  16. Direct methanol fuel cell with extended reaction zone anode: PtRu and PtRuMo supported on graphite felt

    Science.gov (United States)

    Bauer, Alex; Gyenge, Előd L.; Oloman, Colin W.

    Pressed graphite felt (thickness ∼350 μm) with electrodeposited PtRu (43 g m -2, 1.4:1 atomic ratio) or PtRuMo (52 g m -2, 1:1:0.3 atomic ratio) nanoparticle catalysts was investigated as an anode for direct methanol fuel cells. At temperatures above 333 K the fuel cell performance of the PtRuMo catalyst was superior compared to PtRu. The power density was 2200 W m -2 with PtRuMo at 5500 A m -2 and 353 K while under the same conditions PtRu yielded 1925 W m -2. However, the degradation rate of the Mo containing catalyst formulation was higher. Compared to conventional gas diffusion electrodes with comparable PtRu catalyst composition and load, the graphite felt anodes gave higher power densities mainly due to the extended reaction zone for methanol oxidation.

  17. Quality control studies of 99Mo used in 99Mo/99mTc generators produced at IPEN/CNEN-SP, Brazil

    International Nuclear Information System (INIS)

    Said, Daphne S.; Brambilla, Tania P.; Matsuda, Margareth M.N.; Osso Junior, Joao A.

    2015-01-01

    99m Tc is the most used radionuclide in nuclear medicine. In Brazil, the 99 Mo/ 99m Tc generators are produced exclusively by the Center of Radiopharmacy at IPEN-CNEN/SP, by importing 99 Mo from different suppliers. 99 Mo (t 1/2 = 66 h) is a fission product of 235 U, therefore, it can be accompanied by several radioisotopes that are highly prejudicial for human health, demanding a strict quality control of this product for generators safe use. The European Pharmacopoeia established some parameters and limits that evaluate the quality of the solution of sodium [ 99 Mo]molybdate, that is used as raw material for generator's production. The European Pharmacopoeia also recommends some analytical methods to perform these evaluations, however, it has been observed difficulties on the implementation of these methods by the generator's producers. These difficulties are probably related to the lack of practicability of the proposed methods and the extensive list of utilized reagents. In this work some procedures of the European Pharmacopoeia's quality control method for 99 Mo were evaluated. Different types of solid phase exchanger cartridges were tested for retention of 99 Mo in 3 different conditions. Cartridges that presented percentages of retention higher than 90% were also tested for separation of 99 Mo from possible contaminants (Ru e Te). The results shown that solid phase exchanger cartridges that presented percentages of retention of Mo higher than 90% also presented significant percentages of retention of Ru and Te. An alternative method for separation of 99 Mo from 131 I (other contaminant) are also proposed. (author)

  18. Quality control studies of {sup 99}Mo used in {sup 99}Mo/{sup 99m}Tc generators produced at IPEN/CNEN-SP, Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Said, Daphne S.; Brambilla, Tania P.; Matsuda, Margareth M.N.; Osso Junior, Joao A., E-mail: daphnesaid@usp.br, E-mail: taniabrambilla@yahoo.com.br, E-mail: mmatsuda@ipen.br, E-mail: jaosso@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2015-07-01

    {sup 99m}Tc is the most used radionuclide in nuclear medicine. In Brazil, the {sup 99}Mo/{sup 99m}Tc generators are produced exclusively by the Center of Radiopharmacy at IPEN-CNEN/SP, by importing {sup 99}Mo from different suppliers. {sup 99}Mo (t{sub 1/2} = 66 h) is a fission product of {sup 235}U, therefore, it can be accompanied by several radioisotopes that are highly prejudicial for human health, demanding a strict quality control of this product for generators safe use. The European Pharmacopoeia established some parameters and limits that evaluate the quality of the solution of sodium [{sup 99}Mo]molybdate, that is used as raw material for generator's production. The European Pharmacopoeia also recommends some analytical methods to perform these evaluations, however, it has been observed difficulties on the implementation of these methods by the generator's producers. These difficulties are probably related to the lack of practicability of the proposed methods and the extensive list of utilized reagents. In this work some procedures of the European Pharmacopoeia's quality control method for {sup 99}Mo were evaluated. Different types of solid phase exchanger cartridges were tested for retention of {sup 99}Mo in 3 different conditions. Cartridges that presented percentages of retention higher than 90% were also tested for separation of {sup 99}Mo from possible contaminants (Ru e Te). The results shown that solid phase exchanger cartridges that presented percentages of retention of Mo higher than 90% also presented significant percentages of retention of Ru and Te. An alternative method for separation of {sup 99}Mo from {sup 131}I (other contaminant) are also proposed. (author)

  19. Status of Tc-99m and 99Mo/99mTc generator production in Bangladesh

    International Nuclear Information System (INIS)

    Abedin, Md. Zainul; Haque, Md. Azizul; Ali, Md. Ramjan; Hossain, Md. Anwar; Razzaque, Md. Abdur; Yasmin, Lyzu; Waheed, M. Fatima; Akhter, Rabeya; Mondal, Rafiuddin

    2007-01-01

    Radioisotope Production Division (RIPD) produced instant technetium-99m by solvent extraction method for several years. On R and D basis, the division produced portable sterile Tc-99m sublimation generator by irradiating titanium molybdate in the reactor. The division produced (4/batch) from imported fission Mo-99 till June 2005. Since August 2005, as per demand of the government hospitals, the division have been producing 12-14 pieces of 15 GBq chromatographic 99m Tc-generators weekly by using the new generator production plant installed last year having online Mo-99 loading system with the of producing 50 generator per batch. Development of PZC and (n,γ) 99 Mo based generator holds potential in Bangladesh. (author)

  20. New insights into Mo and Ru isotope variation in the nebula and terrestrial planet accretionary genetics

    Science.gov (United States)

    Bermingham, K. R.; Worsham, E. A.; Walker, R. J.

    2018-04-01

    When corrected for the effects of cosmic ray exposure, Mo and Ru nucleosynthetic isotope anomalies in iron meteorites from at least nine different parent bodies are strongly correlated in a manner consistent with variable depletion in s-process nucleosynthetic components. In contrast to prior studies, the new results show no significant deviations from a single correlation trend. In the refined Mo-Ru cosmic correlation, a distinction between the non-carbonaceous (NC) group and carbonaceous chondrite (CC) group is evident. Members of the NC group are characterized by isotope compositions reflective of variable s-process depletion. Members of the CC group analyzed here plot in a tight cluster and have the most s-process depleted Mo and Ru isotopic compositions, with Mo isotopes also slightly enriched in r- and possibly p-process contributions. This indicates that the nebular feeding zone of the NC group parent bodies was characterized by Mo and Ru with variable s-process contributions, but with the two elements always mixed in the same proportions. The CC parent bodies sampled here, by contrast, were derived from a nebular feeding zone that had been mixed to a uniform s-process depleted Mo-Ru isotopic composition. Six molybdenite samples, four glacial diamictites, and two ocean island basalts were analyzed to provide a preliminary constraint on the average Mo isotope composition of the bulk silicate Earth (BSE). Combined results yield an average μ97Mo value of +3 ± 6. This value, coupled with a previously reported μ100Ru value of +1 ± 7 for the BSE, indicates that the isotopic composition of the BSE falls precisely on the refined Mo-Ru cosmic correlation. The overlap of the BSE with the correlation implies that there was homogeneous accretion of siderophile elements for the final accretion of 10 to 20 wt% of Earth's mass. The only known cosmochemical materials with an isotopic match to the BSE, with regard to Mo and Ru, are some members of the IAB iron meteorite

  1. Synthesis and characterization of PtRuMo/C nanoparticle electrocatalyst for direct ethanol fuel cell

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Zhen-Bo; Yin, Ge-Ping [Department of Applied Chemistry, Harbin Institute of Technology, Harbin 150001 (China); Lin, Yong-Ge [Department of Chemistry, University of Puerto Rico, Rio Piedras Campus, San Juan, PR 00931 (United States)

    2007-07-10

    This research aims at enhancement of the performance of anodic catalysts for the direct ethanol fuel cell (DEFC). Two distinct DEFC nanoparticle electrocatalysts, PtRuMo/C and PtRu/C, were prepared and characterized, and one glassy carbon working electrode for each was employed to evaluate the catalytic performance. The cyclic-voltammetric, chronoamperometric, and amperometric current-time measurements were done in the solution 0.5 mol L{sup -1} CH{sub 3}CH{sub 2}OH and 0.5 mol L{sup -1} H{sub 2}SO{sub 4}. The composition, particle sizes, lattice parameters, morphology, and the oxidation states of the metals on nanoparticle catalyst surfaces were determined by energy dispersive analysis of X-ray (EDAX), X-ray diffraction (XRD), transmission electron micrographs (TEM) and X-ray photoelectron spectrometer (XPS), respectively. The results of XRD analysis showed that both PtRuMo/C and PtRu/C had a face-centered cubic (fcc) structure with smaller lattice parameters than that of pure platinum. The typical particle sizes were only about 2.5 nm. Both electrodes showed essentially the same onset potential as shown in the CV for ethanol electrooxidation. Despite their comparable active specific areas, PtRuMo/C was superior to PtRu/C in respect of the catalytic activity, durability and CO-tolerance. The effect of Mo in the PtRuMo/C nanoparticle catalyst was illustrated with a bifunctional mechanism, hydrogen-spillover effect and the modification on the Pt electronic states. (author)

  2. Diversification of 99Mo/99mTc separation: non–fission reactor production of 99Mo as a strategy for enhancing 99mTc availability.

    Science.gov (United States)

    Pillai, Maroor R A; Dash, Ashutosh; Knapp, Furn F Russ

    2015-01-01

    This paper discusses the benefits of obtaining (99m)Tc from non-fission reactor-produced low-specific-activity (99)Mo. This scenario is based on establishing a diversified chain of facilities for the distribution of (99m)Tc separated from reactor-produced (99)Mo by (n,γ) activation of natural or enriched Mo. Such facilities have expected lower investments than required for the proposed chain of cyclotrons for the production of (99m)Tc. Facilities can receive and process reactor-irradiated Mo targets then used for extraction of (99m)Tc over a period of 2 wk, with 3 extractions on the same day. Estimates suggest that a center receiving 1.85 TBq (50 Ci) of (99)Mo once every 4 d can provide 1.48-3.33 TBq (40-90 Ci) of (99m)Tc daily. This model can use research reactors operating in the United States to supply current (99)Mo needs by applying natural (nat)Mo targets. (99)Mo production capacity can be enhanced by using (98)Mo-enriched targets. The proposed model reduces the loss of (99)Mo by decay and avoids proliferation as well as waste management issues associated with fission-produced (99)Mo.

  3. Measurement of Mo-99 column activity in the evaluation of Mo-99/Tc-99m generator

    International Nuclear Information System (INIS)

    Kuster, Z.

    1994-01-01

    In order to calculate the real elution efficiency of Mo-99/Tc-99m generator the Mo-99 content on the column has to be previously determined. As found in this work, the external measurement of Mo-99-column activity by means of Geiger-Mueller counter is a simple, fast and reliable method. Generally, Mo-99-column is placed slightly out of the center of the generator; therefore the externally measured flux of photons (φ) is an angular-dependent function. If the thickness of the lead container is radially uniform, the flux measured at some distance from the generator (which is rotated in 2π/3 steps) is given by the equation φ = A (1 + Bcos (α-2π(i - 2)/3)) -1 , i=1,2 or 3 (Eq.1) where A is a numerical constant depending on the Mo-99-column activity, B is a numerical constant depending on the Mo-99- column position within the lead container, the angle α depends on the initial orientation of the generator. A total of 20 generator were studied. The measured Mo-99-column activities (Capintec dose calibrator) were in the range 13.1- 35.11 GBq. Contrary to the findings of Vinberg and Kristensen (Eur J Nucl Med 1/1976(219), values of A (Eq. 1) are in good correlation (r 2 =0.9794) with the measured Mo-99-column activities. (author)

  4. Direct methanol fuel cell with extended reaction zone anode: PtRu and PtRuMo supported on graphite felt

    Energy Technology Data Exchange (ETDEWEB)

    Bauer, Alex; Gyenge, Elod L.; Oloman, Colin W. [Department of Chemical and Biological Engineering, The University of British Columbia, 2360 East Mall, Vancouver, BC (Canada)

    2007-05-15

    Pressed graphite felt (thickness {proportional_to}350 {mu}m) with electrodeposited PtRu (43 g m{sup -2}, 1.4:1 atomic ratio) or PtRuMo (52 g m{sup -2}, 1:1:0.3 atomic ratio) nanoparticle catalysts was investigated as an anode for direct methanol fuel cells. At temperatures above 333 K the fuel cell performance of the PtRuMo catalyst was superior compared to PtRu. The power density was 2200 W m{sup -2} with PtRuMo at 5500 A m{sup -2} and 353 K while under the same conditions PtRu yielded 1925 W m{sup -2}. However, the degradation rate of the Mo containing catalyst formulation was higher. Compared to conventional gas diffusion electrodes with comparable PtRu catalyst composition and load, the graphite felt anodes gave higher power densities mainly due to the extended reaction zone for methanol oxidation. (author)

  5. Concentration of sup(99m)Tc from the eluate of 99Mo-sup(99m)Tc generators

    International Nuclear Information System (INIS)

    Saucedo, T.; Mora, M.; Fraga de Suarez, A.H.; Mitta, A.E.A.

    1976-04-01

    A method is described to concentrate sup(99m)Tc solutions, originated in 99 Mo-sup(99m)Tc generators, independent of its age. The techniques of preparation of the different radiopharmaceuticals used in nuclear medicine are also described. (author) [es

  6. Pharmaceutical grade sodium (99mTc) pertechnetate from 99Mo/99mTc-TCM-Autosolex generator

    International Nuclear Information System (INIS)

    Chattopadhyay, Sankha; Barua, Luna; Das, Sujata Saha

    2014-01-01

    Technetium-99m (T 1/2 = 6.02h; 140.51 keV (89%)) is the most useful radioisotope in diagnostic nuclear medicine. More than 80% of all diagnostic procedures done worldwide in nuclear medicine centre are performed with 99m Tc. Worldwide crisis of fission 99 Mo based generator in recent past had put the nuclear medicine fraternity in very harsh situation. In order to have an indigenous solution of this problem, we tried to develop a computer controlled semi automated 99 Mo/ 99m Tc generator using MEK solvent extraction technique, which utilizes abundantly available 99 Mo produced by (n,γ) reaction in BARC reactors. The aim of this work is to provide a more reliable, computer controlled module (TCM- AUTOSOLEX) for the recovery of pharmaceutical grade 99m Tc from low specific activity 99 Mo based on solvent extraction methodology

  7. A {sup 99m}Tc Generator using PZC for (n,{gamma}) {sup 99}Mo

    Energy Technology Data Exchange (ETDEWEB)

    Adang, H G; Mutalib, A; Suparman, I; Hamid,; Purwadi, B; Pancoko, M; Setiowati, S; Yulianti, V; Robertus, D H [Radioisotope Production Center, National Atomic Energy Agency Kawasan PUSPIPTEK, Serpong (Indonesia)

    1998-10-01

    The high performance adsorbent Poly Zirconium Compound (PZC) was produced by Department of Radioisotope, Japan Atomic Energy Research Institute. This compound was developed as an adsorbent for natural Mo (n,{gamma}) {sup 99}Mo-{sup 99m}Tc Generator. In the present paper, we report the performance of the PZC for a {sup 99m}Tc Generator which was focused on the yield, on elution profile and {sup 99}Mo breakthrough. (author)

  8. Production of 95mTc with proton bombardment of 95Mo

    International Nuclear Information System (INIS)

    Izumo, M.; Matsuoka, H.; Sorita, T.; Nagame, Y.; Sekine, T.; Hata, K.; Baba, S.

    1991-01-01

    Formation cross sections of 95m Tc and 95g Tc via the 95 Mo (p,n) reaction have been measured to evaluate the production yield of 95m Tc which is expected to be a useful radiotracer of technetium isotopes. It was found from the cross section data that for incident proton energies above 15 MeV, the thick-target yield of 95m Tc was more than 20 μCi/μAh at the end of bombardment and the 95g Tc contamination was less than 1% after 12 d cooling. To examine the separation and purification of 95m Tc from target, we have carried out a test production of 95m Tc using a thick 95 Mo-enriched target. Other reactions of producing 95m Tc are compared and discussed in terms of the production yield and amounts of contaminants. (author)

  9. Carbon-Supported PtRuMo Electrocatalysts for Direct Alcohol Fuel Cells

    Directory of Open Access Journals (Sweden)

    José L.G. Fierro

    2013-10-01

    Full Text Available The review article discusses the current status and recent findings of our investigations on the synthesis and characterization of carbon-supported PtRuMo electrocatalysts for direct alcohol fuel cells. In particular, the effect of the carbon support and the composition on the structure, stability and the activity of the PtRuMo nanoparticles for the electrooxidation of CO, methanol and ethanol have been studied. Different physicochemical techniques have been employed for the analysis of the catalysts structures: X-ray analytical methods (XRD, XPS, TXRF, thermogravimetry (TGA and transmission electron microscopy (TEM, as well as a number of electrochemical techniques like CO adsorption studies, current-time curves and cyclic voltammetry measurements. Furthermore, spectroscopic methods adapted to the electrochemical systems for in situ studies, such as Fourier transform infrared spectroscopy (FTIRS and differential electrochemical mass spectrometry (DEMS, have been used to evaluate the oxidation process of CO, methanol and ethanol over the carbon-supported PtRuMo electrocatalysts.

  10. A modified {sup 99} Mo- {sup 99} Tc generator on Zirconium molybdo- phosphate-{sup 99} Mo gel. Vol. 3

    Energy Technology Data Exchange (ETDEWEB)

    El-Kolaly, M T; Talaat, H [Labelled Compounds Department, Cairo (Egypt); Botros, N [Radioistspe and Generator Department, Radioisotope Production and Sealed Source Division, Hot Laboratories Center, Atomic Energy Authority, Cairo (Egypt)

    1996-03-01

    A modified {sup 99} Mo - {sup 99} Tc gel generator is described. The new generator is based on the use of zirconium molybdophosphate - {sup 99} Mo gel in which {sup 99} Mo chemically combined in the gel structure, where {sup 99m}Tc can be easily eluted with distilled water or saline. The gel was prepared via chemical reaction between zirconyl chloride and molybdophosphate - {sup 99} Mo solution. The PH of the reaction mixture was adjusted with NaOH. Different gels have been prepared by varying the molar ratio of Mo:Zr:p. The PH and time of digeston on complete gel formation was also investigated in order to optimize the condition of gel preparation. Molybdophosphate {sup 32} P solution was used to determine the phosphorous content in the gel and in the {sup 99m}Tc eluate. The temperature and time of drying of the gel and their effect on {sup 99m}Tc elution efficiency were also studied. From the data obtained, the optimum conditions for routine production of {sup 99} Mo - {sup 99m}Tc generator are presented and discussed. 2 figs., 6 tabs.

  11. Benchmark experiment for the cross section of the 100Mo(p,2n)99mTc and 100Mo(p,pn)99Mo reactions

    Science.gov (United States)

    Takács, S.; Ditrói, F.; Aikawa, M.; Haba, H.; Otuka, N.

    2016-05-01

    As nuclear medicine community has shown an increasing interest in accelerator produced 99mTc radionuclide, the possible alternative direct production routes for producing 99mTc were investigated intensively. One of these accelerator production routes is based on the 100Mo(p,2n)99mTc reaction. The cross section of this nuclear reaction was studied by several laboratories earlier but the available data-sets are not in good agreement. For large scale accelerator production of 99mTc based on the 100Mo(p,2n)99mTc reaction, a well-defined excitation function is required to optimise the production process effectively. One of our recent publications pointed out that most of the available experimental excitation functions for the 100Mo(p,2n)99mTc reaction have the same general shape while their amplitudes are different. To confirm the proper amplitude of the excitation function, results of three independent experiments were presented (Takács et al., 2015). In this work we present results of a thick target count rate measurement of the Eγ = 140.5 keV gamma-line from molybdenum irradiated by Ep = 17.9 MeV proton beam, as an integral benchmark experiment, to prove the cross section data reported for the 100Mo(p,2n)99mTc and 100Mo(p,pn)99Mo reactions in Takács et al. (2015).

  12. Investigation of double beta decay of {sup 100}Mo to excited states of {sup 100}Ru

    Energy Technology Data Exchange (ETDEWEB)

    Arnold, R. [IPHC, UPL, CNRS/IN2P3, F-67037 Strasbourg (France); Augier, C. [LAL, Univ Paris-Sud, CNRS/IN2P3, F-91405 Orsay (France); Barabash, A.S. [ITEP, Institute of Theoretical and Experimental Physics, 117218 Moscow (Russian Federation); Basharina-Freshville, A. [University College London, London WC1E 6BT (United Kingdom); Blondel, S. [LAL, Univ Paris-Sud, CNRS/IN2P3, F-91405 Orsay (France); Blot, S. [University of Manchester, Manchester M13 9PL (United Kingdom); Bongrand, M. [LAL, Univ Paris-Sud, CNRS/IN2P3, F-91405 Orsay (France); Brudanin, V. [JINR, Joint Institute for Nuclear Research, 141980 Dubna (Russian Federation); Busto, J. [CPPM, Université de Marseille, CNRS/IN2P3, F-13288 Marseille (France); Caffrey, A.J. [Idaho National Laboratory, Idaho Falls, ID 83415 (United States); Čermák, P. [IEAP, Czech Technical University in Prague, CZ-12800 Prague (Czech Republic); Cerna, C. [CENBG, Université Bordeaux, CNRS/IN2P3, F-33175 Gradignan (France); Chapon, A. [LPC Caen, ENSICAEN, Université de Caen, CNRS/IN2P3, F-14050 Caen (France); Chauveau, E. [University of Manchester, Manchester M13 9PL (United Kingdom); Dragounová, L. [National Radiation Protection Institute, CZ-14000 Prague (Czech Republic); Duchesneau, D. [LAPP, Université de Savoie, CNRS/IN2P3, F-74941 Annecy-le-Vieux (France); Durand, D. [LPC Caen, ENSICAEN, Université de Caen, CNRS/IN2P3, F-14050 Caen (France); Egorov, V. [JINR, Joint Institute for Nuclear Research, 141980 Dubna (Russian Federation); Eurin, G. [LAL, Univ Paris-Sud, CNRS/IN2P3, F-91405 Orsay (France); University College London, London WC1E 6BT (United Kingdom); Evans, J.J. [University of Manchester, Manchester M13 9PL (United Kingdom); and others

    2014-05-15

    Double beta decay of {sup 100}Mo to the excited states of daughter nuclei has been studied using a 600 cm{sup 3} low-background HPGe detector and an external source consisting of 2588 g of 97.5% enriched metallic {sup 100}Mo, which was formerly inside the NEMO-3 detector and used for the NEMO-3 measurements of {sup 100}Mo. The half-life for the two-neutrino double beta decay of {sup 100}Mo to the excited 0{sub 1}{sup +} state in {sup 100}Ru is measured to be T{sub 1/2}=[7.5±0.6(stat)±0.6(syst)]⋅10{sup 20} yr. For other (0ν+2ν) transitions to the 2{sub 1}{sup +}, 2{sub 2}{sup +}, 0{sub 2}{sup +}, 2{sub 3}{sup +} and 0{sub 3}{sup +} levels in {sup 100}Ru, limits are obtained at the level of ∼(0.25–1.1)⋅10{sup 22} yr.

  13. Problems in clinical practice of domestic supply of 99Mo/99mTc. Considerations on the domestic production of 99Mo/99mTc

    International Nuclear Information System (INIS)

    Yamabayashi, Hisamichi

    2012-01-01

    At present, a bulky import product, 99 Mo supplied in Japan is produced by a nuclear fission method which enables to produce a generator system with no need of commercially preparing 99m Tc-labeled radiopharmaceuticals due to its high specific activity. However its usage of enriched uranium target leads to avoiding the fission method from the option of domestic production. In order to secure the domestic supply of 99 Mo/ 99m Tc, the neutron activation method, aiming to meet about 20% of domestic demand, is under development along with the re-start program of JMTR. Development of various production methods using accelerators are also in progress. In those non-fission methods with reactors or accelerators, rapid and effective procedures for concentration and refinement of 99m Tc solution eluted from 99 Mo of low specific activity are the subjects to be considered for attaining the stable labeling performances. (author)

  14. 99Mo-99mTc production development by (n, γ) reaction

    International Nuclear Information System (INIS)

    Izumo, Hironobu; Nishikata, Kaori; Kimura, Akihiro; Tanimoto, Masataka; Tsuchiya, Kunihiko; Ishihara, Masahiro; Kaminaga, Masanori

    2012-01-01

    The renewed JMTR will be started from the later half of JFY2012, and it is expected to various fields. Supply of 99 Mo in Japan depends only on imports from foreign countries. JAEA has a plan to produce 99 Mo, a parent nuclide of 99m Tc. JMTR will contribute to produce 99 Mo by (n, r) method as one of effective uses of the JMTR. In this paper, outline of the technical study items for production method of 99 Mo- 99m Tc in JMTR will be described. (author)

  15. Impurities in Tc-99m radiopharmaceutical solution obtained from Mo-100 in cyclotron.

    Science.gov (United States)

    Tymiński, Zbigniew; Saganowski, Paweł; Kołakowska, Ewa; Listkowska, Anna; Ziemek, Tomasz; Cacko, Daniel; Dziel, Tomasz

    2018-04-01

    The gamma emitting impurities in 99m Tc solution obtained from enriched molybdenum 100 Mo metallic target after its irradiation in a cyclotron were measured using a high-purity germanium (HPGe) detector. The radioactivity range of tested samples of 99m Tc was rather low, in the range from 0.34 to 2.39 MBq, thus creating a challenge to investigate the standard measurement HPGe system for impurity detection and quantification. In the process of 99m Tc separation from irradiated target the AnaLig® Tc-02 resin, Dionex H + and Alumina A columns were used. Fractions of eluates from various steps of separation process were taken and measured for radionuclidic purity. The overall measurement sensitivity of gamma emitters in terms of minimum detectable activity (MDA) was found at the level of 14-70Bq with emission lines in range of 36 - 1836keV resulting in impurity content range of 6.7 × 10 -4 to 3.4 × 10 -3 % for 93 Tc, 93m Tc, 94 Tc, 94m Tc, 95 Tc, 95m Tc, 96 Tc 96 Nb, 97 Nb, 99 Mo contaminants and 9.4 × 10 -3 % for 97m Tc. The usefulness of the chosen measurement conditions and the method applied to testing the potential contaminators was proved by reaching satisfactory results of MDAs less than the criteria of impurity concentration of all nuclides specified in the European Pharmacopoeia. Copyright © 2017 Elsevier Ltd. All rights reserved.

  16. Gas-phase chemistry of Mo, Ru, W, and Os metal carbonyl complexes

    International Nuclear Information System (INIS)

    Wang, Y.; Qin, Z.; Fan, F.L.

    2014-01-01

    Metal carbonyl complexes were used for studying the gas-phase chemical behavior of Mo, Ru, W and Os isotopes with an on-line low temperature isothermal gas chromatography apparatus. Short-lived Mo and Ru isotopes were produced by a 252 Cf spontaneous fission source. Short-lived nuclides of W and Os were produced using the heavy ion reactions 19 F + 159 Tb and 165 Ho, respectively. Short-lived products were thermalized in a recoil chamber filled with a gas mixture of helium and carbon monoxide. The carbonyls formed were then transported through capillaries to an isothermal chromatography column for study of the adsorption behavior as a function of temperature. On-line isothermal chromatography (IC) experiments on Teflon (PTFE) and quartz surfaces showed that short-lived isotopes of the listed elements can form carbonyl complexes which are very volatile and interact most likely in physical sorption processes. Deduced adsorption enthalpies of Mo and Ru carbonyls were -38 ± 2 kJ/mol and -36 ± 2 kJ/mol, respectively. These values are in good agreement with literature data, partly obtained with different chromatographic techniques. A validation of the applied Monte Carlo model to deduce adsorption enthalpies with Mo isotopes of different half-lives proved the validity of the underlying adsorption model. The investigations using a gas-jet system coupled to a heavy ion accelerator without any preseparator clearly showed the limitations of the approach. The He and CO gas mixture, which was directly added into the chamber, will result in decomposition of CO gas and produce some aerosol particles. After the experiment of 173 W and 179 Os in the heavy ion experiments, the Teflon column was covered by a yellowish deposit; the adsorption enthalpy of W and Os carbonyls could therefore not be properly deduced using Monte Carlo simulations. (orig.)

  17. The annealing effects on the micro-structure and properties of RuMoC films as seedless barrier for advanced Cu metallization

    Energy Technology Data Exchange (ETDEWEB)

    Zou, Jianxiong; Liu, Bo, E-mail: liubo2009@scu.edu.cn, E-mail: gh.jiao@siat.ac.cn [Key Laboratory of Radiation Physics and Technology of Ministry of Education, Institute of Nuclear Science and Technology, Sichuan University, Chengdu 610064 (China); Jiao, Guohua, E-mail: liubo2009@scu.edu.cn, E-mail: gh.jiao@siat.ac.cn; Lu, Yuanfu; Dong, Yuming [Shenzhen Institutes of Advanced Technology Chinese Academy of Sciences, Shenzhen 518055 (China); The Chinese University of Hong Kong, Hong Kong (China); Li, Qiran [Institut d' Electronique Fondamentale, CNRS-Université Paris Sud UMR 8622, 91405 Orsay (France)

    2016-09-07

    100 nm thick RuMoC films and 5 nm thick RuMoC films with Cu capping have been deposited on Si(111) by magnetron co-sputtering with Ru and MoC confocal targets. The samples were subsequently annealed at temperatures ranging from 450 to 650 °C in vacuum at a pressure of 3 × 10{sup −4} Pa to study the annealing effects on the microstructures and properties of RuMoC films for advanced seedless Cu metallization applications. The sheet resistances, residual oxygen contents, and microstructures of the RuMoC films have close correlation with the doping contents of Mo and C, which can be easily controlled by the deposition power ratio of MoC versus Ru targets (DPR). When DPR was 0.5, amorphous RuMoC film (marked as RuMoC II) with low sheet resistances and residual oxygen contents was obtained. The fundamental relationship between the annealing temperatures with the microstructures and properties of the RuMoC films was investigated, and a critical temperature point was revealed at about 550 °C where the components and microstructures of the RuMoC II films changed obviously. Results indicated that below 550 °C, the RuMoC II films remained amorphous due to the well-preserved C-Ru and C-Mo bonds. However, above 550 °C, the microstructures of RuMoC II films transformed from amorphous to nano-composite structure due to the breakage of Ru-C bonds, while the supersaturated solid solution MoC segregated out along the grain boundaries of Ru, thus hindering the diffusion of Cu and O atoms. This is the main mechanism of the excellent thermal stability of the RuMoC films after annealing at high temperatures. The results indicated great prospects of amorphous RuMoC films in advanced seedless Cu metallization applications.

  18. Separation of sup(99m)Tc from 99Mo through a hydrous zirconium oxide column

    International Nuclear Information System (INIS)

    Mengatti, J.

    1980-01-01

    The preparation of 99 Mo-,sup(99m)Tc generator based on the adsorption of 99 Mo on hydrous zirconium oxide column, employing the in exchange technique, is described. The adsorption of 99 Mo on hydrous zirconium oxide (HZO) and the separation of sup(99m)Tc, generated by the decay of 99 Mo with saline solution, are analised. The sup(99m)Tc separation yield, pH of the eluted solution, aspect of the elution curve and the adsorption of 99 Mo on hydrous zirconium oxide calcined at 800 0 C are studied. The chemical and radioactive purities of the final product are analysed and the variation of the elution yield for successive elutions is studied. (Author) [pt

  19. Development of 99mTc extraction techniques from 99Mo by (n,γ) reaction

    International Nuclear Information System (INIS)

    Kimura, Akihiro; Hori, Naohiko; Tsuchiya, Kunihiko; Ishihara, Masahiro; Yamabayashi, Hisamichi; Tanase, Masakazu; Fujisaki, Saburo; Sato, Yuichi

    2010-11-01

    Investigation of production method of 99 Mo by (n, γ) reaction, where the processing is relatively simple and generating less amount of radioactive waste, is conducted in the Neutron Irradiation and Testing Reactor Center. The 99 Mo is adsorbed to highly efficient adsorbent PZC after neutron irradiation and 99m Tc is eluted. However, radioactivity concentration of the 99m Tc solution obtained from PZC column loaded with 99 Mo derived by (n, γ) method is lower than that obtained from alumina column with 99 Mo by (n, f) method due to extremely low specific activity of (n, f) 99 Mo. Therefore, it is necessary to develop technique for increasing the amount of 99 Mo and the 99m Tc solution of high radioactivity concentration (minimum: 1Ci/ cm 3 ). In this study, the preliminary fabrication tests using high density MoO 3 pellets were carried out to increase the production of 99 Mo. The method of concentrating 99m Tc solution through solvent extraction with MEK was investigated and a device for this concentration process was also developed. In the preliminary tests of the MoO 3 pellets, the pellets having high density were successfully fabricated by the SPS method. Additionally, it was ascertained that the pellets can be dissolved with 6M-NaOH solution completely. The test for 99 Mo adsorption followed by 99m Tc elution using PZC was carried out. As the result, amount of Mo adsorbed to 1g-PZC was about 250mg, and 99m Tc yield was about 80%. In the concentration test using Re solution instead of 99m Tc solution, it was ascertained that the concentration efficiency is higher than 80% of the theoretical value. A concentration device for 99m Tc solution could be realized based on the method employed in the present experiments. The outcomes of development of 99m Tc extraction techniques from 99 Mo by (n,γ) reaction was reviewed in this paper, and the contents were presented in the 3rd International Symposium on Material Test Reactors. (author)

  20. Accelerator production of 99mTc with proton beams and enriched 100Mo targets

    International Nuclear Information System (INIS)

    Lagunas-Solar, M.C.

    1999-01-01

    The direct production of 99m Tc has been developed based upon the use of the 100 Mo(p,2n) 99m Tc reaction (Q= -7.9 MeV), using enriched 100 Mo targets and accelerated protons of 99m Tc yields measured in this work reached 851 ± 77 MBq/μA/h (23.0 ± 3.0 mCi/μA/h) at end-of-bombardment (EOB) in the 22-12 MeV energy region, with 96 Tc (4.35 d) as the only detectable impurity at - accelerators, and by extracting multiple H + beams to bombard a single or an array of enriched 100 Mo targets, this method could provide nearly 851 GBq (23 Ci) of 99m Tc in 1-h bombardments. Because of this large-batch potential, this new method appears to be an effective alternative to the production and distribution of 99 Mo → 99m Tc generator systems, although it may be limited to daily, regional/local distribution and use. 99m Tc produced in this fashion has high radionuclidic and radiochemical purity, although its specific activity has not been determined. The accelerator-made 99m Tc has been shown to have similar physical and chemical characteristics than 99m Tc eluted from commercial fission-produced 99 Mo → 99m Tc generators. Technical and logistical factors need further study and analysis but the potential and the expected impact of this new method are clear in the context of the operation of large radionuclide distribution centers as well as for small programs in developing regions. (author)

  1. Assessment of Using 99Mo and 99mTc Isotopes in Kuwait Medical Sector.

    Science.gov (United States)

    Ali, Naser

    2016-04-01

    The Ministry of Health (MOH) in the state of Kuwait currently depends on importing the radioisotope molybdenum (Mo) in its isotopic form (Mo) to fulfill its demands. The present study was conducted on all nuclear medicine departments in the state of Kuwait. Daily, weekly, and monthly data were analyzed to statistically determine the current and future demands for the isotope Tc. This analysis was performed by collecting and analyzing data on MOH consumption of Tc for different diagnostic applications. The overall results indicate a partial decrease of 1.012% in the overall total demand for Tc up to the year 2018 for the state of Kuwait.

  2. Synthesis and characterization of zirconium molybdates of 99 Mo/99m Tc generators

    International Nuclear Information System (INIS)

    Contreras R, A.; Monroy G, F.; Diaz A, L.V.

    2002-01-01

    The zirconium molybdates are gels which are used as cation exchangers in the production of 99 Mo/ 99m Tc generators. The synthesis method and the characterization of these gels by thermogravimetry, infrared spectroscopy and X-ray diffraction is presented with the purpose of finding which the factors are that influence in the efficiency of the 99m Tc production. The results show that the quantity of molecular water contained in gel, is possibly the cause of variations of the efficiencies of the 99 Mo/ 99m Tc generator. (Author)

  3. '99Mo/99mTc Generator Based on High Radionuclidic Pure Zirconium Molybdate Gel

    International Nuclear Information System (INIS)

    Amin, M.; Mostafa, M.; El-Amir, M.A.; El-Absy, M.A.; Mohamed, O.I.; Farag, A.B.

    2014-01-01

    99 Mo / 99 mTc radioisotope generator was prepared using in-situ precipitated zirconium molybdate chromatographic column. Zirconium molybdate gel matrix was synthesized by precipitation of neutron activation molybdenum-99 from its solution after variety purification processes to prevent contamination of the 99m Tc eluate with cross-contaminants. Greeter than 82.7 ± 0.4 % of the generated 99m Tc was immediately and reproducible eluted by passing 10 ml 0.9 % NaCl solution through the 1 g zirconium molybdate- 99 Mo column matrix at a flow rate of 0.5 ml / min and room temperature with high chemical, radionuclide ( ≥ 99.9 % 99m Tc) and radiochemical purity ( ≥ 97.7 % % as 99 mTcO 4 - ) with ph value suitable for medical uses.

  4. Development of 99Mo/99mTc Generator System for Production of Medical Radionuclide 99mTc using a Neutron-activated 99Mo and Zirconium Based Material (ZBM as its Adsorbent

    Directory of Open Access Journals (Sweden)

    I. Saptiama

    2016-12-01

    Full Text Available Molybdenum produced from fission of U-235 is the most desirable precursor for 99Mo/99mTc generator system as it is non-carrier added and has high specific activity. However, in the last decade there has been short supply of 99Mo due to several constrains. Therefore, there have been many works performed for development of 99Mo/99mTc generator system using 99Mo which is not produced from either LEU or HEU. This report deals with development of 99Mo/99mTc generator system where zirconium-based material (ZBM is used as adsorbent of neutron-activated 99Mo. The system was prepared by firstly irradiating natural Mo in the G. A. Siwabessy reactor to produce neutron-activated 99Mo. The target was dissolved in NaOH 4N and then neutralized with 12 M HCl. The 99Mo solution was then mixed with a certain amount of ZBM followed by heating at 90°C for three hours to allow the 99Mo adsorbed on ZBM. The 99Mo-ZBM (9.36 GBq of 99Mo was Mo/ 4.2 g ZBM was packed on a fritz-glass column. This column was then fitted serially with an alumina column for trapping 99Mo breakthrough. The columns were then eluted daily with saline solution for up to one week. The yield of 99mTc was found to be between 53.7 – 74% (n= 5. All 99mTc eluates were clear solutions with pH of 5. Breakthrough of 99Mo in 99mTc eluates was found to be 0.031 ± 0.019 μCi 99Mo/ mCi 99mTc (n= 5 which was less than the maximum activity of 99Mo allowed in 99mTc solution ( 99%. Radiolabeling of this 99mTc towards methylene diphosphonate (MDP kit gave a radiolabelling efficiency of 99%. In summary, a new 99Mo/99mTc generator system that used neutron-activated 99Mo and ZBM as its adsorbent has been successfully prepared. The 99mTc produced from this new 99Mo/99mTc generator system attained the quality of 99mTc required for medical purposes.

  5. Preparation and biological profile of 99mTc-lidocaine as a cardioselective imaging agent using 99mTc eluted from 99Mo/99mTc generator based on Al-Mo gel

    International Nuclear Information System (INIS)

    Sakr, T.M.; October University of Modern Sciences and Arts; Ibrahim, A.B.; Rashed, H.M.; Fasih, T.W.

    2017-01-01

    The current study is aimed to prepare 99m Tc-lidocaine as a new myocardial perfusion-imaging agent. The used 99m Tc was obtained from Al- 99 Mo-molybdate(VI) gel matrix. 99m Tc-lidocaine showed higher (15.4 ± 0.11% ID/g) and faster (15 min post injection) cardiac uptake than the recently studied 99m Tc-valsartan and 99m Tc-procainamide. Consequently, 99m Tc-lidocaine will be a valuable myocardial SPECT agent for diagnosis of emergency patients. Besides, the receptor affinity study confirmed the selectivity of 99m Tc-lidocaine for sodium channels in the heart. (author)

  6. Effect of Ni and noble metals (Ru, Pd and Pt) on performance of bifunctional MoP/SiO2 for hydroconversion of methyl laurate

    Science.gov (United States)

    Nie, Ziyang; Zhang, Zhena; Chen, Jixiang

    2017-10-01

    SiO2 supported bifunctional MoP catalysts modified with different metal promoters (Ni, Ru, Pd, Pt), where Mo/Ni and Mo/M(M = Ru, Pd and Pt) atomic ratios was respectively 10 and 40, were prepared by TPR method from the phosphate precursors. It was found that the introduction of metal promoters facilitated the reduction of phosphate precursor and enhanced the dispersion of MoP. However, the MoP catalyst acidity was scarcely influenced by the small amount of metal promoters. In the hydroconversion of methyl laurate, the promoters enhanced the MoP catalyst activity for conversion of methyl laurate and hydrogenation of alkenes (intermediate), but reduced isomerization ability. Among the promoters, Ru was an optimum to decrease selectivity to alkenes while maintain high selectivity to iso-alkanes, and Mo40RuP showed better stability than MoP. At 380 °C and 3.0 MPa, the conversion of methyl laurate, the total selectivity to C11 and C12 hydrocarbons and the selectivity to iso-alkanes maintained at 100%, ∼94% and ∼30% on Mo40RuP during 102 h, respectively. The good stability of Mo40RuP is ascribed to that the presence of Ru prevented the sintering of MoP particles and suppressed carbon deposition.

  7. Study of the viability of hydroxyapatite as matrix of the generator 99 Mo/99m Tc

    International Nuclear Information System (INIS)

    Aguilar D, I.C.; Badillo A, V.E.; Monroy G, F.

    2004-01-01

    The generator more used in the nuclear medicine it is the generator 99 Mo / 99 Tc. The separation of 99 Mo and 99m Tc in the commercial generator is carried out on a column that contains alumina (Al 2 0 3 ). The adsorbent proposed in this investigation work, the hydroxyapatite, is an insoluble solid considered within of the fixers of anions more important. To evaluate the efficiency of the hydroxyapatite in the separation of the Mo and the Tc they were carried out preliminary tests to know the likeness of the one been accustomed to by the molybdate ions (MoO 4 -2 ) and the pertechnetate ions (Tc0 4 - ) in function of the value of the p H, in a solution of CaCI 2 0.01 M. For the study of the retention of the molybdate ion, it was used the radioisotope Mo-99 fission product, and for the pertechnetate ion it was used the Tc- 99 m radionuclide son of the Mo-99. The obtained results in a solution of CaCl 2 0.01 M to different values of p H of the solution, show that the fixation of the pertechnetate ions (TcO 4 - ) and the fixation of the molybdate ions (MoO 4 -2 ), they present very different behaviors in the hydroxyapatite. The results indicate that the synthetic hydroxyapatite BIO-RAD retains to the molybdate ion to values of lightly acid p H (5-6), being the retention of the pertechnetate practically worthless. (Author)

  8. Diversification in the Supply Chain of (99)Mo Ensures a Future for (99m)Tc.

    Science.gov (United States)

    Cutler, Cathy S; Schwarz, Sally W

    2014-07-01

    The uncertain availability of (99m)Tc has become a concern for nuclear medicine departments across the globe. An issue for the United States is that currently it is dependent on a supply of (99m)Tc (from (99)Mo) that is derived solely by production outside the United States. Since the United States uses half the world's (99)Mo production, the U.S. (99)Mo supply chain would be greatly enhanced if a producer were located within the United States. The fragility of the old (99)Mo supply chain is being addressed as new facilities are constructed and new processes are developed to produce (99)Mo without highly enriched uranium. The conversion to low-enriched uranium is necessary to minimize the potential misuse of highly enriched uranium in the world for nonpeaceful means. New production facilities, new methods for the production of (99)Mo, and a new generator elution system for the supply of (99m)Tc are currently being pursued. The progress made in all these areas will be discussed, as they all highlight the need to embrace diversity to ensure that we have a robust and reliable supply of (99m)Tc in the future. © 2014 by the Society of Nuclear Medicine and Molecular Imaging, Inc.

  9. Influence of the irradiation time on the activity of decay products during the cooling. Case: Mo-98 → Mo-99 → Tc-99m

    International Nuclear Information System (INIS)

    Reyes J, J.L.; Ruiz C, M.A.; Alanis M, J.

    2002-01-01

    In this work the behavior of the activity in the cooling time of Mo-99, Tc-99 and Tc-99m obtained by Neutron activation of natural Mo is described. The analytical development is based on the application of the Laplace transform for resolving the balance equations. (Author)

  10. Magnesium-Molybate Compounds as Matrix for 99Mo/99mTc Generators

    Directory of Open Access Journals (Sweden)

    Fabiola Monroy-Guzman

    2011-01-01

    Full Text Available This work reports the preparation of a 99mTc generator based on conversion of 99Mo produced by neutron irradiation, into insoluble magnesium 99Mo-molybdates compounds as matrix. The effect of magnesium salt types and concentration, Mg:Mo molar ratios, pH of molybdate solutions, eluate volume as well as the addition order of molybdate and magnesium solutions’ influences on the final 99mTc were evaluated. Polymetalates and polymolybdates salts either crystallized or amorphous were obtained depending on the magnesium salt and Mg:Mo molar ratio used in matrix preparation. 99Mo/99mTc generator production based on magnesium-99Mo molybdate compounds allow reduction of preparation time and eliminates the use of specialized installations. The best generator performances were attained using matrices prepared from 0.1 mol/L MgCl2·6H2O solutions, ammonium molybdate solutions at pH 7 and at a Mg:Mo molar ratio of 1:1.

  11. Potential Ways to Address Shortage Situations of 99Mo/99mTc.

    Science.gov (United States)

    Filzen, Leah M; Ellingson, Lacey R; Paulsen, Andrew M; Hung, Joseph C

    2017-03-01

    99m Tc, the most common radioisotope used in nuclear medicine, is produced in a nuclear reactor from the decay of 99 Mo. There are only a few aging nuclear reactors around the world that produce 99 Mo, and one of the major contributors, the National Research Universal (Canada), ceased production on October 31, 2016. The National Research Universal produced approximately 40% of the world's 99 Mo supply, so with its shut down, shortages of 99 Mo/ 99m Tc are expected. Methods: Nuclear pharmacies and nuclear medicine departments throughout the United States were contacted and asked to provide their strategies for coping with a shortage of 99 Mo/ 99m Tc. Each of these strategies was evaluated on the basis of its effectiveness for conserving 99m Tc while still meeting the needs of the patients. Results: From the responses, the following 6 categories of strategies, in order of importance, were compiled: contractual agreements with commercial nuclear pharmacies, alternative imaging protocols, changes in imaging schedules, software use, generator management, and reduction of ordered doses or elimination of backup doses. Conclusion: The supply chain of 99 Mo/ 99m Tc is quite fragile; therefore, being aware of the most appropriate coping strategies is crucial. It is essential to build a strong collaboration between the nuclear pharmacy and nuclear medicine department during a shortage situation. With both nuclear medicine departments and nuclear pharmacies implementing viable strategies, such as the ones proposed, the amount of 99m Tc available during a shortage situation can be maximized. © 2017 by the Society of Nuclear Medicine and Molecular Imaging.

  12. Investigation of amorphous RuMoC alloy films as a seedless diffusion barrier for Cu/p-SiOC:H ultralow-k dielectric integration

    Energy Technology Data Exchange (ETDEWEB)

    Jiao, Guohua [Shenzhen Institutes of Advanced Technology Chinese Academy of Sciences, Shenzhen (China); The Chinese University of Hong Kong, Shatin, Hong Kong (China); Liu, Bo [Sichuan University, Key Laboratory of Radiation Physics and Technology of Ministry of Education, Institute of Nuclear Science and Technology, Chengdu (China); Li, Qiran [CNRS-Universite Paris Sud UMR 8622, Institut d' Electronique Fondamentale, Orsay (France)

    2015-08-15

    Ultrathin RuMoC amorphous films prepared by magnetron co-sputtering with Ru and MoC targets in a sandwiched scheme Si/p-SiOC:H/RuMoC/Cu were investigated as barrier in copper metallization. The evolution of final microstructure of RuMoC alloy films show sensitive correlation with the content of doped Mo and C elements and can be easily controlled by adjusting the sputtering power of the MoC target. There was no signal of interdiffusion between the Cu and SiOC:H layer in the sample of Cu/RuMoC/p-SiOC:H/Si, even annealing up to 500 C. Very weak signal of oxygen have been confirmed in the RuMoC barrier layer both as-deposited and after being annealed, and a good performance on preventing oxygen diffusion has been proved. Leakage current and resistivity evaluations also reveal the excellent thermal reliability of this Si/p-SiOC:H/RuMoC/Cu film stack at the temperatures up to 500 C, indicating its potential application in the advanced barrierless Cu metallization. (orig.)

  13. Mo/Si multilayers with enhanced TiO II- and RuO II-capping layers

    Science.gov (United States)

    Yulin, Sergiy; Benoit, Nicolas; Feigl, Torsten; Kaiser, Norbert; Fang, Ming; Chandhok, Manish

    2008-03-01

    The lifetime of Mo/Si multilayer-coated projection optics is one of the outstanding issues on the road of commercialization of extreme-ultraviolet lithography (EUVL). The application of Mo/Si multilayer optics in EUVL requires both sufficient radiation stability and also the highest possible normal-incidence reflectivity. A serious problem of conventional high-reflective Mo/Si multilayers capped by silicon is the considerable degradation of reflective properties due to carbonization and oxidation of the silicon surface layer under exposure by EUV radiation. In this study, we focus on titanium dioxide (TiO II) and ruthenium dioxide (RuO II) as promising capping layer materials for EUVL multilayer coatings. The multilayer designs as well as the deposition parameters of the Mo/Si systems with different capping layers were optimized in terms of maximum peak reflectivity at the wavelength of 13.5 nm and longterm stability under high-intensive irradiation. Optimized TiO II-capped Mo/Si multilayer mirrors with an initial reflectivity of 67.0% presented a reflectivity drop of 0.6% after an irradiation dose of 760 J/mm2. The reflectivity drop was explained by the partial oxidation of the silicon sub-layer. No reflectivity loss after similar irradiation dose was found for RuO II-capped Mo/Si multilayer mirrors having initial peak reflectivity of 66%. In this paper we present data on improved reflectivity of interface-engineered TiO II- and RuO II-capped Mo/Si multilayer mirrors due to the minimization of both interdiffusion processes inside the multilayer stack and absorption loss in the oxide layer. Reflectivities of 68.5% at the wavelength of 13.4 nm were achieved for both TiO II- and RuO II-capped Mo/Si multilayer mirrors.

  14. Homogeneous SLOWPOKE reactors for Mo-99/Tc-99m production in North America

    Energy Technology Data Exchange (ETDEWEB)

    Hilborn, J.W., E-mail: hilbovanw@sympatico.ca [Deep River, Ontario (Canada); Bonin, H.W. [Royal Military College of Canada, Kingston, Ontario (Canada)

    2014-07-01

    The 15 month shutdown of NRU in 2009 - 2010 caused an overall isotope shortage of approximately 30%; and in North America, the annual Tc-99m demand decreased from an estimated 20 million unit doses to about 15 million unit doses. Mo-99/Tc-99m is produced from HEU targets, irradiated in NRU for 11 days, and after chemical removal of uranium it is shipped to Nordion in Kanata, Ontario. Nordion further purifies the material and sends it to Lantheus Medical Imaging in the USA for manufacture of Mo-99 generators, which are then distributed to hundreds of hospital radiopharmacies throughout North America. One other American company, Covidien, manufactures and distributes Mo-99 generators like Lantheus, but they import bulk Mo-99 from Europe or South Africa. At the hospitals, Tc-99m is chemically extracted daily from the Mo-99 generators and loaded into syringes for immediate clinical use. Fortuitously, the 66 hour half-life of Mo-99 allows the replenishment of Tc-99m in the generator over a growth period of about 20 hours; and a generator can be 'milked' daily for up to two weeks. A more efficient model is the direct production and distribution of Tc-99m unit doses to regional hospitals from 10 'industrial' radiopharmacies located at existing licensed reactor sites in North America. A 20 kW homogeneous SLOWPOKE reactor at each site would deliver 15 litres of irradiated uranyl sulphate fuel solution daily to industrial-scale hot cells for extraction of Mo-99, which would be incorporated in large Mo-99/Tc-99m generators for extraction of Tc-99m five days a week; and the Low Enriched Uranium (LEU) would be recycled. Each automated hot-cell facility would be designed to load up to 7,000 Tc-99m syringes daily, for courier delivery to all of the Nuclear Medicine hospitals within a 3 hour average range by road transport. Typically, the delivered doses would be in the range 10 to 30 mCi. Assuming an average unit dose of 25 mCi at the hospital and 5 x 52

  15. Preparation of i.v. 99mTc radiopharmaceuticals from spent moly 99Mo

    International Nuclear Information System (INIS)

    Noronha, O.P.D.

    1998-01-01

    Full text: Expiry dating is an important quality assurance precept in (radio) pharmacy. There are occasions when for the sake of patient service one may be forced to continue using an over aged source of 99 Mo to generate 99m Tc beyond 7d, especially when there is short/no supply of 99 Mo, (In the early days the expiry date was 3 d or 3 extractions, whichever one was earlier). With the passage of time a few physico-chemical changes (apart from decay) do occur in the 99 Mo/ 99m Tc milieu. The cocktail also begins to contain traces of carried over MEK which is subjected to strong β-, γ irradiation. These impurity (in trace amounts) is soluble in MEK and even, to an extent, in aqueous media. Furthermore, the concentrated impurity tends to seemingly increase in the bulk 99m TcO 4 - since one is compelled to leach TcO 4 - in lower volume of saline. On many occasions we have been constrained to extend the use of 99 Mo beyond 7 - 14 d. Adequate activities were obtained by pooling the previous week's lot of 99 Mo with the current over aged lot. On a few occasions over the past 26 years we have used 99 Mo much beyond 14 d and 2 - 3 occasions for 26 - 28 d (i.e. >10 t 1 /2 of 99 Mo). On each of these occasions the purity of 99m TcO- 4 was ascertained by pharmacopoeial procedures. It was found that despite depleting activities, the purity was not compromised and the trace impurities, even if present, did not cause any interference. We have profitably utilised the bulk TcO- 4 to formulate a variety of i.v. dosage forms of 99m Tc radiodiagnostics. The following strategy was adopted for the patient services - the agents requiring larger activity levels/patients dose were made available in the earlier period, the other during the latter half. It is concluded that pure 99m TcO- 4 can be obtained over the entire useful life-period of 99 Mo, even > 10t l/2

  16. Preparation of 99Mo/99mTc generators based on 99Mo zirconium molybdates in the Gel Synthesis Device for Generators

    International Nuclear Information System (INIS)

    Lopez M, I. Z.; Monroy G, F.; Rivero G, T.; Rojas N, P.

    2008-01-01

    The 99m Tc is used for diagnosis and therapy. It is produced commercially from 99 Mo obtained from the fission of 235 U, which is retained in chromatographic columns filled with alumina whose maximum capacity is 0.2%. Given these constraints new methods of preparation 99 Mo/ 99m Tc generators have been developed using zirconium molybdates gels containing up to 30% of Mo, which is part of the generator matrix, and retaining quality and purity similar characteristics to those commercial generators. The present study aims to determine the flow of agitation, temperature and drying time optimal to prepare 99 Mo/ 99m Tc generators based on 99 Mo zirconium molybdates in the Gel Synthesis Device 99 Mo/ 99m Tc Generators designed and built by groups of the Radioactive Materials Research Laboratory and Automation and Instrumentation Department of the National Institute of Nuclear Research. (Author)

  17. Strengthening of the brazed joint for single-crystalline molybdenum by using Mo-40%Ru-B alloys

    Energy Technology Data Exchange (ETDEWEB)

    Hiraoka, Y. [Okayama Univ. of Science (Japan). Department of Applied Physics; Igarashi, T. [Tokyo Tungsten Co. Ltd., Toyama (Japan). Research and Development Division

    1998-12-01

    In this study, the bend properties of the single-crystalline molybdenum brazed by using Mo-40%Ru alloys containing boron of 1-6 mass%Ru alloy for the improvement of the joint strength was determined. (orig.) [Deutsch] Durchgefuehrt wurde die Herstellung von Verbindungen aus einkristallinem Molybdaen. Hierbei kamen Mo-40%Ru-Legierungen mit 1 bis 6 Gew.-% Bor als Lotmaterialien zum Einsatz. Festigkeit und Duktilitaet der Verbindungen wurden mittels 3-Punkt-Biegepruefung bei Raumtemperatur und unter fluessigem Stickstoff ermittelt. Die Bruchflaechen der Proben wurden mit Hilfe eines Rasterelektronenmikroskopes untersucht. Die Ergebnisse lassen sich wie folgt zusammenfassen: Der optimale Borgehalt bezueglich Festigkeit und Duktilitaet der geloeteten Verbindung liegt bei 2 Gew.-%. Die entsprechende Probe hat bei einem Biegewinkel von 100 bei Raumtemperatur nicht versagt. Auch unter fluessigem Stickstoff zeigte diese Probe eine Festigkeit in der Groessenordnung des einkristallinen Vollmaterials. (orig.)

  18. Evaluation of '99Mo presence in eluates of 99mTc used in nuclear medicine

    International Nuclear Information System (INIS)

    Ribeiro, Bianca da Silva

    2010-01-01

    Tc-99m is used for diagnostic imaging in nuclear medicine through SPECT technique. It is obtained by the elution of 99 Mo/ 99m Tc generators. During the elution process 99 Mo can be extracted becoming a radionuclidic impurity. One of the quality parameters of the eluate is the radionuclidic purity, MBT (molybdenum break through), defined as the ratio between 99 Mo and 99m Tc activities in the eluate. The North-American and European pharmacopoeias restrict the 99 Mo content, respectively, in 0.015 e 0.1% and, according to the International Atomic Energy Agency (IAEA), the activity ratio at the moment of administration of the radiopharmaceutical to the patient, should not exceed 0.015%. In Brazil, the control of such parameter is not obliged in official regulations. Thus, the objective of this work is to evaluate the occurrence of 99 Mo in 99m Tc eluates. It was initially optimized a methodology to determine the activity of 99 Mo in eluate samples. Efficiency curves were obtained for a NaI (Tl) 8'' x 4'' scintillation detector installed at the In Vivo Monitoring Laboratory (LABMIV-IRD). The methodology has been validated through the measurement of a 99 Mo standard liquid source calibrated at the National Metrology Laboratory for Ionizing Radiation (LNMRI-IRD). The samples analyzed in this work were gently supplied by 5 Nuclear Medicine Clinics located in the city of Rio de Janeiro. The activities of 99 mTc and 99 Mo in those samples have been measured respectively at the clinics and at the LABMIV. By applying a standardized methodology, the ration between the activities were calculated. The results show that 147 out of 174 samples presented 99 Mo activities above the minimum detectable activity of the technique. On the other hand, only 2 out of 147 samples surpassed the MBT limit suggested by the IAEA and have been detected in samples eluted from generators of 750 mCi. In one of the samples, eluted from a generator of 1000 mCi, the calculated MBT value was very close

  19. New intermetallic MIrP (M=Ti, Zr, Nb, Mo) and MgRuP compounds related with MoM'P (M'=Ni and Ru) superconductor

    Science.gov (United States)

    Kito, Hijiri; Iyo, Akira; Wada, Toshimi

    2011-01-01

    Using a cubic-anvil high-pressure apparatus, ternary iridium phosphides MIrP (M=Ti, Zr, Nb, Mo) and MgRuP have been prepared by reaction of stoichiometric amounts of each metal and phosphide powders at around 2 Gpa and above 1523 K for the first time. The structure of these compounds prepared at high-pressure has been characterized by X-ray powder diffraction. Diffraction lines of these compounds are assigned by the index of the Co2Si-type structure. The electrical resistivity and the d.c magnetic susceptibility of MIrP (M=Ti, Zr, Nb, Mo) have measured at low temperatures. Unfortunately, no superconducting transition for MIrP (M=Ti, Zr, Nb, Mo) and MgRuP are observed down to 2 K.

  20. New intermetallic MIrP (M=Ti, Zr, Nb, Mo) and MgRuP compounds related with MoM'P (M'=Ni and Ru) superconductor

    International Nuclear Information System (INIS)

    Kito, Hijiri; Iyo, Akira; Wada, Toshimi

    2011-01-01

    Using a cubic-anvil high-pressure apparatus, ternary iridium phosphides MIrP (M=Ti, Zr, Nb, Mo) and MgRuP have been prepared by reaction of stoichiometric amounts of each metal and phosphide powders at around 2 Gpa and above 1523 K for the first time. The structure of these compounds prepared at high-pressure has been characterized by X-ray powder diffraction. Diffraction lines of these compounds are assigned by the index of the Co 2 Si-type structure. The electrical resistivity and the d.c magnetic susceptibility of MIrP (M=Ti, Zr, Nb, Mo) have measured at low temperatures. Unfortunately, no superconducting transition for MIrP (M=Ti, Zr, Nb, Mo) and MgRuP are observed down to 2 K.

  1. Nanostructured metal oxides: promise opportunity and challenge to develop clinically useful 99Mo/99mTc generators using (n, gamma)99Mo

    International Nuclear Information System (INIS)

    Dash, Ashutosh

    2014-01-01

    The role of 99m Tc diagnostic nuclear medicine needs hardly to be reiterated. Today, it is the most widely used radionuclide for single photon emission computed tomography (SPECT) imaging procedures. The current strategy of availing 99m Tc is ensured from column chromatographic 99 Mo/ 99m Tc generators using a bed of acidic alumina. While the column chromatographic 99 Mo/ 99m Tc generator constitute a successful exemplar of availing 99m Tc, the limited capacity of alumina (2-20 mg Mo per g of alumina) for taking up molybdate ions necessitates the use of 99 Mo of the highest specific activity available, as can be found in fission produced 99 Mo (F 99 Mo). In order to reduce dependence of F 99 Mo, the scope of using low specific activity (n,γ) 99 Mo along with high capacity adsorbent is an interesting prospect. In this context, the scope of using nanomaterials as a viable adsorbent seemed attractive by virtue of their huge surface to volume ratios, altered physical properties, tailored surface chemistry, favorable adsorption characteristics, and enhanced surface reactivity resulting from the nanoscale dimensions. This emerging class of adsorbent represents an innovative paradigm and is expected to play an important role in the development of 99 Mo/ 99m Tc generators adaptable to the existing and foreseeable demands. This talk outlines a critical assessment on the role of nanostructured metal oxides, recent developments, the contemporary status, and key challenges and apertures to the near future. (author)

  2. Development of the Mo loading apparatus for adsorbing high level 99Mo to PZC and packing in 99mTc generator column

    International Nuclear Information System (INIS)

    Hishinuma, Yukio; Ohmori, Hiroyuki; Noguchi, Tuneyuki; Tatenuma, Katsuyoshi; Genka, Tsuguo; Machi, Sueo

    2006-01-01

    For developing the automatic system to produce the PZC- 99m Tc generator column based on (n, gamma) method, we developed and fabricated the proto-type apparatus for semi hot test to prepare and pack PZC adsorbed 99 Mo produced by (n, gamma) method into the generator column; PZC is Mo adsorbent with practical performance for (n, gamma) 99m Tc generator with high 99 Mo adsorption and high 99m Tc elution. For conducting the constant supply and delivery of 99m Tc generator, it is necessary to establish the technology of (n, gamma) method 99m Tc generator using PZC and to develop the fabrication system for 99 Mo loading to PZC and packing the 99m Tc generator column. By the reason, we are developing the Mo loading apparatus. In order to automatically conduct the process of 99 Mo adsorption to PZC and PZC- 99 Mo packing into the generator column, based on one channel system developed by JAERI-KAKEN at 3 years ago, an advanced automatic loading system functioned with 8 channels was developed as FNCA project proceeded by the core with Kaken Co. and JAIF for realizing a mass production of 99m Tc generators, and moreover the Japanese patent regarding the PZC- 99m Tc generator including the automatic loading system of 99 Mo to PZC and making 99m Tc generator columns has already been applied with joint applicants of BATAN and Kaken Co. Regarding the multi-type Mo loading apparatus mentioned above, we set it up in a hot of BATAN at December 2003 year. In this report, we will introduce mainly about the multi-channel automatic loading system of 99 Mo. (author)

  3. Two neutrino double-beta decay of 100Mo to the first excited 0+ state in 100Ru

    International Nuclear Information System (INIS)

    Barabash, A.S.; Avignone, F.T. III; Guerard, C.K.; Umatov, V.I.

    1992-06-01

    Double-beta decay from the ground state of 100 Mo to the O + excited state at 1,130.29 keV in 100 Ru has been observed. A sample of 956q of Mo metal powder isotopically enriched to 98.468% of 100 Mo was counted in a Marinelli geometry with a well shielded, ultralow-background germanium detector. The cascade gamma-rays at 539.53 and 590.76 keV were observed. The resulting decay half-life is 1.1 -0.2 +0.3 x 10 21 y at 68% CL

  4. Comparative evaluation of different nanostructured metal oxides for preparation of clinically useful 99Mo/99mTc generators

    International Nuclear Information System (INIS)

    Ram, Ramu; Chakravarty, Rubel; Dash, Ashutosh

    2015-01-01

    The potential of nanostructured metal oxides such as nanotitania, nanozirconia, nanoalumina and mesoporous alumina, as new generation sorbent materials for preparation of 99 Mo/ 99m Tc generator has recently been demonstrated. A comparative assessment of such materials is essential for determination of their suitability for preparation of clinically useful generators using (n,γ) 99 Mo. Characteristics which were compared included the sorption capacity, shelf-life of the generator, radioactive concentration and purity of 99m Tc for radiopharmaceutical applications. Mesoporous alumina was identified as the most suitable sorbent for ensuring sustainable production of clinical grade 99 Mo/ 99m Tc generators using low specific activity 99 Mo. (author)

  5. Effect of the leaching of Ru-Se-Fe and Ru-Mo-Fe obtained by mechanical alloying on electrocatalytical behavior for the oxygen reduction reaction

    International Nuclear Information System (INIS)

    Ezeta, A.; Arce, E.M.; Solorza, O.; Gonzalez, R.G.; Dorantes, H.

    2009-01-01

    In the present work, Ru-Se-Fe and Ru-Mo-Fe alloyed nanoparticles were synthesized from high purity powders (Ru, Se and Mo) by means of the high-energy mechanical alloying. Fe was integrated to the alloys because of the erosion of the mill balls. The ORR electrocatalytic performance of the alloys (lixiviated or not) was evaluated in a rotating disc electrode (RDE) at room temperature. X-ray diffraction (XRD), scanning electron microscopy (SEM) and transmission electron microscopy (TEM) were used for the structure characterization of the materials. Small-particle clusters with granular morphology and nanometric sizes were obtained in all the cases. According to the Tafel parameters from the RDE results, a first order ORR is present in both electrocatalytic systems through a 4e - global multielectron transference to form water: O 2 + 4H + + e - → H 2 O. The electrocatalytic activity showed that the mechanical alloying enabled to obtain nanoparticle electrocatalysts with good ORR performance. Lixiviation of the mechanical alloying powders not improves the catalytical responses.

  6. Optimization of the 99m Tc generator with hydrotalcite as support of 99 Mo

    International Nuclear Information System (INIS)

    Aranda O, N.

    2004-01-01

    In the last years, in the laboratories of the National Institute of Nuclear Investigations (ININ) its have been investigating to the hydrotalcite like a material of support of the 99 Mo with the purpose of developing a new technetium generator. During the development of the investigations it has been demonstrated that when putting in contact to the HTC with an aqueous solution that contains anions of any type, the HTC re hydrate and the structure is regenerated to laminate of the hydrotalcite. If the present anions in the solution are molybdate anions (MoO 4 2- ), these anions passed to be part of the structure of the hydrotalcite (HT-MoO 4 ). These anions can contain, in turn, 99 Mo in their composition ( 99 MoO 4 2- ) and equally they can pass to be part of the structure of the hydrotalcite forming the HT- 99 MoO 4 . When the HT- 99 MoO 4 is packed in a column, the 99m Tc that it takes place when decaying the 99 Mo radioactively can separate the column using aqueous solution of NaCl. This way, in previous studies (Serrano, 2000) it was found that the aqueous solution of NaCl to 0.5% it is the but appropriate for elutriate at the 99m Tc from the column the yield of the elution of the 99m Tc was since high (98%) in the first elution, and the radionuclide contamination caused by the presence of 99 Mo in the eluate it was low ( 4 2- for gram of HTC). These facts, standing out the high capacity of the HTC to retain molybdate ions, they drove from a direct way to investigate the optimization of the generator of 99m Tc, with hydrotalcite like support of the 99 Mo, using 99 Mo of low specific activity. This finishes radioactive material it can be obtained by the irradiation of the 98 Mo (in the chemical form of MoO 3 or (NH 4 ) 2 MoO 4 ), with a flow of thermal neutrons in the nuclear reactor TRIGA Mark lll that one has in the Nuclear Center N abor Carrillo Flores . The technetium generators with alumina like support of the 99 Mo use 99 Mo of high specific activity

  7. Current status of research and development of 99Mo/99mTc generator in Korea

    International Nuclear Information System (INIS)

    Park, U.J.; Lee, J.S.; Son, K.J.; Nam, S.S.; Kwak, S.I.; Han, H.S.

    2006-01-01

    To supply 99m Tc in stable and economical manner in Korea, a chromatographic generator has been under development at KAERI since late 1980's. The chromatographic type of technetium generator is preferred in hospital because it is more convenient and less time-restricted for applications. Hence, the demand of 99m Tc in medical applications is keep increasing. In Korea, there are more than 200 gamma cameras including SPECT in hospitals. For these applications, approximately 100 units/week of 99m Tc generators of which annual cost reached 3 million US dollars were required in 2002. Hence, the development of 99m Tc generators and technology of fission 99 Mo processing were started while installing the generator loading facility (GLF) at KAERI. This facility is currently on a trial run for the commercial production of 99m Tc generators and expected to produce more than 200 generators per week in 2004. For the fission 99 Mo production, an annulus U foil target was considered as the LEU target. The designed LEU target is being used for target manufacturing test and accident analysis. The develop gel type 99m Tc generators by using a poly zirconium complex (PZC) and alumina column, KAERI has cooperated with a Japanese company since late 1990's. In 2003, experimental studies for molybdate adsorption capacity and elution characteristics of the PZC samples from three different batches produced by Kaken Co. were carried out. (author)

  8. Bandgap renormalization and work function tuning in MoSe2/hBN/Ru(0001) heterostructures.

    Science.gov (United States)

    Zhang, Qiang; Chen, Yuxuan; Zhang, Chendong; Pan, Chi-Ruei; Chou, Mei-Yin; Zeng, Changgan; Shih, Chih-Kang

    2016-12-14

    The van der Waals interaction in vertical heterostructures made of two-dimensional (2D) materials relaxes the requirement of lattice matching, therefore enabling great design flexibility to tailor novel 2D electronic systems. Here we report the successful growth of MoSe 2 on single-layer hexagonal boron nitride (hBN) on the Ru(0001) substrate using molecular beam epitaxy. Using scanning tunnelling microscopy and spectroscopy, we found that the quasi-particle bandgap of MoSe 2 on hBN/Ru is about 0.25 eV smaller than those on graphene or graphite substrates. We attribute this result to the strong interaction between hBN/Ru, which causes residual metallic screening from the substrate. In addition, the electronic structure and the work function of MoSe 2 are modulated electrostatically with an amplitude of ∼0.13 eV. Most interestingly, this electrostatic modulation is spatially in phase with the Moiré pattern of hBN on Ru(0001) whose surface also exhibits a work function modulation of the same amplitude.

  9. Performance of Tc-99m generator prepared with Mo adsorbent PZC and irradiated nature MoO3

    International Nuclear Information System (INIS)

    Liu Yishu

    2006-01-01

    This paper describes the technical process of Tc-99m generator prepared with reactor actived Mo-99 and PZC and the performance of the generator was also reported. Two generators were prepared with different batch of PZC and by different technical process. The results show that the adsorption rate was ∼65% and the adsorption efficiency of 99 Mo can be seriously affected by the adsorption process (the temperature, intensity and frequency of shaking and the PZC volume in solution etc.). The elution efficiency was 43-73%. The Mo breakthrough 1.2 - 16% without safe column and its can be decreased to be very low by connecting a hydrate zirconia (HZO) safe column. (author)

  10. New measurement of excitation functions for (p,x) reactions on Mo-nat with special regard to the formation of Tc-95m, Tc96m+g, Tc-99m and Mo-99

    Czech Academy of Sciences Publication Activity Database

    Lebeda, Ondřej; Pruszynski, M.

    2010-01-01

    Roč. 68, č. 12 (2010), s. 2355-2365 ISSN 0969-8043 Institutional research plan: CEZ:AV0Z10480505 Keywords : Cross-sections * Tc-99m * Mo-99 Subject RIV: BG - Nuclear, Atomic and Molecular Physics, Colliders Impact factor: 0.999, year: 2010

  11. Generator of 99m Tc with MnO2 as support of 99 Mo

    International Nuclear Information System (INIS)

    Granados C, F.; Serrano G, J.

    2002-01-01

    The generator of 99m Tc with MnO 2 as support of 99 Mo was studied. By mean of static experiments the retention of 99 Mo in MnO 2 in function of the stirring time and of the p H value of the solution of 99 Mo. It was found that the 99 Mo presents 100% of retention in MnO 2 in the rank of p H 3-11 and the balance was reached before of 10 minutes. In dynamic conditions the retention of 99 Mo in MnO 2 at p H=5 was also higher: 99.72%. The generated 99m Tc can be separated from 99 Mo, adsorbed in MnO 2 packed in the column, using distilled water at p H=5 or NaCl solution at 0.9%. With saline solution the elution yields were greater than 80% and only an aliquot of 5 ml was necessary for obtaining this yield. The better results were obtained when the column was packed with 1 g of MnO 2 . The water and the saline solution were passed through of the column with a flux of 1.25 ml/min. (Author)

  12. Comparative study of 99Mo/99mTc generators at base of synthesized gels starting from 99Mo of activation and of fission

    International Nuclear Information System (INIS)

    Lopez M, I.Z.; Monroy G, F.; Rivero G, T.; Rojas N, P.

    2007-01-01

    At the present time the more used and diffused radionuclide in nuclear medicine it is the Technetium 99 metastable ( 99 mTc) it is used for diagnostic and therapy. It is produced starting from molybdenum 99 ( 99 Mo), which is absorbed in chromatographic columns, loaded with alumina that absorb only 0.2% of 99 Mo situation that forces to use high specific activities of 99 Mo that it is obtained starting from the fission of the 235 U. Given these conditions and limitations, new preparation procedures of 99 Mo/ 99m Tc generators, of low or medium specific activity, its have been developed, using gels of zirconium molybdates that incorporates until 30% in weight of 99 Mo in the gel, and also conserve similar characteristics of quality and purity that those obtained by the traditional generator; reducing by this way the cost of production of the 99m Tc, when using 99 Mo of low specific activity, in the preparation of 99 Mo/ 99m Tc generators. The radiochemical characteristics of the elution of 99m Tc, depends strongly on the gel preparation conditions. In particular, the present work has for object to determine the influence of the used type of 99 Mo, fission or activation product, during the gels synthesis, as well as the used air flow for the agitation in the gels preparation and its influence in the quality of the 99 Mo/ 99m Tc generators. When diminishing the agitation air flow the efficiency it increases and in the radionuclide purity of the eluates and when using 99 Mo of fission for the gels production it increases in an important way the elution efficiency, the radiochemical purity and radionuclide of the eluates of 99m Tc. (Author)

  13. Preparation of a gel of zirconium molybdate for use in the generators of 99 Mo - 99m Tc prepared with 99 Mo produced by the 98 Mo(n,γ)99 Mo reaction

    International Nuclear Information System (INIS)

    Osso Junior, Joao A.; Lima, Ana Lucia V.P.; Silva, Nestor C. da; Nieto, Renata C.; Velosa, Adriana C. de

    1998-01-01

    IPEN develops a project concerning the preparation of a gel of Zirconium Molybdate for use in the generators of 99 Mo- 99m Tc . 99m Tc is the most used radioisotope in nuclear medicine diagnosis procedures and nowadays the generators are being prepared with imported 99 Mo, produced by 235 U fission. The production of 99 Mo by the 98 Mo(n, γ) 99 Mo reaction is now possible because of the power upgrade of IPEN's IEA-R1 reactor, from 2 to 5 MW. This work describes the preparation method of Zirconium Molybdate gel that will be used in the 99 Mo- 99m Tc generators. The gel is prepared by the chemical reaction between Mo, in Mo O 3 form, and Zr, in Zr O Cl 2 .8H 2 O form. After the reaction, the gel is filtered, dried and cracked with saline solution. The product is then loaded into glass columns for use as 99m Tc generator. The results showed the good quality of the gel prepared at laboratory level and of the generators evaluated. (author)

  14. Influence of the irradiation time on the activity of decay products during the cooling. Case: Mo-98 {yields} Mo-99 {yields} Tc-99m; Influencia del tiempo de irradiacion en la actividad de los productos de decaimiento durante el enfriamiento. Caso: Mo-98 {yields} Mo-99 {yields} Tc-99m

    Energy Technology Data Exchange (ETDEWEB)

    Reyes J, J.L.; Ruiz C, M.A.; Alanis M, J. [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    2002-07-01

    In this work the behavior of the activity in the cooling time of Mo-99, Tc-99 and Tc-99m obtained by Neutron activation of natural Mo is described. The analytical development is based on the application of the Laplace transform for resolving the balance equations. (Author)

  15. Comparative study of 99Mo/99mTc generators at base of synthesized gels starting from activation and fission 99Mo

    International Nuclear Information System (INIS)

    Lopez M, I.Z.; Monroy G, F.; Rivero G, T.; Rojas N, P.

    2007-01-01

    The 99m Tc is used for diagnostic and therapy. It is produced starting from 99 Mo, absorbed in chromatographic columns, loaded with alumina that absorb only 0.2% of 99 Mo with high specific activities of 99 Mo, obtained from the 235 U fission. Given these conditions and limitations, new preparation procedures of 99 Mo/ 99m Tc generators, its have been developed, using zirconium molybdates gels that incorporates until 30% of 99 Mo, conserve similar characteristics of quality and purity that the traditional generator. The radiochemical characteristics of the 99m Tc elution, depend strongly on the gel preparation conditions. In particular, the present work has by object to determine the influence of the 99 Mo used type, fission or activation product, during the gels synthesis, as well as the used air flow for the agitation in the gels preparation and its influence in the 99 Mo/ 99m Tc generators quality. When diminishing the flow of agitation air the efficiency it increases and in the radionuclide purity of the eluates and when using 99 Mo from fission for the gels production it increases in an important way the elutriation efficiency, the radiochemical and radionuclide purity of the 99m Tc eluates. (Author)

  16. Production of radiopharmaceutical 99mTc using wasteless reactor Zr-Mo gel-technology

    International Nuclear Information System (INIS)

    Savushkin, I.; Gurko, O.; Ravkova, E.

    2002-01-01

    An original methodology and technological process of the wasteless reactor gel-technology of 99m Tc producing on the basis of centralised Zr-Mo gel-generator have been developed by the Institute of Power Engineering Problems, National Academy of Sciences of Belarus in co-operation with the Research Institute of Oncology and Medical Radiology, Ministry of Health of Belarus. This approach allows 99m Tc to be produced on the basis of MoO 3 with an 99 Mo activity of 3-20 Ci. The technological process of 99m Tc sodium pertechnetate production is remotely controlled and automated. Based on clinical tests performed by the Ministry of Health of Belarus, the clinical application of 99m Tc produced by this technology has been approved. The irradiation conditions of the target, consequence of technological process, technological yield of objective product on the example of operation of one generator, reprocessing and rendering of the wastes are analysed and described. The distinctive features of the technology developed are as follows: (a) Use of native molybdenum as the starting target. (b) Absence of deleterious and toxic impurities from the final product (nitrates, organics, etc.). (c) Application of a modified method of 99m Tc extraction from 99 Mo with the help of the Zr-Mo-gel (that is, application of a true gel, not the powder obtained by gel drying), reducing the number of process stages and simplifying the technology. (d) Easy automation and remote control. (e) Simplicity of design and compactness, opening up wide application fields for the unit. It is suggested that clinical centres should be equipped with centralised high-performance 99m Tc generators. Such centres can supply 99m Tc sodium pertechnetate daily to radioisotope laboratories within the radius of 100 km. Technical and economic calculations show that the centralised gel-generators possess industrial, technical and economic parameters making them superior to small/portable generators based on loading with

  17. A simple and sensitive separation technique of 99Mo and 99mTc from their equilibrium mixture

    International Nuclear Information System (INIS)

    Swadesh Mandal; Ajoy Mandal

    2014-01-01

    The present work describes a simple and inexpensive separation method of 99 Mo from the equilibrium mixture. The liquid-liquid extraction technique has been employed to separate 99 Mo and 99m Tc using triisooctylamine (TIOA). The 99 Mo and 99m Tc were quantitatively separated out in 2 M TIOA with tripled distilled water; 99m Tc was back extracted from TIOA organic phase to aqueous phase by 0.1 M DTPA. The species information or indirect speciation of molybdenum was also established by the extraction profile of the molybdenum. (author)

  18. Preperation and performance of {sup 99}Mo/{sup 99m}Tc chromatographic column generator based on zirconium molybdosilicate

    Energy Technology Data Exchange (ETDEWEB)

    Mostafa, M.; Saber, H.M.; El-Sadek, A.A. [Atomic Energy Authority, Cairo (Egypt). Hot Labs. Center; Nassar, M.Y. [Benha Univ. (Egypt). Chemistry Dept.

    2016-08-01

    Zirconium molybdosilicate (ZrMoSi) gel prepared using {sup 99}Mo radiotracer via peroxo route was used as a base material for {sup 99}Mo/{sup 99m}Tc column generator. The {sup 99m}Tc elution yield and {sup 99}Mo breakthrough in the eluate were studied as a function of the pH-value of gel precipitation, gel drying temperature and Zr: Mo: Si molar ratio. Precipitation pH-value of 2, drying temperature of 100 C and Zr: Mo: Si molar ratio of 0.5: 0.5: 1 were found to be the optimum conditions achieving {sup 99m}Tc elution yield of 82% and {sup 99}Mo breakthrough of 1.0 x 10{sup -3}%. The gel prepared with the optimum conditions was characterized by BET surface area and pore size analyzer, IR spectroscopy, thermal analysis (TGA and DTA), XRD, XRF and FESEM. Technetium-99m eluted from the optimum ZrMoSi {sup 99}Mo/{sup 99m}Tc generator was found to have a high radiochemical purity (98% as {sup 99m}TcO{sub 4}{sup -}) and chemical purity meeting criteria of clinical grade.

  19. Studies of the effect of irradiation in a nuclear reactor, of targets containing Mo used for the preparation of 99Mo gel, material that constitutes the 99Mo - 99mTc generators

    International Nuclear Information System (INIS)

    Nieto, Renata Correa

    2004-01-01

    The most used radioisotope in Nuclear Medicine is 99m Tc, obtained in the 99 Mo - 99m Tc generator form. 99 Mo can be produced by several nuclear reactions in Cyclotron and Reactor. The production in Cyclotron is not technically and commercially feasible. The production in Nuclear Reactor can be made in two ways: 235 U fission and 99 Mo (n,γ) 99 Mo reaction. A project aiming the production of 99 Mo by activation of Mo is under way at IPEN, producing a gel type MoZr generator. There are two ways of preparing the gel and the generators: by irradiating MoO 3 and preparing the gel or by the preparation of the gel and further irradiation. This work consists in the study of the irradiation effects in several targets containing Mo for the production of 99 Mo by the 98 Mo (n,γ) 99 Mo reaction and further preparation of the gel for use as a gel type 99 Mo - 99m Tc generator. Three rinds of gel were studied: zirconium, titanium and cerium molybdate, and their morphology, infrared structure and elution yield of 99m Tc were analysed. The best results were achieved with the generators prepared with MoZr post formed gel, with amorphous structure and better elution yields. The pre formed gel induced crystallinity and worst performance of the generators. (author)

  20. Actions needed to ensure a reliable supply of 99Mo and 99mTc?

    International Nuclear Information System (INIS)

    Cameron, R.; Peykov, P.

    2014-01-01

    The NEA established the High-level Group on the Security of Supply of Medical Radioisotopes (HLG-MR) to examine the causes of 99 Mo/ 99 mTc supply shortages in 2009. It undertook an economic analysis and determined that lack of economic sustainability in producing reactors was the major cause of the shortages. From that it developed a policy approach, including principles and supporting recommendations to address those causes. Since then it has looked at the way the supply chain has implemented these policy principles through initiating a self-assessment process, which revealed uneven application and lack of adherence to the key principle of full cost recovery. As part of the analysis, the NEA has also reviewed the global 99 Mo/ 99 mTc supply situation periodically, using the most up-to-date data from supply chain participants, to highlight periods of reduced supply and underscore the case for implementing the HLG-MR policy approach in a timely and globally-consistent manner. This current paper presents the preliminary results from an updated 99 Mo supply and demand forecast, focusing on the potentially critical 2015-2020 period, when two major 99 Mo producers (the NRU reactor in Canada and the OSIRIS reactor in France) are scheduled to cease 99 Mo irradiations. It concludes with a review of the effectiveness of the actions taken to date and indicates where further action is needed. (author)

  1. Performance tests on column materials for {sup 99}Mo-{sup 99m}Tc generator

    Energy Technology Data Exchange (ETDEWEB)

    Sombrito, E Z; Bulos, A D; Tangonan, M C [Chemistry Research Section, Atomic Research Div., Philippine Nuclear Research Inst., Quezon (Philippines)

    1998-10-01

    To meet the need of producing a {sup 99}Mo-{sup 99m}Tc generator, based on low specific activity reactor-produced {sup 99}Mo, different procedures for preparing zirconium molybdate gels were tested. Performance tests were done on molybdate gel columns prepared using the procedures developed by Vietnam and China, and recently, on a polyzirconium compound (PZC) prepared in Japan. The conditions for the batch drying of a large volume of the gel material were studied as well as the conditions in preparing a column to concentrate technetium-99m. The performance of PZC sample as column material for the generator was also evaluated. (author)

  2. Direct elution of sup(99m)Tc complexes from neutron irradiation produced 99Mo incorporated in a MoCl2-MoBr2 mixture

    International Nuclear Information System (INIS)

    Ganzerli Valentini, M.T.; Stella, R.; Genova, N.

    1987-01-01

    A novel type of sup(99m)Tc generator, enabling radiopharmaceutical preparation without reductant addition, was prepared and tested. Neutron activated product 99 Mo, in the form of dichloride cluster, was incorporated into inactive molybdenum dichloride-dibromide mixture (MCB) that was left to settle over an activated alumina layer. Direct elution with aqueous ligands such as salicylate or iminodiacetate derivatives in the pH range 6.5-7.5 yielded chemically stable sup(99m)Tc complexes accompanied by small amounts of secondary products (mostly sup(99m)TcO - 4 ). Pentavalent oxidation state in the salicylate complex and tervalent in the iminodiacetate (IDA) and in the N-(2,6-dimethylphenylcarbamoylmethyl) iminodiacetate (HIDA) complexes were assigned to the element after comparison with reference complexes. The anion exchange version of reverse-phase HPLC was used to resolve the eluted product mixture. (author)

  3. 99Mo-99mTc generator - study of their performance and quality

    International Nuclear Information System (INIS)

    Acar, M.E.D.

    1987-01-01

    In this work the performance of the 99 Mo - 99m Tc generators produced at IPEN-CNEN/SP as well as the quality of the eluted solutions were analysed. The following parameters were studied: elution efficiency, chemical radiochemical, radionuclidic and microbiological purities and pH of the eluates. The 99m Tc yield ranged from 84,7 to 98,5%. The radioactivity due to the pertechnetate ion in the studied solutions was higher than 97,5%. The aluminium content in eluates, determined by spectrophotometry, was lower than 2,5 μg/ml and the pH of the solutions between 4,5 and 5,1. Radioactive impurities of the order of 10 -3 KBq 99 Mc/MBq 99m Tc and 10 -5 KBq 131 I/MBq 99m Tc were found in the eluates at the time of elution. Other γ emitting radioactive impurities were order of 10 -3 KBq/MBq 99m Tc. The eluates were sterile and pyrogen-free. From the results obtained in this work one can state that the IPEN-TEC generator is a reliable source of good quality 99m Tc-pertechnetate. (author) [pt

  4. Progress on the Development of (n,γ)99Mo/99mTc generator, an Alternative of Conventional Generator

    International Nuclear Information System (INIS)

    Lee, Jun Sig; Choi, Seung Rag; Nam, Seong Su; Park, Ul Jae; Son, Kwang Jae; Choi, Kang Hyuk; Choi, Sun Ju

    2010-01-01

    Even though different types of generators have been developed to extract 99m Tc, most of the generators uses 99 Mo from the fission products as the mother radionuclide of 99m Tc. Recently, the crisis of 99 Mo production becomes one of the international issues as 99m Tc is a dominant diagnostic radionuclide. The shortage of 99m Tc has been predicted in the society for more than 10 years. However, actions to prevent such crisis were slow as the initial investment to construct a new research reactor for the production of 99 Mo is high. Currently, it is expected the shortage of 99m Tc will last at least for more than 5 years. As an alternative to minimize such crisis, a new approach is proposed and studied. In this approach, the mother source of 99m Tc comes not from fission products but from the neutron irradiation of molybdenum oxide. Hence, most of the research reactors, which do not have capability to produce fission molybdenum, (n,f) 99 Mo can produce 99 Mo. The key issue in this approach is the uptake capacity of the generator column for (n, γ) 99 Mo, which has extremely low specific activity compared to (n,f) 99 Mo. Currently, the results from the research activities at Korea Atomic Energy Research Institute have shown such approach has enough potential as an alternative of the conventional generator. Hence, the progress of the research is reported in this paper

  5. The risk analysis used to manufacture 99Mo/99mTc generators

    International Nuclear Information System (INIS)

    Fano Machín, Yoiz; Alberti Ramírez, Alejandro; Gamboa Marrero, Regla; Suárez Beyríes, Karina; Cruz Morales, Amed

    2016-01-01

    In this work the steps to be followed for the risk analysis in the process of production of 99 Mo / 99m Tc generators in CENTIS, using the methodology of analysis of modes and effects of failures are collected. The analysis of the type and probability of occurrence of the failures in the process, as well as the impact on the quality of the same and the probability of detection of such failures, were used for the use of techniques used in quality assurance such as: storm Ideas and cause-effect diagram. Scales were established for the determination of severity, probability of occurrence, probability of detection and calculation of the number of risk probabilities. The guidelines were laid down for the future application of this technique, which will establish a decision-making process regarding the risks associated with the production process of 99 Mo / 99m Tc generators. (author)

  6. Determination of 99Mo in 99mTc eluates used in nuclear medicine centers in Rio de Janeiro

    International Nuclear Information System (INIS)

    Ribeiro, Bianca da S.; Souza, Raphael S.S.; Lucena, Eder A.; Dantas, Ana Leticia A.; Dantas, Bernardo M.

    2009-01-01

    99m Tc is used in nuclear medicine for image diagnoses with SPECT. It is obtained from the elution of molybdenum-99/technetium-99m ( 99 Mo/ 99m Tc) generators. During the elution, 99 Mo can detach from the column, passing through the filter and mixing in the solution of pertechnetate eluate and becoming a radionuclidic impurity. The presence of molybdenum in the radiopharmaceutical solution imparts an unnecessary radiation dose to the patient, since its half-life is relatively long (66 hours) and it emits beta particles and high-energy photons of (740 keV). A parameter that indicates the quality of the eluates is the radionuclidic purity, the MBT (molybdenum break through), defined as the ratio between 99 Mo and 99m Tc activities in the eluate. The American and the European Pharmacopoeias restrict 99 Mo content to respectively 0.015% and 0.1% activity ratio 99 Mo/ 99m Tc at the time of the administration to the patient. In Brazil, this parameter is not controlled by official regulations. The objective of this work is to determine the presence of 99 Mo in the eluates used in nuclear medicine centers (NMC). The activity measurements of 99 Mo were performed with a NaI(Tl)8''x4'' scintillation detector installed in the IRD whole body counter. The activity of 99m Tc was measured in the NMC where the eluates were collected and, using the established calculations, it was determined the activity ratio 99 Mo/ 99m Tc. The eluate samples were kindly supplied by the participating NMC of Rio de Janeiro. All measurements indicated the presence of 99 Mo. It is concluded that the technique is sensitive to detect 99 Mo in 99m Tc eluates and permits to verify the quality of the generators used in NMC evaluated in this study. (author)

  7. Photo-production of (99)Mo/(99m)Tc with electron linear accelerator beam.

    Science.gov (United States)

    Avagyan, R; Avetisyan, A; Kerobyan, I; Dallakyan, R

    2014-09-01

    We report on the development of a relatively new method for the production of (99)Mo/(99m)Tc. The method involves the irradiation of natural molybdenum using high-intensity bremsstrahlung photons from the electron beam of the LUE50 linear electron accelerator located at the Yerevan Physics Institute (YerPhi). The production method has been developed and shown to be successful. The linear electron accelerator at YerPhi was upgraded to allow for significant increases of the beam intensity and spatial density. The LUE50 was also instrumented by a remote control system for ease of operation. We have developed and tested the (99m)Tc extraction from the irradiation of natural MoO3. This paper reports on the optimal conditions of our method of (99)Mo production. We show the success of this method with the production and separation of the first usable amounts of (99m)Tc. Copyright © 2014 Elsevier Inc. All rights reserved.

  8. A novel electrochemical technique for the production of clinical grade 99mTc using (n, γ)99Mo

    International Nuclear Information System (INIS)

    Chakravarty, Rubel; Dash, Ashutosh; Venkatesh, Meera

    2010-01-01

    Introduction: In order to meet the growing demand for 99m Tc and to reduce the reliance on fission-produced 99 Mo, an electrochemical pathway for accessing 99m Tc through the (n, γ) 99 Mo was explored as a back-up measure and to supplement 99m Tc supply for radiopharmaceuticals application. Methods: 99m Tc from an equilibrium mixture of 99 Mo/ 99m Tc was selectively deposited on a platinum cathode in an electrochemical cell by applying optimal voltage and stripped back again into the 0.9% saline solution. The radiochemical and radionuclidic purity of the product were determined using standard techniques. 99m Tc thus obtained was used for labeling standard ligands such as dimercaptosuccinic acid (DMSA) and ethylene dicysteine (EC), to ascertain the usability. Results: Selective deposition of 99m Tc on the platinum electrode was achieved at a potential of 5 V over a period of 1 h in NaOH electrobath. The overall yield of 99m Tc was >90%, with >99.99% radionuclidic purity and >99% radiochemical purity. The performance of the generator remained consistent over a period of 10 days. The compatibility of the product in the preparation of 99m Tc-labeled formulations such as 99m Tc-DMSA and 99m Tc-EC was found to be satisfactory in terms of high labeling yields (>98%). Conclusion: A novel and attractive method has been developed to obtain highly concentrated 99m Tc, without using fission-produced 99 Mo.

  9. Synthesis and characterization of zirconium molybdates of {sup 99} Mo/{sup 99m} Tc generators; Sintesis y caracterizacion de molibdatos de zirconio de generadores {sup 99} Mo/{sup 99m} Tc

    Energy Technology Data Exchange (ETDEWEB)

    Contreras R, A.; Monroy G, F.; Diaz A, L.V. [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    2002-07-01

    The zirconium molybdates are gels which are used as cation exchangers in the production of {sup 99} Mo/{sup 99m} Tc generators. The synthesis method and the characterization of these gels by thermogravimetry, infrared spectroscopy and X-ray diffraction is presented with the purpose of finding which the factors are that influence in the efficiency of the {sup 99m} Tc production. The results show that the quantity of molecular water contained in gel, is possibly the cause of variations of the efficiencies of the {sup 99} Mo/{sup 99m} Tc generator. (Author)

  10. Cross-sections for formation of 99mTc through natRu(n,x) 99mTc reaction induced by neutrons at 13.5 and 14.8 MeV

    International Nuclear Information System (INIS)

    Luo Junhua; Han Jiuning; Tuo Fei; Kong Xiangzhong; Liu Rong; Jiang Li

    2012-01-01

    The cross-sections for formation of metastable state of 99 Tc ( 99m Tc, 140.511 keV, 6.01 h) through nat Ru(n,x) 99m Tc reaction induced by 13.5 MeV and 14.8 MeV neutrons were measured. Fast neutrons were produced via the 3 H(d,n) 4 He reaction on the K-400 neutron generator. Induced gamma activities were measured by a high-resolution gamma-ray spectrometer with a high-purity germanium (HpGe) detector. Measurements were corrected for gamma-ray attenuations, dead time and fluctuation of neutron flux. Data for nat Ru(n,x) 99m Tc reaction cross sections are reported to be 9.6±1.5 and 9.2±1.1 mb at 13.5±0.2 and 14.8±0.2 MeV incident neutron energies, respectively. Results were compared with the data by other authors. - Highlights: ► D–T neutron source was used to measure cross sections using activation method. ► 27 Al(n,α) 24 Na was used as the monitor for the measurement. ► Cross-sections for formation of 99m Tc through nat Ru(n,x) 99m Tc were measured. ► Data for nat Ru(n,x) 99m Tc reaction cross sections are reported. ► The results were discussed and compared with experimental data in the literature.

  11. Investigation of activation cross section data of alpha particle induced nuclear reaction on molybdenum up to 40 MeV: Review of production routes of medically relevant {sup 97,103}Ru

    Energy Technology Data Exchange (ETDEWEB)

    Tárkányi, F. [Institute of Nuclear Research of the Hungarian Academy of Sciences, Debrecen (Hungary); Hermanne, A., E-mail: aherman@vub.ac.be [Cyclotron Laboratory, Vrije Universiteit Brussel, Brussels (Belgium); Ditrói, F.; Takács, S. [Institute of Nuclear Research of the Hungarian Academy of Sciences, Debrecen (Hungary); Ignatyuk, A. [Institute of Physics and Power Engineering (IPPE), Obninsk (Russian Federation)

    2017-05-15

    The main goals of this investigations were to expand and consolidate reliable activation cross-section data for the {sup nat}Mo(α,x) reactions in connection with production of medically relevant {sup 97,103}Ru and the use of the {sup nat}Mo(α,x){sup 97}Ru reaction for monitoring beam parameters. The excitation functions for formation of the gamma-emitting radionuclides {sup 94}Ru, {sup 95}Ru, {sup 97}Ru, {sup 103}Ru, {sup 93m}Tc, {sup 93g}Tc(m+), {sup 94m}Tc, {sup 94g}Tc, {sup 95m}Tc, {sup 95g}Tc, {sup 96g}Tc(m+), {sup 99m}Tc, {sup 93m}Mo, {sup 99}Mo(cum), {sup 90}Nb(m+) and {sup 88}Zr were measured up to 40 MeV alpha-particle energy by using the stacked foil technique and activation method. Data of our earlier similar experiments were re-evaluated and resulted in corrections on the reported results. Our experimental data were compared with critically analyzed literature data and with the results of model calculations, obtained by using the ALICE-IPPE, EMPIRE 3.1 (Rivoli) and TALYS codes (TENDL-2011 and TENDL-2015 on-line libraries). Nuclear data for different production routes of {sup 97}Ru and {sup 103}Ru are compiled and reviewed.

  12. Synthesis and irradiation of titanium molybdates used as matrices of the 99 Mo/ 99m Tc generators

    International Nuclear Information System (INIS)

    Diaz V, H.; Monroy G, F.

    2005-01-01

    The 99m Tc is the radioisotope but used in nuclear medicine. Commercially it takes place starting from generators of 99 Mo/ 99m Tc, composed by a chromatography column padded of aluminium oxide of aluminum, where it is deposited the 99 Mo, product of the fission of the 235 U adsorbed and eluted, by means of a saline solution, in form of 99m TcO 4 - . The production of 99 Mo as a result of the fission, imposes radiochemical separations that generate significant quantities of radioactive waste of medium activity, and inflict elaborated radiochemical manipulation. Due to this, its have been carried out intense investigations to substitute the 99 Mo fission product, by chemical compounds that produce 99 Mo via the reaction 98 Mo(n, γ) 99 Mo. Presently work intends the use of gels of titanium molybdates like matrices of these generators. Titanium molybdates were synthesized starting from solutions TiCl 3 and ammonium molybdates and it was studied the effect of the final pH of the gels, the concentration of the Ti +3 and the influence of the laundry of these on the acting of generators. The best efficiencies and chemical purity, radiochemical and radionuclides of the gels like matrices of generators 99 Mo/ 99m Tc were gotten with the washed gel, elaborated with the solution of TiCI 3 0.35M, and to a final pH of 5.9 (Author)

  13. Evaluation of 99Mo/99mTc generator experiment using PZC material and irradiated natural molybdenum

    International Nuclear Information System (INIS)

    Khongpetch, P.; Chingjit, S.; Dangprasert, M.; Rangsawai, W.; Virawat, N.

    2006-01-01

    Technetium-99m ( 99m Tc) is the most widely used radioisotope in nuclear medicine, accounting for more than 80% of all diagnostic nuclear medicine procedure. 99m Tc is almost exclusively produced from the decay of its parent molybdenum-99 ( 99 Mo). The present sources of 99 Mo are research reactors by using the (n, γ) nuclear reaction with natural molybdenum, resulting in inexpensive but low specific activity 99 Mo, or by neutron-induced fission of uranium-235, which result in expensive but high specific activity 99 Mo. The technology requirement for processing of 99 Mo from the (n, γ) 'activation method' is rather simple, and is within the reach of most developing countries operating research reactors. In the fission method' the technological and infrastructure requirements are some complex, and possibly can be sustained only by countries with advanced nuclear technology. To overcome these difficulties, Japan Atomic Energy Research Institute (JAERI) and KAKEN company have developed alternative technology for 99 Mo/ 99m Tc generator by using a molybdenum absorbent called Poly Zirconium compound (PZC) and irradiated natural molybdenum. The paper describes experiments for evaluation the performance of PZC as a column packing material for 99 Mo/ 99m Tc generator from (n, γ) 99 Mo. (author)

  14. The separation of sup(99m)Tc from 99Mo through an aluminium oxide chromatographic columm

    International Nuclear Information System (INIS)

    Imoto, S.T.

    1980-01-01

    The separation of sup(99m)Tc from 99 Mo using the chromatographic method is studied. Alumina is used as adsorbent. The pH values for adsorption of carrier-free 99 Mo on columns filled with ordinary alumina and with that thermically treated at 1000 0 C for five hours, and the separation conditions of sup(99m)Tc using physiologic solution as eluent are determined. The sup(99m)Tc separation yields of both columns are compared and the quality of the products obtained by successive elutions for 10 days is analyzed. (Author) [pt

  15. Status of {sup 99}Mo-{sup 99m}Tc production development by (n, {gamma}) reaction

    Energy Technology Data Exchange (ETDEWEB)

    Tsuchiya, Kunihiko; Kaminaga, Masanori; Ishihara, Masahiro; Kawamura, Hiroshi [Japan Atomic Energy Agency, Oarai Research and Development Center, Oarai, Ibaraki (Japan); Mutalib, Abdul [National Nuclear Energy Agency of Indonesia (BATAN), Tangerang (Indonesia); Chakrov, Petr [Institute of Nuclear Physics, National Nuclear Center of Republic of Kazakhstan (INP-NNC-RK), Almaty (Kazakhstan)

    2012-03-15

    Technetium-99m ({sup 99m}Tc) is one of the most commonly used radioisotopes in the field of nuclear medicine. As one of effective uses of the JMTR, JAEA has a plan to produce {sup 99}Mo by (n, {gamma}) method, a parent nuclide of {sup 99m}Tc. JAEA has performed R and D on production method of {sup 99}Mo-{sup 99m}Tc in JMTR cooperating with foreign organizations and relevant Japanese enterprises under the cooperation programs. In this paper, present status of R and D for production of {sup 99}Mo-{sup 99m}Tc in JMTR under international cooperation is introduced and constructions of the irradiation and PIE facilities at the JMTR site are also described. (author)

  16. 99mTc gel generators based on zirconium molybdate-99Mo: III: Influence of preparatory conditions of zirconium molybdate-99Mo gel on generator performance

    International Nuclear Information System (INIS)

    Saraswathy, P.; Sarkar, S.K.; Arjun, G.; Ramamoorthy, N.; Nandy, S.K.

    2004-01-01

    The effect of subtle variations on zirconium molybdate- 99 Mo gel preparatory conditions, such as stoichiometry of reactants, pH of gel formation, conditioning of gel granules etc., prior to elution were investigated primarily to arrive at the conditions resulting in high 99m Tc release and minimal 99 Mo breakthrough upon elution with normal saline. Zirconium molybdate- 99 Mo gels were prepared by reacting solutions of Zr and Mo in mole ratios of 0.75-1.5. Both water and normal saline were used for gel disintegration, and the release of 99m Tc and 99 Mo from gel columns into eluates was compared. Sharper elution profile of 99m Tc, but with significantly higher 99 Mo breakthrough (5-8 times), was obtained when water alone was used for disintegration and elution, in comparison to when saline was used. Gels exhibiting optimum characteristics were found to be formed at a pH of 4-5 by reacting [Zr]: [Mo] in the mole ratio of 1.25: 1 and after drying, the product was dispersed into granules by disintegration with normal saline. 99m Tc elution efficiency was found to be ∝ 75% and 99 Mo breakthrough ∝ 0.05%. The elution profile was sharp when a 6 g gel column coupled to a 2 g acidic alumina column (to trap 99 Mo) was eluted with 6-9 ml normal saline. Generators containing upto 23 GBq 99 Mo were prepared, eluted extensively without changing the alumina column and found to provide pertechnetate of good quality, commensurate with hospital radiopharmacy requirements. (orig.)

  17. Current status of production and supply of molybdenum-99 and 99Mo/99mTc generators in Indonesia

    International Nuclear Information System (INIS)

    Mutalib, A.

    2003-01-01

    Production of high-specific activity molybdenum-99 and 99 Mo/ 99m Tc Generators in Indonesia commenced when a new production facility supported by the presence of a 30 MW multipurpose reactor (RSG-GAS) was established in Serpong in 1990. This report describes the current production and supply of molybdenum-99m devoted mainly to fulfill the domestic demands in supplying 99 Mo/ 99m Tc Generators. Recent development on the use of LEU (Low Enriched Uranium) targets for replacing current HEU (High Enriched Uranium) targets in the production of 99 Mo will be reviewed briefly. (author)

  18. An embedded system based computer controlled process automation for recovery and purification of 99mTc from (n,γ)99Mo

    International Nuclear Information System (INIS)

    De, Anirban; Pal, S.S.; Bhaskar, P.; Kumari, S.; Khare, V.K.; Duttaroy, A.; Garai, M.; Thakur, S.K.; Saha, S.; Chattopadhyay, Sankha; Barua, Luna; Das, Sujata Saha; Kumar, U.; Das, M.K.

    2012-01-01

    99 Mo produced 99 mTc (t 1/2 = 6 hr, 140 KeV γ-ray) is the most useful radioisotope for nuclear diagnostics. High specific activity 99 Mo is supplied globally mainly by five old reactors whose routine or unscheduled maintenance shutdown causes supply irregularities that adversely affects patient management in nuclear medicine centres. 99m Tc may also be produced via 98 Mo(n,γ) in a natural MoO 3 target in reactor or by 100 Mo(n,2n) 99 Mo or 100 Mo(p,2n) 99 mTc reaction in cyclotron. To meet the crisis proposals are there to produce 99 Mo by 100 Mo(n,2n) 99 Mo or 99m Tc directly by 100 Mo(p,2n) 99m Tc in a cyclotron. Of the several separation methods of 99 mTc from molybdenum, the most common are adsorption column chromatography, sublimation and liquid-liquid solvent extraction. The conventional methods besides being cumbersome are often hazardous, polluting, require skilled manpower and facilities like fume hood and so are not always practically feasible for hospitals. To address these, VECC and BRIT, Kolkata have collaborated to develop an embedded system based automated 99 Mo/ 99m Tc generator from low specific activity 99 Mo using solvent extraction technique, supervised by a PC based GUI. (author)

  19. Minimizing Molybdenum 99 contamination in Technetium 99m Pertechnetate from the elution of 99Mo/ 99m Tc Generator

    International Nuclear Information System (INIS)

    Zakaria Ibrahim; Zulkifli Hashim; Bohari Yaacob

    2011-01-01

    Radioisotope Tc-99m is widely used for variety of nuclear medicine diagnostic procedures. For many commercial applications, it is prepared in a portable type generator. Nuclear Malaysia has been producing a dry type alumina chromatographic column generator utilizing fission Mo-99. This injectable Tc-99m must meet the British Pharmacopeia [1] product specification prior to be apply on patient. This paper provides a method to minimize the up to acceptable level Mo-99 in the final product. Purposely made pertechnetate contaminated with Mo-99 and re-eluate by using old generator. Excellent removal of Mo-99 impurity was achieved and more than 80 % of Tc-99m total activity was recovered. (author)

  20. Comparative study of {sup 99}Mo/{sup 99m}Tc generators at base of synthesized gels starting from activation and fission {sup 99}Mo; Estudio comparativo de generadores {sup 99}Mo/{sup 99m}Tc a base de geles sintetizados a partir de {sup 99}Mo de activacion y de fision

    Energy Technology Data Exchange (ETDEWEB)

    Lopez M, I Z [UAEM, Paseo Colon esq. Paseo Tollocan, 50120 Toluca, Estado de Mexico (Mexico); Monroy G, F; Rivero G, T; Rojas N, P [ININ, Carretera Mexico -Toluca S/N, 52045 La Marquesa Ocoyoacac, Estado de Mexico (Mexico)

    2007-07-01

    The {sup 99m}Tc is used for diagnostic and therapy. It is produced starting from {sup 99}Mo, absorbed in chromatographic columns, loaded with alumina that absorb only 0.2% of {sup 99}Mo with high specific activities of {sup 99}Mo, obtained from the {sup 235}U fission. Given these conditions and limitations, new preparation procedures of {sup 99}Mo/{sup 99m}Tc generators, its have been developed, using zirconium molybdates gels that incorporates until 30% of {sup 99}Mo, conserve similar characteristics of quality and purity that the traditional generator. The radiochemical characteristics of the {sup 99m}Tc elution, depend strongly on the gel preparation conditions. In particular, the present work has by object to determine the influence of the {sup 99}Mo used type, fission or activation product, during the gels synthesis, as well as the used air flow for the agitation in the gels preparation and its influence in the {sup 99}Mo/{sup 99m}Tc generators quality. When diminishing the flow of agitation air the efficiency it increases and in the radionuclide purity of the eluates and when using {sup 99}Mo from fission for the gels production it increases in an important way the elutriation efficiency, the radiochemical and radionuclide purity of the {sup 99m}Tc eluates. (Author)

  1. Design of a type - a transport package for 99Mo-99mTc Coltech generator

    International Nuclear Information System (INIS)

    Kothalkar, Chetan; Suryanarayana, G.V.; Dey, A.C.; Sachdev, S.S.; Choughule, N.; Murali, S.

    2012-01-01

    BRIT is launching a new product called 99 Mo- 99m Tc Coltech generator. The Coltech generator is a devise designed for the transport of 99 Mo radioisotope adsorbed on the acidic alumina in a sealed glass column (max dimensions: 13 mm diameter, 70 mm height) as the primary containment. At hospital end, 99m Tc, the daughter product of 99 Mo, can be eluted out from the generator using saline. The active column is fitted with a leak proof network of stainless steel needles. The glass column carrying 99 Mo is housed inside a lead shielding having minimum thickness of 50 mm all around, which serves as secondary containment. The shielding is housed inside the ABS shell which acts as tertiary containment, also provides protection to the needles, filters etc. Total weight of the generator is 16 kg. Based on the AERB code SC/TR-1 (being revised), 99 Mo- 99m Tc Coltech generator will be transported in a Type-A transport container. A transport package has been designed by following the code SC/TR-1. Principle design of the package is based on the package for transportation of the similar generator produced by POLATOM, Poland and the package is approved by the Polish regulatory authority. Components are manufactured locally taking care of lndian conditions. The package comprised of a MS drum (HOBBOCK) with tamper proof lockable MS lid and a handle to assist in lifting. For absorbing the shock during transportation, the generator assembly is packed inside the two pieces EPS top and bottom support. The package has been designed for transportation by all modes of transport. Since radioactive material is solid in form and sealed a glass column, it has been designed to sustain a free drop test of 1.2 m, in addition to other tests specified in SC/TR-1. During trial batches upto ∼ 1 Ci of 99 Mo generators were produced, packed in the same Type-A package and supplied to local nuclear medicine center RMC, Mumbai in BRIT vehicle in consultation with AERB. The radiometry of the packages

  2. 99Tc, Pb and Ru migration around the Oklo natural fission reactors

    International Nuclear Information System (INIS)

    Gancarz, A.; Cowan, G.; Curtis, D.; Maeck, W.

    1980-01-01

    This work demonstrates the utility of the Oklo uranium ore deposit and natural fission reactors as a long time scale analogue for man-made radioactive waste repositories. It has been shown that the ores and nearby rocks were open to the loss and gain of 99 Tc, ruthenium, and lead relative to uranium. Identified regions of element deficiencies and those which are correspondingly enriched are separated by less than 10 meters. However, more extensive sampling is required to define the overall extent of the element migration. Element fractionation took place on at least two vastly different time scales; 99 Tc was fractionated from ruthenium within one million years of the end of reactor criticality. Lead-uranium fractionation has been ongoing for most of the two billion years since the ores were formed. Diffusion loss of lead from host uraninite appears to be an important process in the fractionation of lead from uranium

  3. Separation of sup(99m)Tc from 99MoO3

    International Nuclear Information System (INIS)

    Tomicic, M.

    1977-07-01

    At the present time sup(99m)Tc is widely used in nuclear medicine and its uses are increasing. It can be produced by various methods, and of those most frequently used today two have special features making them particularly applicable to the large-scale production of instant sup(99m)Tc - these are solvent extraction with methyl-ethyl-ketone and the sublimation methods. This report presents a bibliographic review of these methods, their main perfomance parameters, and experience obtained from the development and operation of a sublimation generator. Separation of sup(99m)Tc from irradiated MoO 3 was carried out with high yields (75-95%) after multiple repetition of the separation process with molybdenum trioxide heated for half an hour at a maximum temperature of 850-890 deg C in an air flow. The activity ratio of molybdenum in the separated sup(99m)Tc was of the order of 4 x 10 -5 . (author)

  4. Studies of techniques for the post-elution concentration of 99mTc obtained from gel type 99Mo/99mTc generators

    International Nuclear Information System (INIS)

    Suzuki, Katia Noriko

    2009-01-01

    On average 80% of the radiopharmaceuticals used in Nuclear Medicine are labeled with 99 mTc due to its physical properties and easy attainment through of 99 Mo/ 99 mTc generators. The Directory of Radiopharmacy (DIRF) of IPEN-CNEN/SP developed a gel type chromatographic generator of MoZr with 99 Mo produced by 98 Mo(n,γ) 99 Mo reaction that occurs at the IEA-R1 Nuclear Reactor. The gel is composed of zirconium molybdate with elution volume of 12 mL with an activity of 11100 MBq (300 mCi) producing a radioactive concentration of 925 MBq (25 mCi)/mL. The fission generator gives a higher radioactive concentration around 1850 MBq (50 mCi)/mL. The aim of this work is to study a system of post-elution concentration of 99 mTc for the attainment of a high enough radioactive concentration to meet the demands of the market, with a proved quality. Two types of systems of post-elution concentration were developed: the single and the tandem. The most appropriate system for the gel generator of 99 Mo/ 99 mTc, being at the same time sterile and vacuum automated, was the tandem system using Dionex 2.5 cc/QMA cartridges. The gel generator is eluted with 10 mL of solution of 0.1% NaCl and the pertechnetate anion is retained in the QMA cartridge and further eluted with 4 mL of saline. The process takes no more than 30 minutes. The elution efficiency of the system of concentration was 90 %. At the beginning of 2009 a global crisis in the supply of 99 Mo took place making it necessary the development of alternative technologies for the production of 99 Mo/ 99 mTc generators using fission produced 99 Mo and the development of an appropriate method to extend the useful life of this generator. The results of this study showed that the same system developed for the post- concentration of the gel generator can be employed for the fission generator, using the tandem system, giving a concentration factor of 3 for the elution of 99 mTc. (author)

  5. Problems in clinical practice of domestic supply of 99Mo/99mTc. The direction and problem of stable supply chain of 99Mo in Japan

    International Nuclear Information System (INIS)

    Inoue, Tomio

    2013-01-01

    The shortage of supply of 99 Mo caused by trouble of old nuclear reactors in Canada and Europe caused international problem in the field of nuclear medicine, which has not been completely resolved yet. Because all of 99 Mo/ 99m Tc generator in Japan has been imported, Japan Atomic Energy Commission (JAEC) suggested the necessity of establishment of stable supply chain of 99 Mo ( 99 Mo/ 99m Tc generator). According this suggestion, an ad hoc committee appointed to consider the stable supply chain, which consisted of persons concerned with industry, academic society, Japan Isotope Association, Ministry of Education, Culture, Sports, Science, and Technology-Japan (MEXT), Ministry of Health, Labour and Welfare (MHLW), Japan Atomic Energy Agency (JAEA), National Institute of Radiological Science (NIRS) et al., evaluated and compared several ways of production and purification of 99 Mo from the view point of technological maturity, regulation compatibility, economic suitability, and stability for supply. In this review, the summary of the committee report is introduced. For short term strategy, we need to keep the variable import routes for 99 Mo. As a mid-term goal, we need to establish the supply chain inside Japan as a conclusion of the committee report but it seems to be not easy for utility of nuclear reactor after nuclear accident of Fukushima Daiichi Nuclear Power Plant. The development of the method for 99 Mo/ 99m Tc production using accelerator is also expected for the establishment of stable supply chain. (author)

  6. Study of the viability of hydroxyapatite as matrix of the generator {sup 99} Mo/{sup 99m} Tc; Estudio de la viabilidad de la hidroxiapatita como matriz del generador {sup 99} Mo/{sup 99m} Tc

    Energy Technology Data Exchange (ETDEWEB)

    Aguilar D, I.C.; Badillo A, V.E. [UAZ, Unidad Academica de Ciencias Quimicas, 98600 Guadalupe, Zacatecas (Mexico); Monroy G, F. [ININ, A.P. 18-1027, 11801 Mexico D.F. (Mexico)]. E-mail: itzelaguilar@hotmail.com

    2004-07-01

    The generator more used in the nuclear medicine it is the generator {sup 99} Mo / {sup 99} Tc. The separation of {sup 99}Mo and {sup 99m}Tc in the commercial generator is carried out on a column that contains alumina (Al{sub 2}0{sub 3}). The adsorbent proposed in this investigation work, the hydroxyapatite, is an insoluble solid considered within of the fixers of anions more important. To evaluate the efficiency of the hydroxyapatite in the separation of the Mo and the Tc they were carried out preliminary tests to know the likeness of the one been accustomed to by the molybdate ions (MoO{sub 4}{sup -2}) and the pertechnetate ions (Tc0{sub 4}{sup -}) in function of the value of the p H, in a solution of CaCI{sub 2} 0.01 M. For the study of the retention of the molybdate ion, it was used the radioisotope Mo-99 fission product, and for the pertechnetate ion it was used the Tc- 99 m radionuclide son of the Mo-99. The obtained results in a solution of CaCl{sub 2} 0.01 M to different values of p H of the solution, show that the fixation of the pertechnetate ions (TcO{sub 4}{sup -}) and the fixation of the molybdate ions (MoO{sub 4}{sup -2}), they present very different behaviors in the hydroxyapatite. The results indicate that the synthetic hydroxyapatite BIO-RAD retains to the molybdate ion to values of lightly acid p H (5-6), being the retention of the pertechnetate practically worthless. (Author)

  7. Present status of Mo-99/Tc-99m generator in Thailand

    International Nuclear Information System (INIS)

    Khongpetch, Pranom

    2007-01-01

    Isotop Production Program, Office of Atoms for Peace had produced technetium-99m by MEK extraction of Mo-99 obtained from (n,γ) reaction in TRIGA Mark III reactor and supplied to nuclear medicine centers in Bangkok from 1980 to 1997. Because of the difficulty to meet the increased demand and limitation of reactor operation, the production of technetium-99m was stopped in 1997. Presently, there are 21 nuclear medicine centers with 25 SPECT, 7 gamma camera and 3 PET. All nuclear medicine centers are currently using imported Tc-99m generator. (author)

  8. Labeling capability of the eluent of gel-type 99Mo-99mTc generator

    International Nuclear Information System (INIS)

    Wu Xiuduo; Zhang Jingu

    1995-01-01

    The results of more than 7909 imaging of various organs which have been carried out on domestic gel-type 99 Mo- 99m Tc generators in the last seven years are presented. In all the 220 times of determination for the radiochemical purity of a portion of imaging agents, there were 15 times in which the labeling efficiency was lower than 90% and only 3 times in which the radiolabeling failed. In comparison with labeling capability of nuclear fission generators, it is showed that there are no evident differences between the eluent's labeling efficiency of the two kinds of generators

  9. {sup 99m}Tc generator preparation using (n, {gamma}){sup 99}Mo produced ex-natural molybdenum

    Energy Technology Data Exchange (ETDEWEB)

    Le, So Van [Nuclear Research Institute, Dalat (Viet Nam)

    2003-03-01

    Theoretical assessment on the chromatographic {sup 99m}Tc generator preparation using (n, {gamma}) {sup 99}Mo produced ex-natural molybdenum was carried out. The relationship between the neutron flux for MoO{sub 3} target activation, Mo-content or Mo adsorption capacity of column packing material, {sup 99m}Tc pertechnetate concentration and/or {sup 99m}Tc radioactivity of eluate was established. The reasonably lower limit of neutron flux of reactor and Molybdenum content of column packing material were found out to estimate the production of portable chromatographic generators available for nuclear medicine application. The concentration of {sup 99m}Tc pertechnetate eluate of low {sup 99m}Tc concentration using the column elution technique was also evaluate theoretically and conducted successfully in practice. Three options of {sup 99m}Tc generator using Titanium-Molybdate, Zirconium-Molybdate and Zirconium Oxide as generator column-packing materials were prepared and successfully put into use in nuclear medicine application. (author)

  10. Light-Induced Activation of a Molybdenum Oxotransferase Model within a Ru(II)-Mo(VI) Dyad.

    Science.gov (United States)

    Ducrot, Aurélien B; Coulson, Ben A; Perutz, Robin N; Duhme-Klair, Anne-Kathrin

    2016-12-19

    Nature uses molybdenum-containing enzymes to catalyze oxygen atom transfer (OAT) from water to organic substrates. In these enzymes, the two electrons that are released during the reaction are rapidly removed, one at a time, by spatially separated electron transfer units. Inspired by this design, a Ru(II)-Mo(VI) dyad was synthesized and characterized, with the aim of accelerating the rate-determining step in the cis-dioxo molybdenum-catalyzed OAT cycle, the transfer of an oxo ligand to triphenyl phosphine, via a photo-oxidation process. The dyad consists of a photoactive bis(bipyridyl)-phenanthroline ruthenium moiety that is covalently linked to a bioinspired cis-dioxo molybdenum thiosemicarbazone complex. The quantum yield and luminescence lifetimes of the dyad [Ru(bpy) 2 (L 2 )MoO 2 (solv)] 2+ were determined. The major component of the luminescence decay in MeCN solution (τ = 1149 ± 2 ns, 67%) corresponds closely to the lifetime of excited [Ru(bpy) 2 (phen-NH 2 )] 2+ , while the minor component (τ = 320 ± 1 ns, 31%) matches that of [Ru(bpy) 2 (H 2 -L 2 )] 2+ . In addition, the (spectro)electrochemical properties of the system were investigated. Catalytic tests showed that the dyad-catalyzed OAT from dimethyl sulfoxide to triphenyl phosphine proceeds significantly faster upon irradiation with visible light than in the dark. Methylviologen acts as a mediator in the photoredox cycle, but it is regenerated and hence only required in stoichiometric amounts with respect to the catalyst rather than sacrificial amounts. It is proposed that oxidative quenching of the photoexcited Ru unit, followed by intramolecular electron transfer, leads to the production of a reactive one-electron oxidized catalyst, which is not accessible by electrochemical methods. A significant, but less pronounced, rate enhancement was observed when an analogous bimolecular system was tested, indicating that intramolecular electron transfer between the photosensitizer and the catalytic center

  11. Study on the multiparticle states in the Zr, Mo and Ru isotopes with N=52-56

    International Nuclear Information System (INIS)

    Baktybaev, K.B.; Abel'dina, Zh.K.

    1978-01-01

    The many-particle states in isotopes of Zr, Mo, Ru with the number of neutrons N=(52-56) are studied. These states are considered as composed from the core-nucleus 88 Sr and outer nucleons. The analysis if performed in the framework of the generalized seniority approach. The generalized seniority of proton states is supposed to be zero. It turns out that the agreement between the calculated and experimental spectra worsens as the number of nucleons increases. It has been also found, that in Mo and Ru isotopes the gap between the ground states and the 2 1 + state decreases as the atomic weight increases, whereas the gap between the 2 1 + and 4 1 + states increases, approaching the sequence, typical for the purely collective vibration levels. In Zr isotopes the contribution of the collective excitations influences the positions of the levels only weakly. The γ-transition probabilities, the magnetic dipole and the electric quadrupole moments are calculated as well. Good agreement with the experimental data is observed. The results obtained are presented in the tabulated form

  12. Studies on treatment of low level radioactive liquid waste for removal of anionic species of 125Sb, 99Tc and 106Ru. Contributed Paper RD-14

    International Nuclear Information System (INIS)

    Shivakamy, K.; Chitra, S.; Rao, S.V.S.; Paul, Biplob

    2014-01-01

    The treatment of intermediate level waste at Waste Immobilization Plant generates low level radioactive waste which would require further management before discharge to sea. This waste is expected to contain polymeric oxo anions of 125 Sb, 99 Tc, 106 Ru in addition to cationic species like 137 Cs, 90 Sr etc. Chemical treatment takes care of the major contributors to radioactivity viz 137 Cs, 90 Sr etc but traces of activity due to anionic species remain in the treated waste effluent. Novel composite anionic exchanger namely Polyurethane foam coated with Hydrous Zirconium Oxide was developed for removal of these anionic species. This material was successfully employed for removal of anionic 1 25S b from radioactive waste effluent at Waste Management Division, Trombay. Based on our experience with Sb removal using the above material it was decided to assess the ability of the exchanger in removal of other anionic species bearing Ru and Tc. It was observed that in addition to complete removal of Sb, 50% Ru removal and 40% Tc could also be removed using this material from radioactive waste effluents. In lab experiments, similar results were obtained with simulated low level waste bearing inactive Ru. Among several hydrous oxides tried in a batch study, Hydrous Zirconium Oxide showed a maximum removal of 40% for Tc in actual waste generated from reprocessing plant. Based on the above it has been planned to set up an anion exchange column with Hydrous Zirconium Oxide coated Polyurethane foam for final treatment of chemically treated waste effluent prior to discharge as a prime step towards achieving our goal of minimum discharge to Sea. (author)

  13. Regeneration of 98Mo enriched from waste 99mTc generators

    International Nuclear Information System (INIS)

    Khujaev, S.; Mirzaeva, N.A.; Ashrapov, U.T.; Berdieva, M.; Nushtaeva, L.B.

    2002-01-01

    Radioisotope generator of technetium-99m have found widespread application in nuclear medicine for production of sodium pertechnetate solution ( 99m Tc). In technology of radioisotope generator making, which developed in Institute of Nuclear Physics of Uzbekistan Academy of Science the parent radioisotopes of molybdenum-90 are produced with neutron capture reaction of the enriched isotope of molybdenum-98 in nuclear reactor of WWR-SM. The specific activity of 99 Mo is reached to 5.0 Ci/g after activation process of original material ( 98 Mo). The basic mass of the original materials ( 98 Mo) which took for the irradiation is remained inactive. The high cost of enriched 97 Mo to make up necessity of development of method of 98 Mo regeneration with end in view of its recurring in manufacture. In general, the chromatographic type generator are produced in manufacture with aluminium oxide as sorbent for the parent radionuclides. So we studied the description conditions of molybdenum from aluminium oxide phase, its purification from possible accompanying admixtures and production of molybdenum in goods state. The systems: sulphur acid, ammonium and ammonium with hydrogen peroxide have been considered for molybdenum desorption from aluminium oxide phase. The sulphur oxid solution is most optimal medium for molybdenum desorption with concentration 0.5 M and elution rate for this makes up 2.0-2.05 ml/min. The 98 Mo yield makes up not over 87 %. The subsequent purification of the desorption of molybdenum-98 from the possible admixture are realized by using column with tetra-phosphonium alkali. At first , 98 Mo sorption is realized by anion exchange resin, after that sorbate is washing and dispiriting by solution with composition: 1.0 M NH 4 NO 3 +8.0 % NH 4 OH+10 -2 % H 2 O 2 . The 98 Mo yield makes up under 80 %. Further from obtained solution is realized by precipitation of molybdenum-98 in acid medium and separation of sediments from liquid phase, drying if sediments and

  14. Synthesis and irradiation of titanium molybdates used as matrices of the {sup 99} Mo/ {sup 99m} Tc generators; Sintesis e irradiacion de molibdatos de titanio utilizados como matrices de los generadores de {sup 99} Mo/ {sup 99m} Tc

    Energy Technology Data Exchange (ETDEWEB)

    Diaz V, H. [Facultad de Quimica, UAEM 50000 Toluca, Estado de Mexico (Mexico); Monroy G, F. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    2005-07-01

    The {sup 99m} Tc is the radioisotope but used in nuclear medicine. Commercially it takes place starting from generators of {sup 99} Mo/{sup 99m} Tc, composed by a chromatography column padded of aluminium oxide of aluminum, where it is deposited the {sup 99} Mo, product of the fission of the {sup 235} U adsorbed and eluted, by means of a saline solution, in form of {sup 99m} TcO{sub 4}{sup -}. The production of {sup 99} Mo as a result of the fission, imposes radiochemical separations that generate significant quantities of radioactive waste of medium activity, and inflict elaborated radiochemical manipulation. Due to this, its have been carried out intense investigations to substitute the {sup 99} Mo fission product, by chemical compounds that produce {sup 99} Mo via the reaction {sup 98} Mo(n, {gamma}){sup 99} Mo. Presently work intends the use of gels of titanium molybdates like matrices of these generators. Titanium molybdates were synthesized starting from solutions TiCl{sub 3} and ammonium molybdates and it was studied the effect of the final pH of the gels, the concentration of the Ti{sup +3} and the influence of the laundry of these on the acting of generators. The best efficiencies and chemical purity, radiochemical and radionuclides of the gels like matrices of generators {sup 99} Mo/{sup 99m} Tc were gotten with the washed gel, elaborated with the solution of TiCI{sub 3} 0.35M, and to a final pH of 5.9 (Author)

  15. The use of 99Mo/99mTc generators in the analysis of low levels of 99Tc in environmental samples by radiochemical methods

    International Nuclear Information System (INIS)

    Dowdall, M.; Selnaes, Oe.G.; Lind, B.; Gwynn, J.P.

    2010-01-01

    The analysis of low levels of 99 Tc in environmental samples presents special challenges, particularly with respect to the selection of an appropriate and practicable chemical yield tracer. Of all the tracers available, 99m Tc eluted from 99 Mo/ 99m Tc generators appears to be the most practicable in terms of availability, ease of use and cost. These factors have led to an increase in the use of such generators for the provision of 99m Tc as yield tracer for 99 Tc. For the analysis of low levels ( 3 or kg) of 99 Tc in environmental samples, consideration must be given to the radiochemical purity of the tracer solution with respect to contamination with both 99 Tc and other radionuclides. Due to the variable nature of the extent of the interference from tracer solution to tracer solution, it is unwise to try and establish a correction factor for any single generator. The only practical solution to the problem therefore is to run a 'blank' sample with each batch of samples drawn from a single tracer solution. (LN)

  16. Production of $^{99}$?? and $^{99m}$Tc in the $^{100}$Mo($\\gamma, n$) Photonuclear Reaction at the Electron Accelerator - MT-25 Microtron

    CERN Document Server

    Sabelnikov, A V; Gustova, M V; Dmitriev, S N

    2004-01-01

    $^{99}$Mo was obtained in the $^{100}$Mo($\\gamma, n$) reaction at the electron accelerator - MT-25 microtron of the LNR. A foil of $^{\\rm nat}$Mo(9.6{\\%} $^{100}$Mo) and $^{100}$MoO$_{3}$ powder (100{\\%} ^{100}$Mo) were used as targets. The $^{99}$Mo radiation yield under experimental conditions amounted to 3.2 kBq/$\\mu $A$\\cdot $h$\\cdot $mg of $^{100}$Mo. The $^{99m}$Tc isolation from the target material and other radioactive impurities was realized by means of ion exchange. A possibility of use of the $^{99}$Mo/$^{99m}$Tc generator based on molybdenumcarbonyl was investigated. The radioactive impurity content in the final $^{99m}$Tc preparations did not exceed 10$^{-5}$ Bq/Bq.

  17. Study of the elution {sup 99}Mo-{sup 99m}Tc generators produced at IPEN-CNEN/SP

    Energy Technology Data Exchange (ETDEWEB)

    Lopes, Paula Regina Corain [Pontificia Univ. Catolica de Sao Paulo, SP (Brazil); Instituto de Pesquisas Energeticas e Nucleares IPEN/CNEN-SP, Sao Paulo, SP (Brazil)]. E-mail: corain.lopes@uol.com.br; Osso Junior, Joao Alberto [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)]. E-mail: jaosso@ipen.br

    2007-07-01

    Over the last years {sup 99m}Tc has become a very important asset in modern nuclear medicine, due to the emission of gamma ray of optimal energy (140 keV) and a suitable half-life (6.04 h). A further attribute of {sup 99m}Tc is its formation from the decay of {sup 99}Mo and the availability from {sup 99}Mo-{sup 99m}Tc generator systems. The most common and practical generator types consist of a chromatographic column packed with aluminium oxide, onto which the highly purified fission product {sup 99}Mo (imported from Canada) is adsorbed in the form of molybdate. {sup 99m}Tc is further eluted with saline solution. The objective of this work is to study the performance and the elution profile of {sup 99m}Tc from high activity generators in order to decrease molybdenum and aluminium concentration. The experiments involved the use of paper filters and Sep Pak columns and also the changing in the time interval between elutions. {sup 99}Mo breakthrough was measured using a dose calibrator and aluminium by UV-Vis spectrophotometry. The best results were achieved using a Sep Pak column containing neutral aluminium oxide. (author)

  18. Study of the elution 99Mo-99mTc generators produced at IPEN-CNEN/SP

    International Nuclear Information System (INIS)

    Lopes, Paula Regina Corain; Osso Junior, Joao Alberto

    2007-01-01

    Over the last years 99m Tc has become a very important asset in modern nuclear medicine, due to the emission of gamma ray of optimal energy (140 keV) and a suitable half-life (6.04 h). A further attribute of 99m Tc is its formation from the decay of 99 Mo and the availability from 99 Mo- 99m Tc generator systems. The most common and practical generator types consist of a chromatographic column packed with aluminium oxide, onto which the highly purified fission product 99 Mo (imported from Canada) is adsorbed in the form of molybdate. 99m Tc is further eluted with saline solution. The objective of this work is to study the performance and the elution profile of 99m Tc from high activity generators in order to decrease molybdenum and aluminium concentration. The experiments involved the use of paper filters and Sep Pak columns and also the changing in the time interval between elutions. 99 Mo breakthrough was measured using a dose calibrator and aluminium by UV-Vis spectrophotometry. The best results were achieved using a Sep Pak column containing neutral aluminium oxide. (author)

  19. Silica-gel modified with zirconium oxide as a novel 99Mo adsorbent 99mTc generators

    International Nuclear Information System (INIS)

    Salehi, H.; Mollarazi, E.; Abbasi, H.

    2010-01-01

    A new 99 Mo adsorbent has been prepared with modified silica gel with zirconium oxide (SiO 2 /ZrO 2 :Na 2 MoO 4 ) and used in technetium-99m generator. The adsorption behaviors of 99 Mo in the form of molybdate and 99m Tc in the form of pertechnetate on the new adsorbent was investigated showed that the adsorption capacity of molybdate on this generator was considerably higher than the usual generator with alumina column. Coating zirconium oxide on the surface of silica gel resulted in higher 99 Mo adsorption of this compound. 99m Tc is eluted with 0.9% NaCl, and the radionuclidic, radiochemical and chemical purities of the eluate were checked. This generator has a great potential as compared to the traditional alumina generators.

  20. 99mTc by 99Mo produced at the ENEA-FNG facility of 14MeV neutrons.

    Science.gov (United States)

    Capogni, M; Pietropaolo, A; Quintieri, L; Fazio, A; De Felice, P; Pillon, M; Pizzuto, A

    2018-04-01

    A severe supply crisis of 99 Mo, precursor of 99m Tc a diagnostic radionuclide largely used in Nuclear Medicine, occurred in 2008-2009 due to repeated shut-down of the two main (aged) fission reactors. An alternative route for producing 99 Mo by 100 Mo(n,2n) 99 Mo reaction was investigated at ENEA. The experiment, designed according to Monte Carlo simulations performed with the Fluka code, produced 99 Mo by irradiating a natural Molybdenum powdered target with 14MeV neutrons produced at the Frascati Neutron Generator. The 99 Mo specific activity was measured at metrological level by γ-ray spectrometry. Copyright © 2017 Elsevier Ltd. All rights reserved.

  1. Determination of 99Mo contamination in a nuclear medicine patient submitted to a diagnostic procedure with 99mTc

    Directory of Open Access Journals (Sweden)

    Bernardo Maranhão Dantas

    2005-10-01

    Full Text Available 99mTc is a radionuclide widely used for imaging diagnosis in nuclear medicine. In Brazil it is obtained by elution from 99Mo-99mTc generators supplied by the Nuclear Energy Research Institute (IPEN. The elution is carried out in radiopharmacy laboratories located in hospitals and clinics. Depending of the quality of the generator and conditions of use during the elution process, 99Mo can be extracted from the column of the generator, becoming a radionuclidic impurity of the eluate used for the obtention of the radiopharmaceutical to be administered to the patient. 99Mo emits high-energy photons and beta particles and its presence degrades the quality of the image and unnecessarily increases the radiation dose delivered to the patient. An in-vivo measurement technique was developed to verify the occurrence of internal contamination by 99Mo in nuclear medicine patients. Direct measurements were made in a volunteer who underwent myocardial scintigraphy with 99mTc-sestamibi. The results indicated the presence of internal contamination of the patien by 99Mot. The activity was tracked for several days, and an assessment of the radiation dose from the contaminant 99Mo was made.O 99mTc é um radionuclídeo largamente utilizado em diagnósticos por imagem em medicina nuclear. No Brasil, ele é obtido por eluição de um gerador de 99Mo-99mTc fornecido pelo IPEN. A eluição do gerador é feita nas clínicas onde se realizam os exames. Durante a eluição o 99Mo pode ser carreado da coluna, tornando-se uma impureza radionuclídica do eluato a ser utilizado para a obtenção do radiofármaco administrado ao paciente. O 99Mo emite fótons de alta energia e partículas beta, e sua presença, além de provocar degradação na qualidade da imagem do exame, aumenta desnecessariamente a dose de radiação no paciente. Assim, com o objetivo de verificar a possível ocorrência de contaminação interna por 99Mo em pacientes de medicina nuclear, foi desenvolvida

  2. Optimization of the {sup 99m} Tc generator with hydrotalcite as support of {sup 99} Mo; Optimizacion del generador de {sup 99m} Tc con hidrotalcita como soporte del {sup 99} Mo

    Energy Technology Data Exchange (ETDEWEB)

    Aranda O, N

    2004-07-01

    In the last years, in the laboratories of the National Institute of Nuclear Investigations (ININ) its have been investigating to the hydrotalcite like a material of support of the {sup 99} Mo with the purpose of developing a new technetium generator. During the development of the investigations it has been demonstrated that when putting in contact to the HTC with an aqueous solution that contains anions of any type, the HTC re hydrate and the structure is regenerated to laminate of the hydrotalcite. If the present anions in the solution are molybdate anions (MoO{sub 4}{sup 2-}), these anions passed to be part of the structure of the hydrotalcite (HT-MoO{sub 4}). These anions can contain, in turn, {sup 99} Mo in their composition ({sup 99}MoO{sub 4}{sup 2-}) and equally they can pass to be part of the structure of the hydrotalcite forming the HT-{sup 99}MoO{sub 4}. When the HT-{sup 99}MoO{sub 4} is packed in a column, the {sup 99m}Tc that it takes place when decaying the {sup 99}Mo radioactively can separate the column using aqueous solution of NaCl. This way, in previous studies (Serrano, 2000) it was found that the aqueous solution of NaCl to 0.5% it is the but appropriate for elutriate at the {sup 99m}Tc from the column the yield of the elution of the {sup 99m}Tc was since high (98%) in the first elution, and the radionuclide contamination caused by the presence of {sup 99}Mo in the eluate it was low (<0.01%). In this investigation it was also found that the HTC has a high capacity to retain molybdate ions (255.1 mg of ions MoO{sub 4}{sup 2-} for gram of HTC). These facts, standing out the high capacity of the HTC to retain molybdate ions, they drove from a direct way to investigate the optimization of the generator of {sup 99m}Tc, with hydrotalcite like support of the {sup 99}Mo, using {sup 99}Mo of low specific activity. This finishes radioactive material it can be obtained by the irradiation of the {sup 98}Mo (in the chemical form of MoO{sub 3} or (NH{sub 4

  3. Performance tests on new chromatographic material for 99Mo-99mTc generators

    International Nuclear Information System (INIS)

    Sombrito, Elvira Z.; Bulos, Adelina D.M.

    2004-01-01

    Technetium-99m continues to be the main workhorse of nuclear medicine in the Philippines. Almost 13TBq of 99m Tc was imported to the country in 2002 supplied as 99m Tc- 99 Mo generators. These generators make use of fission molybdenum adsorbed onto an alumina column. Problems associated with the alumina chromatographic generators arise due to safety and economic issues that would be remedied by gel-type generators using low specific activity reactor-produced molybdenum-99 adsorbed on a high capacity gel column material. The Philippine Nuclear Research Institute (PNRI) exerted efforts in this direction by developing a gel-type column, which showed satisfactory molybdenum adsorptive capacity. Likewise, Kaken Co. in Japan in cooperation with Japan Atomic Energy Research Institute (JAERI) developed a dried form of a gel-type polyzirconium compound (PZC). It is a ready-to-use high molybdenum capacity column material for adsorbing reactor-produced molybedum-99. The performance of this material is being tested under the framework of the FNCA project on Research Reactor Utilization. Performance tests on four batches of PZC were performed using fission molybdenum eluted from a 99 Mo- 99m Tc generator. A total of 3.3 GBq 99 Mo was extracted from an alumina column of a commercial generator and mixed with carrier molybdenum solution. About 0.67 GBq was loaded into each of the 12 x 90 mm column. One batch was prepared and distributed in 1999 and tests showed very poor elution yield of 30%. Three recent batches of PZC (2002) gave elution yields of 71% (Range of 69-75). The adsorptive capacity is 99% with about 4% desorption rate. Elution volume is at 5-6 ml. Daily elution for five days gave from 1.6 to 5.5% variability. The tests were performed all at the same time and a trend of improving elution yield and consistency of daily elution yield was observed with the time of testing nearer to the sample preparation date. X-ray diffraction analysis showed an amorphous structure for

  4. Preparation of a sup(99m) Tc generator for use in nuclear medicine, using calcinated (10000C) alumina as an adsorber for 99Mo

    International Nuclear Information System (INIS)

    Gasiglia, H.T.; Enoshita, M.

    1980-12-01

    The preparation of 99 sup(m) Tc generator using calcinated (1000 0 C) alumina as adsorber for 99 Mo is described. The adsorption of 99 Mo and the elution of 99 sup(m) Tc were studied. When the generator is autoclaved (30 minutes, 121 0 C), after the loading of 99 Mo, elution yields of 99 sup(m) Tc fall to the half if compared whith generators not autoclaved. However, by autoclaving 99 Mo loading solution and alumina column separately and than preparing the generator, 80% elution yields of 99 sup(m) Tc were obtained. The contamination of the generator by microorganism is avoided when the loading of the 99 Mo is carried out in a hot-cell under UV ligth. The radioactive, radiochemical, chemical and microbiological purity criteria were examined for 99 sup(m) Tc solutions. The generator is considered safe for medical purposes. (Author) [pt

  5. Hydrogenation of naphthalene on NiMo- Ni- and Ru/Al{sub 2}O{sub 3} catalysts. Langmuir-Hinshelwood kinetic modelling

    Energy Technology Data Exchange (ETDEWEB)

    Monteiro-Gezork, Ana Cristina Alves; Winterbottom, John Mike [Department of Chemical Engineering, School of Engineering, The University of Birmingham, Birmingham B15 2TT (United Kingdom); Natividad, Reyna [Department of Chemical Engineering, Faculty of Chemistry, Universidad Autonoma del Estado de Mexico, Paseo Colon Esq. Tollocan, Toluca, Edo. de Mexico, Mexico CP 50120 (Mexico)

    2008-01-30

    The importance of the hydrodearomatisation (HDA) is increasing together with tightening legislation of fuel quality and exhaust emissions. The present study focuses on hydrogenation (HYD) kinetics of the model aromatic compound naphthalene, found in typical diesel fraction, in n-hexadecane over a NiMo (nickel molybdenum), Ni (nickel) and Ru (ruthenium) supported on trilobe alumina (Al{sub 2}O{sub 3}) catalysts. Kinetic reaction expressions based on the mechanistic Langmuir-Hinshelwood (L-H) model were derived and tested by regressing the experimental data that translated the effect of both naphthalene and hydrogen concentration at a constant temperature (523.15 and 573.15 K over the NiMo catalyst and at 373.15 K over the Ni and Ru/Al{sub 2}O{sub 3} catalysts) on the initial reaction rate. The L-H equation, giving an adequate fit to the experimental data with physically meaningful parameters, suggested a competitive adsorption between hydrogen and naphthalene over the presulphided NiMo catalyst and a non-competitive adsorption between these two reactants over the prereduced Ni and Ru/Al{sub 2}O{sub 3} catalysts. In addition, the adsorption constant values indicated that the prereduced Ru catalyst was a much more active catalyst towards naphthalene HYD than the prereduced Ni/Al{sub 2}O{sub 3} or the presulphided NiMo/Al{sub 2}O{sub 3} catalyst. (author)

  6. Study of gels of molybdenum with cerium in the preparation of generators of 99Mo-99mTc

    International Nuclear Information System (INIS)

    Moraes, Vanessa; Marczewski, Barbara; Dias, Carla Roberta; Osso Junior, Joao Alberto

    2005-01-01

    99m Tc has ideal nuclear properties for organ imaging in nuclear medicine, and it is obtained from the 99 Mo- 99m Tc generator. Four different types of generators are available: chromatographic that uses 99 Mo from fission of uranium; MEK solvent extraction; Tc 2 O 7 sublimation; gel chromatographic. This work presents the preparation of gel generators of molybdenum with cerium and characterization of the gels: mass ratio between molybdenum and cerium, structure, size of particles and elution percentage of 99m Tc after irradiating the gels. Eight gels were prepared at the same temperature of 50 deg C with concentrations of NaOH of 2 and 4 mol/L, mass ratio of 0.31 and 0.38 and final pH of 3.5 and 4.5. The analysis of the results proved that these gels are not adequate for preparation of the generators of 99 Mo- 99m Tc, since the elution percentages are low, when compared with the gel of molybdenum with zirconium.(author)

  7. Microscopic structure of a new type of collective excitation in odd-mass Mo, Ru, I, Cs and La isotopes

    International Nuclear Information System (INIS)

    Kuriyama, Atsushi; Okamoto, Ryoji; Marumori, Toshio; Matsuyanagi, Kenichi.

    1975-01-01

    With the aid of microscopic theory of collective excitations in spherical odd-mass nuclei proposed by Kuriyama, Marumori and Matsuyanagi, structures of low-lying collective 5/2 + states in odd-mass I, Cs and La isotopes and of collective 3/2 + states in odd-mass Mo and Ru isotopes are investigated. These collective 5/2 + and 3/2 + states, which are hard to understand within the framework of the conventional quasi-particle-phonon-coupling theory, are identified as a new kind of fermion-type collective excitation mode. The change in microscopic structure of these states depending on the mass number is also investigated in relation with the shell structure. (auth.)

  8. Influence of the electrolyte in the fixation of 99 Mo in hydroxyapatite as matrix of the 99 Mo/ 99m Tc generator

    International Nuclear Information System (INIS)

    Vazquez G, S.; Badillo A, V.E.; Monroy G, F.

    2005-01-01

    The more used isotope at the moment in the services of nuclear medicine in the world is the technetium-99m. The 99m Tc emitts gamma rays of 141 keV and it semi disintegration period is of six hours, given it short half life, to produce it is necessary to order generators that are systems that allow to separate periodically at the 99m Tc of the 99 Mo by means of chromatographic techniques. In this work it is sought to evaluate the use of the hydroxyapatite, to separate molybdates 99 MoO 4 2 of pertechnetates 99m TcO 4 - and to be able to determine if it is feasible their use for to build generators of 99m Tc. With this purpose preliminary tests to know the likeness of the hydroxyapatite for the molybdates in function of the pH value, in different solutions were carried out: one of NaCl 0.9%, NaCl 2% and CaCl 2 0.01 M. The obtained results in a NaCl 0.9% solution and at to 2% to different pH values of the solution, shows that the fixation of the molybdate ions (MoO 4 -2 ) it is worthless to basic pH values of (9-11), as long as in solution of CaCI 2 0.01 M show a considerable retention of molybdate ions. (Author)

  9. Preparation of clinical-scale 99Mo/99mTc column generator using neutron activated low specific activity 99Mo and nanocrystalline γ-Al2O3 as column matrix.

    Science.gov (United States)

    Chakravarty, Rubel; Ram, Ramu; Dash, Ashutosh; Pillai, M R A

    2012-10-01

    Preparation of clinical-scale (99)Mo/(99m)Tc generator using (n,γ) activated low specific activity (99)Mo and nanocrystalline γ-Al(2)O(3) as a high capacity sorbent matrix is attempted. Nanocrystalline γ-Al(2)O(3) was synthesized by 'solid state mechanochemical' reaction of aluminum nitrate with ammonium bicarbonate. Experimental parameters were optimized to effectively separate (99m)Tc from (99)Mo using this sorbent as the column matrix. The performance features of a 13 GBq (350 mCi) (99)Mo/(99m)Tc generator using this sorbent and (99)Mo produced by (n,γ) route having specific activity 12.9-18.5 GBq/g were evaluated for 10 days. The sorbent possessed the requisite selectivity for (99)Mo and demonstrated a maximum sorption capacity of 200 ± 5mg Mo/g, which is ~10 times higher than that of ordinary acidic alumina. The overall yield of (99m)Tc was >80%, with radionuclidic purity >99.99% and radiochemical purity >99%. The yield of (99m)Tc varied from 7.8 to 2.1 GBq in the eluate for the six days of operation of the generator. The radioactive concentration of (99m)Tc eluted was adequate for the formulation of radiopharmaceuticals. The performance of the generator remained consistent over an extended period of 10 days. The eluted (99m)Tc was suitable for the formulation of (99m)Tc-DMSA and (99m)Tc-EC resulting in high radiolabeling yields (>98%). The effectiveness of γ-Al(2)O(3) as a new generation sorbent in the development of clinically useful (99)Mo/(99m)Tc generator using low specific activity (99)Mo and yielding (99m)Tc with adequate radioactive concentration and high purity suitable for formulation of radiopharmaceuticals is demonstrated. Copyright © 2012 Elsevier Inc. All rights reserved.

  10. Solvent extraction technology of 90Mo-sup(99m)Tc system: design and operational considerations

    International Nuclear Information System (INIS)

    Noronha, O.P.D.; Sewatkar, A.B.

    1983-01-01

    The design features of 99 Mo-sup(99m)Tc solvent extraction system have been reviewed. An improved semi-automated system has been improvised using the basic equipment of an indigenous unit along with other accessories, and with an added element of radiation protection to handle daily about 300-600 millicurie amounts of reactor-produced very low specific activity 99 Mo. The system has been used routinely for obtaining sup(99m)TcO 4 - - required for diagnostic purposes in nuclear medicine for the last twelve years. The performance characteristics of this unit with respect to yield and purity of 99 TcO 4 - - consistency of the process, the radiation dose to personnel and related health physics aspects have been evaluated. (author)

  11. A draft business plan for the production of PZC 99Mo-99mTc generator in the Philippines

    International Nuclear Information System (INIS)

    Sombrito, Elvira Z.; Cabalfin, Estelita G.; Calix, Virginia S.; Dela Rosa, Alumanda M.; Borras, Ma. Teresa L.; Bulos, Adelina dM.

    2007-01-01

    Technetium-99m ( 99m Tc) remains as the main workhorse of nuclear medicine in the country. Alone or conjugated with other ligands, it is being used to show the function of major organs and other tissues such as the lung, brain, kidney, liver and bone. It is imported to the country as 99 Mo- 99m Tc generator. These commercial generators use fission molybdenum adsorbed onto alumina column. The FNCA project has shown the feasibility of using a PZC column-reactor 99 Mo generator for commercial applications, citing mainly the cheaper cost of the PZC generator than the imported alumina column-fission 99 Mo generator. PNRI proposes in this draft business plan, the commercial production of PZC generator through the establishment of a facility for the in-house production of 99 Mo- 99m Tc generator. The generator will use PZC coming from Japan as the column material, 99 Mo sourced from neighboring countries and an automatic loading and adsorption machine. Because the PNRI has no local production of the generator, the requirements for successfully venturing into this business activity may differ from the other FNCA members. A careful assessment based on verified data will be needed to refine the business plan. (author)

  12. Generator of {sup 99m} Tc with MnO{sub 2} as support of {sup 99} Mo; Generador de {sup 99m} Tc con MnO{sub 2} como soporte del {sup 99}Mo

    Energy Technology Data Exchange (ETDEWEB)

    Granados C, F.; Serrano G, J. [Departamento de Quimica, Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    2002-07-01

    The generator of {sup 99m} Tc with MnO{sub 2} as support of {sup 99} Mo was studied. By mean of static experiments the retention of {sup 99} Mo in MnO{sub 2} in function of the stirring time and of the p H value of the solution of {sup 99} Mo. It was found that the {sup 99} Mo presents 100% of retention in MnO{sub 2} in the rank of p H 3-11 and the balance was reached before of 10 minutes. In dynamic conditions the retention of {sup 99} Mo in MnO{sub 2} at p H=5 was also higher: 99.72%. The generated {sup 99m} Tc can be separated from {sup 99} Mo, adsorbed in MnO{sub 2} packed in the column, using distilled water at p H=5 or NaCl solution at 0.9%. With saline solution the elution yields were greater than 80% and only an aliquot of 5 ml was necessary for obtaining this yield. The better results were obtained when the column was packed with 1 g of MnO{sub 2}. The water and the saline solution were passed through of the column with a flux of 1.25 ml/min. (Author)

  13. A comparison of rat SPECT images obtained using 99mTc derived from 99Mo produced by an electron accelerator with that from a reactor

    International Nuclear Information System (INIS)

    Galea, R; Ross, C K; Moore, K; Wells, R G; Lockwood, J; Harvey, J T; Isensee, G H

    2013-01-01

    Recent shortages of molybdenum-99 ( 99 Mo) have led to an examination of alternate production methods that could contribute to a more robust supply. An electron accelerator and the photoneutron reaction were used to produce 99 Mo from which technetium-99m ( 99m Tc) is extracted. SPECT images of rat anatomy obtained using the accelerator-produced 99m Tc with those obtained using 99m Tc from a commercial generator were compared. Disks of 100 Mo were irradiated with x-rays produced by a 35 MeV electron beam to generate about 1110 MBq (30 mCi) of 99 Mo per disk. After target dissolution, a NorthStar ARSII unit was used to separate the 99m Tc, which was subsequently used to tag pharmaceuticals suitable for cardiac and bone imaging. SPECT images were acquired for three rats and compared to images for the same three rats obtained using 99m Tc from a standard reactor 99 Mo generator. The efficiency of 99 Mo– 99m Tc separation was typically greater than 90%. This study demonstrated the delivery of 99m Tc from the end of beam to the end user of approximately 30 h. Images obtained using the heart and bone scanning agents using reactor and linac-produced 99m Tc were comparable. High-power electron accelerators are an attractive option for producing 99 Mo on a national scale. (paper)

  14. A new inorganic adsorbent of (n, {gamma}){sup 99}Mo for the practical {sup 99m}Tc generator

    Energy Technology Data Exchange (ETDEWEB)

    Hasegawa, Y; Nishino, M [Kaken Co., Asahi, Ibaraki (Japan). Functional Materials Inst.; Ishikawa, K; Tatenuma, K; Kurosawa, K; Tanase, M; Yamabayashi, H

    1998-10-01

    Technetium-99m is used most widely in diagnostic nuclear medicine. By the milking procedure, it is normally eluted as the daughter nuclide from {sup 99}Mo adsorbed in an alumina column as a generator. Molybdenum-99 with high specific activity has been produced in large quantities from the fission of irradiated {sup 235}U. However, the production process involves the troublesome handling process of various fission products in the high radiation field and generates highly radioactive and poisonous wastes. To avoid these drawbacks, some gel generators have been proposed. They are of zirconium molybdate, zirconium molybdophosphate or titanium molybdate gel, which are able to be applied to {sup 99}Mo obtained easily by (n, {gamma}) reaction of natural Mo. However, it has become apparent that the gel has been prepared only under certain strict conditions such as concentrations and reaction temperature, and eventually the elution rate of {sup 99m}Tc was unstable because of any influences of the gel preparation conditions. We have developed and reported a new inorganic adsorbent (Polyinorganic Zirconium Compound: PZC) of {sup 99}Mo with a low specific activity obtained by (n, {gamma}) reaction to overcome the problems of gel generators above mentioned. PZC was prepared from ZrCl{sub 4} and isopropyl alcohol. The adsorbed amount of {sup 99}Mo (Mo) to PZC was about 200 mg/g-PZC, and the yield of {sup 99m}Tc was about 80%. And the breakthrough of {sup 99}Mo was less than 0.5%. In this paper, the properties of the improved PZC, performance of generators with {sup 99}Mo loaded from 0.5 to 470 MBq, and a method to reduce the breakthrough of {sup 99}Mo are described. (author)

  15. A re-examination of thermodynamic modelling of U-Ru binary phase diagram

    Energy Technology Data Exchange (ETDEWEB)

    Wang, L.C.; Kaye, M.H., E-mail: matthew.kaye@uoit.ca [University of Ontario Institute of Technology, Oshawa, ON (Canada)

    2015-07-01

    Ruthenium (Ru) is one of the more abundant fission products (FPs) both in fast breeder reactors and thermal reactors. Post irradiation examinations (PIE) show that both 'the white metallic phase' (MoTc-Ru-Rh-Pd) and 'the other metallic phase' (U(Pd-Rh-Ru)3) are present in spent nuclear fuels. To describe this quaternary system, binary subsystems of uranium (U) with Pd, Rh, and Ru are necessary. Presently, only the U-Ru system has been thermodynamically described but with some problems. As part of research on U-Ru-Rh-Pd quaternary system, an improved consistent thermodynamic model describing the U-Ru binary phase diagram has been obtained. (author)

  16. A simple and rapid technique for recovery of 99mTc from low specific activity (n,γ)99Mo based on solid-liquid extraction and column chromatography methodologies

    International Nuclear Information System (INIS)

    Chattopadhyay, Sankha; Das, Sujata Saha; Barua, Luna

    2010-01-01

    A simple and inexpensive method has been developed for the separation of 99m Tc from 99 Mo produced from the neutron activation of 98 Mo by 98 Mo(n,γ) 99 Mo nuclear reaction. The recovery of 99m Tc was performed by solid-liquid extraction based on alumina column chromatography. The overall radiochemical yield for the complete separation of 99m Tc was 85-97% (n=5). The separated Na[ 99m Tc]TcO 4 was of high radionuclidic, radiochemical and chemical purities. The method can be adopted for routine processing and use of 99m Tc in radiopharmacy operations.

  17. Performance study of molybdenum gels with titanium for preparation of 99Mo-99mTc generators

    International Nuclear Information System (INIS)

    Moraes, Vanessa; Osso Junior, Joao Alberto

    2005-01-01

    99m Tc is the most used radioisotope in Nuclear Medicine, due to nuclear characteristics. It is obtained by the radioactive decay of 99 Mo, generator of radioisotope system. When 99 Mo is produced by the activation in reactor, the most used technique for the preparation of the generators is the gel type generator, which incorporates 99 Mo to the gel that is insoluble, chemically inert to the solutions and with properties of ion exchange. Several countries had already studied this methodology, as is the case of Vietnam, India, China, Australian. This work has the objective of studying the performance and characterization of molybdenum gels with titanium. Four variables in the preparation of the gel were studied: mass ratio between Mo and Ti (1.80 and 2.25), concentration of NaOH (2 and 4 mol/L), final temperature (25 and 50 deg C) and pH (3.5 and 4.5). The prepared gels were analyzed with relation to the size of its particles, identification of its structure, amount of molybdenum, amount of titanium, profile of elution, pH of the elution, determination of the radioisotopes in the eluate and final radiochemical purity. The final result is a formularization of the gel with the best characteristics for posterior preparation of the generator of 99m Tc- 99 Mo. (author)

  18. Evaluation of '9{sup 9}Mo presence in eluates of {sup 99}mTc used in nuclear medicine; Avaliacao da presenca de {sup 99}Mo em eluatos de {sup 99m}Tc utilizados em medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Ribeiro, Bianca da Silva

    2010-07-01

    Tc-99m is used for diagnostic imaging in nuclear medicine through SPECT technique. It is obtained by the elution of {sup 99}Mo/{sup 99m}Tc generators. During the elution process {sup 99}Mo can be extracted becoming a radionuclidic impurity. One of the quality parameters of the eluate is the radionuclidic purity, MBT (molybdenum break through), defined as the ratio between {sup 99}Mo and {sup 99m}Tc activities in the eluate. The North-American and European pharmacopoeias restrict the {sup 99}Mo content, respectively, in 0.015 e 0.1% and, according to the International Atomic Energy Agency (IAEA), the activity ratio at the moment of administration of the radiopharmaceutical to the patient, should not exceed 0.015%. In Brazil, the control of such parameter is not obliged in official regulations. Thus, the objective of this work is to evaluate the occurrence of {sup 99}Mo in {sup 99m}Tc eluates. It was initially optimized a methodology to determine the activity of {sup 99}Mo in eluate samples. Efficiency curves were obtained for a NaI (Tl) 8'' x 4'' scintillation detector installed at the In Vivo Monitoring Laboratory (LABMIV-IRD). The methodology has been validated through the measurement of a {sup 99}Mo standard liquid source calibrated at the National Metrology Laboratory for Ionizing Radiation (LNMRI-IRD). The samples analyzed in this work were gently supplied by 5 Nuclear Medicine Clinics located in the city of Rio de Janeiro. The activities of {sup 99}mTc and {sup 99}Mo in those samples have been measured respectively at the clinics and at the LABMIV. By applying a standardized methodology, the ration between the activities were calculated. The results show that 147 out of 174 samples presented {sup 99}Mo activities above the minimum detectable activity of the technique. On the other hand, only 2 out of 147 samples surpassed the MBT limit suggested by the IAEA and have been detected in samples eluted from generators of 750 mCi. In one of the

  19. Evaluation of highly loaded low specific activity 99Mo on alumina column as 99mTc generator

    International Nuclear Information System (INIS)

    Asif, M.; Mushtaq, A.

    2010-01-01

    Adsorption behavior of molybdate on acidic alumina was studied at boiling water bath temperature (∼100 deg C). Various parameters affecting the adsorption of molybdenum, such as pH, amount of molybdenum, incubation period, etc., were determined. A 99m Tc generator was prepared by adsorbing low specific activity 99 Mo (150 mg) on 1 g alumina. Elutions were carried out with saline. Performance of the generator such as 99 Mo breakthrough, aluminum contents, pH, elution profile, radiochemical purity, and labeling efficiency of kits were checked. (author)

  20. Design of an X -band electron linear accelerator dedicated to decentralized 99Mo/99mTc supply: From beam energy selection to yield estimation

    Science.gov (United States)

    Jang, Jaewoong; Yamamoto, Masashi; Uesaka, Mitsuru

    2017-10-01

    The most frequently used radionuclide in diagnostic nuclear medicine, 99mTc, is generally obtained by the decay of its parent radionuclide, 99Mo. Recently, concerns have been raised over shortages of 99Mo/99mTc, owing to aging of the research reactors which have been supplying practically all of the global demand for 99Mo in a centralized fashion. In an effort to prevent such 99Mo/99mTc supply disruption and, furthermore, to ameliorate the underlying instability of the centralized 99Mo/99mTc supply chain, we designed an X -band electron linear accelerator which can be distributed over multiple regions, whereby 99Mo/99mTc can be supplied with improved accessibility. The electron beam energy was designed to be 35 MeV, at which an average beam power of 9.1 kW was calculated by the following beam dynamics analysis. Subsequent radioactivity modeling suggests that 11 of the designed electron linear accelerators can realize self-sufficiency of 99Mo/99mTc in Japan.

  1. Design of an X-band electron linear accelerator dedicated to decentralized ^{99}Mo/^{99m}Tc supply: From beam energy selection to yield estimation

    Directory of Open Access Journals (Sweden)

    Jaewoong Jang

    2017-10-01

    Full Text Available The most frequently used radionuclide in diagnostic nuclear medicine, ^{99m}Tc, is generally obtained by the decay of its parent radionuclide, ^{99}Mo. Recently, concerns have been raised over shortages of ^{99}Mo/^{99m}Tc, owing to aging of the research reactors which have been supplying practically all of the global demand for ^{99}Mo in a centralized fashion. In an effort to prevent such ^{99}Mo/^{99m}Tc supply disruption and, furthermore, to ameliorate the underlying instability of the centralized ^{99}Mo/^{99m}Tc supply chain, we designed an X-band electron linear accelerator which can be distributed over multiple regions, whereby ^{99}Mo/^{99m}Tc can be supplied with improved accessibility. The electron beam energy was designed to be 35 MeV, at which an average beam power of 9.1 kW was calculated by the following beam dynamics analysis. Subsequent radioactivity modeling suggests that 11 of the designed electron linear accelerators can realize self-sufficiency of ^{99}Mo/^{99m}Tc in Japan.

  2. Measurements of activation cross-sections for the 101Ru(n,p)101Tc reaction for neutrons with energies between 13 and 15 MeV

    International Nuclear Information System (INIS)

    Junhua Luo; Peking University, Beijing; Jiuning Han; Suhong Ge; Zhenlai Liu; Guihua Sun; Rong Liu; Li Jiang

    2013-01-01

    In this study, activation cross-sections were measured for the 101 Ru(n,p) 101 Tc reaction at three different neutron energies from 13.5 to 14.8 MeV. The fast neutrons were produced via the 3 H(d,n) 4 He reaction on K-400 neutron generator. Induced gamma activities were measured by a high-resolution gamma-ray spectrometer with high-purity germanium detector. Measurements were corrected for gamma-ray attenuations, random coincidence (pile-up), dead time and fluctuation of neutron flux. The data for 101 Ru(n,p) 101 Tc reaction cross-sections are reported to be 15.7 ± 2.0, 18.4 ± 2.7 and 22.0 ± 2.4 mb at 13.5 ± 0.2, 14.1 ± 0.2, and 14.8 ± 0.2 MeV incident neutron energies, respectively. Results were compared with the previous works. (author)

  3. The preparation of {sup 99m}Tc from {sup 99}Mo-{sup 99m}Tc using Poly-Zirconium Compound (PZC)

    Energy Technology Data Exchange (ETDEWEB)

    Laohawilai, S [Isotope Production Div., Office of Atomic Energy for Peace (Thailand)

    1998-10-01

    The process of for providing the {sup 99m}Tc-gel generator followed the protocol that received from Department of Radioisotopes, Tokai Research Establishment, JAERI. Sodium molybdate (molybdenum-99), pH 7 with concentration 20 mg/ml and activity nearly 1 mCi/ml was added into the adsorbent (PZC). The total activity of {sup 99}Mo was about 10 mCi and the heating time was varied from 3-18 hours at 70degC. The properties of the gel were studied for elution profile and elution efficiency. The molybdenum breakthrough in sodium pertechnetate (technetium-99m) was also performed. (author)

  4. The Use of Sodium Hypochlorite Solution for (n,γ99Mo/99mTc Generator Based on Zirconium-Based Material (ZBM

    Directory of Open Access Journals (Sweden)

    I. Saptiama

    2015-08-01

    Full Text Available The many problems in preparing fission product 99Mo led into this work to develop 99Mo/99mTc generator using neutron-irradiated natural MoO3 targets and, more specifically, to develop a zirconium-based material (ZBM for chromatography columns that have an adsorption capacity of more than 100 mg Mo/g ZBM. This paper reports our recent experiments in the use of sodium hypochlorite solution of various concentrations to improve the yield of 99mTc in performance of (n,γ99Mo/99mTc generators based on the ZBM. The synthesized ZBM was coated with tetraethyl orthosilicate for improving the hardness of the material. The adsorption of [99Mo]molybdate into ZBM was carried out by reacting ZBM into [99Mo]molybdate solution at 90°C to form ZBM-[99Mo] molybdate. ZBM-[99Mo]molybdate was then packed into generator column, then eluted with 10 × 1 mL of saline followed by 1 × 5 mL of NaOCl solution. The NaOCl solution concentrations used were 0.5%; 1%; 3%; and 5% for each column, respectively. This study resulted in a ZBM which has a 99Mo adsorption capacity of 167.5 ± 3.4 mgMo/g ZBM, as well as in a yield eluate of 99mTc of up to 70%, and the find that the optimum NaOCl concentration was 3%. The use of sodium hypochlorite solution affected 99Mo breakthrough. The higher sodium hypochlorite concentration used, the more 99Mo breaktrough exist on 99mTc eluate.

  5. Neutron Activation Resonance Integrals of 64Zn, 68Zn, 85Rb, 100Mo, 102Ru, 113In, 123Sb, and 180Hf

    International Nuclear Information System (INIS)

    Ricabarra, M. D.; Turjanski, R.; Ricabarra, G. H.

    1969-01-01

    The ratio of resonance integral to thermal activation cross sections of the isotopes 64 Zn, 68 Zn, 85 Rb, 100 Mo, 102 Ru, 113 In, 123 Sb, and 180 Hf relative to gold has been determined by measuring cadmium ratios. The standard gold or a secondary standard was mixed uniformly in the samples and the activities resolved with a lithium-drift germanium γ-ray spectrometer. Expressed as Westcott S 0 values the results were: 64 Zn = 2.06 ± 0.03, 68 Zn = 3.72 ± 0.14, 85 Rb = 18.4 ± 0.6, 100 Mo = 21.7 ± 0.8, 102 Ru = 3.76 ± 0.03, 113 In = 24.7 ± 0.5, 123 Sb = 28.3 ± 2.1, 180 Hf = 2.17 ± 0.09. All measurements are relative to S 0 = 17.7 for gold. (author)

  6. Study of gels of molybdenum with cerium in the preparation of generators of 99Mo - 99mTc

    Directory of Open Access Journals (Sweden)

    Vanessa Moraes

    2005-10-01

    Full Text Available 99mTc has ideal nuclear properties for organ imaging in nuclear medicine, and it is obtained from the 99Mo-99mTc generator. Four different types of generators are available: chromatographic that uses 99Mo from fission of uranium; MEK solvent extraction; Tc2O7 sublimation; gel chromatographic. This work presents the preparation of gel generators of molybdenum with cerium and characterization of the gels: mass ratio between molybdenum and cerium, structure, size of particles and elution percentage of 99mTc after irradiating the gels. Eight gels were prepared at the same temperature of 50 ºC with concentrations of NaOH of 2 and 4 mol/L, mass ratio of 0.31 and 0.38 and final pH of 3.5 and 4.5. The analysis of the results proved that these gels are not adequate for preparation of the generators of 99Mo-99mTc, since the elution percentages are low, when compared with the gel of molybdenum with zirconium.O 99mTc é o radiofármaco mais utilizado em Medicina Nuclear. Ele é obtido do gerador de 99Mo-99mTc e existem quatro tipos diferentes de geradores: cromatográfico que utiliza 99Mo de fissão; extração por solvente com MKT; sublimação do heptaóxido de tecnécio; cromatográfico tipo gel. Este trabalho apresenta a preparação de geradores tipo gel de molibdênio com cério, a caracterização desses géis com relação à quantidade de molibdênio e de cério, sua estrutura, tamanho das partículas e porcentagem de eluição do 99mTc após o gel ser irradiado. Foram preparados oito géis na temperatura de 50ºC com concentração de NaOH de 2 e 4 mol/L, relação de massa de 0,31 e 0,38 e pH final de 3,5 e 4,5. A análise dos resultados comprovou que esses géis não são adequados para preparação dos geradores de 99Mo-99mTc, já que as porcentagens de eluição são baixas, quando comparadas com o gel de molibdênio com zircônio.

  7. Preparation and characterization of iron(III) {sup 99}Mo-molybdate(VI) gels for the assessment of {sup 99m}Tc elution performance

    Energy Technology Data Exchange (ETDEWEB)

    Amin, Mahmoud; Fasih, Tharwat W.; El-Absy, Mohamed A. [Egyptian Atomic Energy Authority, Cairo (Egypt)

    2018-04-01

    New iron(III) {sup 99}Mo-molybdate(VI) gels (Fe{sup 99}Mo) of high Mo content were prepared by the precipitation/filtration method. {sup 99}Mo-MoO{sub 3} dissolved in NaOH was added to aqueous solutions of Fe(NO{sub 3}){sub 3} at Mo/Fe mole fractions ∝2.21 and 1.99 with continuous stirring at ambient room temperature. Two different Fe{sup 99}Mo were precipitated from the mixed solutions adjusted at pH 2 and 4.7. The amount of water of hydration increased with the increasing the gel settling time and pH of the mixed solution. The matrices were characterized by radiometric, XRD, SEM, XRF, FT-IR, TGA, and DTA measurements. Small chromatographic columns of 2.0 g Fe{sup 99}Mo containing ≥800 mg Mo tagged with 740 MBq {sup 99}Mo were eluted with 5 mL saline solution. Highly reproducible {sup 99m}Tc elution indices suitable for preparation of {sup 99}Mo/{sup 99m}Tc generators were achieved from generator supported with 0.5 g Al{sub 2}O{sub 3} filter. Elution performance of {sup 99m}Tc radionuclide was highly dependent on the gel structural properties.

  8. Preparation and characterization of iron(III) 99Mo-molybdate(VI) gels for the assessment of 99mTc elution performance

    International Nuclear Information System (INIS)

    Amin, Mahmoud; Fasih, Tharwat W.; El-Absy, Mohamed A.

    2018-01-01

    New iron(III) 99 Mo-molybdate(VI) gels (Fe 99 Mo) of high Mo content were prepared by the precipitation/filtration method. 99 Mo-MoO 3 dissolved in NaOH was added to aqueous solutions of Fe(NO 3 ) 3 at Mo/Fe mole fractions ∝2.21 and 1.99 with continuous stirring at ambient room temperature. Two different Fe 99 Mo were precipitated from the mixed solutions adjusted at pH 2 and 4.7. The amount of water of hydration increased with the increasing the gel settling time and pH of the mixed solution. The matrices were characterized by radiometric, XRD, SEM, XRF, FT-IR, TGA, and DTA measurements. Small chromatographic columns of 2.0 g Fe 99 Mo containing ≥800 mg Mo tagged with 740 MBq 99 Mo were eluted with 5 mL saline solution. Highly reproducible 99m Tc elution indices suitable for preparation of 99 Mo/ 99m Tc generators were achieved from generator supported with 0.5 g Al 2 O 3 filter. Elution performance of 99m Tc radionuclide was highly dependent on the gel structural properties.

  9. Development of Molybdenum Adsorbent for 99Mo/99mTc Radioisotope Generator Based on Irradiated Natural Molybdenum

    International Nuclear Information System (INIS)

    Rohadi Awaludin; Hotman Lubis; Sriyono; Abidin; Herlina; Endang Sarmini; Indra Saptiama; Hambali

    2011-01-01

    Preparation of 99 Mo/ 99m Tc radioisotope generator using irradiated natural molybdenum requires an adsorbent with high absorption capacity. Zirconium-based materials (ZBM), adsorbent with adsorption capacity of about 183 mg(Mo) / g(adsorbent), has been successfully synthesized. However, the adsorbent was easily broken in the Mo adsorption process due to many fractures in the grain. To increase the hardness, the material was immersed in tetraethyl orthosilicate (TEOS) and coated by TEOS flow in a column. The hardness test results showed that the ZBM with TEOS treatment was not broken when immersed into the Mo solution. Observations using SEM showed that the fractures formed on the ZBM were successfully removed by TEOS treatment. Measurements using EDS showed that after TEOS treatment, the silicon was detected and the oxygen content increased in the material surface. Adsorption test results showed that the TEOS immersion decreased the adsorption capacity of molybdenum from 183 to 79.8 mg of Mo per gram of adsorbent. The TEOS flow-in a column gave material with relatively high adsorption capacity, 140 mgMo per gram adsorbent. The content of Silicon in the surface was lower than that of adsorbent immersed in TEOS. (author)

  10. Production optimization of {sup 99}Mo/{sup 99m}Tc zirconium molybate gel generators at semi-automatic device: DISIGEG

    Energy Technology Data Exchange (ETDEWEB)

    Monroy-Guzman, F., E-mail: fabiola.monroy@inin.gob.mx [Instituto Nacional de Investigaciones Nucleares, Carretera Mexico-Toluca S/N, La Marquesa, Ocoyoacac, 52750, Estado de Mexico (Mexico); Rivero Gutierrez, T., E-mail: tonatiuh.rivero@inin.gob.mx [Instituto Nacional de Investigaciones Nucleares, Carretera Mexico-Toluca S/N, La Marquesa, Ocoyoacac, 52750, Estado de Mexico (Mexico); Lopez Malpica, I.Z.; Hernandez Cortes, S.; Rojas Nava, P.; Vazquez Maldonado, J.C. [Instituto Nacional de Investigaciones Nucleares, Carretera Mexico-Toluca S/N, La Marquesa, Ocoyoacac, 52750, Estado de Mexico (Mexico); Vazquez, A. [Instituto Mexicano del Petroleo, Eje Central Norte Lazaro Cardenas 152, Col. San Bartolo Atepehuacan, 07730, Mexico D.F. (Mexico)

    2012-01-15

    DISIGEG is a synthesis installation of zirconium {sup 99}Mo-molybdate gels for {sup 99}Mo/{sup 99m}Tc generator production, which has been designed, built and installed at the ININ. The device consists of a synthesis reactor and five systems controlled via keyboard: (1) raw material access, (2) chemical air stirring, (3) gel dried by air and infrared heating, (4) moisture removal and (5) gel extraction. DISIGEG operation is described and dried condition effects of zirconium {sup 99}Mo- molybdate gels on {sup 99}Mo/{sup 99m}Tc generator performance were evaluated as well as some physical-chemical properties of these gels. The results reveal that temperature, time and air flow applied during the drying process directly affects zirconium {sup 99}Mo-molybdate gel generator performance. All gels prepared have a similar chemical structure probably constituted by three-dimensional network, based on zirconium pentagonal bipyramids and molybdenum octahedral. Basic structural variations cause a change in gel porosity and permeability, favouring or inhibiting {sup 99m}TcO{sub 4}{sup -} diffusion into the matrix. The {sup 99m}TcO{sub 4}{sup -} eluates produced by {sup 99}Mo/{sup 99m}Tc zirconium {sup 99}Mo-molybdate gel generators prepared in DISIGEG, air dried at 80 Degree-Sign C for 5 h and using an air flow of 90 mm, satisfied all the Pharmacopoeias regulations: {sup 99m}Tc yield between 70-75%, {sup 99}Mo breakthrough less than 3 Multiplication-Sign 10{sup -3}%, radiochemical purities about 97% sterile and pyrogen-free eluates with a pH of 6. - Highlights: Black-Right-Pointing-Pointer {sup 99}Mo/{sup 99m}Tc generators based on {sup 99}Mo-molybdate gels were synthesized at a semi-automatic device. Black-Right-Pointing-Pointer Generator performances depend on synthesis conditions of the zirconium {sup 99}Mo-molybdate gel. Black-Right-Pointing-Pointer {sup 99m}TcO{sub 4}{sup -} diffusion and yield into generator depends on gel porosity and permeability. Black

  11. Evaluation of proton induced reactions on sup 1 sup 0 sup 0 Mo. New cross sections for production of sup 9 sup 9 sup m Tc and sup 9 sup 9 Mo

    CERN Document Server

    Takács, S; Tarkanyi, F; Hermanne, A; Sonck, M

    2003-01-01

    The use of the sup 9 sup 9 Mo -> sup 9 sup 9 sup m Tc generator in nuclear medicine is well established world wide. The production of the sup 9 sup 9 Mo (T sub 1 sub / sub 2 = 66 h) parent as a fission product of sup 2 sup 3 sup 5 U is largely based on the use of reactor technology. From the early 1990's accelerator based production methods to provide either direct produced sup 9 sup 9 sup m Tc or the parent sup 9 sup 9 Mo, were studied and suggested as potential alternatives to the reactor based production of sup 9 sup 9 Mo. A possible pathway for the charged particle production of sup 9 sup 9 sup m Tc and sup 9 sup 9 Mo is irradiation of molybdenum metal with protons via the reaction sup 1 sup 0 sup 0 Mo(p,2n) sup 9 sup 9 sup m Tc and sup 1 sup 0 sup 0 Mo(p,pn) sup 9 sup 9 Mo, respectively. The earlier published excitation functions show large differences in their maximum that result in large differences in the calculated yields. Study the excitation function for these proton-induced reactions was decided. ...

  12. Recycling 100Mo for direct production of 99mTc on medical cyclotrons

    Science.gov (United States)

    Kumlin, Joel O.; Zeisler, Stefan K.; Hanemaayer, Victoire; Schaffer, Paul

    2018-05-01

    A scalable recycling technique for the recovery of 100Mo from previously irradiated and chemically processed targets is described. A combined process for both Cu and Ta supported targets and the respective `waste' solutions has been developed. This process involves selectively dissolving Cu target backings from undissolved portions of 100Mo pellets; precipitating Cu(OH)2 at pH 9; electrochemical removal of Cu traces; precipitating (NH4)2MoO4 at pH 2.5-3; thermally decomposing (NH4)2MoO4; and H2 reduction of MoO3 to Mo metal. Radionuclidic decontamination by a factor of 100 is observed, while overall 100Mo recovery from initial target plating to recycled Mo metal of 96% is achieved.

  13. Direct elution of sup(99m)Tc complexes from neutron irradiation produced /sup 99/Mo incorporated in a MoCl/sub 2/-MoBr/sub 2/ mixture

    Energy Technology Data Exchange (ETDEWEB)

    Ganzerli Valentini, M.T.; Stella, R.; Genova, N.

    1987-01-01

    A novel type of sup(99m)Tc generator, enabling radiopharmaceutical preparation without reductant addition, was prepared and tested. Neutron activated product /sup 99/Mo, in the form of dichloride cluster, was incorporated into inactive molybdenum dichloride-dibromide mixture (MCB) that was left to settle over an activated alumina layer. Direct elution with aqueous ligands such as salicylate or iminodiacetate derivatives in the pH range 6.5-7.5 yielded chemically stable sup(99m)Tc complexes accompanied by small amounts of secondary products (mostly sup(99m)TcO/sup -//sub 4/). Pentavalent oxidation state in the salicylate complex and tervalent in the iminodiacetate (IDA) and in the N-(2,6-dimethylphenylcarbamoylmethyl) iminodiacetate (HIDA) complexes were assigned to the element after comparison with reference complexes. The anion exchange version of reverse-phase HPLC was used to resolve the eluted product mixture.

  14. Evaluation of {sup 99}Mo/{sup 99m}Tc generator columns after irradiation with different absorbed doses

    Energy Technology Data Exchange (ETDEWEB)

    Fukumori, Neuza T.O.; Mengatti, Jair; Matsuda, Margareth M.N., E-mail: ntfukumo@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNE-SP), Sao Paulo, SP (Brazil)

    2017-07-01

    The {sup 99}Mo/{sup 99m}Tc generator is widely used in nuclear medicine and it consists of a glass column containing Teflon® strips and alumina in which {sup 99}Mo produced by {sup 235}U fission is adsorbed. The {sup 99}mTcO4- eluate shall meet the sterile and pyrogen free conditions for injectable radiopharmaceuticals as determined by the Good Manufacturing Practices. The purpose of this study was to evaluate the feasibility of using gamma radiation in the sterilization of the {sup 99}Mo/{sup 99m}Tc generator column and the influence on the elution efficiency. Alumina-containing columns were irradiated with 10, 15, 25 and 50 kGy absorbed doses. Alumina samples and control (non-irradiated) were submitted to X-ray diffraction and the combined use of scanning electron microscopy and elemental analysis. Teflon® samples were evaluated by thermogravimetry (TGA) and differential scanning calorimetry (DSC). X-ray diffractograms and micrographies with elemental analysis showed no significant changes in the crystalline structure of the alumina because it was stable α-Al{sub 2}O{sub 3}. TGA demonstrated that higher doses showed changes in lower temperatures and times than the control material. For DSC the higher the absorbed dose, the greater the polymer chain breakage and crosslinking in the material. The generator system without radioactivity was set up with the irradiated columns and the eluates demonstrated to be sterile and pyrogen free. The effects of different absorbed doses on the generator column, although some reported changes in the materials, demonstrated that the sterilization of the columns by irradiation with gamma rays as an alternative to wet heat sterilization is feasible from a technical and financial point of view. (author)

  15. Development and utilization of the inorganic polymer materials for {sup 99}Mo-{sup 99m}Tc and {sup 188}W-{sup 188}Re generator based on (n, gamma) method

    Energy Technology Data Exchange (ETDEWEB)

    Yoshida, Kosuke; Ishikawa, Koji; Terunuma, Hitoshi; Hasegawa, Yoshio; Tatenuma, Katsuyoshi [KAKEN Co., Mito, Ibaraki (Japan)

    2003-03-01

    A molybdenum (Mo) adsorbent called PZC (Poly Zirconium Compound) with high efficiency of Mo adsorption has been developed in order to generate {sup 99m}Tc from {sup 99}Mo produced from natural Mo by (n, gamma) method. The {sup 99m}Tc generator using PZC has cleared mostly the technical subjects. By the results of many experiments, cold and hot test with {sup 99}Mo activity from low level (10{sup 5} Bq) to high level (10{sup 10} Bq), it has been confirmed that the PZC method can be practically applied for the (n, gamma) {sup 99}Mo-{sup 99m}Tc generator. From the reasons that PZC has the ability and many merits such as high adsorption capacity (>250 mg-Mo/g-PZC) of Mo, high elution yield (av. 80%) of {sup 99m}Tc, the low breakthrough (<0.05 kBq-{sup 99m}Mo/MBq-{sup 99m}Tc) of {sup 99}Mo and others, the current (n, fission) {sup 99m}Tc generator utilizing {sup 99}Mo produced from enriched uranium will be taken the place by PZC method. In this paper, the practicability of PZC and a newly developed functional material PTC(Poly Titanium Compound) as the (n, gamma) {sup 99}Mo-{sup 99m}Tc generator, and an ability of PZC as the {sup 188}W-{sup 188}Re generator will be shown. (author)

  16. 99mTc generator preparation using (n, γ)99Mo produced using natural molybdenum

    International Nuclear Information System (INIS)

    Kim, Hark Rho; Park, Jin Ho; Lee, Kye Hong

    2003-01-01

    The Mo-99 is a widely used radioisotope in Korea. To fulfill the demand, we are producing Mo-99 using a specially designed and fabricated rig containing MoO 3 target. We are using natural molybdenum so far. But considering the utilization of the enriched molybdenum to increase the specific activity further, we desire the realization of PZC with (n, γ)Mo-99 as early as possible. To make the generator loading facility, we are in progress of construction work for the related hot cell facilities. (author)

  17. Radiochemical purity of Mo and Tc solution obtained after irradiation and dissolution of Mo-100-enriched and ultra-high-purity natural Mo disks

    Energy Technology Data Exchange (ETDEWEB)

    Tkac, Peter [Argonne National Lab. (ANL), Argonne, IL (United States); Gromov, Roman [Argonne National Lab. (ANL), Argonne, IL (United States); Chemerisov, Sergey D. [Argonne National Lab. (ANL), Argonne, IL (United States); Rotsch, David A. [Argonne National Lab. (ANL), Argonne, IL (United States); Vandegrift, George F. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2016-09-01

    Four irradiations of ultra-high-purity natural Mo targets and one irradiation using 97.4% Mo-100-enriched material were performed. The purpose of these irradiations was to determine whether the presence of Sn stabilizer in the H2O2 used for the dissolution of sintered Mo disks can affect the radiochemical purity of the final K2MoO4 in 5M KOH solution. Results from radiochemical purity tests performed using thin-layer paper chromatography show that even 2– 3× excess of Sn-stabilized H2O2 typically used for dissolution of sintered Mo disks did not affect the radiochemical purity of the final product.

  18. Influence of the electrolyte in the fixation of {sup 99} Mo in hydroxyapatite as matrix of the {sup 99} Mo/ {sup 99m} Tc generator; Influencia del electrolito en la fijacion de {sup 99} Mo en hidroxiapatita coma matriz del generador {sup 99} Mo/ {sup 99m} Tc

    Energy Technology Data Exchange (ETDEWEB)

    Vazquez G, S.; Badillo A, V.E. [UAZ, Zacatecas (Mexico); Monroy G, F. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)]. e-mail: s_vazgro@hotmail.com

    2005-07-01

    The more used isotope at the moment in the services of nuclear medicine in the world is the technetium-99m. The {sup 99m} Tc emitts gamma rays of 141 keV and it semi disintegration period is of six hours, given it short half life, to produce it is necessary to order generators that are systems that allow to separate periodically at the {sup 99m}Tc of the {sup 99} Mo by means of chromatographic techniques. In this work it is sought to evaluate the use of the hydroxyapatite, to separate molybdates {sup 99} MoO{sub 4}{sup 2} of pertechnetates {sup 99m}TcO{sub 4}{sup -} and to be able to determine if it is feasible their use for to build generators of {sup 99m} Tc. With this purpose preliminary tests to know the likeness of the hydroxyapatite for the molybdates in function of the pH value, in different solutions were carried out: one of NaCl 0.9%, NaCl 2% and CaCl{sub 2} 0.01 M. The obtained results in a NaCl 0.9% solution and at to 2% to different pH values of the solution, shows that the fixation of the molybdate ions (MoO{sub 4}{sup -2}) it is worthless to basic pH values of (9-11), as long as in solution of CaCI{sub 2} 0.01 M show a considerable retention of molybdate ions. (Author)

  19. Excitation functions of deuteron induced nuclear reactions on natMo up to 21 MeV. An alternative route for the production of 99mTc and 99Mo

    International Nuclear Information System (INIS)

    Sonck, M.; Hermanne, A.; Takacs, S.; Szelecsenyi, F.; Tarkanyi, F.

    1999-01-01

    Cross sections of deuteron induced nuclear reactions on natural molybdenum have been studied in the frame of a systematic investigation of charged particle induced nuclear reactions on metals for different applications. The excitation functions of 92m,95 Nb-, 93,94g,94m,95g,95m,96,99m Tc- and 99 Mo were measured up to 21 MeV deuteron energy by using stacked foil technique and activation method. The goal of this work was to study the production possibility of the medical important 94m,99m Tc- and 99 Mo-nuclides. Production of 99m Tc and 99 Mo is of importance for their use in nuclear medicine, whereas 94m Tc is of interest regarding quantification of kinetics of well-established 99m Tc-radiopharmaceuticals. The production possibilities of 99m Tc and 99 Mo above 20 MeV deuteron energies up to 50 MeV were estimated and was found that beside the proton induced reactions the deuteron induced reactions on enriched molybdenum target are very promising. (author)

  20. Evaluation of the influence of pH in the efficiency of the 99Mo-99mTc at basis of zirconium molybdate

    International Nuclear Information System (INIS)

    Diaz A, L.V.

    2003-01-01

    The 99m Tc are the radionuclide more used in the nuclear medicine, it is used for diagnostic and therapy, and he is commonly takes place by means of a generator 99 Mo- 99m Tc, using molybdenum ( 99 Mo) product of the fission of the uranium, adsorbed over alumina. This generator imposes the use of high activities you specify of 99 Mo, as well as of complex processes of separation of the one 99 Mo, generating important quantities of radioactive waste of medium activity. As well as, the production of these generators, demands the use of reactors of great capacity that Mexico not it possesses, in such a way that, presently work is carried out a generator of 99 Mo- 99m Tc, in the one which 99 Mo taken place by the reaction 98 Mo(n, γ) 99 Mo that it was part from a gel to base is used of molybdate and zirconium. It was found, therefore, to produce a generator 99 Mo- 99m Tc with the help of gels of zirconium and molybdates with the same characteristics of quality and purity that those obtained by the one traditional generator and that it can be carried out under the conditions technical-economics prevailing in Mexico. Specifically, this work has been focused to the study of the effect caused by the variation of the one p H in the solutions of ZrOCl 2 * 8H 2 O (zirconil) and of molybdates, of the relationships molars zirconium : molybdenum (Zr:Mo), as well as the effect of the concentration variation, time of preparation and consequently p H of the ZrOCl 2 * 8H 2 O in the synthesis of the gel zirconium - 99 molybdenum, on the efficiency of the generator and the quantity of 99 Mo presents in the 99m Tc taken place by this means. The gel used for the production of 99m Tc will possess a discharge efficiency of recovery of 99m Tc and a contained first floor of pollutants, in particular smaller to 0.015% of 99 Mo, main source of impurity radionuclide of these generators. The obtained results show that to p H average (3.8 and 4.5), the obtained efficiencies they are the biggest

  1. Determination of radionuclidic impurities in 99mTceluate from 99Mo/99mTc generator for quality control

    DEFF Research Database (Denmark)

    Hou, Xiaolin

    2017-01-01

    , 89Sr and 90Sr. Radioactive decay for removal of 99mTc, ion exchange and extraction chromatography for removal of 99Mo and 99Tc are effective for separation of interferences. Gamma spectrometry, LSC with alpha/beta discrimination, and Cherenkov counting using LSC are sensitive methods for measurement...... of the impurity radionuclides. The detection limits of this method are well meet the requirement of the quality control according to the limitation of the pharmacopoeia....

  2. New measurement of excitation functions for (d,x) reactions on Mo-nat with special regard to the formation of Tc-95m, Tc96m+g, Tc-99m and Mo-99

    Czech Academy of Sciences Publication Activity Database

    Lebeda, Ondřej; Fikrle, Marek

    2010-01-01

    Roč. 68, č. 12 (2010), s. 2425-2432 ISSN 0969-8043 R&D Projects: GA ČR GA203/08/1276 Institutional research plan: CEZ:AV0Z10480505 Keywords : Cross-sections * Tc-95m * Tc96m+g Subject RIV: BG - Nuclear, Atomic and Molecular Physics, Colliders Impact factor: 0.999, year: 2010

  3. Design and setup of a portable stirring device for transfer and dissolution of 99Mo applied to the use of a 99mTc generator

    International Nuclear Information System (INIS)

    Lopez, Yon; Rojas, Jorge

    2014-01-01

    This work shows the design and implementation of a portable magnetic stirring device for transfer and efficient dissolution of Mo O 3 coupled to a 99m Tc generator prototype. The development of this equipment will enable an efficient and safe transfer of 99 Mo at a 2 Ci of maximum activity from the nuclear reactor Huarangal to the point of operation of the 99m Tc generator equipment. This article describes the mechanical design, volume and shielding calculation, the electronics design and the programmable speed control of the stirring system for radioactive samples. (authors).

  4. Hydroxyapatite based 99Mo-99mTc and 188W-188Re generator systems

    International Nuclear Information System (INIS)

    Monroy-Guzman, F.; Badillo-Almaraz, V.E.; Flores de la Torre, J.A.; Cosgrove, J.; Knapp, F.F. Jr.

    2007-01-01

    This paper describes studies evaluating the use of hydroxyapatite as the adsorbent material for both 90M o- 90m Tc and 89W - 188 Re generator systems. Hydroxyapatite is an insoluble solid with anion exchange properties. A study of the sorption behaviour of 90M o, 90m Tc, 188 W and 188 Re on hydroxyapatite in NaCl medium was evaluated by batch experiments. The results demonstrated that while 90M o, 90m Tc and 188 Re are not adsorbed by the hydroxyapatite in NaCl solutions (Kd 89W is strongly adsorbed (Kd >500). On the basis of these measurements, hydroxyapatite 89W - 188 Re generator systems were then constructed and eluted in NaCl solutions. The hydroxyapatite based 89W - 188 Re generator performances are presented. (author)

  5. Study of the performance of gels of molybdenum containing several cations for the preparation of 99Mo and 99mTc

    International Nuclear Information System (INIS)

    Moraes, Vanessa

    2005-01-01

    99m Tc is the most employed radioisotope in Nuclear Medicine, due to its nuclear characteristics: short half-life (6.04 h); emission of low energy gamma ray (140 keV); no emission of β - ; generated by the radioactive decay of 99 Mo (radioisotope generator system). 99 Mo can be produced in cyclotron or nuclear reactor by the irradiation of 235 U (n, f) 99 Mo or by the 98 Mo (n, γ) 90 Mo reaction. Four different kinds of generators of 99m Tc can be employed, based on the separation techniques: column chromatographic using alumina, with fission 99 Mo; solvent extraction using methylethylketone; sublimation of technetium heptoxide; gel type chromatographic generator, that contains molybdenum. IPEN, aiming the nationalization of the 99m Tc generators production, developed a gel type generator that uses zirconium molybdate. Three types of gels are studied in the work: molybdenum gel with titanium, molybdenum gel with cerium and molybdenum gel with hafnium, that were compared with the molybdenum gel with zirconium. The variables studied in the gel preparation are: mass relation between Mo and the cation, NaOH concentration, temperature and final pH of the product. After the preparation, the gels are analysed in relation to the amount of Mo and the cation, structure and gel particle size. The gel is irradiated and later a generator system is prepared, and the elutions are analysed in order to measure the 99m Tc elution efficiency. The results showed that the molybdenum gel with titanium had the best performance in all analysis. (author)

  6. Studies on {sup 99}Mo-{sup 99m}Tc adsorption and elution behaviors using the inorganic sorbent ceric tungstate and conventional organic resins

    Energy Technology Data Exchange (ETDEWEB)

    El-Sweify, Fatma H.; Fattah, Alaa El-Din A. Abdel; Aly, Shorouk M.; Ghamry, Mohamed A. [Atomic Energy Authority, Cairo (Egypt). Hot Laboratories Center; El-Sheikh, Ragaa [Zagazig Univ. (Egypt). Chemistry Dept.

    2017-09-01

    Adsorption behavior of {sup 99}Mo(VI) and {sup 99m}Tc(VII) was studied on ceric tungstate (CeW) and compared with the adsorption on the conventional cation and anion exchangers Dowex-50X8 and AG-2X8, respectively. The studies were carried out under static and dynamic conditions. The effect of contact time and pH on the adsorption was investigated under static conditions. High K{sub d}-values for sorption of {sup 99}Mo(VI) on (CeW) were obtained over the investigated pH range. {sup 99m}Tc was adsorbed with much lower K{sub d}-values. The K{sub d}-values were pH dependent. K{sub d}-values of {sup 99}Mo-adsorption on AG-2X8 were lower than those on (CeW) and vice versa for {sup 99m}Tc. Ionic species of both elements were not adsorbed on Dowex-50X8, indicating the absence of cationic species and the adsorption of both elements on AG-2X8 and (CeW) as anionic species. The loading and elution behaviors of {sup 99}Mo and {sup 99m}Tc on (CeW) were studied using different eluents. {sup 99}Mo remained strongly adsorbed under all conditions whereas {sup 99m}Tc was easily eluted. Adsorption of some fission products, i.e. {sup 95}Zr(IV) and {sup 95}Nb(V), in addition to {sup 123m}Te(IV) and {sup 75}Se(IV), as representatives of their corresponding fission product isotopes, as well as {sup 181}Hf, as probable radioactive contaminant was also studied. Solutions of the ionic species of those metals were loaded in mixtures together with {sup 99}Mo on (CeW) columns. Strong adsorption of those ionic species and {sup 99}Mo on (CeW) was found whereas {sup 99m}Tc was easily eluted. Different eluents were investigated for eluting {sup 99m}Tc from {sup 99}Mo-adsorbed on (CeW).

  7. Study of different absorbent materials for the preparation of generator systems of 99Mo - 99mTc and 188W-188Re

    International Nuclear Information System (INIS)

    Lopes, Paula Regina Corain; Osso Junior, Joao Alberto

    2009-01-01

    Amongst some currently radioisotopes, 99m Tc and 188 Re present adequate decay properties for use in Nuclear Medicine. In the current times the most diagnosis examinations are performed with 99m Tc and 188 Re is one radioisotope of potential use in therapy techniques. The objective of this work consists of determining the capacity of some adsorbent materials for retention of molybdenum and tungsten, aiming the optimization of generator systems of 99 Mo- 99m Tc and 188 W- 188 Re with suitable characteristics for application in Nuclear Medicine. Known amounts, in mass, of molybdenum and tungsten were percolated through different chromatographic columns containing different commercial adsorbent materials such as: PZC (poly-zirconium compound), acid alumina and calcinated alumina used in the routine preparation of 99 Mo- 99m Tc generators at IPEN. The tungsten ( 188 W), as well the PZC used in this project, supplied by Russia and Japan, respectively, through the International Atomic Energy Agency (IAEA) and used without any previous preparation. Also trace amounts of 99 Mo and 188 W were added to the initial solutions and the generators were assembled. The 99 Mo- 99m Tc generators were then eluted with known volumes of 0.9% NaCl solution every 24 hours whereas the 188 W- 188 Re generators were eluted every 48 hours. The eluted samples were analyzed by Gamma Spectroscopy and later submitted to quality control evaluation. The results showed that the PZC presents superior retention capacity for Mo of 97.50mg Mo/gPZC, higher than in acid and calcinated alumina, however the elution efficiency at lower pHs is not so high. With regards to the experiments carried out with 188 W and alumina, it was verified that the elution efficiency of 188 Re was not reproducible and the retention capacity of W was 90.23mgW/gAl 2 O 3 at pH 7. (author)

  8. An experimental study of the time dependence of uptake from soil of 137Cs, 106Ru, 144Ce and 99Tc into green vegetables, wheat and potatoes

    International Nuclear Information System (INIS)

    Grogan, H.A.; Bell, J.N.B.; Minski, M.J.; Nair, S.

    1984-03-01

    In this study the experimental data were analysed using the CEGB's dynamic foodchain model, and were used to validate the relevant part of the model structure, to produce model-specific input data and to identify possible future improvements to the model structure. The root uptake of the specified radionuclides was studied and the concentration levels measured. The data were analysed using a simplified version of the general model. The compartment system incorporated within the model was shown to be capable of reproducing the data for 137 Cs, 106 Ru and 144 Ce to an extent sufficient to justify its use in ingestion radiological dose assessments, but to be less successful in fitting the 99 Tc data. The analysis resulted in the production of a well validated set of model-specific input data relevant to UK conditions and agricultural practice differing significantly from values obtained from global literature surveys. Possible future improvements to the model structure were also identified, aimed at providing improved estimates of crop contamination levels for timescales in excess of those considered in this study. (U.K.)

  9. Study of gels of molybdenum with cerium in the preparation of generators of {sup 99}Mo-{sup 99m}Tc

    Energy Technology Data Exchange (ETDEWEB)

    Moraes, Vanessa; Marczewski, Barbara; Dias, Carla Roberta; Osso Junior, Joao Alberto [Instituto de Pesquisas Energeticas e Nucleares (IPEN-CNEN/SP), SP (Brazil). Centro de Radiofarmacia

    2005-10-15

    {sup 99m} Tc has ideal nuclear properties for organ imaging in nuclear medicine, and it is obtained from the {sup 99}Mo-{sup 99m} Tc generator. Four different types of generators are available: chromatographic that uses {sup 99}Mo from fission of uranium; MEK solvent extraction; Tc{sub 2}O{sub 7} sublimation; gel chromatographic. This work presents the preparation of gel generators of molybdenum with cerium and characterization of the gels: mass ratio between molybdenum and cerium, structure, size of particles and elution percentage of {sup 99m} Tc after irradiating the gels. Eight gels were prepared at the same temperature of 50 deg C with concentrations of NaOH of 2 and 4 mol/L, mass ratio of 0.31 and 0.38 and final pH of 3.5 and 4.5. The analysis of the results proved that these gels are not adequate for preparation of the generators of {sup 99}Mo-{sup 99m} Tc, since the elution percentages are low, when compared with the gel of molybdenum with zirconium.(author)

  10. Evaluation of fresh and old eluate of 99Mo/99mTc generators used for labeling of different pharmaceutical kits

    International Nuclear Information System (INIS)

    Urbano, N.; Chinol, M.; Modoni, S.; Guerra, M.

    2005-01-01

    Sixty 99 Mo/ 99m Tc wet column generators, loaded with two different 99 Mo activities, were analyzed in order to assess the quality of their eluates. Each elution was used for labeling of different radiopharmaceuticals, in order to evaluate whether 'risky' elutions, namely those performed just after generator delivery and at 72 hours or more from the last elution, could be conveniently employed when fresh available radioactivity is not enough for the planned labeling or when shipping problems arise, or delay in delivery of a new generator occurs. Radiochemical quality control of all radiopharmaceuticals labeled with these elutions was performed. The elutions differed mainly in 99 Tc ground state ( 99g Tc) and amounts of oxidizing impurities. Radiolabeling procedures, however, were not affected, suggesting that these 'risky' elutions might be appropriately used, in 'emergency' conditions, for labeling radiopharmaceuticals although their radiochemical purity control is recommended prior to patient administration. (author)

  11. Problems in clinical practice of domestic supply of 99Mo/99mTc. Current status and action plans on domestic production of 99Mo raw materials for medical use

    International Nuclear Information System (INIS)

    Nakamura, Yoshihide

    2012-01-01

    NRU in Canada and HFR in the Netherlands which had been producing the most important medical isotope, 99 Mo, were shut down in 2009-2010. As the production of more than 95% of global 99 Mo supply were performed in only five research reactors in the world including the two reactors mentioned above, these shutdowns resulted in global supply shortage of 99 Mo. Although the medical isotope crisis were alleviated after the two reactors returning to service, all of these five 99 Mo producing reactors are approximately 50 years old. Because the remaining life time of these reactors is not so long, the construction of new reactors or the development of new technologies to produce bulk 99 Mo, such as the neutron activation of 98 Mo in a reactor or charged particle reaction by accelerator, are proposed for the long-term security of supply of 99 Mo. The methods using the molybdenum target lead to much lower specific activity of 99 Mo compared to the production with fission method. The new chemical processing technologies, such as manufacturing 99m Tc-labeled radiopharmaceuticals from such low specific activity 99 Mo, are required for the development of domestic practical production of 99 Mo. (author)

  12. Detection of thrombi using a Tc-99m labelled antifibrin monoclonal antibody (MoAb)

    International Nuclear Information System (INIS)

    Wasser, M.N.J.M.

    1989-01-01

    This thesis presents an investigation into the possibility of immunoscintigraphic detection of thrombi using an antifibrin monoclonal antibody, and fragments of the latter. The antifibrin antibody and tis fragments were labelled with Ec-99m, which has excellent characteristics for imaging with a gamma camera. The characterization of the antifibrin antibody and its fragments, the assessment of quality of labelling with Tc-99m, and results of experiments in vitro and in animals, which show the potential of immunoscintigraphic detection, are described. (author). 142 refs.; 44 figs.; 5 tabs

  13. PENGARUH REGENERASI KOLOM ALUMINA ASAM TERHADAP RECOVERY DAN KUALITAS 99mTc HASIL EKSTRAKSI PELARUT MEK DARI 99Mo HASIL AKTIVASI NEUTRON

    Directory of Open Access Journals (Sweden)

    Adang H G

    2017-01-01

    Full Text Available ABSTRAK PENGARUH REGENERASI KOLOM ALUMINA ASAM TERHADAP RECOVERY DAN KUALITAS 99mTc HASIL EKSTRAKSI PELARUT MEK DARI 99Mo HASIL AKTIVASI NEUTRON. Melalui kerjasama antara PTRR-BATAN, Chiyoda dan JAEA Jepang telah dilakukan pemurnian 99mTc dari 99Mo hasil aktivasi neutron dengan menggunakan metode kromatografi kolom alumina asam terhadap hasil ekstraksi MEK (Metil Etil Keton. Pemurnian 99mTc dengan metode kolom alumina asam hanya dapat digunakan satu kali dan pemurnian berikutnya harus diganti dengan kolom baru. Hal ini dinilai kurang praktis dan juga memerlukan biaya yang mahal. Dalam penelitian ini dicoba penggunaan kolom alumina asam untuk pemurnian 99mTc lebih dari satu kali dengan melakukan proses regenerasi dengan cara melewatkan larutan HNO3 0,1N setiap kali proses pemurnian selesai. Penelitian ini bertujuan untuk mendapatkan larutan 99mTc yang dapat digunakan untuk penandaan kit radiofarmaka. Parameter yang diamati dalam penelitian ini adalah recovery, profil elusi, pH, kemurnian radiokimia dan kemurnian radionuklida (lolosan 99Mo. Hasil penelitian yang dilakukan selama 5 hari telah diperoleh pH ~5, recovery > 60 %, kemurnian radiokimia > 95 % dan lolosan 99Mo tidak terdeteksi. Dari hasil perlakuan terhadap kolom alumina asam dengan larutan HNO3 0,1 N disimpulkan bahwa kolom alumina asam tidak perlu diganti setiap hari. Kata kunci: 99mTc, 99Mo, MEK, kolom alumina asam, kemurnian radiokimia. ABSTRACT Purification of 99mTc from 99Mo activation using acidic alumina column chromatography system from MEK (Methyl Ethyl Keton extraction has been carried out through cooperation between PTRR - BATAN, Chiyoda and JAEA Japan. This method has a limitation that acidic alumina column for purification of 99mTc can be used only once, for the next purification acidic alumina column should be replaced with new column, so it is less practical and also requires high cost. This study aims to obtain a 99mTc solution can be use for labelling of a

  14. New results for double-beta decay of {sup 100}Mo to excited final states of {sup 100}Ru using the TUNL-ITEP apparatus

    Energy Technology Data Exchange (ETDEWEB)

    Kidd, M.F.; Esterline, J.H. [Department of Physics, Duke University and Triangle Universities Nuclear Laboratory, Durham, NC 27708-0308 (United States); Tornow, W. [Department of Physics, Duke University and Triangle Universities Nuclear Laboratory, Durham, NC 27708-0308 (United States)], E-mail: tornow@tunl.duke.edu; Barabash, A.S.; Umatov, V.I. [Institute for Theoretical and Experimental Physics, 117259 Moscow (Russian Federation)

    2009-04-15

    The coincidence detection efficiency of the TUNL-ITEP apparatus designed for measuring half-life times of two-neutrino double-beta (2{nu}{beta}{beta}) decay transitions to excited final states in daughter nuclei has been measured with a factor of 2.4 improved accuracy. In addition, the previous measuring time of 455 days for the study of the {sup 100}Mo 2{nu}{beta}{beta} decay to the first excited 0{sub 1}{sup +} state in {sup 100}Ru has been increased by 450 days, and a new result (combined with the previous measurement obtained with the same apparatus) for this transition is presented: T{sub 1/2}=[5.5{sub -0.8}{sup +1.2}(stat){+-}0.3(syst)]x10{sup 20} yr. Measured 2{nu}{beta}{beta} decay half-life times to excited states can be used to test the reliability of nuclear matrix element calculations needed for determining the effective neutrino mass from zero-neutrino double-beta decay data. We also present new limits for transitions to higher excited states in {sup 100}Ru which, if improved, may be of interest for more exotic conjectures, like a bosonic component to neutrino statistics.

  15. New results for double-beta decay of 100Mo to excited final states of 100Ru using the TUNL-ITEP apparatus

    International Nuclear Information System (INIS)

    Kidd, M.F.; Esterline, J.H.; Tornow, W.; Barabash, A.S.; Umatov, V.I.

    2009-01-01

    The coincidence detection efficiency of the TUNL-ITEP apparatus designed for measuring half-life times of two-neutrino double-beta (2νββ) decay transitions to excited final states in daughter nuclei has been measured with a factor of 2.4 improved accuracy. In addition, the previous measuring time of 455 days for the study of the 100 Mo 2νββ decay to the first excited 0 1 + state in 100 Ru has been increased by 450 days, and a new result (combined with the previous measurement obtained with the same apparatus) for this transition is presented: T 1/2 =[5.5 -0.8 +1.2 (stat)±0.3(syst)]x10 20 yr. Measured 2νββ decay half-life times to excited states can be used to test the reliability of nuclear matrix element calculations needed for determining the effective neutrino mass from zero-neutrino double-beta decay data. We also present new limits for transitions to higher excited states in 100 Ru which, if improved, may be of interest for more exotic conjectures, like a bosonic component to neutrino statistics.

  16. Evaluation of the influence of pH in the efficiency of the {sup 99}Mo-{sup 99m}Tc at basis of zirconium molybdate; Evaluacion de la influencia de pH en la eficiencia del generador {sup 99}Mo-{sup 99m}Tc a base de molibdato de zirconio

    Energy Technology Data Exchange (ETDEWEB)

    Diaz A, L V

    2003-07-01

    The {sup 99m}Tc are the radionuclide more used in the nuclear medicine, it is used for diagnostic and therapy, and he is commonly takes place by means of a generator {sup 99} Mo-{sup 99m}Tc, using molybdenum ({sup 99}Mo) product of the fission of the uranium, adsorbed over alumina. This generator imposes the use of high activities you specify of {sup 99} Mo, as well as of complex processes of separation of the one {sup 99} Mo, generating important quantities of radioactive waste of medium activity. As well as, the production of these generators, demands the use of reactors of great capacity that Mexico not it possesses, in such a way that, presently work is carried out a generator of {sup 99} Mo- {sup 99m} Tc, in the one which {sup 99} Mo taken place by the reaction {sup 98} Mo(n, {gamma}) {sup 99} Mo that it was part from a gel to base is used of molybdate and zirconium. It was found, therefore, to produce a generator {sup 99} Mo- {sup 99m}Tc with the help of gels of zirconium and molybdates with the same characteristics of quality and purity that those obtained by the one traditional generator and that it can be carried out under the conditions technical-economics prevailing in Mexico. Specifically, this work has been focused to the study of the effect caused by the variation of the one p H in the solutions of ZrOCl{sub 2} * 8H{sub 2}O (zirconil) and of molybdates, of the relationships molars zirconium : molybdenum (Zr:Mo), as well as the effect of the concentration variation, time of preparation and consequently p H of the ZrOCl{sub 2} * 8H{sub 2}O in the synthesis of the gel zirconium - {sup 99} molybdenum, on the efficiency of the generator and the quantity of {sup 99} Mo presents in the {sup 99m} Tc taken place by this means. The gel used for the production of {sup 99m}Tc will possess a discharge efficiency of recovery of {sup 99m}Tc and a contained first floor of pollutants, in particular smaller to 0.015% of {sup 99} Mo, main source of impurity radionuclide

  17. Design and setup of a portable stirring device for transfer and dissolution of {sup 99}Mo applied to the use of a {sup 99m}Tc generator; Diseno e implementacion de un modulo portatil para el traslado y disolucion de Mo-99 aplicado al empleo de un generador de Tc-99m

    Energy Technology Data Exchange (ETDEWEB)

    Lopez, Yon [Universidad Nacional de Ingenieria, Lima (Peru). Facultad de Ingenieria Mecanica; Urquizo, Rafael [Universidad Tecnologica del Peru, Lima (Peru). Facultad de Ingenieria de Sistemas y Electronica; Mendoza, Pablo [Direccion de Investigacion y Desarrollo, Instituto Peruano de Energia Nuclear, Lima (Peru); Rojas, Jorge [Universidad Nacional Mayor San Marcos, Lima (Peru). Facultad de Quimica e Ingenieria Quimica

    2014-07-01

    This work shows the design and implementation of a portable magnetic stirring device for transfer and efficient dissolution of Mo{sub O}3 coupled to a {sup 99m}Tc generator prototype. The development of this equipment will enable an efficient and safe transfer of {sup 99}Mo at a 2 Ci of maximum activity from the nuclear reactor Huarangal to the point of operation of the {sup 99m}Tc generator equipment. This article describes the mechanical design, volume and shielding calculation, the electronics design and the programmable speed control of the stirring system for radioactive samples. (authors).

  18. Chemical and technological investigations to establish the production of 99Mo/sup(99m)Tc-Generators from uranium fission in Egypt

    International Nuclear Information System (INIS)

    Munze, R.; El-Bayoumy, S.; Mosaad, K.; Hallaba, E.

    1980-01-01

    Different possibilities to meet the current estimated demand of sup(99m)Tc for medical uses in the Arab Republic of Egypt have been investigated using irradiation and separation experiments and theoretical calculations. The investigation includes the evaluation of the real present irradiation capability of the Egyptian Research Reactor as well as pilot runs suitable technological schemes for target design and chemical processing of irradiated uranium targets. The suitability of the produced 99 Mo for the preparation of 99 Mo/sup(99m)Tc-generators has been confirmed. Separation yield (80%) as well as the radiochemical and radionuclidic purity of the sup(99m)Tc (TcO 4 98%, sup(99m)Tc 99,9%) corresponds to comparable results for similar processes cited in recent literature. The necessary requirements, related to the irradiation capability of the reactor and the demands of the radiochemical facilities, have been derived. The present work is the fruit of three months cooperation between the Agency expert and the Egyptian Counterpart

  19. Present status of 99Mo/99mTc supply in Japan

    International Nuclear Information System (INIS)

    Yamashita, Takashi; Nakamura, Yoshihide

    2017-01-01

    The use of medical radioisotopes is an important part of modern medical practice. Disruptions in the radioisotope supply chain can disturb the availability of medical testing for millions of patients around the world. The NEA established the High-level Group on the Security of Supply of Medical Radioisotopes (HLG-MR) in 2009. During the 2009-2010 period, there were substantial shortages, but in the period since 2011 there have been only a limited number of minor supply shortages of the most widely used medical radioisotope. Japan does not have a reactor for 99 Mo production or a processing facility, and has been considering a number of alternative technology approaches to produce material domestically. (author)

  20. Influence of the Ti concentration and of the Ti:Mo molar ratio, in the efficiency of the 99 Mo - 99m Tc generator, at basis of gels of titanium molybdates

    International Nuclear Information System (INIS)

    Cortes R, O.; Monroy G, F.; Martinez C, T.

    2003-01-01

    The 99m Tc, continues being the radionuclide more used in nuclear medicine to world scale. The production of this radioisotope, is carried out by means of generators 99 Mo/ 99m Tc that get ready commercially with 99 Mo of high specific activity, adsorbed in alumina (2 mg 99 Mo/g alumina) and that they are elutriated every 23 hours. In an alternative way, it is intended to use gels of titanium molybdates, as matrices of this generators. The gels are synthesized starting from solutions of ammonium molybdates and of titanium tetrachloride in aqueous media. These gels allow to incorporate until 25% of molybdenum in their structure, being been able to use 99 Mo of low specific activity that can be obtained starting from the reaction 98 Mo (n, γ) 99 Mo. With the object of producing generators of medium activity, with the base of gels of titanium molybdates, intends in this work, to study the influence of two synthesis parameters of these gels: the concentration of the titanium solutions and the molar ratio Ti: Mo. The decrease of the concentration of the titanium solution, used during the synthesis of the gels, is converted in an efficiency decrease and radionuclide purity of the generators, as well as an increment so much of the volume of elutriation, as of the pH of the elutriates. The gels that contain an major number of titanium moles, regarding the molybdenum moles, present a greater radionuclide purity, but they diminish their efficiency. The best characteristics for the gels synthesis of titanium molybdates are: a molar ratio 1:1 for Ti and Mo, and to use solutions of titanium whose concentration is near at 1 M. (Author)

  1. Study of different absorbent materials for the preparation of generator systems of {sup 99}Mo - {sup 99m}Tc and {sup 188}W-{sup 188}Re

    Energy Technology Data Exchange (ETDEWEB)

    Lopes, Paula Regina Corain; Osso Junior, Joao Alberto, E-mail: paulinhacorain@usp.b, E-mail: jaosso@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2009-07-01

    Amongst some currently radioisotopes, {sup 99m}Tc and {sup 188}Re present adequate decay properties for use in Nuclear Medicine. In the current times the most diagnosis examinations are performed with {sup 99m}Tc and {sup 188}Re is one radioisotope of potential use in therapy techniques. The objective of this work consists of determining the capacity of some adsorbent materials for retention of molybdenum and tungsten, aiming the optimization of generator systems of {sup 99}Mo-{sup 99m}Tc and {sup 188}W-{sup 188}Re with suitable characteristics for application in Nuclear Medicine. Known amounts, in mass, of molybdenum and tungsten were percolated through different chromatographic columns containing different commercial adsorbent materials such as: PZC (poly-zirconium compound), acid alumina and calcinated alumina used in the routine preparation of {sup 99}Mo-{sup 99m}Tc generators at IPEN. The tungsten ({sup 188}W), as well the PZC used in this project, supplied by Russia and Japan, respectively, through the International Atomic Energy Agency (IAEA) and used without any previous preparation. Also trace amounts of {sup 99}Mo and {sup 188}W were added to the initial solutions and the generators were assembled. The {sup 99}Mo-{sup 99m}Tc generators were then eluted with known volumes of 0.9% NaCl solution every 24 hours whereas the {sup 188}W-{sup 188}Re generators were eluted every 48 hours. The eluted samples were analyzed by Gamma Spectroscopy and later submitted to quality control evaluation. The results showed that the PZC presents superior retention capacity for Mo of 97.50mg Mo/gPZC, higher than in acid and calcinated alumina, however the elution efficiency at lower pHs is not so high. With regards to the experiments carried out with {sup 188}W and alumina, it was verified that the elution efficiency of {sup 188}Re was not reproducible and the retention capacity of W was 90.23mgW/gAl{sub 2}O{sub 3} at pH 7. (author)

  2. The Supply of Medical Radioisotopes. Medical Isotope Supply in the Future: Production Capacity and Demand. Forecast for the 99Mo/99mTc Market, 2015-2020

    International Nuclear Information System (INIS)

    Peykov, Pavel; Cameron, Ron

    2014-04-01

    This document presents a forecast of 99 Mo/ 99m Tc production capacity and demand in 2015-2020, when two major irradiators - the OSIRIS and NRU reactors in France and Canada - are expected to exit the global supply chain and new alternative technology projects may be commissioned. The forecast does not attempt to predict shortages, but identify periods when there is an increased risk of disrupted supply, to inform policy makers and other stakeholders. (authors)

  3. Influence of the Ti concentration and of the Ti:Mo molar ratio, in the efficiency of the {sup 99} Mo - {sup 99m} Tc generator, at basis of gels of titanium molybdates; Influencia de la concentracion de Ti y de la relacion molar Ti:Mo, en la eficiencia del generador {sup 99} Mo - {sup 99m} Tc a base de geles de molibdatos de titanio

    Energy Technology Data Exchange (ETDEWEB)

    Cortes R, O.; Monroy G, F.; Martinez C, T. [Facultad de Quimica, UNAM, 04510 Mexico D.F. (Mexico)]. e-mail: ocielcr@hotmail.com

    2003-07-01

    The {sup 99m} Tc, continues being the radionuclide more used in nuclear medicine to world scale. The production of this radioisotope, is carried out by means of generators {sup 99} Mo/{sup 99m} Tc that get ready commercially with {sup 99} Mo of high specific activity, adsorbed in alumina (2 mg {sup 99} Mo/g alumina) and that they are elutriated every 23 hours. In an alternative way, it is intended to use gels of titanium molybdates, as matrices of this generators. The gels are synthesized starting from solutions of ammonium molybdates and of titanium tetrachloride in aqueous media. These gels allow to incorporate until 25% of molybdenum in their structure, being been able to use {sup 99} Mo of low specific activity that can be obtained starting from the reaction {sup 98} Mo (n, {gamma}) {sup 99} Mo. With the object of producing generators of medium activity, with the base of gels of titanium molybdates, intends in this work, to study the influence of two synthesis parameters of these gels: the concentration of the titanium solutions and the molar ratio Ti: Mo. The decrease of the concentration of the titanium solution, used during the synthesis of the gels, is converted in an efficiency decrease and radionuclide purity of the generators, as well as an increment so much of the volume of elutriation, as of the pH of the elutriates. The gels that contain an major number of titanium moles, regarding the molybdenum moles, present a greater radionuclide purity, but they diminish their efficiency. The best characteristics for the gels synthesis of titanium molybdates are: a molar ratio 1:1 for Ti and Mo, and to use solutions of titanium whose concentration is near at 1 M. (Author)

  4. Human reliability assessment in a 99Mo/99mTc generator production facility using the standardized plant analysis risk-human (SPAR-H) technique.

    Science.gov (United States)

    Eyvazlou, Meysam; Dadashpour Ahangar, Ali; Rahimi, Azin; Davarpanah, Mohammad Reza; Sayyahi, Seyed Soheil; Mohebali, Mehdi

    2018-02-13

    Reducing human error is an important factor for enhancing safety protocols in various industries. Hence, analysis of the likelihood of human error in nuclear industries such as radiopharmaceutical production facilities has become more essential. This cross-sectional descriptive study was conducted to quantify the probability of human errors in a 99 Mo/ 99m Tc generator production facility in Iran. First, through expert interviews, the production process of the 99 Mo/ 99m Tc generator was analyzed using hierarchical task analysis (HTA). The standardized plant analysis risk-human (SPAR-H) method was then applied in order to calculate the probability of human error. Twenty tasks were determined using HTA. All of the eight performance shaping factors (PSF S ) were evaluated for the tasks. The mean probability of human error was 0.320. The highest and the lowest probability of human error in the 99 Mo/ 99m Tc generator production process, related to the 'loading the generator with the molybdenum solution' task and the 'generator elution' task, were 0.858 and 0.059, respectively. Required measures for reducing the human error probability (HEP) were suggested. These measures were derived from the level of PSF S that were evaluated in this study.

  5. Quaternary Pt{sub 2}Ru{sub 1}Fe{sub 1}M{sub 1}/C (M=Ni, Mo, or W) catalysts for methanol electro-oxidation reaction

    Energy Technology Data Exchange (ETDEWEB)

    Jeon, Min Ku; Lee, Ki Rak; Kang, Kweon Ho; Park, Geun Il [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Jeon, Hyung Joon [Kyoto University, Kyoto (Japan); McGinn, Paul J. [University of Notre Dame, Indiana (United States)

    2015-02-15

    Quaternary Pt{sub 2}Ru{sub 1}Fe{sub 1}M{sub 1}/C (M=Ni, Mo, or W) catalysts were investigated for the methanol electro-oxidation reaction (MOR). Electrocatalytic activities of the quaternary catalysts for CO electro-oxidation were studied via CO stripping experiments, and the Pt{sub 2}Ru{sub 1}Fe{sub 1}Ni{sub 1}/C and Pt{sub 2}Ru{sub 1}Fe{sub 1}W{sub 1}/C catalysts exhibited lowered on-set potential compared to that of a commercial PtRu/C catalyst. MOR activities of the quaternary catalysts were determined by linear sweep voltammetry (LSV) experiments, and the Pt{sub 2}Ru{sub 1}Fe{sub 1}W{sub 1}/C catalyst outperformed the commercial PtRu/C catalyst by 170 and 150% for the mass and specific activities, respectively. X-ray photoelectron spectroscopy (XPS) was employed to analyze surface oxidation states of constituent atoms, and it was identified that the structure of the synthesized catalysts are close to a nano-composite of Pt and constituent metal hydroxides and oxides. In addition, the XPS results suggested that the bi-functional mechanism accounts for the improved performance of the Pt{sub 2}Ru{sub 1}Fe{sub 1}Ni{sub 1}/C and Pt{sub 2}Ru{sub 1} Fe{sub 1}W{sub 1}/C catalysts.

  6. Evaluation of the 99Mo contamination in eluates samples generated of 99mTc in a clinic of Recife, Brazil

    International Nuclear Information System (INIS)

    Andrade, W.G.; Lima, F.F.

    2008-01-01

    This study evaluates the 99 Mo content in eluates of 99 Mo/ 99 m Tc generators, used in a nuclear medicine service in Recife. To do this, were collected eluates samples from 5 elution of 10 different generators using the attenuation method in own nuclear medicine service which provided routine activimeter CRC-127R model, manufactured by Capintec. The samples were measured, and the activities of 99m Tc and 99 Mo were determined and calculated the MBT (molybdenum break through) for 1 st , 3 rd , 5 th , 7 th and 9 th elution of each generator. It was observed in a sample the presence of molybdenum in the amount near the limit set by the United States Pharmacopoeia (USP), 0,15μCi/mCi). A second sample presented good high value, more than double the USP limit. The results obtained demonstrate the possibility of finding 99 Mo in the eluted solution, which reinforces the need to deploy the control test of the molybdenum content in all elution in quality control programs of service nuclear medicine

  7. Study of different adsorbent materials for the preparation of generator systems of 99Mo - 99mTc and 188W-188Re

    International Nuclear Information System (INIS)

    Lopes, Paula Regina Corain

    2009-01-01

    Amongst some existing radioisotopes, 99m Tc and 188 Re present adequate physical chemical properties for use in Nuclear Medicine in the areas of diagnosis and therapy, respectively. Moreover, these radioisotopes can be distributed to medical centers in the form of generator systems of 99 Mo- 99m Tc and 188 W- 188 Re, allowing autonomy and practicity in use. The objective of this work consists of determining the capacity of some adsorbent materials for retention of molibdenium and tungsten, aiming the optimization of generator systems of 99 Mo- 99 mTc and 188 W- 188 Re with suitable characteristics for application in Nuclear Medicine. Known amounts, in mass, of molybdenum (Mo) and tungsten (W) were added to the loading solutions previously prepared, with values of pH adjusted between 1 and 7, and these were then percolated through different devices containing in its interior alumina, resin or poly-zirconium compound also known as PZC. The elutions were carried out within an interval of time of approximately 24 hours for the generator systems of 99 Mo - 99 mTc and 48 hours for the generator systems of 188 W- 188 Re due to the difference between the half-lives of radionuclides involved in the reactions. The eluted samples from both generator systems containing 99m Tc or 188 Re were submitted to quality control tests aiming to evaluate the radionuclidic, radiochemical and chemical purity, but no significant contamination for 99 Mo, 188 W, technetium or rhenium in the colloidal states and zirconium were detected in the eluted solutions and in the solutions extracted with saline solution for any value of pH studied. The commercial alumina cartridges known as Acid Sep Pak were more efficient in retaining the molybdenum in the loading solutions when compared with the others commercial retention devices employed. However, when this comparison extends to the chromatographic alumina columns, the use of acid alumina as adsorbent is more efficient when compared to the Acid Sep

  8. Preparation of 99Mo for 99mTc generators and the issue of further development. A survey report

    International Nuclear Information System (INIS)

    Malek, Z.

    1998-01-01

    The following topics are dealt with: World production of Mo-99 for technetium generators; Typical procedures for the preparation of Mo-99; Current and expected decline in the production of Mo-99; and Directions of further development (Water reactors-irradiation systems for the preparation of Mo-99; Homogeneous reactor systems for the preparation of Mo-99 based on molten salts; Systems with accelerators; Thermal processes for the reprocessing of irradiated target material). (P.A.)

  9. The Supply of Medical Radioisotopes. Results from the Second Self-assessment of the Global 99Mo/99mTc Supply Chain

    International Nuclear Information System (INIS)

    Peykov, Pavel; Cameron, Ron

    2014-07-01

    At the request of its member countries, the OECD Nuclear Energy Agency (NEA) became involved in global efforts to ensure a secure supply of 99 Mo/ 99m Tc. Since June 2009, the NEA and its High-level Group on the Security of Supply of Medical Radioisotopes (HLG-MR) examined the issues that led to supply shortages and developed a policy approach, including six principles and supporting recommendations to address those issues. The governments of HLG-MR member countries agreed to implement the policy approach, within three years of its adoption, i.e. by June 2014. In the second mandate of the HLG-MR (2011-2013), the NEA secretariat undertook a review of the 99 Mo/ 99m Tc supply chain, based on input from key supply chain participants, with a focus on full-cost recovery, outage reserve capacity and the governments' role in the market. The results from this first self-assessment were published in Implementation of the HLG-MR Policy Approach: Results from a Self-assessment by the Global 99 Mo/ 99m Tc Supply Chain (NEA, 2013a). In its third mandate (2013-2015), the HLG-MR has continued to evaluate progress towards the implementation of the six policy principles and encourage governments and supply chain participants to take actions for secure supply of 99 Mo/ 99m Tc in the future. This report provides information from the second self-assessment by supply chain participants and analyses the progress made towards the implementation of the HLG-MR policy approach, compared with the first self-assessment. The focus of the second self-assessment is on all agreed policy principles (Principle 6 calls for periodic reviews of the supply chain and is being implemented by undertaking the self-assessment.) The report is organised as follows: Chapter 2 presents a brief summary of the HLG-MR policy approach, including the six principles that are critical to achieving long-term security of supply, and supporting recommendations. Chapter 3 explains the objectives and methodology of the

  10. Electronic and magnetic properties of infinite 1D chains of paddlewheel carboxylates M2(COOR)4 (M = Mo, W, Ru, Rh, Ir, Cu)

    KAUST Repository

    Peskov, Maxim

    2013-03-14

    Dinuclear complexes of transition metals bridged by four carboxylate-groups are examples of stable atomic configurations serving as fundamental building blocks of catalysts and prototypical molecular electronic devices. The electronic structure and magnetic properties of many molecular tetracarboxylate complexes were meticulously studied; however, the properties of the one-dimensional (1D) polymeric chain of associated tetracarboxylates have so far evaded much attention. Using periodic density-functional theory calculations, we analyze the electronic structure of condensed tetracarboxylates Mo(II), W(II), Ru(II), Rh(II), Ir(II), and Cu(II). The relationship between crystal structure of the polymerized tetracarboxylates and the electronic properties of the metal-metal bond in the M24+ core is studied. The electronic effects emanating from the association of dinuclear transition metal tetracarboxylates are important for designing molecular electronic devices. In this study, its influence on both direct and indirect metal-metal interactions, and the electronic structure, in particular transport properties, is discussed. © 2013 American Chemical Society.

  11. Study of fission products (Cs, Ba, Mo, Ru) behaviour in irradiated and simulated nuclear fuels during severe accidents using X-ray absorption Spectroscopy, SIMS and EPMA

    International Nuclear Information System (INIS)

    Geiger, Ernesto

    2016-01-01

    The identification of Fission Products (FP) release mechanism from irradiated nuclear fuels during a severe accident is of main importance for the development of codes for the estimation of the source-term (nature and quantity of radionuclides released into the environment). among the many FP Ba, Cs, Mo and Ru present a particular interest, since they may interact with each other or other elements and thus affect their release. In the framework of this thesis, two work axes have been set up in order to identify, firstly, the chemical phases initially present before the accident and, secondly, their evolution during the accident itself. The experimental approach consisted in reproducing nuclear severe accidents conditions at laboratory scale using both irradiated fuels and model materials (natural UO_2 doped with 12 FP). The advantage of these latter is the possibility of using characterization methods such as X-ray absorption Spectroscopy which are not available for irradiated fuels. Three irradiated fuel samples have been studied, representative to an initial state (before the accident), to an intermediate stage (1773 K) and to an advanced stage (2873 K) of a nuclear severe accident. Regarding to model materials, many accident sequences have been carried out, from 573 to 1973 K. Experimental results have allowed to establish a new release mechanism, considering both reducing and oxidizing conditions during an accident. These results have also demonstrated the importance of model materials as a complement to irradiated nuclear fuels in the study of nuclear severe accidents. (author) [fr

  12. Superconductivity, magnetic susceptibility, and electronic properties of amorphous (Mo/sub 1-x/Ru/sub x/)80P20 alloys obtained by liquid quenching

    International Nuclear Information System (INIS)

    Johnson, W.L.; Poon, S.J.; Duwez, P.

    1977-11-01

    Results of x-ray diffraction, transmission electron diffraction, and crystallization studies on amorphous (Mo/sub 1-x/Ru/sub x/) 80 P 20 alloys obtained by liquid quenching are presented and discussed. The alloys are all found to be superconducting with transition temperatures ranging from approximately 3 0 K to approximately 9 0 K. The variation of T/sub c/ with alloy composition is compared to that obtained by Collver and Hammond for vapor quenched transition metal films. Results of magnetic susceptibility measurements are used to estimate the variation of the electronic density of states at the Fermi level, N(0), from the Pauli paramagnetic contribution. The relationship between the variation of T/sub c/ and N(0) is discussed in terms of the microscope theory of superconductivity. Finally, results of measurements of the upper critical field H/sub c2/, and the normal state electronic transport properties are presented and compared with recent theoretical models for amorphous superconductors

  13. The Supply of Medical Radioisotopes. 2016 Medical Isotope Supply Review: 99Mo/99mTc Market Demand and Production Capacity Projection 2016-2021

    International Nuclear Information System (INIS)

    Charlton, Kevin; )

    2016-03-01

    Medical diagnostic imaging techniques using technetium-99m ( 99 mTc) account for approximately 80% of all nuclear medicine procedures, representing 30-40 million examinations Worldwide every year. Disruptions in the supply chain of these medical isotopes - which have half-lives of 66 hours for molybdenum-99 ( 99 Mo) and only 6 hours for 99m Tc, and thus must be produced continuously - can lead to cancellations or delays in important medical testing services. Supply reliability has been challenged over the past decade due to unexpected shutdowns and extended refurbishment periods at some of the 99 Mo-producing research reactors and processing facilities. These shutdowns have at times created conditions for extended global supply shortages (e.g. 2009-2010). At the request of its member countries, the Nuclear Energy Agency (NEA) became involved in global efforts to ensure a secure supply of 99 Mo/ 99m Tc. Since June 2009, the NEA and its High-level Group on the Security of Supply of Medical Radioisotopes (HLG-MR) have examined the causes of supply shortages and developed a policy approach, including principles and supporting recommendations to address those causes. The NEA has also reviewed the global 99 Mo supply situation periodically, to highlight periods of potential reduced supply and to underscore the case for implementing the HLG-MR policy approach in a timely and globally consistent manner. In 2012, the NEA released a 99 Mo supply and demand forecast up to 2030, identifying periods of potential low supply relative to demand. That 2012 forecast was updated with a report in 2014 that focused on the much shorter 2015-2020 period. That report was updated in 2015 with a report, '2015 Medical Isotope Supply Review: 99 Mo/ 99m Tc Market Demand and Production Capacity Projection 2015-2020' (NEA, 2015), which focused on the same period. This report updates the 2015 report, and focuses on the important 2016-2021 period. At the end of 2015, the OSIRIS reactor

  14. Performance study of molybdenum gels with titanium for preparation of {sup 99}Mo-{sup 99m}Tc generators; Estudo do desempenho de geis de molibdenio com titanio no preparo de geradores de {sup 99}Mo-{sup 99m}Tc

    Energy Technology Data Exchange (ETDEWEB)

    Moraes, Vanessa; Osso Junior, Joao Alberto [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)]. E-mail: vmoraes@ipen.br

    2005-07-01

    {sup 99m}Tc is the most used radioisotope in Nuclear Medicine, due to nuclear characteristics. It is obtained by the radioactive decay of {sup 99}Mo, generator of radioisotope system. When {sup 99}Mo is produced by the activation in reactor, the most used technique for the preparation of the generators is the gel type generator, which incorporates {sup 99}Mo to the gel that is insoluble, chemically inert to the solutions and with properties of ion exchange. Several countries had already studied this methodology, as is the case of Vietnam, India, China, Australian. This work has the objective of studying the performance and characterization of molybdenum gels with titanium. Four variables in the preparation of the gel were studied: mass ratio between Mo and Ti (1.80 and 2.25), concentration of NaOH (2 and 4 mol/L), final temperature (25 and 50 deg C) and pH (3.5 and 4.5). The prepared gels were analyzed with relation to the size of its particles, identification of its structure, amount of molybdenum, amount of titanium, profile of elution, pH of the elution, determination of the radioisotopes in the eluate and final radiochemical purity. The final result is a formularization of the gel with the best characteristics for posterior preparation of the generator of {sup 99m}Tc-{sup 99}Mo. (author)

  15. labeling of some organic compounds of expected biological activity with Tc-99m eluted from a chromatographic column packed with zirconium molybdate containing mo-99

    International Nuclear Information System (INIS)

    Abd Elaal, M.A.A.

    2011-01-01

    The growth of nuclear medicine has been due mainly to the availability of 99m Tc-radiopharmaceuticals; this single isotope is used in over 80% of all diagnostic procedures. Each year, roughly 25 million procedures are carried out with 99m Tc-radio-pharmaceuticals, the universal use of this radioisotope (Technetium-99m, t 1/2 = 6.02 h) is due to its advantageous properties such as suitable half-life (it is short enough to save the patient from high radiation dose, and long enough to carry out labeling and scintigraphic measurements), γ-ray energy (140 keV; 89.4%) reasonable for SPECT, and very low abundance β - emission. Technetium-99m is readily available in a sterile, pyrogen free, and no-carrier added state from 99 Mo/ 99m Tc generators.The selection of iminodiacetic acid (IDA) derivatives to target 99m Tc as radioactive element to the hepatobiliary system is based on the reported finding that iminodiacetic acid capable of complexing reduced Tc-99m and easily incorporated into biologically active molecules. 99m Tc labeled iminodiacetic acid (IDA) derivatives offer a high degree of specificity for localization in the gallbladder with rapid extraction by the polygonal cells of the liver and very low urinary excretion. Various diseases related to liver function, such as jaundice and biliary obstruction, are diagnosed by the use of 99m Tc-labeled IDA derivatives. Chronic and acute cholecystitis can be differentiated with 99m Tc-IDA derivatives.In the presented work, 99m Tc in an acceptable radionuclidic, radiochemical and chemical purity using an easy and cheap method was produced. The produced 99m Tc was suitable to be used in the labeling techniques and in studying of the biological behavior of some synthesized iminodiacetic acid derivatives (1-naphthyl carbamoylmethyl iminodiacetic acid (NIDA), Diphenyl methyl carbamoylmethyl iminodiacetic acid (DMIDA) and Biphenyl-2-yl carbamoylmethyl iminodiacetic acid (BPIDA)). NIDA, DMIDA and BPIDA were synthesized and well

  16. The Supply of Medical Radioisotopes. 2015 Medical Isotope Supply Review: 99Mo/99mTc Market Demand and Production Capacity Projection 2015-2020

    International Nuclear Information System (INIS)

    Charlton, Kevin; )

    2015-08-01

    Medical diagnostic imaging techniques using technetium-99m ( 99m Tc) account for approximately 80% of all nuclear medicine procedures, representing 30-40 million examinations Worldwide every year. Disruptions in the supply chain of these medical isotopes - which have half-lives of 66 hours for molybdenum-99 ( 99 Mo) and only 6 hours for 99m Tc, and thus must be produced continuously - can lead to cancellations or delays in important medical testing services. Unfortunately, supply reliability has been challenged over the past decade due to unexpected shutdowns and extended refurbishment periods at some of the mostly ageing, 99 Mo-producing research reactors and processing facilities. These shutdowns have at times created conditions for extended global supply shortages (e.g. 2009-2010). At the request of its member countries, the Nuclear Energy Agency (NEA) became involved in global efforts to ensure a secure supply of 99 Mo/ 99m Tc. Since June 2009, the NEA and its High-level Group on the Security of Supply of Medical Radioisotopes (HLG-MR) have examined the causes of supply shortages and developed a policy approach, including principles and supporting recommendations to address those causes. The NEA has also reviewed the global 99 Mo supply situation periodically, using the most up-to-date data available from supply chain participants, to highlight periods of potential reduced supply and to underscore the case for implementing the HLG-MR policy approach in a timely and globally consistent manner. In 2012, the NEA released a M o supply and demand forecast up to 2030, identifying periods of potential low supply relative to demand. That 2012 forecast was updated with a report 'Medical Isotope Supply in the Future: Production Capacity and Demand Forecast for the 99 Mo/ 99m Tc Market 2015-2020' (NEA, 2014) in 2014 that focused on the much shorter 2015-2020 period. This report updates the 2014 report, and continues to focus on the potentially critical 2015

  17. DFT investigation of electronic structures and magnetic properties of halides family MeHal3 (Me=Ti, Mo,Zr,Nb, Ru, Hal=Cl,Br,I) one dimensional structures

    Science.gov (United States)

    Kuzubov, A. A.; Kovaleva, E. A.; Popova, M. I.; Kholtobina, A. S.; Mikhaleva, N. S.; Visotin, M. A.; Fedorov, A. S.

    2017-10-01

    Using DFT GGA calculations, electronic structure and magnetic properties of wide family of transition metal trihalides (TMHal3) (Zr, Ti and Nb iodides, Mo, Ru, Ti and Zr bromides and Ti or Zr chlorides) are investigated. These structures consist of transition metal atoms chains surrounded by halides atoms. Chains are connected to each other by weak interactions. All TMHal3 compounds were found to be conductive along chain axis except of MoBr3 which is indirect gap semiconductor. It was shown that NbI3 and MoBr3 have large magnetic moments on metal atoms (1.17 and 1.81 μB, respectively) but other TMHal3 materials have small or zero magnetic moments. For all structures ferromagnetic and anti-ferromagnetic phases have almost the same energies. The causes of these properties are debated.

  18. Influence of alumina phases on the molybdenum adsorption capacity and chemical stability for {sup 99}Mo/{sup 99m}Tc generators columns

    Energy Technology Data Exchange (ETDEWEB)

    Guedes-Silva, Cecilia C.; Ferreira, Thiago dos Santos; Paula, Carolina M. de; Otubo, Larissa, E-mail: cecilia.guedes@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil); Carvalho, Flavio M.S. [Universidade de Sao Paulo (IGC/USP), SP (Brazil). Instituto de Geociencias

    2016-07-15

    Technetium-{sup 99m} is the clinically most used radionuclide worldwide. Although many techniques can be applied to separate {sup 99}Mo and {sup 99m}Tc, the most commonly used method is the column chromatography with alumina as stationary phase. However, the alumina nowadays used has limited adsorption capacity of molybdate ions which implies the need to develop or improve materials to produce high specific activity generators. In this paper, alumina was obtained by a solid state method and heat treatments at different conditions. The powders had a microstructure with porous particles of γ, δ, θ and α-Al{sub 2}O{sub 3} phases as well as specific surface area between 36 and 312 m{sup 2} g{sup -1}. Most interesting results were reached by powders calcined at 900 deg C for 5 hours which had high chemical stability and a molybdenum adsorption capacity of 92.45 mg Mo per g alumina. (author)

  19. Pseudogap behavior of RuP probed by photoemission spectroscopy

    OpenAIRE

    Sato, K.; Ootsuki, D.; Wakisaka, Y.; Saini, N. L.; Mizokawa, T.; Arita, M.; Anzai, H.; Namatame, H.; Taniguchi, M.; Hirai, D.; Takagi, H.

    2012-01-01

    We have studied the electronic structure of RuP and related Ru pnictides using photoemission spectroscopy. Ru 3d core-level and valence-band spectra of RuP show that the Ru valence is +3 with t_{2g}^5 configuration. The photoemisson spectral weight near the Fermi level is moderately suppressed in the pseudogap phase of RuP, consistent with the pseudogap opening of 2\\Delta/k_BT_c ~ 3 (gap size \\Delta ~ 50 meV and transition temperature T_c ~ 330 K). The Ru 3d peak remains sharp in the pseudoga...

  20. A Novel Ruthenium-Decorating Polyoxomolybdate Cs3Na6H[MoVI14RuIV2O50(OH2]·24H2O: An Active Heterogeneous Oxidation Catalyst for Alcohols

    Directory of Open Access Journals (Sweden)

    Rong Wan

    2018-01-01

    Full Text Available The first example of wholly inorganic ruthenium-containing polyoxomolybdate Cs3Na6H[MoVI14RuIV2O50(OH2]·24H2O (1 was isolated and systematically characterized by element analysis, infrared spectroscopy (IR, thermogravimetric analyses (TGA, X-ray photoelectron spectroscopy (XPS, energy dispersive X-ray spectroscopy (EDX and single-crystal X-ray diffraction. Compound 1 is composed of an unprecedented {Mo14}-type isopolymolybdate with a di-ruthenium core precisely encapsulated in its center, exhibiting a three-tiered ladder-like structure. The title compound can act as an efficient heterogeneous catalyst in the transformation of 1-phenylethanol to acetophenone. This catalyst is also capable of being recycled and reused for at least ten cycles with its activity being retained under the optimal conditions.

  1. Effect of milking efficiency on Tc-99 content of Tc-99m derived from Tc-99m generators

    International Nuclear Information System (INIS)

    Bonnyman, J.

    1983-01-01

    Tc-99m obtained by separation from its parent Mo-99 always contains Tc-99 produced by decay of Tc-99m and Mo-99. Factors effecting the Tc-99/Tc-99m ratios are discussed. An HPLC method has been developed to measure the 99 TcO 4- content of sodium pertechnetate from generators with a detection limit of 0.9 ng Tc-99 for a 500 μl/ aliquot of TcO 4- -99m. First eluates of 10 chromatograph-ic generators gave Tc-99/Tc-99m ratios ranging from 3.5-46 ng Tc/mCi Tc-99m measured at the time of milking. The measurements indicate that Tc-99/Tc-99m ratios high enough to cause adverse labelling effects could be found in 'instant pertechnetate' and in the first eluate from Tc-99m generators for the activities normally used in radiopharmaceutical production

  2. High performance Mo adsorbent PZC

    Energy Technology Data Exchange (ETDEWEB)

    Anon,

    1998-10-01

    We have developed Mo adsorbents for natural Mo(n, {gamma}){sup 99}Mo-{sup 99m}Tc generator. Among them, we called the highest performance adsorbent PZC that could adsorb about 250 mg-Mo/g. In this report, we will show the structure, adsorption mechanism of Mo, and the other useful properties of PZC when you carry out the examination of Mo adsorption and elution of {sup 99m}Tc. (author)

  3. Reaction of H{sub 2}S with MoRu(CO){sub 6}(dppm){sub 2} to give H{sub 2} and a bridged-sulfide product via hydrido-sulfhydryl intermediates (dppm equals Ph{sub 2}PCH{sub 2}PPh{sub 2})

    Energy Technology Data Exchange (ETDEWEB)

    Khorasani-Motlagh, M. [Sistan and Baluchestan Univ., Zahedan (Iran, Islamic Republic of). Dept. of Chemistry; Safari, N. [Shahid Beheshti Univ., Tehran (Iran, Islamic Republic of). Dept. of Chemistry; Pamplin, C.B.; Patrick, B.O.; James, B.R. [British Columbia Univ., Vancouver, BC (Canada). Dept. of Chemistry

    2006-02-15

    The reactivity of hydrogen sulphide toward transition metal complexes was studied with particular focus on the reactions of hydrogen sulphide (H{sub 2}S) with solutions of bimetallic-dppm complexes. The complex MoRu(CO){sub 6}({mu}-dppm){sub 2} (1) (dppm equals Ph{sub 2}PCH{sub 2}PPh{sub 2}) reaction toward hydrogen sulphide was examined because of the fact that Ru is the second-row analogue of Fe and because of the key role of sulphur ligands in the Mo-Fe enzyme systems. This paper reported on the interaction of the Mo-Ru complex with hydrogen sulphide to form the bridged sulphide complex Mo(CO){sub 2}({mu}-CO)({mu}-S)(dppm){sub 2}Ru(CO) which can be synthesized with elemental sulphur. Oxidative addition of H{sub 2}S to MoRu(CO){sub 6}({mu}-dppm){sub 2} (1) at 20 degrees C in toluene yields an isolable complex formulated as Mo(CO){sub 3}({mu}-SH)({mu}-CO)({mu}-dppm){sub 2}RuH(CO) (2) via the possible intermediate Mo(CO){sub 3}({mu}-H)({mu}-CO)({mu}-dppm){sub 2}Ru(SH)(CO) (4) (dppm equals Ph{sub 2}PCH{sub 2}PPh{sub 2}) that is detectable at lower temperatures. Over 2 days, species 2 in toluene lost H{sub 2} (and CO) to yield the bridged-sulfide product, Mo(CO){sub 2}({mu}-CO)({mu}-S)({mu}-dppm){sub 2}Ru(CO) (5) that is also formed directly from the reaction of 1 with elemental sulfur. The solid-state molecular structure of 5 was determined by X-ray crystallography. A further hydrido-sulfhydryl species was found to be in equilibrium with 2 at ambient temperature. It was concluded that it is not impossible that hydrogen sulphide can react in a concerted manner with dimetallic precursors, without prior formation of an adduct. 24 refs., 2 tabs., 3 figs.

  4. Thermodynamic assessment of the rhodium-ruthenium-oxygen (Rh-Ru-O) system

    Science.gov (United States)

    Gossé, S.; Bordier, S.; Guéneau, C.; Brackx, E.; Domenger, R.; Rogez, J.

    2018-03-01

    Ruthenium (Ru) and rhodium (Rh) are abundant platinum-group metals formed during burn-up of nuclear fuels. Under normal operating conditions, Rh and Ru accumulate and predominantly form metallic precipitates with other fission products like Mo, Pd and Tc. In the framework of vitrification of high-level nuclear waste, these fission products are poorly soluble in molten glasses. They precipitate as metallic particles and oxide phases. Moreover, these Ru and Rh rich phases strongly depend on temperature and the oxygen fugacity of the glass melt. In case of severe accidental conditions with air ingress, oxidation of the Ru and Rh is possible. At low temperatures (T 1422 K for rhodium sesquioxide and T > 1815 K for ruthenium dioxide), they may decompose into (Rh)-FCC or (Ru)-HCP metallic phases and radiotoxic volatile gaseous species. A thermodynamic assessment of the Rh-Ru-O system will enable the prediction of: (1) the metallic and oxide phases that form during the vitrification of high-level nuclear wastes and (2) the release of volatile gaseous species during a severe accident. The Calphad method developed herein employs a thermodynamic approach in the investigation of the thermochemistry of rhodium and ruthenium at high temperatures. Current literature on the thermodynamic properties and phase diagram data enables preliminary thermodynamic assessments of the Rh-O and Ru-O systems. Additionally, select compositions in the ternary Rh-Ru-O system underwent experimental tests to complement data found in literature and to establish the phase equilibria in the ternary system.

  5. Comparison of elution efficiency of 99Mo/99mTc generator using theoretical and a free web based software method

    International Nuclear Information System (INIS)

    Kiran Kumar, J.K.; Sharma, S.; Chakraborty, D.; Singh, B.; Bhattacharaya, A.; Mittal, B.R.; Gayana, S.

    2010-01-01

    Full text: Generator is constructed on the principle of decay growth relationship between a long lived parent radionuclide and short lived daughter radionuclide. Difference in chemical properties of daughter and parent radionuclide helps in efficient separation of the two radionuclides. Aim and Objectives: The present study was designed to calculate the elution efficiency of the generator using the traditional formula based method and free web based software method. Materials and Methods: 99 Mo/ 99m Tc MON.TEK (Monrol, Gebze) generator and sterile 0.9% NaCl vial and vacuum vial in the lead shield were used for the elution. A new 99 Mo/ 99m Tc generator (calibrated activity 30GBq) calibrated for thursday was received on monday morning in our department. Generator was placed behind lead bricks in fume hood. The rubber plugs of both vacuum and 0.9% NaCl vial were wiped with 70% isopropyl alcohol swabs. Vacuum vial placed inside the lead shield was inserted in the vacuum position simultaneously 10 ml NaCl vial was inserted in the second slot. After 1-2 min vacuum vial was removed without moving the emptied 0.9%NaCl vial. The vacuum slot was covered with another sterile vial to maintain sterility. The RAC was measured in the calibrated dose calibrator (Capintec, 15 CRC). The elution efficiency was calculated theoretically and using free web based software (Apache Web server (www.apache.org) and PHP (www.php.net). Web site of the Italian Association of Nuclear Medicine and Molecular Imaging (www.aimn.it). Results: The mean elution efficiency calculated by theoretical method was 93.95% +0.61. The mean elution efficiency as calculated by the software was 92.85% + 0.89. There was no statistical difference in both the methods. Conclusion: The free web based software provides precise and reproducible results and thus saves time and mathematical calculation steps. This enables a rational use of available activity and also enabling a selection of the type and number of

  6. Production and availability of 99mTc generators and of 99Mo: technology considerations and the IAEA's contributions

    International Nuclear Information System (INIS)

    Ramamoorthy, N.; )

    2007-01-01

    The serendipitous discovery of 99m T c generator at the BNL, USA in 1957 laid the foundation for the subsequent revolution of in vivo imaging of physiological functions in humans to aid diagnostic decisions and patient management. The widespread use of diagnostic imaging in nuclear medicine would not have attained a pre-eminent status world over but for the 99m T c generator and 99m T c labelled products. In order to sustain the nearly 20 million studies annually performed using 99m T c , it is of utmost importance to assure access to appropriate technologies for continued, reliable availability of 99m T c generators and in turn, that of the raw material radionuclide 99 Mo required in extremely large quantities. A walk down the path of their production technologies to trace the trends and issues reveals several major milestones. The IAEA has been involved for well over three decades in fostering developments in 99m T c generator systems through (i) implementation of a number of CRPs including an on-going one related to the production of 99 Mo using LEU targets, (ii) arranging expert reviews through Technical/Consultancy Meetings and (iii) publication of various technical documents, e.g. IAEA-TECDOC: 515 (1989), 852, (1995), 1051 (1998) and 1065 (1999). The IAEA has also supported a number of interested Member States in establishing and/or operating 99m T c generator production facilities, as for example in Bangladesh, China, Indonesia, Iran, Pakistan and Syria. The author has been involved in several of the above initiatives of the IAEA and was also an active participant in the Indian programmes on 99m T c generators during 1972 to 2003. The present review is accordingly tailored as a narration, interspersed with the IAEA's important contributions and glimpses of the Indian scenario. (author)

  7. Importance of a 99Mo/99mTc generator and a perspective of nuclear medicine in the face of the difficult situation of supply shortage of 99mTc from the view-point of a nuclear medicine specialist

    International Nuclear Information System (INIS)

    Kosuda, Shigeru

    2010-01-01

    In this review a list of commercially available 99m Tc-labeled radiopharmaceuticals was presented, and the significance to use them clinically was described in the face of this difficult situation due to the 99m Tc shortage. The supply history and the chronological change in the sales of 99 Mo/ 99m Tc generators in Japan were also described. I emphasize the importance of a nationwide spread of dedicated single photon emission computed tomography (SPECT)/CT equipments, which provide not only a simultaneous acquisition of dual tracers, but also information on both function and morphology. The present issues to address this difficult situation were discussed, referring to the summary of the Organization for Economic Co-operation and Development (OECD)/the Nuclear Energy Agency (NEA) workshop held in Paris and the press conference at the 56 th Society of Nuclear Medicine (SNM) annual meeting held in Toronto. The results of a questionnaire survey conducted in Saitama prefecture suggested the procedures, such as a domestic self-supply of 99 Mo, to resolve the issues related to the shortage. In addition, the ongoing Japan Materials Testing Reactor (JMTR) project regarding self-supply of 99 Mo was described. Based on a reliable supply of 99m Tc, the following suggestions to develop nuclear medicine were presented from the viewpoint of a nuclear medicine specialist; development of a brand-new SPECT/CT equipment using semi-conductor, clinical application of new tracers, and reassessment of the existing SPECT studies. (author)

  8. Correlation factors for C-14, Cl-36, Ni-59, Ni-63, Mo-93, Tc-99, I-129 and Cs-135. In operational waste for SFR 1

    Energy Technology Data Exchange (ETDEWEB)

    Lindgren, Maria; Pettersson, Michael; Wiborgh, Marie (Kemakta AB, Stockholm (SE))

    2007-01-15

    The use of correlation factors is one possibility to estimate a reference radionuclide inventory for the purpose of safety assessment studies, when waste-type specific information is not at hand. The correlation factor approach requires that there is a correlation between the activity content of the difficult-to-measure nuclide and the key nuclide. A safety assessment of a future deep repository for low and intermediate level waste (SFL 3-5) was conducted during the second half of the 1990's. Within that project, correlation factors for estimating the inventory of radionuclides which are difficult to measure experimentally were developed. These factors have also partly been used to estimate a reference inventory for SFR 1. Based on a literature survey and recent reports published by SKB, it is concluded that new information is available making an update of some correlation factors relevant. For these radionuclides, reported data from estimations and measurements of radionuclide content and correlation factors in different types of radioactive wastes are summarised. The data is evaluated and updated correlation factors representative for fresh waste for eight radionuclides (C-14, Cl-36, Ni-59, Ni-63, Mo-93, Tc-99, I-129 and Cs-135) are suggested. New information from measurements in Swedish NPP has made it possible to define factors that are BWR and PWR specific for C-14, Ni-59 and Ni-63. The uncertainties in suggested data and the applicability of the correlation factors for estimates of the radionuclide content in operational waste are commented upon

  9. All-atom force field for molecular dynamics simulations on organotransition metal solids and liquids. Application to M(CO)(n) (M = Cr, Fe, Ni, Mo, Ru, or W) compounds.

    Science.gov (United States)

    Bernardes, Carlos E S; Canongia Lopes, José N; Minas da Piedade, Manuel E

    2013-10-31

    A previously developed OPLS-based all-atom force field for organometallic compounds was extended to a series of first-, second-, and third-row transition metals based on the study of M(CO)(n) (M = Cr, Fe, Ni, Mo, Ru, or W) complexes. For materials that are solid at ambient temperature and pressure (M = Cr, Mo, W) the validation of the force field was based on reported structural data and on the standard molar enthalpies of sublimation at 298.15 K, experimentally determined by Calvet-drop microcalorimetry using samples corresponding to a specific and well-characterized crystalline phase: Δ(sub)H(m)° = 72.6 ± 0.3 kJ·mol(–1) for Cr(CO)(6), 73.4 ± 0.3 kJ·mol(–1) for Mo(CO)(6), and 77.8 ± 0.3 kJ·mol(–1) for W(CO)(6). For liquids, where problems of polymorphism or phase mixtures are absent, critically analyzed literature data were used. The force field was able to reproduce the volumetric properties of the test set (density and unit cell volume) with an average deviations smaller than 2% and the experimentally determined enthalpies of sublimation and vaporization with an accuracy better than 2.3 kJ·mol(–1). The Lennard-Jones (12-6) potential function parameters used to calculate the repulsive and dispersion contributions of the metals within the framework of the force field were found to be transferable between chromium, iron, and nickel (first row) and between molybdenum and ruthenium (second row).

  10. A new detection method of 99Tc by nuclear excitation

    International Nuclear Information System (INIS)

    Sekine, T.; Yoshihara, Kenji; Nemeth, Zs.; Lakosi, L.; Veres, A.

    1989-01-01

    A new nuclear excitation process, 99 Tc(γ,γ') 99m Tc reaction, was applied for the first time to radioactivation analysis of technetium. Bremsstrahlung irradiation of 99 Tc samples gave the reaction product 99m Tc which emits γ-ray easily measurable by a semiconductor detector. The production rate of 99m Tc per μg 99 Tc was linearly correlated with the flux of bremsstrahlung. The detection limit of 99 Tc was estimated to be nanogram order (0.63 Bq 99 Tc) under the optimum irradiation condition. Possible interference by 100 Ru(γ, p) 99m Tc reaction was also studied, which could be discriminated from the (γ,γ') reaction by simultaneously occurring 98 Ru(γ,p) 97 Ru reaction. (author) 17 refs.; 7 figs

  11. Decay of 99Mo

    International Nuclear Information System (INIS)

    Dickens, J.K.; Love, T.A.

    1976-01-01

    Relative intensities for K x-rays and gamma rays emanating from 99 Mo in equilibrium with its 99 Tc* daughter have been measured using several Ge photon detectors. Combining these intensities with an evaluated set of electron-conversion coefficients has provided a set of absolute intensities for the observed gamma rays. The absolute intensity for the dominant 140.5-keV gamma ray in 99 Tc was determined to be 90.7 +- 0.6/100 99 Mo disintegrations for 99 Mo decay in equilibrium with decay of the 99 Tc* daughter

  12. Preparation of Sr{sub 2}(MgMo){sub 1-x}Ru{sub x}O{sub 6} ceramics for use in a solid oxide fuel cell anode

    Energy Technology Data Exchange (ETDEWEB)

    Bezerra, Matheus Eiji Ohno; Florio, Daniel Zanetti de [Universidade Federal do ABC (UFABC), SP (Brazil); Fonseca, Fabio Coral, E-mail: matheus.eiji@aluno.ufabc.edu.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2016-07-01

    Full text: Solid Oxide Fuel Cells are the most efficient devices known for the direct conversion of fuels into electric energy. Such devices have advanced steadily and are already available for specific applications such as portable power and residential stationary generation. The main objective of this work is the development of anodes for SOFC operating directly with renewable fuels, without the addition of water and using strategic fuels such as ethanol and natural gas. Specifically, a family of mixed ionic-electronic compounds has been investigated: the double perovskites with compositions Sr{sub 2}(MgMo){sub 1-x}Ru{sub x}O{sub 6} with x = 0; 1; 2; 5; 10 e 20 at.%. This material has been synthesized by polymeric precursor method. The resins were prepared by combining stoichiometric amounts of the starting solutions. The resulting solution was heated treated under magnetic stirring. The thermal decomposition of the polymeric resin was studied by means of simultaneous thermogravimetric and differential scanning calorimetry up to 1500 °C with heating and cooling rates of 10 °/min in Ar. The thermal decomposition result shows mass loss up to, approximately, 900 °C. However X-ray diffraction analyses of the powder heat treated at 900 °C and 1200 °C presents a considerable content of an undesiderate phase (SrMoO{sub 4}). According to the literature for similar compounds a thermal treatment under reduction conditions could be necessary to obtain the double perovskites single phase. After this treatment the material will be characterized regarding its electrical properties. The expected results will contribute to advance both the understanding of the mixed ionic electronic ceramics and the SOFC technology using renewable fuels. (author)

  13. The Supply of Medical Radioisotopes. Implementation of the HLG-MR Policy Approach: Results from a Self-assessment by the Global 99Mo/'99mTc Supply Chain

    International Nuclear Information System (INIS)

    Peykov, Pavel; Cameron, Ron

    2013-03-01

    At the request of its member countries, OECD/NEA became involved in global efforts to ensure a secure supply of 99 Mo and ' 99m Tc. Since June 2009, the NEA and its High-level Group on the Security of Supply of Medical Radioisotopes (HLG-MR) examined the causes of supply shortages and developed a policy approach, including principles and supporting recommendations to address those causes. The 'Economic Study' of the molybdenum-99 ( 99 Mo) and technetium-99m (' 99m Tc) supply chain published by the NEA clearly demonstrated that the pricing structure at nuclear research reactors prior to the most recent supply shortage in 2009-10 was not economically sustainable. Host nations traditionally subsidised the cost of irradiation services for 99 Mo production, along with experimental research at reactors. With a move away from subsidising 99 Mo production that often benefits foreign nations or foreign companies, pricing must recover the full cost of production to ensure economic sustainability and a long-term secure supply of medical isotopes. Appropriate pricing would also encourage an efficient use of the product, reducing wasted 99 Mo/' 99m Tc and thus reducing excess production and the associated radioactive waste. A key principle adopted by the HLG-MR was that all producers should move towards full-cost recovery and should implement the other principles adopted by the group. In February 2012, the NEA web-published a guidance document with a methodology for full- cost recovery and an associated Excel spreadsheet. This costing methodology identifies the essential elements that should be included when determining the full cost of 99 Mo irradiation services and how these elements should be allocated between various missions in the case of multipurpose facilities. The application of the costing methodology at all 99 Mo/' 99m Tc-producing research reactors and other production technology facilities within the global supply chain will ensure a common approach to full

  14. Spectroscopy of 96-98Ru and neighboring nuclei: shell model calculations and lifetime measurements

    International Nuclear Information System (INIS)

    Kharraja, B.; Garg, U.; Ghugre, S.S.

    1997-01-01

    High Spin states in 94,95 Mo, 94-96 Tc, 96-98 Ru and 97,98 Rh were populated via the 65 Cu( 36 S,xpyn) reactions at 142 MeV. Level schemes of these nuclei have been extended up to a spin of J ∼ 20ℎ and an excitation energy of E x ∼12 -14 MeV. Information on the high spin structure for 96 Tc and 98 Rh has been obtained for the first time. Spherical shell model calculations have been performed and compared with the experimental excitation energies. The level structures of the N=51, 52 isotones exhibit single-particle nature even at the highest spins and excitation energies. A fragmentation of intensity into several branches after breaking of the N = 50 core has been observed. There are indications for the onset of collectivity around neutron number N = 53 in this mass region. A sequence of E2 transitions, reminiscent of vibrational degree of freedom, were observed in 98 Ru at spins just above the observed N = 50 core breaking. RDM lifetime measurements have been performed to ascertain the intrinsic structures of these level sequences. (author)

  15. MO-F-CAMPUS-I-05: Radiation Dosimetry of 99mTc-IDA-D-[c(RGDfK)]2, a SPECT Agent for Angiogenesis Imaging

    Energy Technology Data Exchange (ETDEWEB)

    Kim, J [Korea Research Institute of Standards and Science, Daejeon (Korea, Republic of)

    2015-06-15

    Purpose: Tc-99m labeled IDA-D-[c(RGDfK){sub 2} ( {sup 99m}Tc-RGD) is a recently developed radiotracer for gamma camera or single photon emission computed tomography (SPECT) imaging and promising agent for the visualization of angiogenesis. In this study, we investigated the internal radiation dosimetry of {sup 99m}Tc-RGD in humans. Methods: Six normal controls (F:M=4:2; 68.3±3.2 years; 56.5±10.7 kg) were participated in this study. Simultaneous anterior and posterior scans of whole-body were performed using dual head gamma camera system. Before the emission scan, transmission scan was performed just before injection of {sup 99m}Tc-RGD using Co-57 flood source. After an intravenous injection of 388.7±29.3 MBq of {sup 99m}Tc-RGD, six serial emission scans were performed at 0, 1, 2, 4, 8 and 24 hours post-injection. The anterior and posterior images were geometrically averaged and attenuation correction was applied using transmission scan image. Regions of interest (ROIs) were drawn on liver, gallbladder, kidneys, urinary bladder, spleen, brain, and large intestine. Time activity curves were obtained from serial emission scan and ROIs. The number of disintegrations per unit activity administered (residence time) were calculated from the area under the curve of time activity curves and injected dose of each patient. Finally, the radiation dose for each organ and effective doses were obtained using OLINDA/EXM 1.1 software and residence time. Results: High radiation doses were reported on renal and biliary excretion tracks such as urinary bladder wall, upper large intestine, kidneys, liver and gallbladder wall and their doses were 19.15±6.84, 19.28±4.78, 15.67±0.90, 9.13±1.71 and 9.09±2.03 µGy/MBq, respectively. The effective dose and effective dose equivalent were 5.08±0.53 and 7.11±0.58 µSv/MBq, respectively. Conclusion: We evaluated the radiation dose of 99mTc-RGD, which has an acceptable effective radiation dose compare to the other Tc-99m labeled radio-tracers.

  16. 99Mo production by 100Mo(n,2n)99Mo using accelerator neutrons

    International Nuclear Information System (INIS)

    Sato, Nozomi; Kawabata, Masako; Nagai, Yasuki; Hashimoto, Kazuyuki; Hatsukawa, Yuichi; Saeki, Hideya; Motoishi, Shoji; Kin, Tadahiro; Konno, Chikara; Ochiai, Kentaro; Takakura, Kosuke; Minato, Futoshi; Iwamoto, Osamu; Iwamoto, Nobuyuki; Hashimoto, Shintaro

    2013-01-01

    We proposed a new route to produce a medical radioisotope 99 Mo by the 100 Mo(n,2n) 99 Mo reaction using accelerator neutrons. A high-quality 99 Mo with a minimum level of radioactive waste can be obtained by the proposed reaction. The decay product of 99 Mo, 99m Tc, is separated from 99 Mo by the sublimation method. The proposed route could bring a major breakthrough in the solution of ensuring a constant and reliable supply of 99 Mo. (author)

  17. X-ray fluorescence analysis of Fe - Ni - Mo systems

    International Nuclear Information System (INIS)

    Belyaev, E.E.; Ershov, A.V.; Mashin, A.I.; Mashin, N.I.; Rudnevskij, N.K.

    1998-01-01

    Procedures for the X-ray fluorescence determination of the composition and thickness of Fe - Ni - Mo thin films and the concentration of elements in thick films of the Fe - Ni - Mo alloy are developed [ru

  18. Investigation on the performance of polymer zirconium compound (PZC) for chromatographic Tc-99m generator preparation

    International Nuclear Information System (INIS)

    Le Van So

    2004-01-01

    The performance of PZC was investigated for chromatographic Tc-99m generator preparation. Mo-adsorption of PZC in different Mo-solutions and Tc-99m elution of 99 Mo-PZC column were studied. Mo- adsorption capacity of higher than 250mgMo/gPZC and Tc-99m elution yield of higher than 80% were achieved with PZC adsorbent. Mo-99 breakthrough of 0.02% and Molybdenum element breakthrough of around 5μg Mo/ml were found in Tc-99m eluate. A good relationship between the Mo-content of adsorption solution and the Mo-adsorption capacity, adsorption percentage, Mo-breakthrough and Tc-99m elution yield was found. The preparation of PZC based Tc-99m chromatographic generator with 4 gram weight of PZC was successfully conducted. (author)

  19. Process modifications of obtaining Tc-99m by solvent extraction

    International Nuclear Information System (INIS)

    Leon, A.; Verdera, S.

    1978-01-01

    This paper describes a modification in the process to obtaining Tc-99m by the extraction method of solvent from Mo-99 produced by irradiation. Tc-99m is considered an ideal radionuclide for medical and biological applications

  20. 93Tc and sup(93m)Tc gamma spectra

    International Nuclear Information System (INIS)

    Podkopaev, Yu.N.; Zarubin, P.P.; Kobelev, V.F.; Padalko, V.Yu.; Khrisanfov, Yu.V.

    1977-01-01

    The sup(93,93m)Tc decay was studied. The spectra of γ-rays accompanying the decay of this nuclide were studied. 93 Tc and sup(93m)Tc were obtained in the (dn)-reaction on 92 Mo. To ensure a more reliable identification of γ-rays, the isotopic composition of the targets, the bombardment time, the energy of the bombarding deuterons (5-12 MeV) and the spectrum processing program were varied. The energies and relative intensities of the γ-rays of the 93 Tc and sup(93m)Tc decay are listed in tables together with data of other investigatxons. The results obtained largely confirm the known data. Four new transitions were added in the sup(93m)Tc spectrum namely 1046.8, 2011.8, 2182.0, and 2861.5 keV. The 2739.0 keV transition was eliminated from the 93 Tc spectrum. The appropriate changes and additions were made in the 93 Tc decay scheme, and three new levels were introduced: 2479.0, 2821.7, and 3025.8 keV. The values of log ft of some levels of 93 Tc were estimated

  1. 99Tc atom counting by quadrupole ICP-MS. Optimisation of the instrumental response

    International Nuclear Information System (INIS)

    Mas, Jose L.; Garcia-Leon, Manuel; Bolivar, Juan P.

    2002-01-01

    In this paper, an extensive work is done on the specific tune of a conventional ICP-MS for 99 Tc atom counting. For this, two methods have been used and compared: the partial variable control method and the 5D Simplex method. Instrumental limits of detection of 0.2 and 0.8 ppt, respectively, were obtained. They are noticeably lower than that found with the automatic tune method of the spectrometer, 47 ppt, which shows the need of a specific tune when very low levels of 99 Tc have to be determined. A study is presented on the mass interferences for 99 Tc. Our experiments show that the formation of polyatomic atoms or refractory oxides as well as 98 Mo hydrides seem to be irrelevant for 99 Tc atom counting. The opposite occurs with the presence of isobaric interferences, i.e. 99 Ru, and the effect of abundance sensitivity, or low-mass resolution, which can modify the response at m/z=99 to a non-negligible extent

  2. Extraction of Tc(VII) and Re(VII) on TRU resin

    Energy Technology Data Exchange (ETDEWEB)

    Guerin, Nicolas; Riopel, Remi; Kramer-Tremblay, Sheila [Canadian Nuclear Laboratories (CNL), Chalk River, ON (Canada). Radiobiology and Health Branch; De Silva, Nimal; Cornett, Jack [Ottawa Univ., ON (Canada). Dept. of Earth and Environmental Sciences; Dai, Xiongxin [China Institute for Radiation Protection, Beijing (China)

    2017-06-01

    TRU resin can be used to rapidly and selectively extract Tc(VII) and Re(VII). The retention capacity curves of Tc(VII) and Re(VII) for HNO{sub 3}, HCl, H{sub 2}SO{sub 4} and H{sub 3}PO{sub 4} solutions were studied and prepared. Tc(VII) and Re(VII) were simultaneously extracted in 2 M H{sub 2}SO{sub 4} and 1.5 M H{sub 3}PO{sub 4} and were effectively separated from Mo(VI) and Ru(III). Tc(VII) and Re(VII) remained strongly bonded to the resin even after washing using a large volume of 2 M H{sub 2}SO{sub 4} at a relatively high flow rate. Also, they were both completely eluted from the resin using 15 mL of near boiling water, an eluent directly compatible for ICP-MS instrument measurements.

  3. Development of fission Mo-99 production technology

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jin Ho; Choung, W. M.; Lee, K. I. and others

    2000-05-01

    Fission Mo-99 is the only parent nuclide of Tc-99m, an extremely useful tool for mdeical diagnosis, with an estimated usage of greater than 80% of nuclear medicine applicatons. HEU and LEU targets to optimize in HANARO irradiation condition suggested and designed for domestic production of fission Mo-99. The optimum process conditions are established in each unit process to meet quality requirements of fission Mo-99 products, and the results of performance test in combined process show Mo separation and purification yield of the above 97%. The concept of Tc generator production process is established, and the result of performance test show Tc production yield of 98.4% in Tc generator procuction process. The drafts is prepared for cooperation of technical cooperation and business investment with foreign country. Evaluation on economic feasibility is accompanied for fission Mo-99 and Tc-99m generator production.

  4. Development of fission Mo-99 production technology

    International Nuclear Information System (INIS)

    Park, Jin Ho; Choung, W. M.; Lee, K. I. and others

    2000-05-01

    Fission Mo-99 is the only parent nuclide of Tc-99m, an extremely useful tool for mdeical diagnosis, with an estimated usage of greater than 80% of nuclear medicine applicatons. HEU and LEU targets to optimize in HANARO irradiation condition suggested and designed for domestic production of fission Mo-99. The optimum process conditions are established in each unit process to meet quality requirements of fission Mo-99 products, and the results of performance test in combined process show Mo separation and purification yield of the above 97%. The concept of Tc generator production process is established, and the result of performance test show Tc production yield of 98.4% in Tc generator procuction process. The drafts is prepared for cooperation of technical cooperation and business investment with foreign country. Evaluation on economic feasibility is accompanied for fission Mo-99 and Tc-99m generator production

  5. Biodistribution of Ru-97-labeled DTPA, DMSA and transferrin

    International Nuclear Information System (INIS)

    Som, P.; Oster, Z.H.; Fairchild, R.G.; Atkins, H.L.; Brill, A.B.; Gil, M.C.; Srivastava, S.C.; Meinken, G.E.; Goldman, A.G.; Richards, P.

    1980-01-01

    Ruthenium-97 is being produced at the Brookhaven Linac Isotope Producer (BLIP). The favorable physical properties of Ru-97 and chemical reactivity of ruthenium offer a potential for using this isotope to label compounds useful for delayed scanning. Diethylenetriamine pentaacetic acid (DTPA), 2,3-Dimercaptosuccinic acid (DMSA), and Transferrin (TF) were labeled with Ru-97-chloride. Ru-97-DTPA and In-111-DTPA, injected intravenously, showed similar organ distribution, kinetics, and more than 80% excretion by 0.5 h. Ru-97-DTPA and In-111-DTPA injected into the cisterna magna of dogs showed similar kinetics in brain, blood, and urinary bladder. The energy deposited by 1 mCi In-111-DTPA is twice that from 1 mCi Ru-97-DTPA. High quality camera images of the CSF space in the dog were obtained with both isotopes. Ru-97-DMSA was prepared with and without the addition of SnCl 2 .2H 2 O. Tin-free DMSA was rapidly excreted via the kidneys, whereas for maximum cortical deposition, the tin-containing preparation was superior. This compound is suitable for delayed imaging of both normal and impaired kidneys. Tissue distribution studies were performed in abscess-bearing rats with Ru-97-transferrin. Although blood levels were higher than with Ga-67-citrate, the abscess had twice as much Ru-97-TF as Ga-67-citrate and the Ru-97 muscle activity was one-third that of Ga-67. Imaging of abscess-bearing rabbits with Ru-97-TF visualized the abscesses as early as 1/2 hr after injection. Since the initial images visualize the abscess so clearly and since the TF portion of the compound binds to the abscess, Tc-99m-TF is being studied for the same purpose. Ru-97-labeled compounds are a promising replacement for In-111 and possibly also for Ga-67 compounds with the advantages of lower radiation dose and high quality image

  6. Operation of plant to produce Mo-99 from fission products

    International Nuclear Information System (INIS)

    Marques, R.O.; Cristini, P.R.; Marziale, D.P.; Furnari, E.S.; Fernandez, H.O.

    1987-01-01

    As it is well known, the production of Mo-99/Tc-99m generators has an outstanding place in radioisotope programs of the Argentine National Atomic Energy Commission. The basic raw material is Mo-99 from fission of U-235. In 1985 the production plant of this radionuclide began to operate, according to an adaptation of the method that was developed in Kernforschungszentrum Karlsruhe. The present work describes the target irradiation conditions in the reactor RA-3 (mini plates of U/Al alloy with 90% enriched uranium), the flow diagram and the operative conditions of the production process. The containment, filtration and removal conditions of the generated fission gases and the disposal of liquid and solid wastes are also analyzed. On the basis of the experience achieved in the development of more than twenty production processes, process efficiency is analyzed, taking into account the theoretical evaluation resulting from the application of the computer program 'Origin'(ORML) to the conditions of our case. The purity characteristics of the final product are reported (Zr-95 0,1 ppm; Nb-95 1 ppm; Ru-103 20 ppm; I-131 10 ppm) as well as the chemical characteristics that make it suitable to be used in the production of Mo-99/I c-99m generators. (Author)

  7. Direct evidence for double-exchange coupling in Ru- substituted La0.7Pb0.3Mn 1 - x Ru x O3, 0.0 <= x <= 0.4

    Science.gov (United States)

    Sundar Manoharan, S.; Sahu, R. K.; Rao, M. L.; Elefant, D.; Schneider, C. M.

    2002-08-01

    The La0.7Pb0.3Mn 1 - x Ru x O3 (0.0 innate relationship between Mn and Ru ions by a unique double-exchange mediated transport behavior. This is exonerated by the coexistence of Tp and Tc (range 330 K 245 K for 0.0 30%, the hole carrier mass influences the transport property. X-ray absorption spectra suggest that the Tc-Tp match is due to the transport mediated by the Mn3+/Mn4+ leftrightarrow Ru4+/Ru5+ redox pair and also due to the broad low-spin Ru:4d conduction band. For x > 0.2, T < 0.5Tc obeys a modified variable-range hopping model, where kT0 propto (M/Ms)2, suggesting a random magnetic potential which localizes the charge carriers.

  8. sup 9 sup 9 Tc atom counting by quadrupole ICP-MS. Optimisation of the instrumental response

    CERN Document Server

    Mas, J L; Garcia-Leon, M

    2002-01-01

    In this paper, an extensive work is done on the specific tune of a conventional ICP-MS for sup 9 sup 9 Tc atom counting. For this, two methods have been used and compared: the partial variable control method and the 5D Simplex method. Instrumental limits of detection of 0.2 and 0.8 ppt, respectively, were obtained. They are noticeably lower than that found with the automatic tune method of the spectrometer, 47 ppt, which shows the need of a specific tune when very low levels of sup 9 sup 9 Tc have to be determined. A study is presented on the mass interferences for sup 9 sup 9 Tc. Our experiments show that the formation of polyatomic atoms or refractory oxides as well as sup 9 sup 8 Mo hydrides seem to be irrelevant for sup 9 sup 9 Tc atom counting. The opposite occurs with the presence of isobaric interferences, i.e. sup 9 sup 9 Ru, and the effect of abundance sensitivity, or low-mass resolution, which can modify the response at m/z=99 to a non-negligible extent.

  9. Phase formation in Na2MoO4 - MgMoO4 - Cr2(MoO4)3 system

    International Nuclear Information System (INIS)

    Kotova, I.Yu.; Kozhevnikova, N.M.

    1998-01-01

    Interaction within Na 2 MoO 4 - MgMoO 4 - Cr 2 (MoO 4 ) 3 ternary system is studied by X ray phase and DTA methods. State diagram of NaCr(MoO 4 ) 2 - MgMoO 4 section is plotted. Production of ternary molybdates of Na 1-x Mg 1-x Cr 1+x (MoO 4 ) 3 , where 0 ≤ x ≤ 0.3, and NaMg 3 Cr(MoO 4 ) 5 composition is ascertained [ru

  10. Transfer from soil to plants of 106Ru as nitrosyl and as chloride

    International Nuclear Information System (INIS)

    Handl, J.

    1988-01-01

    The transfer of 106 Ru in a soil-plant ecosystem was investigated with respect to two chemical forms in compact soil samples under greenhouse conditions with surface and deep-layer contamination. Considerable differences in the uptake of 106 Ru were observed between 106 RuCl3 and 106 Ru-nitrosyl during the first 5-8 wk after the contamination of the soil. The translocation of 106 Ru in the soil showed an inhomogeneous distribution of the radioruthenium, with a great part of the total activity remaining in the upper soil layer between 0 and 5 cm even 10 mo after contamination of the soil surface. During the whole experiment, reemission of 106 Ru into the air was investigated by using special air collectors under different temperature and light conditions. Although a continuous checking out for a time of about 8 mo, no measurable concentrations of 106 Ru could be out for a time of about 8 mo, no measurable concentrations of 106 Ru could be found in examined air filters

  11. Measurement and Estimation of the 99Mo Production Yield by 100Mo(n,2n)99Mo

    Science.gov (United States)

    Minato, Futoshi; Tsukada, Kazuaki; Sato, Nozomi; Watanabe, Satoshi; Saeki, Hideya; Kawabata, Masako; Hashimoto, Shintaro; Nagai, Yasuki

    2017-11-01

    We, for the first time, measured the yield of 99Mo, the mother nuclide of 99mTc used in nuclear medicine diagnostic procedures, produced by the 100Mo(n,2n)99Mo reaction with accelerator neutrons. The neutrons with a continuous energy spectrum from the thermal energy up to about 40 MeV were provided by the C(d,n) reaction with 40 MeV deuteron beams. It was proved that the 99Mo yield agrees with that estimated by using the latest data on neutrons from the C(d,n) reaction and the evaluated cross section of the 100Mo(n,2n)99Mo reaction given in the Japanese Evaluated Nuclear Data Library. On the basis of the agreement, a systematic calculation was carried out to search for an optimum condition that enables us to produce as much 99Mo as possible with a good 99Mo/100Mo value from an economical point of view. The calculated 99Mo yield from a 150 g 100MoO3 sample indicated that about 30% of the demand for 99Mo in Japan can be met with a single accelerator capable of 40 MeV, 2 mA deuteron beams. Here, by referring to an existing 18F-fluorodeoxyglucose (FDG) distribution system we assumed that 99mTc radiopharmaceuticals formed after separating 99mTc from 99Mo can be delivered to hospitals from a radiopharmaceutical company within 6 h. The elution of 99mTc from 99Mo twice a day would meet about 50% of the demand for 99Mo.

  12. Transmutation of 99Tc as a new source of stable ruthenium

    International Nuclear Information System (INIS)

    Kozar', A.A.; Peretrukhin, V.F.

    1997-01-01

    Dynamic of 99 Tc transmutation by irradiation through thermal neutrons with the spectrum tension of 0.3 is calculated and the 100, 101, 102 Ru yield and its volumetric distribution in targets of various thickness are determined. It is shown that after the targets irradiation of metallic 99 Tc of 0.5 mm thick through thermal fluence about (5-10)x10 22 cm -2 the 100, 101, 102 Ru yield reaches its maximum-about 97.5-99% of all the target nuclei. For industrial Ru application the actinide content in the targets should not exceed 5x10 -10 g/g 99 Tc and the content of nonburnt 99 Tc after the reprocessing of the irradiated target should be less than 10 -5 g/g Ru

  13. Alternative generators of the 99mTc

    International Nuclear Information System (INIS)

    Khujaev, S.

    2004-01-01

    9 9mTc is the most widely used radionuclide in nuclear medicine. 9 9mTc radionuclide is obtained from a generator, in which 9 9Mo servest as the parent radionuclide. In the generator 9 9mTc and 9 9Mo radionuclides are found in genetic balance and 9 9mTc radionuclide is chemically extracted from the system periodically. Although there already exists many ways and variants of manufacturing 9 9mTc generators, search for new variants of the 9 9Mo → 9 9mTc generator systems continue. An example is the investigations carried out with the support of the IAEA. In these research works, generators based on elution of poly molybdate gels have been developed and evaluated. These generators will be serving as alternative technologies for production of 9 9mTc radionuclide, which use 9 9Mo produced by non-fission means. It is known that in Australia and China more than 30% of 9 9mTc generators are gel-generators. The works of authors are devoted to the problem of searching new perspective materials as a column material that will serve as adsorbent. The main purpose of all the research on alternative technologies is the usage of parent radionuclide 9 9Mo that is obtained from 9 8Mo(n, γ) 9 9Mo reaction instead of as a fission product. Our work examines the possibility of reception of generators 9 9Mo → 9 9mTc using non-fission 9 9Mo that is based on insoluble salts of molybdate

  14. Inelastic scattering on 100Ru

    International Nuclear Information System (INIS)

    Sirota, S.

    1987-01-01

    Aspects of the nuclear structure of 100 Ru whe investigated by means of the scattering of 100 Ru (p,p') 100 Ru* with 16 MeV protons, where 21 states were investigated. The emergent protons were analysed by a magnetic spectrograph, of the enge type with a typical resolution of ≅ 9 KeV. (A.C.A.S.) [pt

  15. Double-beta decay measurement of 100Mo to the excited 01+ state of 100Ru in the NEMO3 experiment - R/D program for SuperNEMO: development of a BiPo detector to measure ultra low contaminations in the source foils

    International Nuclear Information System (INIS)

    Chapon, A.

    2011-10-01

    The NEMO3 detector was designed for the study of double beta decay and in particular the search for neutrinoless double beta decay (ββ0ν). The quantity of 100 Mo in the detector (7 kg) allows also a competitive measurement of the two-neutrino double beta decay (ββ2ν) of 100 Mo to the excited 0 1 + state of 100 Ru (eeNγ channel). Monte-Carlo simulations of the effect and of all the possible sources of background have been studied in order to determine their contributions to the full NEMO3 experimental data (2003-2011). These one have then been analysed: the ββ2ν decay half-life has been measured, and a limit on the ββ0ν decay has been obtained. Moreover, the SuperNEMO experiment aims to reach a sensitivity up to 10 26 years on the half-life of neutrinoless double beta decay. The SuperNEMO detector radioactivity has to be as low as possible. Especially radio-purity levels of 2 μBq*kg -1 in 208 Tl and 10 μBq*kg -1 in 214 Bi are required for the source foils. The gamma-spectrometry can not measure such low contamination levels. Hence, a BiPo dedicated detector has been developed to measure 208 Tl and 214 Bi contaminations, identifying the Bi→Po→Pb β-α chains. A proof of principle has been performed and the detector background has been measured. Assuming these values, a full BiPo detector of 3.6 m 2 can achieve the required sensitivities for the SuperNEMO source foils within six months of measurement. (author)

  16. The method of activity determination of Tc-99m in ionization chamber

    International Nuclear Information System (INIS)

    Broda, R.

    1980-01-01

    The paper presents a method of finding the efficiency of sup(99m)Tc activity measurements in the ionization chamber, basing on 99 Mo activity measurements and the activity ratio of sup(99m)Tc to 99 Mo in 99 Mo + sup(99m)Tc solution. The activity of 99 Mo has been determined in 4πβ-γ coincidence system with liquid scintillator in β channel by means of the absolute method of two-stage coincidence. The activity ratio of sup(99m)Tc to 99 Mo has been determined by means of spectrometric method. The 99 Mo and sup(99m)Tc activities have been measured in 99 Mo + sup(99m)Tc generators, and the activity of sup(99m)Tc solution after elution has been measured. It has been shown that sup(99m)Tc activity, determined by means of the chamber method on the basis of the efficiency found, corresponds to the activity determined by means of spectrometric method, and that sup(99m)Tc activity, measured in generator before elution, is equal to the sum of sup(99m)Tc activity eluted and the one remained in generator. (author)

  17. In-house cyclotron production of high-purity Tc-99m and Tc-99m radiopharmaceuticals.

    Science.gov (United States)

    Martini, Petra; Boschi, Alessandra; Cicoria, Gianfranco; Zagni, Federico; Corazza, Andrea; Uccelli, Licia; Pasquali, Micòl; Pupillo, Gaia; Marengo, Mario; Loriggiola, Massimo; Skliarova, Hanna; Mou, Liliana; Cisternino, Sara; Carturan, Sara; Melendez-Alafort, Laura; Uzunov, Nikolay M; Bello, Michele; Alvarez, Carlos Rossi; Esposito, Juan; Duatti, Adriano

    2018-05-30

    In the last years, the technology for producing the important medical radionuclide technetium-99m by cyclotrons has become sufficiently mature to justify its introduction as an alternative source of the starting precursor [ 99m Tc][TcO 4 ] - ubiquitously employed for the production of 99m Tc-radiopharmaceuticals in hospitals. These technologies make use almost exclusively of the nuclear reaction 100 Mo(p,2n) 99m Tc that allows direct production of Tc-99m. In this study, it is conjectured that this alternative production route will not replace the current supply chain based on the distribution of 99 Mo/ 99m Tc generators, but could become a convenient emergency source of Tc-99m only for in-house hospitals equipped with a conventional, low-energy, medical cyclotron. On this ground, an outline of the essential steps that should be implemented for setting up a hospital radiopharmacy aimed at the occasional production of Tc-99m by a small cyclotron is discussed. These include (1) target production, (2) irradiation conditions, (3) separation/purification procedures, (4) terminal sterilization, (5) quality control, and (6) Mo-100 recovery. To address these issues, a comprehensive technology for cyclotron-production of Tc-99m, developed at the Legnaro National Laboratories of the Italian National Institute of Nuclear Physics (LNL-INFN), will be used as a reference example. Copyright © 2018 Elsevier Ltd. All rights reserved.

  18. Laminated structure in internally oxidized Ru-Ta coatings

    Energy Technology Data Exchange (ETDEWEB)

    Chen, Yung-I, E-mail: yichen@mail.ntou.edu.tw

    2012-12-01

    During the development of refractory alloy coatings for protective purposes at high temperature under oxygen-containing atmospheres, previous studies noted and examined the internal oxidation phenomenon for Mo-Ru and Ru-Ta coatings. The internally oxidized zone shows a laminated structure, consisting of alternating oxygen-rich and deficient layers stacked with a general orientation. Previous studies proposed a forming mechanism. To investigate in detail, Ru-Ta coatings were prepared with various rotating speeds of a substrate-holder. The coatings were annealed at 600 Degree-Sign C in an atmosphere continuously purged with 1% O{sub 2}-99% Ar mixed gas for 30 min. Transmission electron microscopy was used to examine the laminated-layer periods. Auger electron spectroscopy depth profiles certified the periodical variation of the related constituents. X-ray photoelectron spectroscopy proved the valence variation of Ta in the near surface, accompanied by the introduction of oxygen ions. The inward diffusion of oxygen was dominated by lattice diffusion. - Highlights: Black-Right-Pointing-Pointer Laminated Ru-Ta coatings consisted of a cyclical gradient concentration. Black-Right-Pointing-Pointer The as-deposited coatings showed a laminated structure with a period of 4-34 nm. Black-Right-Pointing-Pointer Internal oxidation of Ru-Ta coatings executed after annealing in 1% O{sub 2}-Ar atmosphere. Black-Right-Pointing-Pointer Oxygen inward diffusion was dominated by lattice diffusion.

  19. Determination of Tc-99 in radioactive wastes

    International Nuclear Information System (INIS)

    Rivera S, A. A.

    2015-01-01

    Tc-99 is a fission product and one of the most important radionuclides from the view point of safety assessment for the disposal of radioactive waste because of its long half-life (2.1 x 10 5 years) and high mobility in soil-water systems, if this is released into the environment in significant quantities can concentrate on plants and animals. Tc-99 is a pure beta emitter with a maximum energy of 292 KeV, so their quantification imposes destructive methods to be analyzed by liquid scintillation. Therefore the quantification of Tc-99 in ion exchange resins requires of the mineralization of these and separation of Tc-99 of other radioisotopes present in the resin. Therefore the object of this thesis is to develop a quantification method of Tc-99 content in spent exchange resins. So in order to track the behavior of technetium during digestion exchange resins and radiochemical separation, given its high volatility, in this work the 99m Tc is used. To determine the degree of mineralization of the resins, an analysis was performed by chromatography. Subsequently the method used to determine the percentage of 99m Tc aerosolized during mineralization of resin is described. After the method for the radiochemical separation of 99m Tc is presented by liquid-liquid extraction using crown ether as extractant; for this testing was performed by varying the molarity of the extractant, the ratio of solvent extractant, type of digestion of the resin and the presence of Sr-85, in order to study the behavior of 99m Tc in the presence of this radioisotope. Finally, a track beta spectra of a sample of 99m Tc eluted from a generator 99 Mo/ 99m Tc function of time was performed. (Author)

  20. Dibenzothiophene hydrodesulfurization over Ru promoted alumina based catalysts using in situ generated hydrogen

    International Nuclear Information System (INIS)

    Muhammad, Yaseen; Lu Yingzhou; Shen Chong; Li Chunxi

    2011-01-01

    Catalytic hydrodesulfurization (HDS) of dibenzothiophene (DBT) was carried out in a temperature range of 320-400 o C using in situ generated hydrogen coupled with the effect of selected organic additives for the first time. Four kinds of alumina based catalysts i.e. Co-Mo/Al 2 O 3 , Ni-Mo/Al 2 O 3 , Ru-Co-Mo/Al 2 O 3 and Ru-Ni-Mo/Al 2 O 3 were used for the desulfurization process, which were prepared following incipient impregnation method with fixed metal loadings (wt.%) of Co, Ni, Mo and Ru. The surface area, average pore diameter and pore volume distribution of the fresh and used catalysts were measured by N 2 adsorption using BET method. Catalytic activity was investigated in a batch autoclave reactor in the complete absence of external hydrogen gas. Addition and mutual reaction of specific quantities of water and ethanol provided the necessary in situ hydrogen for the desulfurization reaction. Organic additives like diethylene glycol (DEG), phenol, naphthalene, anthracene, o-xylene, tetralin, decalin and pyridine did impinge the HDS activity of the catalysts in different ways. Liquid samples from reaction products were quantitatively analyzed by HPLC technique while qualitative analyses were made using GC-MS. Both of these techniques showed that Ni-based catalysts were more active than Co-based ones at all conditions. Moreover, incorporation of Ru to both Co and Ni-based catalysts greatly promoted desulfurization activity of these catalysts. DBT conversion of up to 84% was achieved with Ru-Ni-Mo/Al 2 O 3 catalyst at 380 o C temperature for 11 h. Catalyst systems followed the HDS activity order as: Ru-Ni-Mo/Al 2 O 3 > Ni-Mo/Al 2 O 3 > Ru-Co-Mo/Al 2 O 3 > Co-Mo/Al 2 O 3 at all conditions. Cost effectiveness, mild operating conditions and reasonably high catalytic activity using in situ generated hydrogen mechanism proved our process to be useful for HDS of DBT.

  1. Dibenzothiophene hydrodesulfurization over Ru promoted alumina based catalysts using in situ generated hydrogen

    Energy Technology Data Exchange (ETDEWEB)

    Muhammad, Yaseen; Shen, Chong; Li, Chunxi [State Key Laboratory of Chemical Resource Engineering, Beijing University of Chemical Technology, Beijing 100029 (China); College of Chemical Engineering, Beijing University of Chemical Technology, Beijing 100029 (China); Lu, Yingzhou [College of Chemical Engineering, Beijing University of Chemical Technology, Beijing 100029 (China)

    2011-02-15

    Catalytic hydrodesulfurization (HDS) of dibenzothiophene (DBT) was carried out in a temperature range of 320-400 C using in situ generated hydrogen coupled with the effect of selected organic additives for the first time. Four kinds of alumina based catalysts i.e. Co-Mo/Al{sub 2}O{sub 3}, Ni-Mo/Al{sub 2}O{sub 3}, Ru-Co-Mo/Al{sub 2}O{sub 3} and Ru-Ni-Mo/Al{sub 2}O{sub 3} were used for the desulfurization process, which were prepared following incipient impregnation method with fixed metal loadings (wt.%) of Co, Ni, Mo and Ru. The surface area, average pore diameter and pore volume distribution of the fresh and used catalysts were measured by N{sub 2} adsorption using BET method. Catalytic activity was investigated in a batch autoclave reactor in the complete absence of external hydrogen gas. Addition and mutual reaction of specific quantities of water and ethanol provided the necessary in situ hydrogen for the desulfurization reaction. Organic additives like diethylene glycol (DEG), phenol, naphthalene, anthracene, o-xylene, tetralin, decalin and pyridine did impinge the HDS activity of the catalysts in different ways. Liquid samples from reaction products were quantitatively analyzed by HPLC technique while qualitative analyses were made using GC-MS. Both of these techniques showed that Ni-based catalysts were more active than Co-based ones at all conditions. Moreover, incorporation of Ru to both Co and Ni-based catalysts greatly promoted desulfurization activity of these catalysts. DBT conversion of up to 84% was achieved with Ru-Ni-Mo/Al{sub 2}O{sub 3} catalyst at 380 C temperature for 11 h. Catalyst systems followed the HDS activity order as: Ru-Ni-Mo/Al{sub 2}O{sub 3}> Ni-Mo/Al{sub 2}O{sub 3}> Ru-Co-Mo/Al{sub 2}O{sub 3}> Co-Mo/Al{sub 2}O{sub 3} at all conditions. Cost effectiveness, mild operating conditions and reasonably high catalytic activity using in situ generated hydrogen mechanism proved our process to be useful for HDS of DBT. (author)

  2. Study of the activation of targets containing Mo for the production of 99Mo by the 98Mo(n,γ)99Mo nuclear reaction and the behaviour of the radionuclidic impurities of the process

    International Nuclear Information System (INIS)

    Nieto, Renata Correa

    1998-01-01

    The most used radioisotope in Nuclear Medicine is 99m Tc, in the 99 Mo- 99m Tc generator form. 99 Mo can be produced by several nuclear reactions in reactors and cyclotrons. The cyclotron production is not technically and economically viable. The production in the reactor can be done in two different ways: by the fission of 235 U and by 98 Mo(n,γ) 99 Mo reaction. A project for the production of 99 Mo by the activation of Mo and the preparation of gel type generators is under development at the 'Instituto de Pesquisas Energeticas e Nucleares'. In the present work, the radionuclidic impurities produced in the activation of MOO 3 and MoZr gel were evaluated, and these represent the two possible ways of preparing the gel of MoZr. A target of metallic Mo was also studied. The radionuclidic purity of 99m Tc eluted from generators prepared in these ways was also measured and compared with the generators prepared with fission 99 Mo. The results showed that, by all the parameters analysed, the best way of preparing the generator of 99 Mo - 99m Tc is the irradiation of MOO 3 and further preparation of the gel and the generators. (author)

  3. Reactions of ethanol on Ru

    NARCIS (Netherlands)

    Sturm, Jacobus Marinus; Liu, Feng; Lee, Christopher James; Bijkerk, Frederik

    2012-01-01

    The adsorption and reactions of ethanol on Ru(0001) were studied with temperatureprogrammed desorption (TPD) and reflection-absorption infrared spectroscopy (RAIRS). Ethanol was found to adsorb intact onto Ru(0001) below 100 K. Heating to 250 K resulted in formation of ethoxy groups, which undergo

  4. Phase formation in the Rb2MoO4-Li2MoO4-Hf(MoO4)2 system and the crystal structure of Rb5(Li1/3Hf5/3)(MoO4)6

    International Nuclear Information System (INIS)

    Solodovnikov, S.F.; Zolotova, E.S.; Balsanova, L.V.; Bazarov, B.G.; Bazarova, Zh.G.

    2003-01-01

    Phase formation in the Rb 2 MoO 4 -Li 2 MoO 4 -Hf(MoO 4 ) 2 system is studied in subsolidus region in air by the method of crossing sections. Three ternary molybdates are detected in the system. Compositions of two of them are corroborated by selection of isostructural analogues [ru

  5. Mass spectrometric determination of stability of gaseous BaMoO2, Ba2MoO4, Ba2MoO5, Ba2Mo2O8 molecules

    International Nuclear Information System (INIS)

    Kudin, L.S.; Balduchchi, Dzh.; Dzhil'i, G.; Gvido, M.

    1982-01-01

    During the mass spectrometric investigation of BaCrO 4 evaporation Cr + , Ba + , BaO + main ions are recorded as well as BaMoO 4 + , BaMoO 3 + , BaMoO 2 + , BaMoO + , BaMoO 4 + , Ba 2 MoO 5 + , BaMo 2 O 8 + ions - the products of ionization of three-component (Ba, Mo, M) molecules, forming as a result of substance chemical interaction with the material of an effusion cell (Mo). Heats of formation of BaMoO 2 , Ba 2 MoO 4 , Ba 2 MoO 5 and Ba 2 Mo 2 O 8 molecules which constituted - 577+-70, -1343+-115, -1464+-70, -2393+-90 k J/mol respectively are determined on the base of the analysis of curves of ionisation efficiency and of reaction heats Ba 2 MoO 5 =BaO+BaMoO 4 , ΔH 0 0 =322+-60 kJ/mol Ba 2 Mo 2 O 8 =2BaMoO 4 , ΔH 0 0 =351+-80 kJ/mol calculated with the use of third low of thermodynamics [ru

  6. Peierls-distorted Ru-chains and boron dumbbells in Nb{sub 2}RuB{sub 2} and Ta{sub 2}RuB{sub 2} from first-principles calculations and experiments

    Energy Technology Data Exchange (ETDEWEB)

    Touzani, Rachid S.; Mbarki, Mohammed; Chen, Ximeng [Institute of Inorganic Chemistry, RWTH Aachen University (Germany); Fokwa, Boniface P.T. [Institute of Inorganic Chemistry, RWTH Aachen University (Germany); Department of Chemistry, University of California Riverside (UCR), Riverside, CA (United States)

    2016-09-15

    Nb{sub 2}RuB{sub 2} and Ta{sub 2}RuB{sub 2} phases were recently predicted by GGA-VASP structure optimization to crystallize in the Nb{sub 2}OsB{sub 2}-type structure. Although the Fe-based (Mo{sub 2}FeB{sub 2} type) and Os-based (Nb{sub 2}OsB{sub 2} type, superstructure variant of Mo{sub 2}FeB{sub 2} type) analogues have been synthesized and characterized successfully, the Ru-based phases remained unknown. Crystal structure prediction of Nb{sub 2}RuB{sub 2} and Ta{sub 2}RuB{sub 2} phases, using an evolutionary algorithm, led to the AlMn{sub 2}B{sub 2}-type structure in contrast to the aforementioned optimization; however, phonon calculations showed that the Nb{sub 2}OsB{sub 2}-type phases are dynamically more stable than the AlMn{sub 2}B{sub 2}-type phases. A slightly modified synthetic strategy finally led to the successful preparation of the predicted phases. The extremely quick arc-melting procedure, under argon atmosphere, not only led to a quantitative amount of the phases but also to single crystals suitable for structure determination. Powder and single-crystal X-ray diffraction as well as EDX analysis of the metal ratio have confirmed the GGA-VASP structure optimization: Nb{sub 2}RuB{sub 2} and Ta{sub 2}RuB{sub 2} compounds indeed crystallize isotypically with Nb{sub 2}OsB{sub 2} structure, a superstructure variant of Mo{sub 2}FeB{sub 2} type, in which B-dumbbells and Peierls-distorted Ru-chains are found. Susceptibility measurements on a Ta{sub 2}RuB{sub 2} single crystal reveal no superconducting transition down to 2 K, even though some features in the band structures of both phases, similar to those reported in superconducting NbRuB, hinted at possible superconductivity. (copyright 2016 WILEY-VCH Verlag GmbH and Co. KGaA, Weinheim)

  7. Rapid determination of 99Tc in environmental samples by high resolution ICP-MS coupled with on-line flow injection system

    International Nuclear Information System (INIS)

    Kim, C.K.; Kim, C.S.; Rho, B.H.; Lee, J.I.

    2002-01-01

    High resolution inductively coupled plasma mass spectrometry coupled with an on-line flow injection system (FI-HR-ICP-MS) was applied to determine the ultra-trace level 99 Tc in soil. The flow injection system (PrepLab TM ) was composed of two TEVA-Spec R resins, reduced remarkably the sample amounts and the analysis time, compared to the conventional analytical methods. In the flow injection system, Mo and Ru were sufficiently eliminated by using the flow injection system, with the decontamination factors of 1.6 x 10 4 and 9.9 x 10 5 , respectively. With the present method, it was possible to determine ultra-low level of 99 Tc in 3∼6 soil at 3-5 hours of analysis time per sample. The relative standard deviation for each sample was less than 4%. The detection limits for 99 Tc was 85 fg x ml -1 (0.05 mBq x ml -1 ), which was calculated from the three times standard deviation of the count rate of the blank. (author)

  8. Study of the effect of irradiation of Mo targets at nuclear reactor

    International Nuclear Information System (INIS)

    Nieto, Renata C.; Lima, Ana Lucia V.P.; Silva, Nestor C. da; Osso Junior, Joao Alberto

    2000-01-01

    The most used radioisotope in nuclear medicine is 99m Tc, in the 99 Mo- 99m Tc generator form. 99 Mo can be produced by several nuclear reactions in reactors and cyclotrons. The cyclotron production is not technically and economically viable. The production in the reactor can be done in two different ways: by the fission of 235 U and by the 98 Mo(n,γ) 99 Mo reaction. A project for the production of 99 Mo by the activation of Mo and the preparation of gel type generators is under development at the 'Instituto de Pesquisas Energeticas e Nucleares'. In the present work, the radionuclidic impurities produced in the activation of MoO 3 , metallic Mo and Mo Zr gel were evaluated, as well as the radionuclidic purity of 99m Tc eluted from generators prepared. (author)

  9. 101Ru NQR study in superconducting CeRu2

    International Nuclear Information System (INIS)

    Matsuda, Kazuyuki; Kohori, Yoh; Kohara, Takao

    1995-01-01

    We present measurements of the NQR spectrum and the nuclear spin lattice relaxation rate, 1/T 1 , of 101 Ru in superconducting CeRu 2 from 1.9 K to 10 K. From the NQR spectrum, the electric quadrupole interaction parameters were determined to be ν Q =13.2 MHz and η=0.1/T 1 varies in proportion to temperature in the normal state, and has the Hebel-Slichter coherence peak just below the superconducting transition temperature, T C , of 6.2 K, and decreases exponentially at low temperatures with the energy gap of 2Δ=4.0k B T C . 101 Ru NQR study indicates that CeRu 2 is an s-wave and strong-coupling superconductor. (author)

  10. Conceptual study of 99Mo production in JRR-3

    International Nuclear Information System (INIS)

    Hirose, Akira; Komeda, Masao; Kinase, Masami; Sorita, Takami; Wada, Shigeru

    2010-06-01

    We investigated the production process of 99 Mo, which is parent nuclide of 99m Tc, in JRR-3. 99m Tc is most commonly used as a radiopharmaceutical in the field of nuclear medicine. Currently the supplying of 99 Mo is only dependent on imports from foreign countries, so JAEA is aiming at domestic production of a part of 99 Mo in cooperation with the industrial arena. This report presents the technical study for the production process of 99 Mo by using the neutron radiation method of (n, γ) reaction in JRR-3. (author)

  11. A review on the process technology for Mo-99 production

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jin Hoh; Yoo, Jae Hyung; Jung, Won Myung; Lee, Kyoo Il; Woo, Moon Sik; Hwang, Doo Sung; Kim, Yun Koo [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1994-07-01

    Tc-99m is most frequently used in nuclear medical diagnostics because of its favourable nuclear properties and reasonable prices, and the demand of Tc-99m, is on the increase recently. Mo-99, the parent radionuclide of Tc-99m, is the only source of Tc-99m. This review described overall aspects of process technologies for Mo-99 production. Firstly, the chemical, physical and radioactive properties of Tc-99m, Mo-99 were examined to understand Mo-99 separation process. Also, the technology for Mo-99 production with both the neutron capture and nuclear fission method were examined. But the neutron capture method was scarcely used for large production of Mo-99 because of its low specific activity and high production cost. This review also described mainly process technologies in the nuclear fission method, fabrication and condition for irradiation of targets, transport and dissolution of targets irradiated, separation and purification of Mo-99, etc. Especially, for Mo-99 separation and purification process, the characteristics, merits and demerits of various processes, which have been developed in a few countries, were examined and analyzed. 30 figs., 16 tabs., 60 refs. (Author).

  12. Determination of Tc-99 in radioactive wastes; Determinacion de Tc-99 en desechos radiactivos

    Energy Technology Data Exchange (ETDEWEB)

    Rivera S, A. A.

    2015-07-01

    Tc-99 is a fission product and one of the most important radionuclides from the view point of safety assessment for the disposal of radioactive waste because of its long half-life (2.1 x 10{sup 5} years) and high mobility in soil-water systems, if this is released into the environment in significant quantities can concentrate on plants and animals. Tc-99 is a pure beta emitter with a maximum energy of 292 KeV, so their quantification imposes destructive methods to be analyzed by liquid scintillation. Therefore the quantification of Tc-99 in ion exchange resins requires of the mineralization of these and separation of Tc-99 of other radioisotopes present in the resin. Therefore the object of this thesis is to develop a quantification method of Tc-99 content in spent exchange resins. So in order to track the behavior of technetium during digestion exchange resins and radiochemical separation, given its high volatility, in this work the {sup 99m}Tc is used. To determine the degree of mineralization of the resins, an analysis was performed by chromatography. Subsequently the method used to determine the percentage of {sup 99m}Tc aerosolized during mineralization of resin is described. After the method for the radiochemical separation of {sup 99m}Tc is presented by liquid-liquid extraction using crown ether as extractant; for this testing was performed by varying the molarity of the extractant, the ratio of solvent extractant, type of digestion of the resin and the presence of Sr-85, in order to study the behavior of {sup 99m}Tc in the presence of this radioisotope. Finally, a track beta spectra of a sample of {sup 99m}Tc eluted from a generator {sup 99}Mo/{sup 99m}Tc function of time was performed. (Author)

  13. A review of sup(99m)Tc generator technology

    International Nuclear Information System (INIS)

    Molinski, V.J.

    1982-01-01

    The sup(99m)Tc generator has found widespread use because it is ideally suited for scintigraphy. The preparation of sup(99m)Tc generators using alumina and other ion exchange systems is described. Other methods of separating 99 Mo and sup(99m)Tc, such as solvent extraction and sublimation, are also discussed. Some of the problems associated with the alumina column type sup(99m)Tc generator are listed with possible causes and solutions to their problems. The current biomedical applications of the sup(99m)Tc radioisotope are the basis of a $100 million nuclear medicine business. The importance of the sup(99m)Tc generator makes it imperative that we understand and solve the problems associated with its manufacture. (author)

  14. Superconductivity in the Nb-Ru-Ge σ phase

    Science.gov (United States)

    Carnicom, Elizabeth M.; Xie, Weiwei; Sobczak, Zuzanna; Kong, Tai; Klimczuk, Tomasz; Cava, R. J.

    2017-12-01

    We show that the previously unreported ternary σ -phase material N b20.4R u5.7G e3.9 (N b0.68R u0.19G e0.13 ) is a superconductor with a critical temperature of 2.2 K. Temperature-dependent magnetic susceptibility, resistance, and specific-heat measurements were used to characterize the superconducting transition. The Sommerfeld constant γ for N b20.4R u5.7G e3.9 is 91 mJ mol f .u .-1K-2 (˜3 mJ mol ato m-1K-2 ) and the specific-heat anomaly at the superconducting transition, Δ C /γ Tc , is approximately 1.38. The zero-temperature upper critical field [μ0H c2(0 ) ] was estimated to be 2 T by resistance data. Field-dependent magnetization data analysis estimated μ0H c1(0 ) to be 5.5 mT. Thus, the characterization shows N b20.4R u5.7G e3.9 to be a type-II BCS superconductor. This material appears to be the first reported ternary phase in the Nb-Ru-Ge system, and the fact that there are no previously reported binary Nb-Ru, Nb-Ge, or Ru-Ge σ phases shows that all three elements are necessary to stabilize the material. An analogous σ phase in the Ta-Ru-Ge system did not display superconductivity above 1.7 K, which suggests that electron count cannot govern the superconductivity observed. Preliminary characterization of a possible superconducting σ phase in the Nb-Ru-Ga system is also reported.

  15. Hydrogenation of Lactic Acid to 1,2-propanediol over Ru-based catalysts

    NARCIS (Netherlands)

    Liu, K.; Huang, X.; Pidko, E.A.; Hensen, E.J.M.

    2018-01-01

    The catalytic hydrogenation of lactic acid to 1,2-propanediol with supported Ru catalysts in water was investigated. The influence of catalyst support (activated carbon, γ-Al2O3, SiO2, TiO2, and CeO2) and promoters (Pd, Au, Mo, Re, Sn) on the catalytic performance was evaluated. Catalytic tests

  16. Pt–Ru decorated self-assembled TiO2–carbon hybrid nanostructure ...

    Indian Academy of Sciences (India)

    an anode catalyst for direct methanol fuel cells (DMFCs). X-ray diffraction, Raman ... surface CO with oxygen species associated with an element like Ru, Mo, etc to yield CO2. .... pared by dispersion of Vulcan XC 72R in 2-propanol with.

  17. Structure and magnetic properties of Heusler alloy Co{sub 2}RuSi melt-spun ribbons

    Energy Technology Data Exchange (ETDEWEB)

    Xin, Yuepeng; Ma, Yuexing; Hao, Hongyue [School of Materials Science and Engineering, Hebei University of Technology, Tianjin 300130 (China); Luo, Hongzhi, E-mail: luo_hongzhi@163.com [School of Materials Science and Engineering, Hebei University of Technology, Tianjin 300130 (China); Beijing National Laboratory for Condensed Matter Physics, Institute of Physics, Chinese Academy of Sciences, Beijing 100190 (China); Meng, Fanbin; Liu, Heyan [School of Materials Science and Engineering, Hebei University of Technology, Tianjin 300130 (China); Liu, Enke; Wu, Guangheng [Beijing National Laboratory for Condensed Matter Physics, Institute of Physics, Chinese Academy of Sciences, Beijing 100190 (China)

    2017-08-01

    Highlights: • New Heusler alloy Co{sub 2}RuSi has been prepared by melt-spinning successfully. • Magnetic and electronic properties of Co{sub 2}RuSi were investigated. • Ru has a strong site preference for A, C sites in the lattice of Co{sub 2}RuSi. • Site preference of Ru cannot be determined by “number of valence electrons”. - Abstract: Heusler alloy Co{sub 2}RuSi has been synthesized by melt-spinning technology successfully. Co{sub 2}RuSi bulk sample after annealing is composed of an HCP Co-rich phase and a BCC Ru-Si phase, but melt-spinning can suppress the precipitation of the HCP phase and produce a single Co{sub 2}RuSi Heusler phase. In the XRD pattern, it is found that Ru has a strong preference for the (A, C) sites, though it has fewer valence electrons compared with Co. This site preference is different from the case in Heusler alloys containing only 3d elements and is supported further by first-principles calculations. Melt-spun Co{sub 2}RuSi has a M{sub s} of 2.67 μ{sub B}/f.u. at 5 K and a Tc of 491 K. An exothermic peak is observed at 871 K in the DTA curve, corresponding to the decomposition of the Heusler phase. Finally, the site preference and magnetic properties of Co{sub 2}RuSi were discussed based on electronic structure calculation and charge density difference.

  18. Ferromagnetic transition and double exchange of electrons in the Ru1-xCrxCaO3 compounds

    Directory of Open Access Journals (Sweden)

    H Hadipour

    2009-08-01

    Full Text Available   We have investigated the electronic structure of Ru1-xCrxCaO3 using the full potential linearized augmented plane wave method within the local spin density approximation. We have obtained the spin magnetic moment centered at Ru sites from LSDA calculation. The Ru magnetic moment is consistent with the experimental estimates and is lower than the t32g↑t12g↓ electronic configuration. Cr decreases the extension of the 4d orbitals and increases the exchange coupling between electrons which may increase the magnetic moment further. Parameters of the electron-electron interaction for the RuMO3 and CrMO3 with M=Ca have been estimated by the standard LSDA-constraint technique. These calculations show that both the DOS and effective Coulomb interaction increase with the increase of Cr content.

  19. Level structure of 99Tc by inelastic scattering and proton stripping

    International Nuclear Information System (INIS)

    Peterson, R.J.; Emigh, R.A.; Anderson, R.E.

    1977-01-01

    The 98 Mo( 3 He,d) 99 Tc and 99 Tc(d,d') reactions have been used to study the levels of 99 Tc. Spin-parity assignments are made for nearly all states below 1.5 MeV excitation. Strong j-dependence is noted for l=1 transitions in the proton stripping reaction, making possible several new spin assignments. The inelastic scattering data on 99 Tc are compared to similar data on 98 Mo, and are found to be in agreement with a coupling scheme based on a shell model with good seniority. (Auth.)

  20. A system for routine production of 99mTc by thermal separation technique

    International Nuclear Information System (INIS)

    Sahm, U.; Helus, F.; Krauss, O.; Baier-Borst, W.

    1976-01-01

    Technetium-99m is one of the most widely used radionuclides in diagnostic medicine, and it is a general opinion that 99m Tc and the radiopharmaceuticals obtained from it will be used for a long time. 99m Tc has convenient physical and biological parameters for clinical applications. 99m Tc is formed by the beta decay from its 99 Mo parent. 99 Mo is produced by neutron irradiation of natural Mo or enriched 98 Mo, or as a fission product of 235 U. A third approach is cyclotron production of 99 Mo by proton bombardment of enriched 100 Mo over 100 Mo(p,pn) 99 Mo reaction. The most common method of separating 99m Tc from its 99 Mo parent is the elution of 99m Tc with normal saline from an aluminum oxide column containing adsorbed 99 Mo. The second method is solvent extraction using methylethylketon. The sublimation method is based on different volatility of MoO 3 and Tc 2 O 7 . Previously the development of a practical sublimation generator has been studied and some of them have been used routinely. As a reactor and cyclotron owner we have examined the possibility of producing our own 99m Tc with the aim of being independent from supplier and transportation problems. We have studied the separation of 99m Tc with the aim of being independent from supplier and transportation problems. We have studied the separation of 99m Tc from MoO 3 by complete distillation of gram amounts of natural MoO 3 or enriched 98 MoO 3 irradiated in reactor. The principle of the described method is based on the complete evaporation of MoO 3 and Tc 2 O 7 oxides and its following fractionated condensation. To realize this idea, two different generator systems for repeated multiple separation were developed and studied. The first based on using a two-oven technique. A quartz apparatus is placed in two ovens which are situated side by side and heated to different temperatures. Sweeping gas carries irradiated 99 MoO 3 from a middle part of the first oven heated to a higher temperature (1100 deg. C

  1. Mo-99 supply issues: Status report and lessons learned

    International Nuclear Information System (INIS)

    Ponsard, B.

    2010-01-01

    The worldwide supply of 99 Mo relies on a limited number of research reactors and processing facilities. Its production is essential for the nuclear medicine as 99m Tc, obtained from 99 Mo/ 99m Tc generators, is used in about 80% of the diagnostic nuclear imaging procedures. These applications represent yearly approximately 30 million examinations worldwide. The short half-life's of 99 Mo (66 hours) and its daughter 99m Tc (6 hours) require a regular supply of 99 Mo/ 99m Tc generators to hospitals or central radiopharmacies. Currently, there are only five nuclear reactors involved in the production of 99 Mo on industrial scale: NRU (Canada), HFR (Netherlands), BR2 (Belgium), OSIRIS (France) and SAFARI (South Africa). They irradiate highly enriched uranium targets for the production of about 95% of the available 99 Mo by four processing facilities: AECL/MDS NORDION (Canada), COVIDIEN (Netherlands), IRE (Belgium) and NTP (South Africa). However, these ageing reactors are subject to unscheduled shutdowns and longer maintenance periods making the 99 Mo supply chain vulnerable and unreliable. Several severe disruptions have been experienced since the fall 2005 due to the occurrence of problems at different stages of the supply chain: reactor outages, release of activity from processing facilities, recall of 99 Mo/ 99m Tc generators by the manufacturers, ... It is not expected that the situation will improve significantly in the near future. Therefore, several workshops have been organized in 2009 by the OECD Nuclear Energy Agency (NEA), the International Atomic Energy Agency (IAEA) and the Association of Imaging Producers and Equipment Suppliers (AIPES) to define measures that should be taken to secure the 99 Mo supply in the short, medium and long term. This paper summarizes the current status of the 99 Mo supply, discusses the ongoing plans for additional 99 Mo production capacity and outlines the issues for a reliable global supply chain. (author)

  2. Round table on RU486.

    Science.gov (United States)

    Shallat, L

    1993-01-01

    As a non-invasive means of early abortion, RU-486 has the potential to increase women's reproductive options; at the same time, the "abortion pill" has stimulated debate about the ethics and safety of new medical technologies. When combined with a prostaglandin (PG), the success rate for RU-486 is 96% for pregnancies of up to 9 weeks' gestation. In France, over 120,000 women have used RU-486/PG to terminate pregnancy, and this regimen is now used in about 25% of abortions. Clinical trials of RU-486 are underway in Cuba, China, India, Singapore, and Zambia. The Program for Appropriate Technology has identified four considerations for introducing RU-486 to developing countries: whether abortion or menstrual regulation is legal; whether women find the method acceptable and can comply with the multiple visit treatment regimen; whether the health infrastructure can support safe method use, including prevention of misuse and provision of appropriate medical backup personnel and facilities; and whether the cost of the regimen is affordable to individuals and/or programs --conditions unlikely to be met in most such countries. Ideal would be development of a medical abortifacient that is single dose and the lowest possible dose of each drug, provokes miscarriage within a more predictable time frame with less acute and prolonged bleeding, is safe and effective beyond two months, has minimal side effects, and maximizes short-term safety and minimizes long-term effects. Technological advances are being undermined, however, by political and religious attacks on the method. Even some feminists have expressed concerns about potential long-term effects of RU-486 use.

  3. Magnesium-molybdenum compounds as matrices of generators of {sup 99m} Tc; Compuestos de magnesio-molibdeno como matrices de generadores de {sup 99m} Tc

    Energy Technology Data Exchange (ETDEWEB)

    Jimenez M, T.S.; Monroy G, F. [ININ, A.P. 18-1027, 11801 Mexico D.F. (Mexico)]. E-mail: thania_susana@terra.com.mx

    2004-07-01

    The generator system of radionuclides more diffused, and used in the world, it is the{sup 99}Mo / {sup 99m} Tc. These use {sup 99} Mo, product of fission of the {sup 235} U of very high specific activity, adsorbed on alumina (0.2% of {sup 99} Mo/gram of alumina). An alternative for the production of generators of low activity specifies, via the reaction {sup 98} Mo(n, {gamma}) {sup 99} Mo, it is based on the use of compounds with molybdates base, as matrices of the generators {sup 99} Mo / {sup 99m} Tc. In this work is proposed to develop a generator at base of compounds of magnesium molybdates that could be irradiated after its synthesis, given the short half life of the only radioisotope produced by magnesium: {sup 27} Mg (t{sub 1/2} = 9.46 m). In this work two parameters were studied, fundamental in the preparation of the magnesium molybdates, matrices of the generators {sup 99}Mo / {sup 99m}Tc, and their influence in the efficiency and radionuclide purity: the washing of the gels previous to its irradiation and the molar ratio Mo:Mg. The magnesium molybdates non washing presents bigger efficiencies (72%), but they don't fulfill a smaller percentage to 0.015% of {sup 99} Mo, neither with a radiochemical purity of 90%, except when the molar ratio Mo: Mg of 1:1.08 which provide the best results. (Author)

  4. 103Ru for tumor scanning, 2

    International Nuclear Information System (INIS)

    Mizukawa, Kiichiro

    1979-01-01

    The mechanism of 103 Ru-uptake in tumors was investigated through the incubation of rat ascites hepatoma cells (AH-130) in vitro with various concentrations of Ru-chloride containing 103 Ru-chloride as a tracer. Quantitative analysis of Ru binding to the cells indicated that ascites hepatoma cells contained high- and low-affinity binding sites for Ru. When ascites hepatoma cells were incubated with Ru after incubation with a low concentration of papain, most of the Ru was not bound to the cells but was found in the medium containing solubilized glycoproteins. However Ru bound mainly to washed cells after the incubation with papain. About 65% of the Ru bound to ascites hepatoma cells was liberated by the papain treatment, and about 45% of the liberated Ru was precipitated by cetyltrimethylammonium bromide, indicating that Ru bound tightly to glycopeptides. These results suggest that the tumor affinity of 103 Ru is related to specific binding to glycopeptides on the tumor cell surface. (author)

  5. Ru (amp)(bipy)Cl

    Indian Academy of Sciences (India)

    Administrator

    [RuV(amp)(bipy)O]+ intermediate complex which leads to the high affinity for hydrogen atom/hydride abstraction. Acknowledgement. We gratefully acknowledge the financial support from the Department of Science &. Technology, Government of India. We are thankful to Shri Hardyal Singh for his encouragement. Reference.

  6. Ruthenium-97 hepatobiliary agents for delayed studies of the bilary tract I: Ru-97 PIPIDA: concise communication

    International Nuclear Information System (INIS)

    Schachner, E.R.; Gil, M.C.; Atkins, H.L.; Som, P.; Srivastava, S.C.; Badia, J.; Sacker, D.F.; Fairchild, R.G.; Richards, P.

    1981-01-01

    Failure of early diagnosis of biliary atresia results in the development of cirrhosis and death. Commonly used hepatobiliary agents are not ideal for follow-up studies because of their unfavorable physical properties or short half-life. The excellent physical properties of Ru-97 should overcome these limitations. Therefore, Ru-97 PIPIDA (N,α-(p-isopropyl acetanilide) iminoacetic acid) is being investigated as a potential hepatobiliary agent that would allow an improved diagnosis of the disease. Ruthenium-97 PIPIDA and Tc-99m PIPIDA showed similar blood clearance rates in dogs. Ru-97 PIPIDA scintigrams in dogs showed early uptake in liver and gallbladder and slow excretion through the gastrointestinal tract. Biodistribution studies were performed in normal rats and rats with biliary obstruction. The findings suggest that Ru-97 PIPIDA should be useful for delayed studies ( 1 to 3 days) of the biliary tract

  7. Strategies toward the commercialization PZC-based Tc-99m generator in the Philippines

    International Nuclear Information System (INIS)

    Borras, Ma. Teresa L.; Sombrito, Elvira Z.; Dela Rosa, Alumanda M.; Osorio, Rizalina G.; Bulos, Adelina DM.

    2007-01-01

    Technetium-99m ( 99m Tc) is the most widely used radioisotope in nuclear medicine. It accounts for more than 80% of the total demand for radioisotopes. Alone or conjugated with other ligands, it is very useful in the imaging and scanning of various organs such as the brain, lungs, kidneys, liver, thyroid and bone and in the diagnosis of metabolic disorders. It is imported to the country as 99 Mo- 99m Tc generators. These commercial generators use fission molybdenum adsorbed onto alumina column. A Draft Business Plan for the Production of PZC 99 Mo- 99m Tc Generator in the Philippines was presented during the FNCA 2005 Workshop on the Utilization of Research Reactors, August 08-12, 2005. The Philippine Nuclear Research Institute (PNRI) proposed in the draft business plan, the commercial production of PZC generator through the establishment of a facility for the in-house production of 99 Mo- 99m Tc generators. The radioisotope laboratory of the Irradiation Services Unit will be renovated to house the PZC based 99 Mo- 99m Tc generator experiment/production facility. Since the research reactor is on extended shutdown, the supply of 99 Mo will be sourced out from neighboring countries. Information dissemination and promotions will be made in order to bring this PZC based 99 Mo- 99m Tc generator to the nuclear medicine users. (author)

  8. A new approach for manufacturing and processing targets to produce 99mTc with cyclotrons

    Science.gov (United States)

    Matei, L.; McRae, G.; Galea, R.; Niculae, D.; Craciun, L.; Leonte, R.; Surette, G.; Langille, S.; Louis, C. St.; Gelbart, W.; Abeysekera, B.; Johnson, R. R.

    2017-06-01

    The most important radioisotope for nuclear medicine is 99mTc. After the supply crisis of 99Mo starting in 2008, the availability of 99mTc became a worldwide concern. Alternative methods for producing the medical imaging isotope 99mTc are actively being developed around the world. The reaction 100Mo(p, 2n)99mTc provides a direct route that can be incorporated into routine production in nuclear medicine centers that possess medical cyclotrons for production of other isotopes, such as those used for Positron Emission Tomography. This paper describes a new approach for manufacturing targets for the (p, 2n) nuclear reaction on 100Mo and the foundation for the subsequent commercial separation and purification of the 99mTc produced. Two designs of targets are presented. The targets used to produce 99mTc are subject to a number of operational constraints.They must withstand the temperatures generated by the irradiation, accommodate temperature gradients from cooling system of the target, must be resilient and must be easily post-processed to separate the 99mTc. After irradiation, the separation of Tc from Mo was carried out using an innovative two-step approach. The process described in this paper can be automated with modules that easily fit in standard production hot cells found in nuclear medicine facilities.

  9. Phase relations in the M2MoO4 - Ag2MoO4 - Hf(MoO4)2 (M=Li, Na) systems

    International Nuclear Information System (INIS)

    Bazarova, Zh.G.; Bazarov, B.G.; Balsanova, L.V.

    2002-01-01

    The M 2 MoO 4 - Ag 2 MoO 4 - Hf(MoO 4 ) 2 (M=Li, Na) systems were studied by X-ray diffraction and differential thermal analyses in the subsolidus area (450 - 500 Deg C) for the first time. The formation of the binary compound with the variable composition Li 4-x Hf 1+0.2x (MoO 4 ) 4 (0 ≤ x ≤ 0.6) in the Li 2 MoO 4 - Hf(MoO 4 ) 2 system and the ternary molybdates Li 4 Ag 2 Hf(MoO 4 ) 5 (S 1 ) and Na 2 Ag 2 Hf(MoO 4 ) 4 (S 2 ) was established and the thermal characteristics of the prepared compounds were examined. The new binary molybdate Ag 2 Hf(MoO 4 ) 3 was prepared by the reaction between Ag 2 MoO 4 and Hf(MoO 4 ) 2 [ru

  10. Experimental thin-target and thick-target yields for natOs(α, xn)Pt, natOs(α, X)Os, Ir and natMo(p, xn)Tc nuclear reactions from threshold up to 38 and 45 MeV, by combined single and stacked foil techniques

    International Nuclear Information System (INIS)

    Birattari, Claudio; Bonardi, Mauro; Gini, Luigi; Groppi, Flavia; Menapace, Enzo

    2002-01-01

    The experimental values of thin-target excitation functions for the nuclear reactions: nat Os(α, X) 188,189,191 Pt, 192g,194m Ir in the energy range 11 - 38 MeV and nat Mo(p, xn) 94g,95g,95m,96(m+g) Tc in the energy range 5 - 44 MeV are presented. The experimental values were obtained by cyclotron activation followed by off-line HPGe γ-spectrometry and corrected at the End Of an Instantaneous Bombardment, EOIB. In different cases use was made of single foil and stacked foil techniques, which present significantly different advantages and disadvantages. The thin-target yield values can be easily either numerically or analytically integrated, as a function of both incoming particle energy and energy loss in target itself, in order to calculate apriori the thick-target yield of various radionuclides under any different experimental condition. Moreover, the thin-target yields are directly related to the effective cross-sections of various nuclear reaction channels involved. The data are of relevant interest for optimizing cyclotron production of platinum and technetium radionuclides to be used as radiotracers for metallo-biochemical, biomedical, toxicological and environmental studies. (author)

  11. Cyclotron produced Tc-99m: testing compatibility with established kits

    Czech Academy of Sciences Publication Activity Database

    Lebeda, Ondřej; Ráliš, Jan; Hradilek, Pavel; Hanč, Petr; van Lier, E. J.; Zyuzin, A.; Moša, M.

    2013-01-01

    Roč. 40, 2 Supplement (2013), S424-S425 ISSN 1619-7070. [Annual Congress of the European Association of Nuclear Medicine (EANM). 19.10.2013-23.10.2013, Lyon] Institutional support: RVO:61389005 Keywords : cyclotron U-120M * Tc-99m * 100Mo Subject RIV: BG - Nuclear, Atomic and Molecular Physics , Colliders

  12. Metal-insulator transition and superconductivity induced by Rh doping in the binary pnictides RuPn (Pn=P, As, Sb)

    Science.gov (United States)

    Hirai, Daigorou; Takayama, Tomohiro; Hashizume, Daisuke; Takagi, Hidenori

    2012-04-01

    Binary ruthenium pnictides, RuP and RuAs, with an orthorhombic MnP structure, were found to show a metal to a nonmagnetic insulator transition at TMI = 270 and 200 K, respectively. In the metallic region above TMI, a structural phase transition, accompanied with a weak anomaly in the resistivity and the magnetic susceptibility, indicative of a pseudogap formation, was identified at Ts = 330 and 280 K, respectively. These two transitions were suppressed by substituting Ru with Rh. We found superconductivity with a maximum Tc = 3.7 and 1.8 K in a narrow composition range around the critical point for the pseudogap phase, Rh content xc = 0.45 and 0.25 for Ru1-xRhxP and Ru1-xRhxAs, respectively, which may provide us with a nonmagnetic route to superconductivity at a quantum critical point.

  13. Phase equilibria in the CdMoO4-Gd2(MoO4)3 system

    International Nuclear Information System (INIS)

    Tunik, T.A.; Fedorov, N.F.; Razumovskij, S.N.

    1980-01-01

    The constitutional diagram of the CdMoO 4 -Cd 2 (MoO 4 ) 3 system has been plotted using statistical and dynamic methods as well as a complex of instrumental analysis procedures. Three major phases have been found to occur in the systems, viz.: CdMoO 4 based solid solutions that crystallize in the range from 0 to 25 mol.percent of Cd 2 (MoO 4 ) 3 and pass in transit the two-phase narrow region becoming then solid solutions having a distorted scheelite structure and existing in concentrations from 40 to 65 mol.% of Cd 2 (MoO 4 ) 3 . The entire range, in which the Cd 2 (MoO 4 ) 3 solid solutions can exist, amounts to less than 5 mol.%. Certain crystallochemical constants of the phases that occur in the system have been determined [ru

  14. Magnesium-molybdenum compounds as matrices of generators of 99m Tc

    International Nuclear Information System (INIS)

    Jimenez M, T.S.; Monroy G, F.

    2004-01-01

    The generator system of radionuclides more diffused, and used in the world, it is the 99 Mo / 99m Tc. These use 99 Mo, product of fission of the 235 U of very high specific activity, adsorbed on alumina (0.2% of 99 Mo/gram of alumina). An alternative for the production of generators of low activity specifies, via the reaction 98 Mo(n, γ) 99 Mo, it is based on the use of compounds with molybdates base, as matrices of the generators 99 Mo / 99m Tc. In this work is proposed to develop a generator at base of compounds of magnesium molybdates that could be irradiated after its synthesis, given the short half life of the only radioisotope produced by magnesium: 27 Mg (t 1/2 = 9.46 m). In this work two parameters were studied, fundamental in the preparation of the magnesium molybdates, matrices of the generators 99 Mo / 99m Tc, and their influence in the efficiency and radionuclide purity: the washing of the gels previous to its irradiation and the molar ratio Mo:Mg. The magnesium molybdates non washing presents bigger efficiencies (72%), but they don't fulfill a smaller percentage to 0.015% of 99 Mo, neither with a radiochemical purity of 90%, except when the molar ratio Mo: Mg of 1:1.08 which provide the best results. (Author)

  15. LEUbased Fission Mo-99 Process with Reduced Solid Wastes

    International Nuclear Information System (INIS)

    Lee, Seungkon; Lee, Suseung; Jung, Sunghee; Hong, Soonbog; Jang, Kyungduk; Choi, Sang Mu; Lee, Jun Sig; Lim, Incheol

    2014-01-01

    99m Tc emits 140 keV of very low gamma-ray radiation energy, as low as conventional diagnostic X-ray, and has short half-life of 6.0058 hours. Therefore, as radioactive tracer, 99m Tc provides high quality diagnostic images but keeps total patient radiation exposure low. Depending on the tagging pharmaceuticals and procedures, 99m Tc can be applied for the diagnostics of various target organs and diseases: brain, myocardium, thyroid, lungs, liver, gallbladder, kidneys, skeleton, blood and tumors. More than 95% of 99 Mo is produced through fission of 235 U worldwide because, 99m o generated from the fission (fission 99 Mo) exhibits very high specific activity (<100 Ci/g). Over 90% of fission 99 Mo producers have been used highly enriched uranium (HEU) targets so far. However, the IAEA recommends the use of low enriched uranium (LEU) to the 99 Mo producers for nonproliferation reason. These days, worldwide 99 Mo supply is not only insufficient but also unstable. Because, most of the main 99 Mo production reactors are about 50 years old and suffered from frequent and unscheduled shutdown. Planned weekly productivity of 2000 Ci fission 99 Mo, in a 6-day reference, will cover 100% domestic demand of Korea, as well as 20% of international market. It is expected to replace 4.3 million USD ($800/Ci) of 99 Mo import for domestic market while exporting 82.8 million USD for world market, annually

  16. Toroidal deuteron accelerator for Mo-98 neutron activation

    International Nuclear Information System (INIS)

    Araujo, Wagner L.; Campos, Tarcisio P.R. Universidade Federal de Minas Gerais

    2017-01-01

    The radionuclide Tc- 99m is the most useful radioisotope in nuclear medicine. It can be produced by the Mo-99 beta minus decay. Mo-99 has often been produced in a high- flux nuclear reactor through radioactive neutron capture reactions on Mo-98. The present paper provides a preliminary design of a toroidal transmutation system (TTS) based on a toroidal compact deuteron accelerator, which can provide the Mo-98 transmutation into Mo-99. This system is essentially composed of a multi-aperture plasma electrode and a target, submitted to 180 kV, where a positive deuteron beam is accelerated toward a titanium-target loaded with deuterium in which nuclear d-d fusion reactions are induced. The Particle Studio package of the Computer Simulation Technology (CST) software was applied to design, simulate and optimize the deuteron beam on the target. MCNP code provided to neutronic analysis. Based on electromagnetic and neutronic simulations, the neutron yield and reaction rates were estimated. The simulated data allowed appraising the Mo-99 activity. A TTS, in a specific configuration, could produce a total deuterium current of 1.6 A at the target and a neutron yield of 10 13 n.s -1 . In a arrangement of 30 column samples, TTS provides 230 mCi s -1 Mo 99 in each column, which represents 80% of Tc-99m in secular equilibrium. As conclusion, the system holds potential for generating Mo-99 and Tc-99m in a suitable activity in secular equilibrium. (author)

  17. Validity of 99mTc-DMSA renal uptake by planar posterior-view method in children

    International Nuclear Information System (INIS)

    Tsukamoto, Eriko; Katoh, Chietsugu; Mochizuki, Takafumi; Shiga, Toru; Morita, Koichi; Tamaki, Nagara; Itoh, Kazuo

    1999-01-01

    Renal uptake 99m Tc-DMSA has been quantified by various methods. The aim of this study is to obtain a normal value for 99m Tc-DMSA renal uptake calculated by the posterior view method and age variation, and to assess its clinical validity. Scintigrams of 238 children (0-12 years) with 99m Tc-DMSA were reviewed. All the children had a clinical history of primary vesicoureteral reflux and/or neurogenic bladder, ureteral or urethral anomalies. Their kidneys were divided into two groups, ''normal'' and abnormal'' according to their scintigraphic findings and split renal functions. Percent renal uptake per injected dose (% RU) was quantitated from planar images at 2 hours after injection of an age-adjusted dose (26-95 MBq) of 99m Tc-DMSA. Calculated total % RU, individual % UR of the right and left kidneys (mean±sd) in patients with normal kidneys were 40.7±5.0%, 20.2±3.0%, 20.4±2.7%, respectively. There was no significant correlation between % RU and age (r=0.231). Longitudinal variation in the % RU in 9 patients ranged from 1.2% to 18%. Our conventional method for quantifying % RU is simple, practical and feasible in routine clinical practice, especially for children under follow up. (author)

  18. The trend of 99mTc generator in FNCA countries

    International Nuclear Information System (INIS)

    Genka, Tsuguo; Machi, Sueo

    2004-01-01

    In the 2001 Workshop on Utilization of Research Reactors held in Beijing, eight delegates from the FNCA countries, namely China, Indonesia, Japan, Korea, Malaysia, the Philippines, Thailand and Vietnam, for the 99m Tc Generator Project, presented papers or orally pleaded the current status of utilization and production in terms of 99 Mo solution, 99 Mo/ 99m Tc generator or extracted 99m Tc solution in each country. This paper is a brief compilation of these topics and some additional information obtained afterward the workshop. (author)

  19. Recent achievements in Tc-99m radiopharmaceutical direct production by medical cyclotrons.

    Science.gov (United States)

    Boschi, Alessandra; Martini, Petra; Pasquali, Micol; Uccelli, Licia

    2017-09-01

    99m Tc is the most commonly used radionuclide in the field of diagnostic imaging, a noninvasive method intended to diagnose a disease, assess the disease state and monitor the effects of treatments. Annually, the use of 99m Tc, covers about 85% of nuclear medicine applications. This isotope releases gamma rays at about the same wavelength as conventional X-ray diagnostic equipment, and owing to its short half-life (t ½  = 6 h) is ideal for diagnostic nuclear imaging. A patient can be injected with a small amount of 99m Tc and within 24 h almost 94% of the injected radionuclide would have decayed and left the body, limiting the patient's radiation exposure. 99m Tc is usually supplied to hospitals through a 99 Mo/ 99m Tc radionuclide generator system where it is produced from the β decay of the parent nuclide 99 Mo (t ½  = 66 h), which is produced in nuclear reactors via neutron fission. Recently, the interruption of the global supply chain of reactor-produced 99 Mo, has forced the scientific community to investigate alternative production routes for 99m Tc. One solution was to consider cyclotron-based methods as potential replacement of reactor-based technology and the nuclear reaction 100 Mo(p,2n) 99m Tc emerged as the most worthwhile approach. This review reports some achievements about 99m Tc produced by medical cyclotrons. In particular, the available technologies for target design, the most efficient extraction and separation procedure developed for the purification of 99m Tc from the irradiated targets, the preparation of high purity 99m Tc radiopharmaceuticals and the first clinical studies carried out with cyclotron produced 99m Tc are described.

  20. Metalloradical Reactivity of RuI and Ru0 Stabilized by an Indole-Based Tripodal Tetraphosphine Ligand

    NARCIS (Netherlands)

    van de Watering, F.F.; van der Vlugt, J.I.; Dzik, W.I.; de Bruin, B.; Reek, J.N.H.

    2017-01-01

    The tripodal, tetradentate tris(1-(diphenylphosphanyl)-3-methyl-1H-indol-2-yl)phosphane PP3-ligand 1 stabilizes Ru in the RuII, RuI, and Ru0 oxidation states. The octahedral [(PP3)RuII(Cl)2] ( 2 ), distorted trigonal bipyramidal [(PP3)RuI(Cl)] ( 3 ), and trigonal bipyramidal [(PP3)Ru0(N2)] ( 4 )

  1. Quaternary reciprocal system Na,K//Cl,Co3,MoO4

    International Nuclear Information System (INIS)

    Kochkarov, Zh.A.; Gasanaliev, A.M.

    2004-01-01

    Quaternary reciprocal system Na,K//Cl,Co 3 ,MoO 4 has been investigated for the first time by differential thermal analysis using the methods of projective and differential geometry. A stable (KCl) 2 -Na 2 CO 3 -K 2 CO 3 -K 2 MoO 4 tetrahedron and (NaCl) 2 -(KCl) 2 -Na 2 CO 3 -K 2 MoO 4 -Na 2 MoO 4 pentatope have been revealed in the system. It has been found that four quadruple invariant points are realized in the Na,K//Cl,Co 3 ,MoO 4 system, including one eutectic and three peritectic points [ru

  2. Synthesis and Crystal Structure of a New Ruthenium Silicophosphate: RuP 3SiO 11

    Science.gov (United States)

    Fukuoka, Hiroshi; Imoto, Hideo; Saito, Taro

    1996-01-01

    A new ruthenium silicophosphate RuP3SiO11was obtained and the structure was determined by single-crystal X-ray diffraction. It crystallizes in the trigonal space groupR3cwitha= 8.253(3)Å,c= 39.317(4)Å,V= 2319(2)Å3,Z= 12,R= 0.029, andRW= 0.026. The structure is composed of RuO6, Si2O7, and P2O7units. The Si2O7unit shares the six oxygen atoms with six P2O7units, while the P2O7unit shares the six oxygen atoms with two Si2O7units and four RuO6octahedra. The anionic part forms an infinite three-dimensional network of silicophosphate. RuP3SiO11is isotypic with MoP3SiO11.

  3. Thrombus imaging with [sup 99m]Tc-HMPAO-labeled platelets and [sup 111]In-labeled monoclonal antifibrin antibodies

    Energy Technology Data Exchange (ETDEWEB)

    Vorne, M.S.; Honkanen, T.T.; Lantto, T.J.; Laitinen, R.O.; Karppinen, K.J.; Jauhola, S.V. (Depts. of Nuclear Medicine and Diagnostic Radiology, Paeijaet-Haeme Central Hospital, Lahti (Finland))

    1993-01-01

    Eighteen patients with suspicion of deep venous thrombosis (DVT) in the lower extremities were imaged both with autologous [sup 99m]Tc-HMPAO-labeled platelets (Tc-PLT) and [sup 111]In-labeled monoclonal antifibrin antibodies (In-MoAbs) on the same day. Precence or absence of thrombosis was verified by venography. Tc-PLT was given i.v. followed after 30 min by In-MoAbs. Anterior and posterior projections of the lower extremities were obtained with a large field-of-view gamma camera at 5 to 25 min, 2 h, 4 to 6 h, and 20 h after administration of the marker. Both Tc-PLT and In-MoAbs detected DVT well but less frequently than venography. Thrombi were visualized at 2 to 4 h after injection. The quality of images was better with Tc-PLT than with In-MoAbs. In the patients treated during the study, heparin significantly (p< 0.01) inhibited the uptake of Tc-PLT but not of In-MoAbs. We conclude that both Tc-PLT and In-MoAbs are suitable agents for the detection of DVT especially in patients without anticoagulation. (orig.).

  4. The {sup 99m}Tc generator using poly zirconium chloride (PZC)

    Energy Technology Data Exchange (ETDEWEB)

    Wan Awang, Wan Anuar; Dahalan, Rehir; Kasim, Shaaban [Medical Technology Div., Malaysian Inst. for Nuclear Technology Research (MINT), Selangor (Malaysia)

    1998-10-01

    The {sup 99m}Tc generator system has been prepared using poly zirconium chloride (PZC) to replace alumina (Al{sub 2}O{sub 3}) as a adsorbent. The Mo-98 (MoO{sub 3}) was irradiated using our 1 MW TRIGA MARK II research reactor. The amount of Mo-99 adsorbed to the PZC has been studied and the yield from the elution was about 20%. (author)

  5. Preparation of 99 sup(m)Tc labeled fibrinogen

    International Nuclear Information System (INIS)

    Almeida, M.A.T.M. de; Silva, C.P.G. da.

    1984-01-01

    A simple method for the preparation of 99 sup(m) TC labelled Fibrinogen using stannous chloride as reducing agent of 99 sup(m) TcO- 4 ion is presented. A sample of 20 mg of Fibrinogen is dissolved in 2 ml of buffer carbonate (pH=8) and 0.3 ml stannous chloride 0.2% is added. A sterile solution of sodium pertechnetate 99 sup(m) Tc eluted from a Mo-Tc generator is immediately added. The mixture rests for 30 minutes and after this period, the obtained yield is about 70%. The lyophilized kits also presented a yield of 70%, being therefore suitable for medical applications. (Author) [pt

  6. Sup(99m)Tc compounds for diagnostic purposes

    International Nuclear Information System (INIS)

    Cifka, J.; Budsky, F.

    1980-01-01

    The applications of sup(99m)Tc in nuclear medicine are discussed, such as sodium pertechnetate in thyroid and brain scintigraphy, complex compounds in lungs and liver diao.nosis. Technetium generators are classified according to the method of separating sup(99m)Tc from 99 Mo. Adsorption generators are used, molybdate-99 is adsorbed on an Al 2 O 3 -packed column while pertechnetate-99m is eluted with 0.9% NaCl solution. Also used is continuous pertechnetate-99m extraction with methyl ethyl ketone from 0.5 M potassium molybdate and 2.5 M of potassium carbonate. The manufacture is described of kits for sup(99m)Tc radiopharmaceuticals preparation, eg., Diagos I, a gluconate complex, a lyophilisate for sup(99m)Tc-sodium pyrophosphate injections, a diagnostic kit for lung scintiscanning. (H.S.)

  7. Anomalous enhancement of the lower critical field deep in the superconducting state of LaRu4As12

    Science.gov (United States)

    Juraszek, J.; Bochenek, Ł.; Wawryk, R.; Henkie, Z.; Konczykowski, M.; Cichorek, T.

    2018-05-01

    LaRu4As12 with the critical temperature Tc = 10.4 K displays several features which point at a non-singlet superconducting order parameter, although the bcc crystal structure of the filled skutterudites does not favour the emergence of multiple energy gaps. LaRu4As12 displays an unexpected enhancement of the lower critical field deep in superconducting state which can be attributed to the existence of two superconducting gaps. At T = 0.4 K, the local magnetization measurements were performed utilizing miniaturized Hall sensors.

  8. Solid targets for 99mTc production on medical cyclotrons

    International Nuclear Information System (INIS)

    Hanemaayer, V.; Buckley, K.R.; Klug, J.; Ruth, T.J.; Schaffer, P.; Zeisler, S.K.; Benard, F.; Kovacs, M.; Leon, C.

    2014-01-01

    Recent disruptions in the molybdenum-technetium generator supply chain prompted a review of non-reactor based production methods for both 99 Mo and 99m Tc. Small medical cyclotrons (E p ∼ 16-24 MeV) are capable of producing Curie quantities of 99m Tc from isotopically enriched 100 Mo using the 100 Mo(p,2n) 99m Tc reaction. Unlike most other metallic target materials for routine production of medical radioisotopes, molybdenum cannot be deposited by reductive electroplating from aqueous salt solutions. To overcome this issue, we developed a new process for solid molybdenum targets based on the electrophoretic deposition of fine 100 Mo powder onto a tantalum plate, followed by high temperature sintering. The targets obtained were mechanically robust and thermally stable when irradiated with protons at high power density. (author)

  9. Phase relations in the systems M2MoO4-Cr2(MoO4)3-Zr(MoO4)2 (M=Li, Na, or Rb)

    International Nuclear Information System (INIS)

    Bazarov, B.G.; Chimitova, O.D.; Bazarova, Ts.T.; Arkhincheeva, S.I.; Bazarova, Zh.G.

    2008-01-01

    Phase equilibria in the systems M 2 MoO 4 -Cr 2 (MoO 4 ) 3 -Zr(MoO 4 ) 2 (M=Li, Na, or Rb) were investigated by X-ray powder diffraction analysis, DTA, and IR spectroscopy. The subsolidus structure of the phase diagrams of the systems under study was established. Two phases are formed in the Rb 2 MoO 4 -Cr 2 (MoO 4 ) 3 -Zr(MoO 4 ) 2 system with the molar ratios of the starting components equal to 5:1:1 (S 2 ) and 1:1:1 (S 1 ). Proceeding from isostructural character of Rb 5 FeHf(MoO 4 ) 6 and S 2 , the unit cell parameters are determined for S 2 [ru

  10. Geochemical evidence of the double β decay of 100Mo

    International Nuclear Information System (INIS)

    Hidaka, Hiroshi; Ly, Chi V.; Suzuki, Katsuhiko

    2004-01-01

    Enrichment of the 100 Ru isotope, resulting from the double beta (ββ) decay of 100 Mo, has been found in old molybdenites from Australia. Using Re-Os ages determined here together with the amount of excess 100 Ru determined via isotope dilution mass spectrometry, consistent half-lives were obtained from two different molybdenite samples of varying ages (2.90 billion and 1.05 billion years old) with an average half-life of (2.1±0.3)x10 18 years. This half-life is highly consistent with the theoretical model for a two-neutrino ββ decay

  11. Formation of Ni(Al, Mo) solid solutions by mechanical alloying and their ordering on heating

    International Nuclear Information System (INIS)

    Portnoj, V.K.; Tomilin, I.A.; Blinov, A.M.; Kulik, T.

    2002-01-01

    The Ni(Al, Mo) solid solutions with different crystalline lattice periods (0.3592 and 0.3570 nm correspondingly) are formed in the course of the Ni 70 Al 25 Mo 5 and Ni 75 Al 20 Mo 5 powder mixtures mechanical alloying (MA) (through the mechanical activation in a vibrating mill). After MA the Mo atoms in the Ni 75 Al 20 Mo 5 mixture completely replace the aluminium positions with formation of the Ni 75 (AlMo) 25 (the L1 2 -type) ternary ordered phase, whereby such a distribution remains after heating up to 700 deg C. The Ni(Al, Mo) metastable solution is formed by MA in the Ni 75 Al 20 Mo 5 mixture, which decays with the release of molybdenum and the remained aluminide undergoes ordering by the L1 2 -type [ru

  12. Inner-shell photodetachment from Ru-

    International Nuclear Information System (INIS)

    Dumitriu, I.; Gorczyca, T. W.; Berrah, N.; Bilodeau, R. C.; Pesic, Z. D.; Rolles, D.; Walter, C. W.; Gibson, N. D.

    2010-01-01

    Inner-shell photodetachment from Ru - was studied near and above the 4p excitation region, 29-to-91-eV photon energy range, using a merged ion-photon-beam technique. The absolute photodetachment cross sections of Ru - ([Kr]4d 7 5s 2 ) leading to Ru + , Ru 2+ , and Ru 3+ ion production were measured. In the near-threshold region, a Wigner s-wave law, including estimated postcollision interaction effects, locates the 4p 3/2 detachment threshold between 40.10 and 40.27 eV. Additionally, the Ru 2+ product spectrum provides evidence for simultaneous two-electron photodetachment (likely to the Ru + 4p 5 4d 6 5s 2 state) located near 49 eV. Resonance effects are observed due to interference between transitions of the 4p electrons to the quasibound 4p 5 4d 8 5s 2 states and the 4d→εf continuum. Despite the large number of possible terms resulting from the Ru - 4d open shell, the cross section obtained from a 51-state LS-coupled R-matrix calculation agrees qualitatively well with the experimental data.

  13. Photo-transmutation of {sup 100}Mo to {sup 99}Mo with Laser-Compton Scattering Gamma-ray

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jiyoung; Rehman, Haseeb ur; Kim, Yonghee [KAIST, Daejeon (Korea, Republic of)

    2016-10-15

    This paper presents a photonuclear transmutation method using laser Compton scattering (LCS) gamma-ray beam. Potential production rate (reaction rate) of 99Mo using the photonuclear (γ,n) reaction is evaluated. Rigorous optimization of the LCS spectrum has also been performed to maximize production of the 99Mo. Cyclotron proton accelerators are used worldwide to produce many short-living medical isotopes. However, few are capable of producing Mo-99 and none are suitable for producing more than a small fraction of the required amounts. More than 90% of the world's demand of 99Mo is sourced from five nuclear reactors. Two of these reactors have already been decommissioned and the rest are more than 45 years old. Relatively short half-life of the parent 99Mo requires continuous re-supply to meet the requirements of medical industry. Therefore, there is an urgent need to produce the 99Mo and 99mTc isotopes by alternative ways. One such alternative is giant dipole resonance (GDR) based photonuclear transmutation of 100Mo to 99Mo. For 99Mo production with the LCS photons using GDR-based (γ,n) reaction, the gamma-ray energy should be around 15 MeV. This study indicates that optimization of LCS spectrum by varying the electron and laser energies within practical limits can enhance the transmutation of Mo-100 to M-99 quite significantly. It has been found that irradiation time should be rather short, e.g., less than 6 hours, to maximize the weekly production of Mo-99 in the GDR-based Mo-99 production facility using the LCS photons. The analysis shows that production of 99Mo using a high-performance LCS facility offers a potentially-promising alternative for the production of 99mTc.

  14. Formation of graphene on Ru(0001) surface

    Institute of Scientific and Technical Information of China (English)

    Pan Yi; Shi Dong-Xia; Gao Hong-Jun

    2007-01-01

    We report on the formation of a graphene monolayer on a Ru(0001) surface by annealing the Ru(0001) crystal.The samples are characterized by scanning tunnelling microscopy (STM) and Auger electron spectroscopy (AES). STM images show that the Moiré pattern is caused by the graphene layer mismatched with the underlying Ru(0001) surface and has an N × N superlattice. It is further found that the graphene monolayer on a Ru(0001) surface is very stable at high temperatures. Our results provide a simple and convenient method to produce a graphene monolayer on the Ru(0001) surface, which is used as a template for fabricating functional nanostructures needed in future nano devices and catalysis.

  15. Separation of fission produced 106Ru from simulated high level nuclear wastes for production of brachytherapy sources

    International Nuclear Information System (INIS)

    Blicharska, Magdalena; Bartoś, Barbara; Krajewski, Seweryn; Bilewicz, Aleksander

    2014-01-01

    Brachytherapy is the common method for treating various tumors, and currently 106 Ru and 125 I applicators are the most frequently used. Considering that 106 Ru is a β emitter with maximum energy of 3.54 MeV, it is best indicated in the treatment of small melanomas, with up to 20 mm tissue range. 106 Ru is commercially obtained from neutron irradiated high enrichment 235 U target in process of production 99 Mo. At present, there are only a handful of ageing reactors worldwide capable of producing the 99 Mo, therefore alternative strategies for production of this key medical isotope are explored. In our work, we propose to use liquid high-level radioactive waste as a source of high activity of 106 Ru. Simple calculations indicate that 1 dm 3 of HLLW solution after 4 years of cooling contains about 500 GBq of 106 Ru. This amount of activity is enough for production of about few thousands of brachytherapy sources. Present communication reports results of our process development studies on the recovery of ruthenium radioisotopes from simulated solution of high level radioactive waste using oxidation-extraction method

  16. Recent global crisis in 99Mo production and supplies: analysis and lessons

    International Nuclear Information System (INIS)

    Ramamoorthy, Natesan; Ed Bradley; Adelfang, Pablo; )

    2011-01-01

    The radioisotope 99m Tc is a vital need for diagnostic functional imaging of organs and physiologic processes in nuclear medicine centres and hospitals all over the world. 99m Tc (6 h) is obtained from the radioactive (beta) decay of 99 Mo (66 h) and is generally availed at the user end in hospitals or radiopharmacies from a 99 Mo- 99m Tc generator, and therefore reliable weekly availability of 99 Mo of very high specific activity is essential for sustainable supplies of 99m Tc. Over the past several decades, the commercial availability of 99 Mo (mostly fission-produced) from corporate sources has been satisfactory. However, from around the end of 2007, the production and supplies of 99 Mo were severely and repeatedly affected causing worldwide concerns and led to calls for international efforts to address the security of supplies of 99 Mo and 99m Tc. Various initiatives and analytical reviews during the past two years, including at the IAEA and OECD-NEA, have revealed a number of issues and lessons learnt. Research reactor managers and their governments serving 99 Mo- 99m Tc industry have faced several challenges, technological, regulatory and economical among others, apart from the fact that these reactors are not dedicated to isotopes production. Furthermore, towards long term security of 99 Mo supplies, switch over to using LEU targets and establishing some additional processing capacity need to be addressed. Several alternative non-HEU technologies for producing 99 Mo and 99m Tc are also under consideration, including through non-fission and non-reactor based methods. The article will draw analytical conclusions and recommendations based on the available professional knowledge and experience in the field as well as from the findings reported in the recent documents and in meetings including that of the IAEA and OECD-NEA. (author)

  17. Possible multigap type-I superconductivity in the layered boride RuB2

    Science.gov (United States)

    Singh, Jaskaran; Jayaraj, Anooja; Srivastava, D.; Gayen, S.; Thamizhavel, A.; Singh, Yogesh

    2018-02-01

    The structure of the layered transition-metal borides A B2 (A =Os,Ru ) is built up by alternating T and B layers with the B layers forming a puckered honeycomb. Here we report superconducting properties of RuB2 with a Tc≈1.5 K using measurements of the magnetic susceptibility versus temperature T , magnetization M versus magnetic field H , resistivity versus T , and heat capacity versus T at various H . We observe a reduced heat capacity anomaly at Tc given by Δ C /γ Tc≈1.1 suggesting multigap superconductivity. Strong support for this is obtained by the successful fitting of the electronic specific heat data to a two-gap model with gap values Δ1/kBTc≈1.88 and Δ2/kBTc≈1.13 . Additionally, M versus H measurements reveal a behavior consistent with type-I superconductivity. This is confirmed by comparing the experimental critical field ≈122 Oe obtained from extrapolation to T =0 of the H -T phase diagram, with an estimate of the T =0 thermodynamic critical field ≈114 Oe. Additionally, the Ginzburg-Landau parameter was estimated to be κ ≈0.1 -0.66 . These results strongly suggest multigap type-I superconductivity in RuB2. We also calculate the band structure and obtain the Fermi surface for RuB2. The Fermi surface consists of one quasi-two-dimensional sheet and two concentric ellipsoidal sheets very similar to OsB2. An additional small fourth sheet is also found for RuB2. RuB2 could thus be an example of a multigap type-I superconductor.

  18. A rapid and simple separation method of Tc-99 in water samples

    International Nuclear Information System (INIS)

    Uchida, Shigeo; Tagami, Keiko

    1999-01-01

    Technetium-99 ( 99 Tc) is one of the important elements on safety evaluation of reprocessing plant and waste disposal plant, because it is a long half-life nuclide and large fission yield (about 6%) from 235 U and 239 Pu. We studied in this work a rapid and simple separation method of 99 Tc in water samples by ICP-MS. Tc in 2 litre of inland water or 1.5 litre of sea water sample solutions was condensed and separated by mini-column resin (TEVA·Spec resin) (Eichrom Co., Ltd.). The experimental results showed the best conditions as followed that 1) after controlling 0.1M nitric acid sample solution, passed it through the column, 2) then the inhibitory elements such as Ru are removed by 40 ml of 2M nitric acid solution, and 3) Tc was recovered by 4 ml of 8M nitric acid solution. 95% or more recovery of Tc was obtained. 100% Ru, an inhibited element of ICP-MS, was removed. The elute obtained from 4 ml of 8M nitric acid solution was diluted ten times with pure water and 99 Tc was measured by ICP-MS. The limit of detection of 2 litre inland water and 1.5 litre sea water were 3 mBql -1 and 4 mBql -1 , respectively. The organic compounds were not removed before running to column, because the concentration of organic compounds was not so large. When large amounts of them are contained, they should be removed. If suspended materials absorb Tc, Tc should be changed to TcO 4 - . (S.Y.)

  19. Pressure effects on the magnetic and transport properties of the Kondo lattice system Ce3RuSn6

    Science.gov (United States)

    Wakiya, Kazuhei; Tomaki, Takeru; Kimura, Minami; Uehara, Masatomo; Gouchi, Jun; Uwatoko, Yoshiya; Umehara, Izuru

    2018-05-01

    The magnetization and electrical resistivity of Ce3RuSn6 have been measured in the temperature range from 2 to 300 K and in the pressure range up to 1 GPa. At ambient pressure, the magnetization shows a ferromagnetic-like steep rise below 4 K. The electrical resistivity drops at TC = 3.3 K due to the magnetic transition. We found that TC is slightly enhanced by applying pressure, suggesting that this compound sits on the left side of the peak in the Doniach phase diagram.

  20. Studies on chemical effects on x-ray intensity ratios of K/sub β//K/sub α/ in nuclear decay of technetium nuclides /sup 99m/Tc, /sup 97m/Tc, and /sup 95m/Tc

    International Nuclear Information System (INIS)

    Yamoto, I.; Kaji, H.; Yoshihara, K.

    1986-01-01

    Chemical effects of characteristic x-ray intensity ratios of K/sub β//K/sub α/ were investigated for the second d-group element Tc in the decay processes /sup 99m/Tc → 99 Tc (two-step isomeric transition), /sup 97m/Tc → 97 Tc (one-step isomeric transition), and /sup 95m/Tc → 95 Mo (electron capture). The objective nuclides were produced by (n, γ)β - , (d, xn), and (α, xn) reactions and were chemically separated from the target materials. The x rays were measured with a pure germanium detector, and the K/sub β/ x rays were analyzed into the two components K/sup prime//sub beta1/ and K/sup //sub beta2/ using a computer program. The chemical effect of the intensity ratio was more pronounced for K/sup prime//sub beta2//K/sub α/ than for K/sup //sub beta1//K/sub α/, as expected. The effect was larger in KTcO 4 than in the other species of Tc 2 S 7 , K 2 TcCl 6 , and Tc metal. The effect in the two-step isomeric transition in /sup 99m/Tc was found to be larger than in the one-step isomeric transition in /sup 97m/Tc. The effect in the electron capture in /sup 95m/Tc (Mo x rays) was similar to that in /sup 97m/Tc although the ratio K/sub β//K/sub α/ was smaller in /sup 95m/Tc than in /sup 97m/Tc, reflecting the change of nuclear charge. The tendency of the observed chemical effect was explained by taking into account the interfering factors which involve Pauling's ionicity in chemical bonding between Tc and its counter atom

  1. Experimental cross-sections for proton-induced nuclear reactions on Mo-nat

    Czech Academy of Sciences Publication Activity Database

    Červenák, Jaroslav; Lebeda, Ondřej

    2016-01-01

    Roč. 380, AUG (2016), s. 32-49 ISSN 0168-583X R&D Projects: GA MŠk(CZ) LM2011019 Institutional support: RVO:61389005 Keywords : cross-sections * excitation functions * proton-induced nuclear reactions * natural molybdenum * Mo-99 * Tc-99m * Tc96m+g * Tc-95m * thick target yields * U-120M cyclotron Subject RIV: BG - Nuclear, Atomic and Molecular Physics, Colliders Impact factor: 1.109, year: 2016

  2. A proposal for spreading and commercializing the (n, gamma) 99Tc generator

    International Nuclear Information System (INIS)

    Yoshida, Kosuke; Hishinuma, Yukio; Tatenuma, Katsuyoshi

    2006-01-01

    A practicability of 99m Tc generator based on (n, gamma) method using PZC (Poly Zirconium Compound), a Mo adsorbent with a high adsorption efficiency, has been studied by the FNCA member countries as a part of the FNCA activities; three research collaboration projects, Technetium Generator Project (TCG), Neutron Activation Analysis Project (NAA) and Neutron Spreading Project (NS) have been set up in order to achieve the significant results of the research reactor use among Asian countries. As a result of the collaboration research, practical data on the 99m Tc elution and 99 Mo breakthrough has recently been obtained by using the new 99m Tc generator based on (n, gamma) method using PZC (indicate 'PZC- 99m Tc generator' as follows). Even though unexpected amount of 99 Mo breakthrough accompanied with the 99m Tc elution treatment were currently occurred, the problem has been solved by subsequently adding an alumina column underneath the generator column containing PZC. In accordance with the realization of the practical PZC- 99m Tc generator, an administering tests to the mice with labeled compound of 99m Tc generated by PZC method have already been started by BATAN, a loading machine to simplify the process of the 99 Mo adsorption to PZC and the 99 Mo-PZC packing to a generator column has been fabricated in BATAN's hot cell to realize a mass production of PZC- 99m Tc generator, and moreover the Japanese and Indonesian patents pertaining to the production process and the loading machine of PZC- 99m Tc generator have been applied with joint application of BATAN and KAKEN Co. By the current collaboration approaches mentioned above, it is clear that the Technetium Generator Project of FNCA is now reaching to a phase where the aims of the project shall be turned from establishment of the practical PZC- 99m C generator to establishment of the delivery system of PZC- 99m Tc generator to put them into commercial use. In this paper, a practical application of the PZC- 99m

  3. Synthesis and magnetic properties of carbon-coated FeRu, CoRu, and NiRu nanoalloys

    Energy Technology Data Exchange (ETDEWEB)

    El-Gendy, A.A.; Khavrus, V.O.; Hampel, S.; Leonhardt, A.; Klingeler, R.; Buechner, B. [Leibniz Institute for Solid State and Materials Research (IFW) Dresden (Germany)

    2010-07-01

    Carbon coated FeRu, CoRu and NiRu nanoalloys have been synthesised by high pressure chemical vapour deposition (HPCVD). The formation of the core-shell nanoalloys with a mean diameter around 8 nm has been confirmed by means of high resolution transmission electron microscopy imaging (HRTEM), energy dispersive X-ray (EDX) analysis, and X-ray diffraction (XRD). We show the effect of the synthesis parameters on the actual composition of the nanoalloys and on their magnetic properties and we discuss their feasibility for applications in medical hyperthermia.

  4. Preparation of chromatographic and solid-solvent extraction 99mTc generators using gel-type targets

    International Nuclear Information System (INIS)

    Le Van So

    2000-01-01

    We have studied two types of targets zirconium-molybdate (ZrMo) and titanium-molybdate (TiMo) prepared by precipitating reaction between ammonium-molybdate and zirconium-chloride or titanium-chloride solutions, respectively. Other types of targets were also prepared by co-precipitating ZrMo or TiMo with hydrous manganese-dioxide, hydrous silica, and hydrous titanium-dioxide or by impregnated ZrMo or TiMo with Iodate anions. The results on extraction of Tc-99m from neutron irradiated TiMo solid phase using solvents such as MEK, aceton, ethylic ether, chloroform, etc showed that separation yield (SY) of Tc-99m in case of aceton extraction was from 70% to 80% and in other cases non higher than 40%. The Tc-99m elution curves and column kinetic in case of aceton extraction (after evaporation of aceton and recovery of Tc-99m in 0,9% NaCl solution) was superior than in case chromatographic generator using saline eluant. As result obtained, two types of generators were successfully prepared and put into use: Chromatographic generator using titanium-molybdate target as packing material and saline as eluant. Solid-solvent extraction 99m Tc generator using titanium-molybdate target (as solid phase) and aceton as extracting solvent. (author)

  5. Novel Electronic Structures of Ru-pnictides RuPn (Pn = P, As, Sb)

    Science.gov (United States)

    Goto, H.; Toriyama, T.; Konishi, T.; Ohta, Y.

    Density-functional-theory-based electronic structure calculations are made to consider the novel electronic states of Ru-pnictides RuP and RuAs where the intriguing phase transitions and superconductivity under doping of Rh have been reported. We find that there appear nearly degenerate flat bands just at the Fermi level in the high-temperature metallic phase of RuP and RuAs; the flat-band states come mainly from the 4dxy orbitals of Ru ions and the Rh doping shifts the Fermi level just above the flat bands. The splitting of the flat bands caused by their electronic instability may then be responsible for the observed phase transition to the nonmagnetic insulating phase at low temperatures. We also find that the band structure calculated for RuSb resembles that of the doped RuP and RuAs, which is consistent with experiment where superconductivity occurs in RuSb without Rh doping.

  6. Effect of Mo and C additions on magnetic properties of TiC–TiN–Ni cermets

    International Nuclear Information System (INIS)

    Zhang, Man; Yang, Qingqing; Xiong, Weihao; Zheng, Liyun; Huang, Bin; Chen, Shan; Yao, Zhenhua

    2015-01-01

    The effect of 2–8 mol.% Mo and 4 mol.% C additions on magnetic properties of TiC–10TiN–30Ni (mol.%) cermet was investigated. Saturation magnetization M_s, remanence M_r and Curie temperature T_c of as-sintered cermets (1420 °C, 1 h) decreased with increasing Mo. This was mainly attributed to that the total content of non-magnetic alloying elements Mo and Ti in Ni-based binder phase increased with increasing Mo in cermets, leading to the weakening of magnetic exchange interaction among Ni atoms in binder phase. The further addition of 4 mol.% C inversely increased M_s, M_r and T_c of cermets, which was mainly attributed to that it decreased the total content of Mo and Ti in binder phase, leading to the strengthening of magnetic exchange interaction among Ni atoms in binder phase. T_c of cermets without C addition was about 250 K at 6 mol.% Mo and 115 K at 8 mol.% Mo, respectively, and that of cermets with 4 mol.% C addition was about 194 K at 8 mol.% Mo. - Highlights: • M_s, M_r and T_c of TiC–10TiN–30Ni–xMo cermets decreased with the increase of Mo content, x. • Further addition of 4 mol.% C inversely increased M_s, M_r and T_c of cermets at the same Mo content. • T_c of cermets without C addition was about 250 K at x = 6 and 115 K at x = 8, respectively. • T_c of cermets with 4 mol.% C addition was about 194 K at x = 8.

  7. Device-dependent activity estimation and decay correction of radionuclide mixtures with application to Tc-94m PET studies

    International Nuclear Information System (INIS)

    Smith, Mark F.; Daube-Witherspoon, Margaret E.; Plascjak, Paul S.; Szajek, Lawrence P.; Carson, Richard E.; Everett, James R.; Green, Shielah L.; Territo, Paul R.; Balaban, Robert S.; Bacharach, Stephen L.; Eckelman, William C.

    2001-01-01

    Multi-instrument activity estimation and decay correction techniques were developed for radionuclide mixtures, motivated by the desire for accurate quantitation of Tc-94m positron emission tomography (PET) studies. Tc-94m and byproduct Tc isotopes were produced by proton irradiation of enriched Mo-94 and natural Mo targets. Mixture activities at the end of bombardment were determined with a calibrated high purity germanium detector. The activity fractions of the greatest mixture impurities relative to 100% for Tc-94m averaged 10.0% (Tc-94g) and 3.3% (Tc-93) for enriched targets and 10.1% (Tc-94g), 11.0% (Tc-95), 255.8% (Tc-96m), and 7.2% (Tc-99m) for natural targets. These radioisotopes have different half-lives (e.g., 52.5 min for Tc-94m, 293 min for Tc-94g), positron branching ratios (e.g., 0.72 for Tc-94m, 0.11 for Tc-94g) and gamma ray emissions for themselves and their short-lived, excited Mo daughters. This complicates estimation of injected activity with a dose calibrator, in vivo activity with PET and blood sample activity with a gamma counter. Decay correction using only the Tc-94m half-life overestimates activity and is inadequate. For this reason analytic formulas for activity estimation and decay correction of radionuclide mixtures were developed. Isotope-dependent sensitivity factors for a PET scanner, dose calibrator, and gamma counter were determined using theoretical sensitivity models and fits of experimental decay curves to sums of exponentials with fixed decay rates. For up to 8 h after the end of bombardment with activity from enriched and natural Mo targets, decay-corrected activities were within 3% of the mean for three PET studies of a uniform cylinder, within 3% of the mean for six dose calibrator decay studies, and within 6% of the mean for four gamma counter decay studies. Activity estimation and decay correction for Tc-94m mixtures enable routine use of Tc-94m in quantitative PET, as illustrated by application to a canine Tc-94m sestamibi

  8. Generators of 99Mo-99mTc

    International Nuclear Information System (INIS)

    Robles, A.M.

    1994-01-01

    Between the radioisotopes family pairs we find the 99 Molibdenum - 99m technetium pairs. Such as isotope production,decay and chemical toxic, humid and dry generators,radiation protection handling practice and blinding had been sudied in this work.Tabs

  9. A new method for 99mTc-labelling of proteins, leucocytes and platelets for nuclear medicine application

    International Nuclear Information System (INIS)

    Sundrehagen, E.

    1984-01-01

    A reduced state of 99mTc was obtained by concentrated hydrocloric acid treatment of the 99mTc(VII)/0.15 M NaCl eluate from 99Mo/99mTc generators. Non-acidic reduced state of 99mTc in dry NaCl deposit was obtained by vacuum evaporation of concentrated HCl and water. A monitored vacuum evaporator built for this purpose is presented, as well as methods of formation of various 99mTc-protein and 99mTc-polypeptide complexes. After careful protein precipation or anionic adsorption of pertechnetate and 99mTc-gentisic acid complexes, high radiochemical purities of labelled proteins were demonstrated by gel chromatography studies, radioimmunological methods, radioaffinity testing studies and ampholyte displacement radiochromatography. Preparative methods for 99mTc-plasmin (at pH=2), 99mTc-secretin (at pH=3) and 99mTc-IgG (at pH=4) are presented. The role and the limitations of 99mTc-plasmin for diagnosis of deep vein thrombosis were investigated in experimentally induced jugular vein thrombosis in rabbits. The in vivo distribution of intravenously injected 99mTc-secretin was found to be in correspondance with that of unlabelled secretin. Labelling of platelets and leucoytes from human blood with 99mTc was carried out at pH=7.2. Data for a remarkable high stability of the labelled cells are presented

  10. Thermodynamic assessment of the Al-Ru system

    CSIR Research Space (South Africa)

    Prins, SN

    2003-03-01

    Full Text Available describes the order disorder transformation with one Gibbs energy function. The RuAl6 phase was described as a stoichiometric phase and the remaining intermetallic phases (Ru4Al13, RuAl2 and Ru2Al3) were modelled with the sublattice model. The solubility...

  11. Performance testing of PZC generators for 99mTc production

    International Nuclear Information System (INIS)

    Bulos, Adelina DM.

    2006-01-01

    The report briefly describes the performance testing done on seven batches of polyzirconium column (PZC) material. PZC is a ready-to-use high molybdenum-capacity column material for adsorbing reactor-produced 99 Mo. The PZC material was manufactured by Kaken Co in Japan and was sent to PNRI for performance evaluation. Fission molybdenum was eluted from a commercial 99 Mo - 99m Tc generator. The eluted 99 Mo in a molybdenum carrier solution was adsorbed on PZC through a series of procedures. The mixture was decanted to a 90 x 12 mm glass column. 99m Tc was eluted with saline solution. The parameters measured were Tc 99m yield, %molybdenum adsorption and desorption, elution profile and radiochemical purity. (author)

  12. The crisis of 99Mo. Current trends and challenges

    International Nuclear Information System (INIS)

    Leyva, René; Duatti, Adriano

    2016-01-01

    In recent years they have exacerbated the problems with the availability of 99 Mo in the international market for the production of radio isotopic generators 99 Mo / 99 mTc. The main situation is given by the shutdown, maintenance or damage to the nuclear reactors of the reductor plants. The search for solutions, analysis of alternatives and development of new methods for the 99 Mo, the well-known workhorse of nuclear medicine, are addressed in this paper. Are interesting new routes using cyclotrons. Also shown are the steps taken internationally to alleviate the growing demand against a limited supply in production. (author)

  13. Nanoscale decomposition of Nb-Ru-O

    Science.gov (United States)

    Music, Denis; Geyer, Richard W.; Chen, Yen-Ting

    2016-11-01

    A correlative theoretical and experimental methodology has been employed to explore the decomposition of amorphous Nb-Ru-O at elevated temperatures. Density functional theory based molecular dynamics simulations reveal that amorphous Nb-Ru-O is structurally modified within 10 ps at 800 K giving rise to an increase in the planar metal - oxygen and metal - metal population and hence formation of large clusters, which signifies atomic segregation. The driving force for this atomic segregation process is 0.5 eV/atom. This is validated by diffraction experiments and transmission electron microscopy of sputter-synthesized Nb-Ru-O thin films. Room temperature samples are amorphous, while at 800 K nanoscale rutile RuO2 grains, self-organized in an amorphous Nb-O matrix, are observed, which is consistent with our theoretical predictions. This amorphous/crystalline interplay may be of importance for next generation of thermoelectric devices.

  14. Development of Mo recycle technique from generator materials

    Energy Technology Data Exchange (ETDEWEB)

    Tanimoto, Masataka; Kurosawa, Makoto; Kimura, Akihiro; Nishikata, Kaori; Tsuchiya, Kunihiko [Japan Atomic Energy Agency, Oarai Research and Development Center, Oarai, Ibaraki (Japan); Kakei, Sadanori; Yoshinaga, Hideo [Taiyo Koko Corp., Ako Laboratory, Ako, Hyogo (Japan)

    2012-03-15

    The domestic {sup 99}Mo production by the (n,{gamma}) method is proposed in JMTR because of low amount of radioactive wastes and easy {sup 99}Mo/{sup 99m}Tc production process. For the development of domestic production, it is necessary to use the enriched {sup 98}MoO{sub 3}, which is very expensive, for high specific activity of {sup 99}Mo. A large amount of used PZC/PTC embraced {sup 98}Mo is also generated after the decay of {sup 99}Mo. JAEA and Taiyo Koko is proposed to recover molybdenum from the used PZC/PTC for an effective use of resources and reduction of radioactive wastes. Preliminary experiments of Mo recycling with un-irradiated MoO{sub 3} were carried out by the elution and sublimation methods. From the results, Mo recovery rate from the PZC/PTC was more than 95% by two kinds of methods. The prospects are bright for Mo recycle and reduction of radioactive wastes using these methods. (author)

  15. A draft plan for the routine production of PZC based 99mTc generator in the Vietnam

    International Nuclear Information System (INIS)

    Duong Van Dong

    2007-01-01

    This is an outline of the radioisotope production programme using a research reactor of 500 kW in Vietnam. Under the framework of Forum for Nuclear Cooperation in Asia (FNCA) cooperation program, the PZC based technology for production of 99m Tc-generator has been studied at Dalat Nuclear Research Institute (DNRI) as well as FNCA members countries in the past several years. The FNCA project has shown the feasibility of using a PZC column-reactor 99 Mo- 99m Tc-generator for commercial applications, citing mainly the cheaper cost of the PZC generator than the imported alumina column-fission 99 Mo generator and excellent technology achievement has been established and optimized by close cooperation between FNCA country members and KAKEN, JAERI. DNRI proposes in this draft business plan, the commercial production of PZC generator through the establishment of national project stage 2006-2008 for the routine production of 99 Mo- 99m Tc generator. In this national project the 99m Tc-generator will use PZC coming from KAKEN - Japan or locally synthesis as the column material, 99 Mo sourced from neighboring countries or irradiated at or reactor and the semi-automatic loading and adsorption machine will be studied, designed and installed in the hot cells available. Because the DNRI have facility 99m Tc-generator production line with two hot cells used production of the 99m Tc generator by using fission 99 Mo. The generator assembly will be designed and fabricated. (author)

  16. Feasibility studies of producing 99 Mo by capture in the IEA-R1 research reactor

    International Nuclear Information System (INIS)

    Concilio, Roberta; Mendonca, Arlindo Gilson; Maiorino, Jose Rubens

    1998-01-01

    Everyday the production of 99 Mo for 99m Tc generators, becomes more necessary, whose properties are ideal for medical diagnosis. This works presents a description and an analysis of the production of 99 Mo by radioactive capture at 98 Mo using the research reactor IEA-R1 in 5 MW and operating 5 days a week, referring to the use of targets, separation methods, total and specific activity attained and its limitations. (author)

  17. EPR study of interactions in the MoOCl3 - diethyl dithiophosphate - diethylamine system

    International Nuclear Information System (INIS)

    Larin, G.M.; Minin, V.V.

    2004-01-01

    By the method of EPR in MoOCl 3 -DDFH-DEta system when reagents ration is 1:1:>3 formation of a new molybdenum(V) imidocomplex in situ solution is detected. Composition and structure of a new molybdenum(V) imidocomplex - composition is MoNRCl(DDF) 3 (DDFH), coordination number is 7, structure is pentagonal bipyramid - are determined using analysis of additional superfine structure from atoms of ligands forming coordination sphere of molybdenum(V) imidocomplex [ru

  18. Initial generation and separation of 99Mo at Sandia National Laboratories

    International Nuclear Information System (INIS)

    Talley, D.G.; Bourcier, S.C.; McDonald, M.J.; Longley, S.W.; Parma, E.J.

    1997-01-01

    Medical isotopes play an important role in the medical industry in both the United States and the world. Isotopes such as 99 Tc, 201 Tl, 111 In, and 123 I are utilized in diagnostic imaging studies, while others such as 131 I and 89 Sr are used as therapeutic agents. The particular medical isotope 99m Tc is used in 80% of all nuclear medical procedures in the United States. This isotope is produced from the decay of 99 Mo, which has a 66 hour half-life. The importance of 99m Tc and the fact of its 6 hour half-life indicate the necessity to maintain a constant supply of 99 Mo. The most prominent method for the production of significant quantities of 99 Mo is by fission in highly-enriched uranium loaded targets. This paper describes the work performed at SNL for the production of 99 Mo

  19. Manufacturing and characterization of molybdenum pellets used as targets for 99mTc production in cyclotron

    International Nuclear Information System (INIS)

    Cieszykowska, Izabela; Janiak, Tomasz; Barcikowski, Tadeusz; Mielcarski, Mieczysław; Mikołajczak, Renata; Choiński, Jarosław; Barlak, Marek; Kurpaska, Łukasz

    2017-01-01

    The method of 100 Mo metallic target preparation for production of 99m Tc by proton irradiation in 100 Mo(p,2 n) 99m Tc reaction was demonstrated. For this purpose, pressing of molybdenum powder into pellets and their subsequent sintering in reductive atmosphere were applied. The influence of parameters such as molybdenum mass and time of both pressing and sintering on the 100 Mo target durability was investigated. Under the optimized conditions, 100 Mo metallic pellet targets with density of 9.95±0.06 g/cm 3 were obtained. Morphology and structure of pressed pellets before and after sintering were studied by using standard optical microscope and Scanning Electron Microscope (SEM). Nanoindentation technique was used to investigate the mechanical properties such as nanohardness and Young modulus. Prepared 100 Mo pellets were successfully irradiated with protons and 99m Tc was efficiently isolated. - Highlights: • Pressing and sintering of 100 Mo powder into pellets. • Optimization of 100 Mo target manufacture process. • Determination of nanohardness of prepared 100 Mo targets. • Irradiation of self-supporting 100 Mo target in cyclotron.

  20. Toroidal deuteron accelerator for Mo-98 neutron activation

    Energy Technology Data Exchange (ETDEWEB)

    Araujo, Wagner L., E-mail: wagner.leite@ifnmg.edu.br, E-mail: tprcampos@pq.cnpq.br [Instituto Federal do Norte de Minas Gerais (IFN-MG), Montes Claros, MG (Brazil); Campos, Tarcisio P.R. Universidade Federal de Minas Gerais (UFMG), Belo Horizonte, MG (Brazil). Departamento de Engenharia Nuclear

    2017-07-01

    The radionuclide Tc-{sup 99m} is the most useful radioisotope in nuclear medicine. It can be produced by the Mo-99 beta minus decay. Mo-99 has often been produced in a high- flux nuclear reactor through radioactive neutron capture reactions on Mo-98. The present paper provides a preliminary design of a toroidal transmutation system (TTS) based on a toroidal compact deuteron accelerator, which can provide the Mo-98 transmutation into Mo-99. This system is essentially composed of a multi-aperture plasma electrode and a target, submitted to 180 kV, where a positive deuteron beam is accelerated toward a titanium-target loaded with deuterium in which nuclear d-d fusion reactions are induced. The Particle Studio package of the Computer Simulation Technology (CST) software was applied to design, simulate and optimize the deuteron beam on the target. MCNP code provided to neutronic analysis. Based on electromagnetic and neutronic simulations, the neutron yield and reaction rates were estimated. The simulated data allowed appraising the Mo-99 activity. A TTS, in a specific configuration, could produce a total deuterium current of 1.6 A at the target and a neutron yield of 10{sup 13} n.s{sup -1}. In a arrangement of 30 column samples, TTS provides 230 mCi s{sup -1} Mo{sup 99} in each column, which represents 80% of Tc-99m in secular equilibrium. As conclusion, the system holds potential for generating Mo-99 and Tc-99m in a suitable activity in secular equilibrium. (author)

  1. {sup 99}Mo sorption by thermally treated hydrotalcites

    Energy Technology Data Exchange (ETDEWEB)

    Serrano, J.; Bertin, V.; Bulbulian, S.

    2000-04-04

    MoO{sub 4}{sup {minus}2} ions were sorbed in calcined hydrotalcite contained in a column. It was found that 98% of {sup 99m}Tc formed by {sup 99}Mo decay was eluted through the column in the form of pertechnetate. The content of radionuclides was determined by {gamma}-spectrometry, and natural molybdenum was measured by neutron activation analysis. Solids were characterized by thermal analysis, X-ray diffraction, and infrared spectroscopy. Through batch experiments, the hydrotalcite capacity toward molybdate ions (1.12 x 10{sup {minus}3} M) was found to be 3.2 mequiv g{sup {minus}1}. It was found that the high molybdate adsorbing capacity of calcined hydrotalcite could be utilized in designing a {sup 99m}Tc generator made with low specific activity {sup 99}Mo-molybdate samples.

  2. Procedure for the production of PZC based chromatographic Tc-99m generator to be available for clinical application

    International Nuclear Information System (INIS)

    Le Van So; Pham Ngoc Dien; Truong Hong Nghia; Nguyen Thi Thu; Nguyen Cong Duc; Vo Thi Cam Hoa; Bui Van Cuong

    2004-01-01

    The chemical synthesis for the preparation of polymer compound of Zirconium (PZC) and the column pre-loading procedure for the preparation of PZC based chromatographic Tc-99m generators were described in detail. In-process documentation, flow-chart of process, specific Tc-99m generator designs and picturially illustrative description of Tc-99 generator production process were systematically reported. The column pre-loading procedure was highly evaluated as a competent technology for the preparation of PZC based Tc-99m chromatographic generator of high performance using (n,γ) 99 Mo of low specific radioactivity produced on low power research reactors. (author)

  3. Questionnaire survey of SPECT studies after the supply shortage of Tc-99m and model analysis concerning earnings and expenditure of generator use

    International Nuclear Information System (INIS)

    Kinoshita, Ryo; Kosuda, Shigeru; Koike, Katsumi; Arai, Takashi

    2012-01-01

    A questionnaire survey was conducted to evaluate decrease in SPECT studies and its causes after the cessation of long supply shortage of 99 Mo/ 99 mTc generators. Of the replies by the chief nuclear medicine technologists, no necessity for 99 Mo/ 99 mTc generator use or for domestic supply of 99 mTc unexpectedly accounted for 25% and 46%, respectively. Generator use leads to an additional profit by 8654 yen per patient, compared to purchase of commercially available 99 mTc-labeled kits. It is essential to install a 99 Mo/ 99 mTc generator to perform emergency SPECT studies, increase a profit in hospital management, reduction of financial issues in patients, and pediatric studies. This adverse circumstance, however, may provide a good opportunity to instruct nuclear medicine specialists to be aware of the importance mentioned above in medical meetings. (author)

  4. Sorption of {sup 99}MoO{sub 4}{sup 2-} ions on commercial hydrotalcites

    Energy Technology Data Exchange (ETDEWEB)

    Serrano, J.; Gonzalez, H.; Lopez, H.; Aranda, N.; Granados, F.; Bulbulian, S. [Delegacion Miguel Hidalgo, Mexico (Mexico). Instituto Nacional de Investigaciones Nucleares

    2005-07-01

    {sup 99}MoO{sub 4}{sup 2-} sorption behavior on 3 commercial hydrotalcites, produced by Sasol Chemie, was studied through batch experiments. Only one of them showed high sorption capacity. This product, the MG70 was identified by XRD diffraction analysis as hydrotalcite (Mg{sub 6}Al{sub 2}(OH){sub 16}CO{sub 3} x 4H{sub 2}O), while the other two, MG50 and MG30, were identified mainly as magnesium aluminum hydroxide hydrate, MgAl{sub 2}(OH){sub 14} x 3H{sub 2}O. Calcined MG70 (CMG70) was used to retain about 298.17{+-}8.3 mg of {sup 99}Mo-MoO{sub 4}{sup 2-} (MG70-{sup 99}MoO{sub 4}). When this material was packed in a glass column, the generated {sup 99m}Tc was eluted by using NaCl or HNO{sub 3} aqueous solutions. Saline solutions eluted {sup 99m}Tc with considerable amounts of {sup 99}Mo while 0.1 M HNO{sub 3} eluted {sup 99m}Tc together with a such small amount of {sup 99}Mo that the {sup 99}Mo {mu}Ci/{sup 99m}Tc mCi ratios are close to the value recommended by the American Pharmacopeia. (orig.)

  5. Vertical Line Nodes in the Superconducting Gap Structure of Sr_{2}RuO_{4}

    Directory of Open Access Journals (Sweden)

    E. Hassinger

    2017-03-01

    Full Text Available There is strong experimental evidence that the superconductor Sr_{2}RuO_{4} has a chiral p-wave order parameter. This symmetry does not require that the associated gap has nodes, yet specific heat, ultrasound, and thermal conductivity measurements indicate the presence of nodes in the superconducting gap structure of Sr_{2}RuO_{4}. Theoretical scenarios have been proposed to account for the existence of deep minima or accidental nodes (minima tuned to zero or below by material parameters within a p-wave state. Other scenarios propose chiral d-wave and f-wave states, with horizontal and vertical line nodes, respectively. To elucidate the nodal structure of the gap, it is essential to know whether the lines of nodes (or minima are vertical (parallel to the tetragonal c axis or horizontal (perpendicular to the c axis. Here, we report thermal conductivity measurements on single crystals of Sr_{2}RuO_{4} down to 50 mK for currents parallel and perpendicular to the c axis. We find that there is substantial quasiparticle transport in the T=0 limit for both current directions. A magnetic field H immediately excites quasiparticles with velocities both in the basal plane and in the c direction. Our data down to T_{c}/30 and down to H_{c2}/100 show no evidence that the nodes are in fact deep minima. Relative to the normal state, the thermal conductivity of the superconducting state is found to be very similar for the two current directions, from H=0 to H=H_{c2}. These findings show that the gap structure of Sr_{2}RuO_{4} consists of vertical line nodes. This rules out a chiral d-wave state. Given that the c-axis dispersion (warping of the Fermi surface in Sr_{2}RuO_{4} varies strongly from sheet to sheet, the small a-c anisotropy suggests that the line nodes are present on all three sheets of the Fermi surface. If imposed by symmetry, vertical line nodes would be inconsistent with a p-wave order parameter for Sr_{2}RuO_{4}. To reconcile the gap structure

  6. Technetium-99 in ''instant'' sup(99m)Tc-pertechnetate

    International Nuclear Information System (INIS)

    Mattsson, S.

    1978-01-01

    The 99 Tc-content in sup(99m)Tc-pertechnetate separated from 99 Mo by distillation or extraction has been studied with a plastic scintillation detector. The identification of the measured activity was achieved by beta-spectrometry, chemical separation and half-life studies. The frequency distribution of the sup(99)Tc/sup(99m)Tc-ratios in the different samples was observed to be log-normal. The most likely activity ratio was 0.4x10 -6 , the maximum value being 5x10 -6 . The specific activity of ''instant'' pertechnetate is approximately a factor of 60 lower than that normally recorded in pertechnetate derived from daily eluted column generators. The low specific activity of ''instant'' pertechnetate is primarily explained by the long time between separation and usage and secondly by the low yield of Tc in the distillation and extraction processes. In several of the ''instant'' pertechnetate solutions the carrier concentration exceeded the reductive capacity of the stannous ions in ''kits'' with small amounts of Sn(II) in usable form. (T.G.)

  7. Carbon supported nanoparticles Pt Ru (Pt Ru/C electrocatalysts) prepared using electron beam irradiation; Preparacao de nanoparticulas de PtRu suportadas em carbono (eletrocatalisadores PtRu/C) utilizando feixe de eletrons

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Dionisio F. da; Oliveira Neto, Almir; Pino, Eddy S.; Linardi, Marcelo; Spinace, Estevam V. [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil). Programa de Celulas a Combustivel], e-mail: espinace@ipen.br, e-mail: dfsilva@ipen.br

    2006-07-01

    Carbon-supported Pt Ru (electrocatalysts PtRu/C nanoparticles) were prepared submitting a water/ethylene glycol mixture containing Pt(IV) and Ru(III) ions and the carbon support to electron beam irradiation. The PtRu/C electrocatalysts were characterized by EDX, XRD and cyclic voltammetry and tested for methanol electro-oxidation aiming fuel cell application. The obtained PtRu/C electrocatalysts were more active for methanol electro-oxidation than the commercial PtRu/C ETEK electrocatalyst at ambient temperature. (author)

  8. The PZC-based Tc-99m generator preparation and its performance test

    International Nuclear Information System (INIS)

    Liu Yishu

    2007-01-01

    This paper described the preparation of Tc-99m generator prepared with Japan distributing Mo adsorbent PZC and irradiated nature MoO 3 and its performance test. Four Tc-99m generators were prepared with different batches of PZC and reactor irradiated nature MoO 3 . The adsorption capacity of PZC to Mo is approximately 200mgMo/gPZC. The adsorption efficiency of three batches PZC is good (>90%) and that of one batch of PZC is not good enough (∼83%). The loss of fine powder (The PZC is fragile) is quite different with the different preparation process of PZC. The elution efficiency is 80-90% and has the up trend with the elution date. The Mo breakthrough can be controlled to acceptable level by connecting HZO safe column containing 1.0g HZO. All the specifications of eluted from PZC-based Tc-99m generator can meet the requirements under Sodium Pertechnetate injection in China Pharmacopoeia. (author)

  9. Magnetic properties of Heusler alloy Mn2RuGe and Mn2RuGa ribbons

    International Nuclear Information System (INIS)

    Yang, Ling; Liu, Bohua; Meng, Fanbin; Liu, Heyan; Luo, Hongzhi; Liu, Enke; Wang, Wenhong; Wu, Guangheng

    2015-01-01

    Heusler alloys Mn 2 RuGe and Mn 2 RuGa have been prepared by melt-spinning method successfully. Theoretical and experimental studies reveal a ferrimagnetic ground state in the two alloys. The Curie temperatures are 303 K for Mn 2 RuGe and 272 K for Mn 2 RuGa. The calculated total spin moments of Mn 2 RuGe and Mn 2 RuGa are integral values of 2.00 μ B and 1.03 μ B , respectively. And the theoretical spin polarization ratio is also quite high. However, due to the atomic disorder in the ribbons, the saturation moments of them measured at 5 K are smaller than the calculated values, especially that of Mn 2 RuGa. This coincides with the disappearance of the superlattice reflection (111) and (200) peaks in the XRD pattern of Mn 2 RuGa. Annealing Mn 2 RuGa ribbon at 773 K can enhance the atomic ordering. Both saturation magnetic moment and Curie temperature increase obviously after the heat treatment. - Highlights: • Mn 2 RuGe and Mn 2 RuGa have been prepared by melt-spinning successfully. • Ferrimagnetic ground state has been confirmed in Mn 2 RuGe and Mn 2 RuGa. • High spin polarization has been predicted in Mn 2 RuGe. • Melt-spinning can be a possible way to adjust the atomic order of Heusler alloys

  10. Synopsis of French experimental and in situ research on the terrestrial and marine behavior of Tc

    International Nuclear Information System (INIS)

    Masson, M.; Patti, F.; Colle, C.; Roucoux, P.; Grauby, A.; Saas, A.

    1989-01-01

    Terrestrial environment studies have been essentially concerned with the evolution of soil deposition and soil-plant transfers. Experimentally determined coefficients of distribution in soils are low: 60-80% of Tc remains hydrosoluble during the first months. Technetium emissions resulting from microbiological activity have been quantified. Antagonistic effects on Mo and Tc retention by soils are dependent on their respective concentrations. Four areas of soil-plant transfers have been studied: (1) root absorption kinetics relative to deposition of Tc, (2) interaction of stable Mo (environmental parameter) with the transfer of Tc to plants, (3) interaction of some long-lived radioisotopes (effluent parameters) with the transfer of Tc to plants, and (4) long-term soil-plant transfer and aging of deposited material. Of aquatic systems, only the marine environment has been studied. Under anoxic conditions in the presence of reducing sediments, the distribution coefficients (Kd) were very high (10(3)). Concentration factors (CF) from water to organisms were generally very low (1 to 10); however, CF greater than 1000 have been observed for some biota such as macrophytic brown algae, worms and lobsters. Biochemical analysis showed that Tc was essentially free and partially bonded to proteins. The transfer factors between sediments and species were very low (TF less than 0.5). The biological half-time was determined in some marine organisms that had accumulated Tc from water, food or sediments; the loss is biphasic. Uptake in edible parts was low. The physiochemical form affects the accumulation and loss of Tc. Analyses have quantified 99Tc in marine fauna and biota in the English Channel in relation with releases of the reprocessing plant of La Hague. Brown algae are the best bioindicators for following 99Tc dispersion in marine ecosystems. 24 references

  11. Metabolism and dosimetry of 106Ru inhaled as 106RuO4 by beagle dogs

    International Nuclear Information System (INIS)

    Snipes, M.B.

    1981-01-01

    This report provides metabolism and dosimetry data for inhaled ruthenium developed from studies in Beagle dogs that were exposed by inhalation to 106 RuO 4 . Twenty-six dogs were exposed nose-only to 106 RuO 4 and sacrificed at times from 2 hr to 512 days after inhalation exposure. Ninety-nine percent of the initial body burden was retained with an effective half-time of 1.2 days, 0.7% with a half-time of 14 days and 0.3% with a half-time of 170 days. Initial deposition was primarily in the nasopharyngeal and tracheobronchial regions. Results for deposition and retention of 106 Ru inhaled as 106 RuO 4 in dogs were similar to what has been observed for humans. The data for dogs were used to develop a model to predict potential radiation exposure patterns for humans after inhalation exposure to 106 RuO 4 . The model indicates that for humans the nasopharyngeal region, lower large intestine, and tracheobronchial epithelium would receive approx. 36, 13 and 10 times, respectively, the dose to 500 days after inhalation exposure to 106 RuO 4 that the lung would receive. The nasopharyngeal region should be considered the critical region for inhalation exposures to 106 RuO 4 . (author)

  12. Excitation functions of the 98Mo+d reactions

    International Nuclear Information System (INIS)

    Zarubin, P.P.; Padalko, V.Yu.; Khrisanfov, Yu.V.; Lebedev, P.P.; Podkopaev, Yu.N.

    The excitation functions of the 98 Mo+d reactions were studied. The energy dependence of (d,p),(d,n) and (d,α) reactions was investigated by the activation analysis. The energies of deuterons in the range (6-12) MeV were determined by means of the aluminium filters. 98 Mo foils with surface densities of 1.02, 0.23 and 0.14 mgxcm -2 with 98 Mo enrichment of 94.1% were used as targets. The gamma spectra were measured by a Ge(Li) detector. The 98 Mo(d,p) 99 Mo reaction excitation function was determined via detection of 739 and 181 keV γ-radiation of 99 Mo (Tsub(1/2)=66.47h); 140 keV γ-radiation of 99 Tc (Tsub(1/2)=6h) was detected for the 98 Mo(d,n) 99 Tc reaction excitation function determination and 460, 568, 1091, 1200 and 1492 keV γ-quanta of 96 Nb (Tsub(1/2)=23.35h) - for the 98 Mo(d,α) 96 Nb reaction. In the excitation function the wide extremum was observed at Esub(d) approximately 10 MeV. The ratio of cross sections σsup(m)(d,n)/σ(d,p) on the 98 Mo target was determined. The ratio σsup(m)(d,n)/σ(d,p) was found to be decreasing function of the deuteron energy. The relative cross sections were determined with an accuracy of +-5%, while for the absolute values of cross sections the accuracy was +-15%

  13. Influence of the electronic structures on the heterogeneous photoelectrocatalytic performance of Ti/Ru{sub x}Sn{sub 1-x}O{sub 2} electrodes

    Energy Technology Data Exchange (ETDEWEB)

    Chen, Zhijie, E-mail: 1061739408@qq.com [College of Materials Science and Engineering, Fuzhou University, Fuzhou, Fujian 350108 (China); Zhu, Junqiu, E-mail: zhujunqiu@xmut.edu.com [School of Chemical Engineering and Materials Science, Quanzhou Normal University, Quanzhou, Fujian 362000 (China); Zhang, Shuai, E-mail: 601314274@qq.com [College of Materials Science and Engineering, Fuzhou University, Fuzhou, Fujian 350108 (China); Shao, Yanqun, E-mail: yqshao1989@163.com [College of Materials Science and Engineering, Fuzhou University, Fuzhou, Fujian 350108 (China); Lin, Deyuan, E-mail: lindeyuan_fj@126.com [Electric Power Research Institute of State Grid Fujian Electric Power Co. Ltd., Fuzhou 350007 (China); Zhou, Jianfeng, E-mail: 1277018923@qq.com [College of Materials Science and Engineering, Fuzhou University, Fuzhou, Fujian 350108 (China); Chen, Yunxiang, E-mail: rogerchen@163.com [Electric Power Research Institute of State Grid Fujian Electric Power Co. Ltd., Fuzhou 350007 (China); Tang, Dian, E-mail: diantang@fzu.edu.cn [College of Materials Science and Engineering, Fuzhou University, Fuzhou, Fujian 350108 (China)

    2017-07-05

    Highlights: • Ti/Ru{sub x}Sn{sub 1-x}O{sub 2} electrodes possessed photocatalytic and electrocatalytic activity were prepared by thermal decomposition method. • The effect of electronic structure on electronic conductivity, electrocatalytic and photocatalytic activity were studied. • The photoelectric-synergistic catalytic activity of the Ti/Ru{sub x}Sn{sub 1-x}O{sub 2} electrodes was studied upon UV irradiation. • The Ti/Ru{sub 0.05}Sn{sub 0.95}O{sub 2} electrode has good catalytic activity and excellent stability. - Abstract: DSA-type Ti/Ru{sub x}Sn{sub 1-x}O{sub 2} electrodes were prepared by thermal decomposition method as photoelectrocatalysts (PECs) and extensively characterized by various sophisticated techniques. First-principles calculations was employed to study the effects of Ru content on the electronic structures of the Ru{sub x}Sn{sub 1-x}O{sub 2} coatings. The photoelectric-synergistic catalytic activity of the Ti/Ru{sub x}Sn{sub 1-x}O{sub 2} electrodes was evaluated for the degradation of methyl orange (MO) in aqueous solution. The results show that the RuO{sub 2}−SnO{sub 2} solid solution could be formed. The band gaps of the Ru{sub x}Sn{sub 1-x}O{sub 2} coatings gradually decreased and eventually turned into metallic conductivity with the increase of ruthenium content. As a PEC electrode, reducing band gap is helpful to improve electronic conductivity and the electrocatalytic activity, but not always advantageous to increase the photocatalytic activity. Because too narrow band gap will sacrifice the photogenerated charge carriers and thus reduce photocatalytic activity of the electrode. In our experiments, the rate constant of Ti/Ru{sub 0.05}Sn{sub 0.95}O{sub 2} electrode increased with increasing Ru content and exhibited the maximum rate for 5% Ru loading. The stability test showed the photoelectrocatalytic activity of the Ti/Ru{sub 0.05}Sn{sub 0.95}O{sub 2} electrode almost had no attenuation after 100 h photoelectrolysis, revealing

  14. Management of radioactive waste from 99Mo production

    International Nuclear Information System (INIS)

    1998-11-01

    99m Tc used for labelling different pharmaceuticals is the most important radionuclide in nuclear medicine practice, and probably will continue to play this important role for the foreseeable future. 99m Tc is the short lived daughter product of the parent 99 Mo, which is mainly produced by the nuclear fission of 235 U. Recognizing the importance of the waste management issue associated with 99 Mo production the IAEA initiated preparation of this report to provide Member States and existing and potential producers of 99 Mo with practical approaches and the available information on the subject. Waste management in the context of this report encompasses all waste-related aspects, for example, handling, treatment, conditioning, storage, transport, and disposal. The document is organized in several chapters giving the following information: short description of the basic nuclear and physical properties of 99 Mo and 99m Tc; an overview of past, present and possible future production methods; characteristics of the various waste streams produced in the aforementioned processes; description of the necessary waste management practices needed to handle the relevant waste streams in a responsible and internationally-accepted manner; conclusion and recommendations

  15. Performance of PZC-Mo generator and labeling results prepared with its eluate and MDP kit

    International Nuclear Information System (INIS)

    Yishu Liu

    2006-01-01

    This paper described the performance of Tc-99m generator prepared with Mo adsorbent PZC and irradiated nature MoO 3 , and the labeling results of MDP kit prepared with Tc-99m eluted from PZC-Mo generator and MDP was report as well. ThreeTc-99m generators was prepared with different batches of PZC and reactor irradiated nature Mo. The adsorption efficiency of two batches of the PZC is good (96.4% and 93.4%) and that of one batch of PZC is not satisfy (77.8%). The elution efficiency is not so high, and it increases along with the elution date. The elution file is very broad till to 30 ml and the Mo breakthrough is high to unacceptable. The labelling efficiency of MDP kit, prepared with Tc-99m eluate eluted with saline containing 0.05% NaClO from Mo-PZC generator, is approximately 77∼84% and it can reach to >98% labelling with eluate without containing 0.05%HClO in eluate. (author)

  16. Feasibility study on mass production of (n,γ)99Mo

    International Nuclear Information System (INIS)

    Jun, Byung Jin; Tanimoto, Masataka; Kimura, Akihiro; Hori, Naohiko; Izumo, Hironobu; Tsuchiya, Kunihiko

    2011-01-01

    The world is currently suffering from a severe shortage of 99 Mo and various efforts have been given for its availability. The (n,γ) method is one of candidates for the alternative supply of 99 Mo. The only but critical shortage of (n,γ) 99 Mo is its extremely low specific activity, which gives inconveniency in the extraction of 99m Tc and is consequently converted to additional cost. Potential technologies which make the (n,γ) 99 Mo competitive by reducing the additional cost are already available. It is expected that verification of such technologies is much easy and cost effective compared to any other options known for the alternative 99 Mo production. Because Japan and Korea import all 99 Mo from long distance, the cost benefit of local (n,γ) 99 Mo production in these countries is especially large. If five high flux reactors in China, Japan and Korea are utilized for the cross backup supply of (n,γ) 99 Mo, stable availability of 99 Mo in the region can be secured. Therefore, it is necessary to evaluate its feasibility on (n,γ) 99 Mo production in the Asia region. In this report, we studied feasibility of the mass (n,γ) 99 Mo production from viewpoints of global and regional status of 99 Mo demand and supply, competitiveness with other production methods, requirements and flow of the 99 Mo, production capability, cost, convenience in usage, and alternative technologies to overcome its shortage. (author)

  17. Analysis of 99Tc in the radioactive liquid waste after extraction into suitable solvent

    International Nuclear Information System (INIS)

    Sonar, N.L.; Vaishali De; Pardeshi, V.; Raghvendra, Y.; Valsala, T.P.; Sonavane, M.S.; Kulkarni, Y.; Raj Kanwar

    2012-01-01

    99 Tc is one of the long lived fission product with high fission yield. >From radioactive waste management point of view it is very much essential to evaluate the concentration of technetium in the radioactive liquid waste in order to finalise the treatment process to extract/isolate it from the stream which is discharged to the environment. For the estimation of 99 Tc in the radioactive liquid waste stream, extraction of the stable complex of technetium-tetraphenyl arsonium chloride (TPAC) into chloroform followed by beta counting was studied. Various parameters like pH, time of equilibration, concentration of TPAC in chloroform, use of other solvent for extraction as well as interference of various other radionuclides present in the waste were also studied. The radioactive liquid waste being handled in plant contains high concentrations of salts in the form of sodium nitrate. Hence effect of salt concentration on the percentage extraction was also evaluated. The extraction behavior does not dependent on change in the pH of the solution. Almost 99.5% extraction was observed in the pH range of 1-13.0. High concentration of salt is affecting the extraction. However, this can be taken care by diluting the radioactive waste. It takes almost 90 min time for maximum extraction. Presence of radionuclides like 137 Cs, 90 Sr are not interfering the extraction of 99 Tc. However, 106 Ru is getting slightly extracted along with 99 Tc. The error due to 106 Ru can be eliminated by taking gamma spectrum and deducting the activity from the total beta activity to get 99 Tc activity. Nitrobenzene can be used for extraction of Tc-TPAC complex in place of chloroform. (author)

  18. Chalcogenide oxygen reduction reaction catalysis: X-ray photoelectron spectroscopy with Ru, Ru/Se and Ru/S samples emersed from aqueous media

    Energy Technology Data Exchange (ETDEWEB)

    Lewera, A. [Department of Chemistry, University of Illinois at Urbana-Champaign, Urbana, IL 61801 (United States); Department of Chemistry, Warsaw University, Pasteura 1, 02-093 Warsaw (Poland); Inukai, J. [Clean Energy Research Center, University of Yamanashi, 7-32 Miyamae-cho, Kofu 400-0006 (Japan); Zhou, W.P. [Department of Chemistry, University of Illinois at Urbana-Champaign, Urbana, IL 61801 (United States); Cao, D. [Department of Chemistry, University of Illinois at Urbana-Champaign, Urbana, IL 61801 (United States); College of Material Science and Chemical Engineering, Harbin Engineering University, Harbin 150001 (China); Duong, H.T. [Department of Chemistry, University of Illinois at Urbana-Champaign, Urbana, IL 61801 (United States); Alonso-Vante, N. [Laboratory of Electrocatalysis, UMR-CNRS 6503, University of Poitiers, F-86022 Poitiers (France)]. E-mail: Nicolas.Alonso.Vante@univ-poitiers.fr; Wieckowski, A. [Department of Chemistry, University of Illinois at Urbana-Champaign, Urbana, IL 61801 (United States)]. E-mail: andrzej@scs.uiuc.edu

    2007-05-10

    Oxygen reduction Ru/Se and Ru/S fuel cell surface chalcogenide catalysts were prepared via chemical reaction of reduced Ru nanoparticles with selenium and sulfur in xylenes [D. Cao, A. Wieckowski, J. Inukai, N. Alonso-Vante, J. Electrochem. Soc. 153 (2006) A869]. The chalcogenide samples - as well as the starting chalcogens-free Ru nanoparticle material - were immobilized on a gold disk for X-ray Photoelectron Spectroscopy (XPS) characterization. While we found oxygen in most of the samples, predominantly from Ru oxides, we conclude that the oxygen on Ru/S may be located in subsurface sites: the subsurface oxygen. We also found that the transformation of the oxidized Ru black to metallic Ru required intensive electrochemical treatment, including hydrogen evolution. In contrast, five cyclic voltammetric scans in the potential range from 0.00 and 0.75 V versus RHE were sufficient to remove the oxygen forms from Ru/Se and, to a large extent, from Ru/S. We therefore conclude that Ru metal is protected against oxidation to Ru oxides by the chalcogens additives. The voltammetric treatment in the 0.00 and 0.75 V range also removed the SeO{sub 2} or SO {sub x} forms leaving anionic/elemental Se or S on the surface. Upon larger amplitude voltammetric cycling, from 0.00 to 1.20 V versus RHE, both Se and S were dissolved and the dissolution process was coincidental with the oxygen growth in/on the Ru samples.

  19. Chalcogenide oxygen reduction reaction catalysis: X-ray photoelectron spectroscopy with Ru, Ru/Se and Ru/S samples emersed from aqueous media

    International Nuclear Information System (INIS)

    Lewera, A.; Inukai, J.; Zhou, W.P.; Cao, D.; Duong, H.T.; Alonso-Vante, N.; Wieckowski, A.

    2007-01-01

    Oxygen reduction Ru/Se and Ru/S fuel cell surface chalcogenide catalysts were prepared via chemical reaction of reduced Ru nanoparticles with selenium and sulfur in xylenes [D. Cao, A. Wieckowski, J. Inukai, N. Alonso-Vante, J. Electrochem. Soc. 153 (2006) A869]. The chalcogenide samples - as well as the starting chalcogens-free Ru nanoparticle material - were immobilized on a gold disk for X-ray Photoelectron Spectroscopy (XPS) characterization. While we found oxygen in most of the samples, predominantly from Ru oxides, we conclude that the oxygen on Ru/S may be located in subsurface sites: the subsurface oxygen. We also found that the transformation of the oxidized Ru black to metallic Ru required intensive electrochemical treatment, including hydrogen evolution. In contrast, five cyclic voltammetric scans in the potential range from 0.00 and 0.75 V versus RHE were sufficient to remove the oxygen forms from Ru/Se and, to a large extent, from Ru/S. We therefore conclude that Ru metal is protected against oxidation to Ru oxides by the chalcogens additives. The voltammetric treatment in the 0.00 and 0.75 V range also removed the SeO 2 or SO x forms leaving anionic/elemental Se or S on the surface. Upon larger amplitude voltammetric cycling, from 0.00 to 1.20 V versus RHE, both Se and S were dissolved and the dissolution process was coincidental with the oxygen growth in/on the Ru samples

  20. Analysis of 99Tc and Its Activity Level in the Korean Soil

    International Nuclear Information System (INIS)

    Lee, Chang Woo; Chung, Kun Ho; Cho, Young Hyun; Kang, Mun Ja; Lee, Wanno; Kim, Hee Reyoung; Choi, Geun Sik

    2009-01-01

    An analytical method of 99 Tc concentration in soil was set up and discussed considering the 99 Tc concentration in Korean soil measured with its analytical method. A selective TEVA resin was used to separate and purify 99 Tc the in the soil sample. 99 Tc from a commercial 99 Mo/ 99m Tc generator was used as a yield tracer for the chemical separation of 99 Tc and its problem when using as a tracer was discussed. The chemical recovery yield of was above 70%. The optimum conditions of inductively coupled plasma mass spectrometry system (ICP-MS) were set up to determine the 99 Tc after the separation process. The minimum detectable activity (MDA) was 15 mBq/kg-dry in this analytical procedure. The 99 Tc concentration in soils of Jeju and Kori were measured in the rage of 33.73-89.16 mBq/kg-dry. Those values were less than those reported in other countries and seemed to be originated from atmospheric fallout.

  1. Systems Tl2MoO4-E(MoO4)2, where E=Zr or Hf, and the crystal structure of Tl8Hf(MoO4)6

    International Nuclear Information System (INIS)

    Bazarov, B.G.; Bazarova, Ts.T.; Fedorov, K.N.; Bazarova, Zh.G.; Chimitova, O.D.; Klevtsova, R.F.; Glinskaya, L.A.

    2006-01-01

    Systems Tl 2 MoO 4 -E(MoO 4 ) 2 (E=Zr, Hf) were studied by X-ray diffraction, differential thermal analysis and IR spectroscopy. Formation of Tl 8 E(MoO 4 ) 6 and Tl 2 E(MoO 4 ) 2 compounds was established. Phase T-x diagrams of the Tl 2 MoO 4 -Zr(MoO 4 ) 2 system were constructed. Monocrystals were grown, and structure of Tl 8 Hf(MoO 4 ) 6 was studied. The compound is crystallized in monoclinic syngony with elementary cell parameters a=9.9688(6), b=18.830(1), c=7.8488(5) A, β=108.538(1) Deg, Z=2, sp. gr. C2/m. The isolated group [HfMo 6 O 24 ] 8- is responsible for fundamental fragment of the structure. Three varieties of crystallographically independent Tl-polyhedra fill space evenly between fragments [HfMo 6 O 24 ] 8- forming three-dimensional form [ru

  2. Phase equilibria in the MgMoO4-Ln2(MoO4)3 (Ln=La,Gd) systems

    International Nuclear Information System (INIS)

    Fedorov, N.F.; Ipatov, V.V.; Kvyatkovskij, O.V.

    1980-01-01

    Phase equilibria in the MgMoO 4 -Ln 2 (MoO 4 ) 3 systems (Ln=La, Gd) have been studied by static and dynamic methods of the physico-chemical analysis, using differential thermal, visual-polythermal, crystal-optical, X-ray phase, and infrared spectroscopic methods, and their phase diagrams have been constructed. Phase equilibria in the systems studied are characterized by limited solubility of components in the liquid state, formation of solid solutions on the base of α- and β-forms of Gd 2 (MoO 4 ) 3 . Eutectics in the MgMoO 4 -Ln 2 (MoO 4 ) 3 (Ln=La, Gd) systems corresponds to the composition of 71 mode % La 2 (MoO 4 ) 3 -29 mole % MgMoO 4 , tsub(melt)--935+-5 deg C and 57 mole % Gd 2 (MoO 4 ) 3 -43 mole % MgMoO 4 , tsub(melt)=1020+-5 deg C. The region of glass formation has been established [ru

  3. Ru-assisted synthesis of Pd/Ru nanodendrites with high activity for ethanol electrooxidation

    Science.gov (United States)

    Zhang, Ke; Bin, Duan; Yang, Beibei; Wang, Caiqin; Ren, Fangfang; Du, Yukou

    2015-07-01

    Due to the specific physical and chemical properties of a highly branched noble metal, the controllable synthesis has attracted much attention. This article reports the synthesis of Pd/Ru nanodendrites by a facile method using an oil bath in the presence of polyvinyl pyrrolidone, potassium bromide and ascorbic acid. The morphology, structure, and composition of the as-prepared catalysts were characterized by means of X-ray diffraction, X-ray photoelectron spectroscopy and transmission electron microscopy. In the electrochemical measurement, the as-prepared Pd7/Ru1 bimetallic nanodendrites provide a large electrochemically active surface area and exhibit high peak current density in the forward scan toward ethanol electrooxidation, which is nearly four times higher than those of a pure Pd catalyst. The as-prepared Pd7/Ru1 catalysts also exhibit significantly enhanced cycling stability toward ethanol oxidation in alkaline medium, which are mainly ascribed to the synergetic effect between Pd and Ru. This indicates that the Pd7/Ru1 catalysts should have great potential applications in direct ethanol fuel cells.Due to the specific physical and chemical properties of a highly branched noble metal, the controllable synthesis has attracted much attention. This article reports the synthesis of Pd/Ru nanodendrites by a facile method using an oil bath in the presence of polyvinyl pyrrolidone, potassium bromide and ascorbic acid. The morphology, structure, and composition of the as-prepared catalysts were characterized by means of X-ray diffraction, X-ray photoelectron spectroscopy and transmission electron microscopy. In the electrochemical measurement, the as-prepared Pd7/Ru1 bimetallic nanodendrites provide a large electrochemically active surface area and exhibit high peak current density in the forward scan toward ethanol electrooxidation, which is nearly four times higher than those of a pure Pd catalyst. The as-prepared Pd7/Ru1 catalysts also exhibit significantly

  4. Separation of 99Mo from 132Te using thiourea as complexing agent. Application to the separation of 99Mo from the fission products

    International Nuclear Information System (INIS)

    Mestnik, S.A.C.; Silva, C.P.G. da.

    1989-02-01

    A radiochemical method to isolate 99 Mo from 132 Te both produced in the fission of 235 U has been developed. The methods is based on the formation of a cationic complex of tellerium with thiourea in acid medium which is retained (98.7 +- 0.5)% on a cation exchange resin (Dowex 50W-X8, 100 - 200 mesh) while (99.8 +- 0.05)% 99 Mo passes through it, due to the non formation of such complex in the same experimental conditions. The radionuclidic purity of the separated 99 Mo verified by using gamma spectrometry was found to be suitable for the preparation of 99 Mo - 99 sup (m)Tc generators. The retention of 99 Mo on an alumina column as function of ph was investigated. the best pH range for this purpose was found to be between 4.0 - 4.5. the 99 Mo - 99m Tc generator was prepared. the elution of 99m Tc was carried out with physiologic saline solution. The radionuclidic purity of the eluate was found suitable and the product can be used for Nuclear Medicine applications. (author) [pt

  5. Carbon monoxide oxidation on bimetallic Ru/Au(111 surfaces

    Directory of Open Access Journals (Sweden)

    ROLF-JÜRGEN BEHM

    2001-02-01

    Full Text Available The electrochemical deposition of Ru on Au(111 was performed in 0.5 M H2SO4+10-4 M RuCl3 . The obtained bimetallic Ru/Au(111 surfaces were character-ised by cyclic voltammetry and in situ STM in 0.5 MH2SO4. The Ru deposit consists of nanoscale islands, which merge with increasing coverage. Two different types of bimetallic Ru/Au(111 surfaces with respect to the distribution of Ru islands over the Au(111 substrate surface were obtained. When the deposition was performed at potentials more positive than the range of Au(111 reconstruction, homogeneous nucleation occured resulting in a random distribution of Ru islands. When the deposition was performed on reconstructed Au(111 at low overpotentials, selective nucleation occured resulting in the replication of the Au(111 reconstruction. Only at higher deposition overpotentials, can multilayer deposits be formed, which exhibit a very rough surface morphology. The electrocatalytic activity of such structurally well defined Ru/Au(111 bimetallic surfaces was studied towards CO oxidation with the Ru coverage ranging from submonolayer to several monolayer. COstripping commences at about 0.2 Vand occurs over a broad potential range. The observed influence of the Ru structure on the CO stripping voltammetry is explained by local variations in the COadsorption energy, caused by differences in the local Ru structure and by effects induced by the Au(111 substrate.

  6. The provenance investigation on ancient chinese Ru porcelains by NAA

    International Nuclear Information System (INIS)

    Gao Zhengyao; Wang Jie; Chen Songhua

    1997-01-01

    The 28 samples of glazes and bodies of ancient Chinese Ru porcelains are analyzed by neutron activation. The 36 element contents in each sample are determined. The neutron activation analysis (NAA) data are analyzed by fuzzy cluster. The trend cluster diagram is obtained. The result shows that the ancient Chinese Ru porcelains were most probably from the same raw material source though they were from different time, fired in different kilns and in different colors. The near provenance relation between ancient Jun porcelain and ancient Ru porcelain is preliminarily analyzed. The two modern Ru porcelains approximate to ancient Ru porcelains, one becomes estranged from ancient Ru porcelains. Jingdezhen porcelain is unconcerned with Ru porcelains

  7. Method to produce a sup(99m)Tc generator

    International Nuclear Information System (INIS)

    Brown, J.L.; Harris, O.A.

    1977-01-01

    A 400 millicurie Tc generator for medical application is made on the basis of chromatographic Al 2 O3 plased in a glass generator clumn. The Al 2 O 3 is subjected to thermal activation at 394K. A charge with sodium molybdate 99 solution training a pH value of 3.5 fallowe. After washing the generator with acetic, a 0.9% NaCl solution is added. The remaining solution is sucked off by introducing air through the column. The eluate has a molybdenum cost ent of 0.001 to 0.005 μCi Mo/mCi Tc 99m. The pH-value of the eluate is between 5.0 and 5.3. The aluminium ion content is less than 0.3 g/ml. (DG) [de

  8. Phase formation in the K2MoO4-Lu2(MoO4)3-Hf(MoO4)2 system and the structural study of triple molybdate K5LuHf(MoO4)6

    International Nuclear Information System (INIS)

    Romanova, E.Yu.; Bazarov, B.G.; Tushinova, Yu.L.; Fedorov, K.N.; Bazarova, Zh.G.; Klevtsova, R.F.; Glinskaya, L.A.

    2007-01-01

    Interactions in the ternary system K 2 MoO 4 -Lu 2 (MoO 4 ) 3 -Hf(MoO 4 ) 2 have been studied by X-ray powder diffraction and differential thermal analysis. A new triple (potassium lutetium hafnium) molybdate with the 5 : 1 : 2 stoichiometry has been found. Monocrystals of this molybdate have been grown. Its X-ray diffraction structure has been refined (an X8 APEX automated diffractometer, MoK α radiation, 1960 F(hkl), R = 0.0166). The trigonal unit cell has the following parameters: a = 10.6536(1) A, c = 37.8434(8) A, V=3719.75(9) A, Z = 6, space group R3-bar c. The mixed 3D framework of the structure is built of Mo tetrahedra sharing corners with two independent (Lu,Hf)O 6 octahedra. Two sorts of potassium atoms occupy large framework voids [ru

  9. Reagent' sets for the concentration of sup(99m)Tc and sup(113m)In

    International Nuclear Information System (INIS)

    Bianco de Salas, G.N.; Arciprete, J.; Mitta, A.E.A.

    1976-10-01

    A simple technique for the concentration of the eluates from 99 Mo/sup(99m)Tc and 113 Sn/sup(113m)In generators is described. The reagents' sets provided by the C.N.E.A. for the labelling of different radiopharmaceuticals can be used by only reducing their volumes proportionally. Both concentration techniques for Tc-99m and In-113m will be supplied to users as reagents' sets. (author) [es

  10. An alternative route for the preparation of the medical isotope 99Mo from the 238U(γ, f) and 100Mo(γ, n) reactions

    International Nuclear Information System (INIS)

    Naik, H.; Goswami, A.; Suryanarayana, S.V.; Jagadeesan, K.C.; Thakare, S.V.; Joshi, P.V.; Nimje, V.T.; Mittal, K.C.; Venugopal, V.; Kailas, S.

    2013-01-01

    The radionuclide 99 Mo, which has a half-life of 65.94 h was produced from 238 U(γ, f) and 100 Mo(γ, n) reactions using a 10 MeV electron linac at EBC, Kharghar Navi-Mumbai, India. This has been investigated since the daughter product 99m Tc is very important from a medical point of view and can be produced in a generator from the parent 99 Mo. The activity of 99 Mo was analyzed by a γ-ray spectrometric technique using a HPGe detector. From the detected γ-rays activity of 140.5 and 739.8 keV, the amount of 99 Mo produced was determined. For comparison, the amount of 99 Mo from 238 U(γ, f) and 100 Mo(γ, n) reactions was also estimated using the experimental photon flux from 197 Au(γ, n) 196 Au reaction. The amount of 99 Mo from the detected γ-lines is in agreement with the estimated value for 238 U(γ, f) and 100 Mo(γ, n) reactions. The production of 99 Mo activity from 238 U(γ, f) and 100 Mo(γ, n) reactions is a relevant and novel approach, which provides alternative routes to 235,238 U(n, f) and 98 Mo(n, γ) reactions, circumventing the need for a reactor. The viability and practicality of the 99 Mo production from the 238 U(γ, f) and 100 Mo(γ, n) reactions alternative to 235,238 U(n, f) and 98 Mo(n, γ) reactions has been emphasize. An estimate has been also arrived based on the experimental data of present work to fulfill the requirement of DOE. (author)

  11. Kinetic model for the dosimetry of radiopharmaceuticals contaminated by Mo-99

    International Nuclear Information System (INIS)

    Shearer, D.R.; Pezzullo, J.C.

    1986-01-01

    Radiopharmaceuticals tagged with Tc-99m may become contaminated with breakthrough products from the Mo-99/Tc-99m generator. If a fraction of the contaminant becomes bound to the radiopharmaceutical, the dose to the radiopharmaceutical target organ from the contaminant must be considered. The dose to the contaminant target organ may then be calculated as the sum of the doses from a) the initially unbound contaminant, and b) the contaminant later released by degradation of the radiopharmaceutical. This paper presents a model which takes the above processes into account. The model is illustrated with clinical data derived from Mo-99 contaminated radiopharmaceuticals. 5 references, 2 figures, 6 tables

  12. Radioactive study of Mo{sup 93} and Mo{sup 95} levels and research of subshell effects for the shell 2d 5/2; Etude, par radioactivite des niveaux de {sup 93}Mo et de {sup 95}Mo et essai de mise en evidence de la sous-couche 2d{sub 5/2}

    Energy Technology Data Exchange (ETDEWEB)

    Levi Lesueur, Ch [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1961-03-15

    We studied the decay schemes of Tc{sup 93} et Tc{sup 95} to determine the spins of Mo{sup 93} and M{sup 95} levels, and especially the position of the single-particle level 1g 7/2. We found a large spacing between the neutron shells 2d 5/2 and 1g 7/2 like that observed first in Mo{sup 97}. As the subshell 2d 5/2 is so far from its neighbours, we thought that subshell effects could perhaps be discovered in the systematics of separation energies and beta-decay energies. We found such effects. (author) [French] Par l'etude des schemas de desintegration de {sup 93}Tc et {sup 95}Tc, nous avons essaye de determiner les spins des niveaux de {sup 93}Mo et {sup 95}Mo et en particulier la position du niveau de particule 1g 7/2. Nous avons ainsi confirme l'ecart important entre les couches de neutrons 2d 5/2 et 1g 7/2 deja constate a propos de {sup 97}Mo. Nous avons pense que la sous-couche 2d 5/2 ainsi isolee des couches voisines pouvait, peut etre, etre mise en evidence par l'etude des systematiques d'energies de separation et d'energies de desintegration beta. Nous avons verifie qu'il en etait bien ainsi. (auteur)

  13. Excitation function and isomeric ratio of Tc-isotopes from the 93Nb(α, xn) reaction

    International Nuclear Information System (INIS)

    Kim, K.; Kim, G.N.; Naik, H.; Zaman, M.; Yang, S.-C.; Song, T.-Y.; Guin, R.; Das, S.K.

    2015-01-01

    The excitation functions of 94–96 Tc isotopes and independent isomeric ratios of 93m, g Tc, 94m, g Tc, and 95m, g Tc from the 93 Nb(α, xn) reaction within the energy range below 40 MeV have been determined by using a stacked-foil activation and an off-line γ-ray spectrometric technique at the Variable Energy Cyclotron Center, Kolkota, India. The excitation function of 94–96 Tc in the 93 Nb(α, xn) reaction was also calculated by using the computer code TALYS 1.6. The present data are found to be in general agreement with the literature data but have similar trend with some deviation from calculated data of the TALYS 1.6 code. The isomeric ratios of 93m, g Tc, 94m, g Tc, and 95m, g Tc in the 93 Nb(α, xn) reactions from the present work and literature data were compared with similar data in the 93 Nb( 3 He, xn) and 96 Mo(p, xn) reactions. In all the three reactions, the isomeric ratios increase with the increasing excitation energy. However, at all excitation energies, the isomeric ratios of 93m, g Tc, 94m, g Tc, and 95m, g Tc in the 93 Nb(α, xn) and 93 Nb( 3 He, xn) reactions are higher than those in the 96 Mo(p, xn) reactions, which indicate the role of input angular momentum besides excitation energy. Above the excitation energy of 35–55 MeV, the isomeric ratios of 95m, g Tc, 94m, g Tc, and 93m, g Tc decrease in all the 93 Nb(α, xn), 93 Nb( 3 He, xn) and 96 Mo(p, xn) reactions. This decreasing trend at higher excitation energy indicates the starting of pre-equilibrium reaction, which depends on the target, projectile, and type of reaction products

  14. Average resonance capture studies of 102Ru

    International Nuclear Information System (INIS)

    Shi, Z.R.; Casten, R.F.; Stachel, J.; Bruce, A.M.

    1984-01-01

    The 102 Ru nucleus has been investigated via the ARC technique which ensures a complete set of J/sup π/ = 0 + , 1 +- , 2 +- , 3 +- , 4 +- , and 5 + levels up to 2 MeV. The results are discussed in the framework of the IBA-1 with Consistent Q. The calculations show good agreement with the empirical data especially for the O 2 + state, suggesting that it can be described in terms of collective degrees of freedom

  15. Ni-Doping Effects on Oxygen Removal from an Orthorhombic Mo 2 C (001) Surface: A Density Functional Theory Study

    Energy Technology Data Exchange (ETDEWEB)

    Zhou, Mingxia [Department; Cheng, Lei [Materials; Choi, Jae-Soon [Oak Ridge National Laboratory, 1 Bethel Valley Road, Oak Ridge, TN 37831, Unites States; Liu, Bin [Department; Curtiss, Larry A. [Materials; Assary, Rajeev S. [Materials

    2018-01-11

    Density functional theory (DFT) calculations were used to investigate the effect of Ni dopants on the removal of chemisorbed oxygen (O*) from the Mo-terminated (T-Mo) and C-terminated (Tc) Mo2C(001) surfaces. The removal of adsorbed oxygen from the catalytic site is essential to maintain the long-term activity and selectivity of the carbide catalysts in the deoxygenation process related to bio-oil stabilization and upgrading. In this contribution, the computed reaction energetics and reaction barriers of O* removal were compared among undoped and Ni-doped Mo2C(001) surfaces. The DFT calculations indicate that selected Ni-doped surfaces such as Ni adsorbed on T-Mo and Tc Mo2C(001) surfaces enable weaker binding of important reactive intermediates (O*, OH*) compared to the undoped counterparts, which is beneficial for the O* removal from the catalyst surface. This study thus confirms the promoting effect of the Ni dopant on O* removal reaction on the T-Mo Mo2C(001) and Tc Mo2C(001) surfaces. This computational prediction has been confirmed by the temperature-programmed reduction profiles of Mo2C and Ni-doped Mo2C catalysts, which had been passivated and stored in an oxygen environment.

  16. Laser Spectroscopy of Ruthenium Containing Diatomic Molecules: RuH/D and RuP.

    Science.gov (United States)

    Adam, Allan G.; Konder, Ricarda M.; Nickerson, Nicole M.; Linton, Colan; Tokaryk, D. W.

    2015-06-01

    In the last few years, the Cheung group in Hong Kong and the Steimle group in Arizona have successfully studied several ruthenium containing diatomic molecules, RuX (X =C, O, N, B, using the laser-ablation molecular jet technique. Based on this success, the UNB spectroscopy group decided to try and find the optical signatures of other RuX molecules. Using CH_3OH and PH_3 as reactant gases, the RuH and RuP diatomic molecules have been detected in surveys of the 420 - 675 nm spectral region. RuD has also been made using fully deuterated methanol as a reactant. Dispersed fluorescence experiments have been performed to determine ground state vibrational frequencies and the presence of any low-lying electronic states. Rotationally resolved spectra for these molecules have also been taken and the analysis is proceeding. The most recent results will be presented. F. Wang et al., Journal of Chemical Physics 139, 174318 (2013). N. Wang et al., Journal of Physical Chemistry A 117, 13279 (2013). T. Steimle et al., Journal of Chemical Physics 119, 12965 (2003). N. Wang et al., Chemical Physics Letters 547, 21 (2012).

  17. Ru nanostructure fabrication using an anodic aluminum oxide nanotemplate and highly conformal Ru atomic layer deposition

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Woo-Hee; Park, Sang-Joon; Son, Jong-Yeog; Kim, Hyungjun [Department of Material Science and Engineering, POSTECH Pohang University of Science and Technology, San 31, Hyoja-Dong, Nam-Gu, Pohang 790-784 (Korea, Republic of)

    2008-01-30

    We fabricated metallic nanostructures directly on Si substrates through a hybrid nanoprocess combining atomic layer deposition (ALD) and a self-assembled anodic aluminum oxide (AAO) nanotemplate. ALD Ru films with Ru(DMPD)(EtCp) as a precursor and O{sub 2} as a reactant exhibited high purity and low resistivity with negligible nucleation delay and low roughness. These good growth characteristics resulted in the excellent conformality for nanometer-scale vias and trenches. Additionally, AAO nanotemplates were fabricated directly on Si and Ti/Si substrates through a multiple anodization process. AAO nanotemplates with various hole sizes (30-100 nm) and aspect ratios (2:1-20:1) were fabricated by controlling the anodizing process parameters. The barrier layers between AAO nanotemplates and Si substrates were completely removed by reactive ion etching (RIE) using BCl{sub 3} plasma. By combining the ALD Ru and the AAO nanotemplate, Ru nanostructures with controllable sizes and shapes were prepared on Si and Ti/Si substrates. The Ru nanowire array devices as a platform for sensor devices exhibited befitting properties of good ohmic contact and high surface/volume ratio.

  18. Spectroscopy of {sup 96}Ru and {sup 98}Ru: structures of varied character at N {>=} 52

    Energy Technology Data Exchange (ETDEWEB)

    Reviol, W; Garg, U; Aprahamian, A; Davis, B F; Herr, M C; Naguleswaran, S; Walpe, J C; Ye, D [Notre Dame Univ., IN (United States); Ahmad, I; Carpenter, M P; Janssens, R V.F.; Khoo, T L; Lauritsen, T; Liang, Y [Argonne National Lab., IL (United States)

    1992-08-01

    The authors have investigated the onset of deformation at N {>=} 52 by performing high-spin gamma spectroscopy of {sup 96-98}Ru using the {sup 65}Cu({sup 36}S,pxn) reaction with the Argonne-Notre Dame {gamma}-ray facility. From the coincidence data associated with high multiplicity (k {>=} 8) events, they have established two main band structures in {sup 96-98}Ru which extend the previously-known level schemes significantly (up to > 20 {Dirac_h}). In {sup 96}Ru, one of the newly observed structures consists of five rotation-like E2 transitions and feeds into the known 9{sup (-)} state; the other structure bypasses the first one, and based on the observed level-spacings, is tentatively described as vibration-like. A rotational-like structure above a spin of 8 {Dirac_h}, along with a parallel vibration-like structure, has been observed in {sup 98}Ru as well. The data also contain some evidence for a weak sequence of dipole (presumably M1) transitions in {sup 96}Ru. This structure might be similar to the high-K oblate bands recently observed in {sup 119-123}I and {sup 198-20P}b. 9 refs., 3 figs.

  19. Experimental cross section evaluation for innovative 99Mo production via the (α,n) reaction on 96Zr target

    International Nuclear Information System (INIS)

    Pupillo, Gaia; Gambaccini, M.; Esposito, J.; Haddad, F.; Michel, N.

    2014-01-01

    The recent crisis of 99 Mo production by nuclear reactors caused an unexpected worldwide 99m Tc shortening, forcing the international scientific community to find alternative production routes for these vital nuclides. One of the possibilities is to replace the current reactor-based method with the accelerator-based one. The aim of this work is the experimental evaluation of the 96 Zr(α,n) 99 Mo reaction, using the well known stacked foil technique with natural Zr targets, in the energy range 33-8 MeV. The results were compared with the published experimental values, finding good agreement in the trend of the cross section but at higher peak value. The results refer to 100% enriched 96 Zr target. The cross section values measured in the different irradiations show excellent agreement and indicate that the ideal energy range for 99 Mo production is 13-25 MeV. In comparison with the literature, there is good agreement in the trend of the cross section but at higher peak value. The 96 Zr(α,n) 99 Mo reaction is an interesting alternative production route of 99 Mo aimed at the realization of 99 Mo/ 99 mTc generators. Using enriched 96 Zr as target, 99 Mo is the only radioactive Mo-isotope produced, while using natural Zr as target, the resulting 99 Mo still has an high radioisotopic purity (only the radioactive 93 Mo is co-produced), but a lower specific activity. In both cases no Tc-nuclides are directly produced in target and the high purity 99m Tc results only from the decay of 99 Mo

  20. Chemically mediated diffusion of d-metals and B through Si and agglomeration at Si-on-Mo interfaces

    NARCIS (Netherlands)

    T. Tsarfati,; Zoethout, E.; van de Kruijs, R.; F. Bijkerk,

    2009-01-01

    Chemical diffusion and interlayer formation in thin layers and at interfaces is of increasing influence in nanoscopic devices, such as nanoelectronics and reflective multilayer optics. Chemical diffusion and agglomeration at interfaces of thin Ru, Mo, Si, and B4C layers have been studied with x-ray

  1. Development of more efficacious Tc-99m organ imaging agents for use in nuclear medicine by analytical characterization of radiopharmaceutical mixtures. Progress report, May 1, 1981-April 30, 1982

    International Nuclear Information System (INIS)

    Heineman, W.R.; Deutsch, E.A.

    1981-12-01

    The objectives of this year's research were to develop a method for rapidly determining TcO 4 - in 99 Mo//sup 99m/Tc generator eluates, to improve the ability to chromatographically determine individual Tc-HEDP complexes in radiopharmaceuticals, and to investigate the effects of TcO 4 - concentration and electrochemical reduction on the types and relative amounts of Tc-HEDP complexes present in a radiopharmaceutical formulation. A rapid and sensitive high performance liquid chromatographic (HPLC) method for the quantitative determination of pertechnetate (TcO 4 - ) was developed. This HPLC-based analysis may be of considerable utility in assessing the history and function of 99 MO/sup 99m/Tc generators as well as in the routine analysis of reduced technetium radiopharmaceuticals for the presence of undesired TcO 4 - . Encouraging results were obtained on a dimethyl amine column using aqueous (NH 4 ) 2 SO 4 as the mobile phase. The preparation of Tc(NaBH 4 ) HEDP radiopharmaceutical analogues using varying concentrations of total TcO 4 - shows a dramatic effect in the number and distribution of Tc-HEDP complexes over a TcO 4 - concentration range of 10 -2 to 10 -8 M. These results suggest that total TcO 4 - concentration is an important parameter to be considered in the preparation of a specific Tc-HEDP complex to improve skeletal imaging. The preparation of Tc(electrode) HEDP radiopharmaceutical analogues by using electrochemical reduction was explored. The resulting solutions contain Tc-HEDP complexes that are tentatively identified as being the same complexes formed by NaBH 4 reduction, although the relative concentrations of these complexes are quite different with the two modes of reduction. Thus, electrochemical reduction shows promise as a viable route to the preparation of specific Tc-HEDP complexes for improved skeletal imaging

  2. Procedures for the production of poly-zirconium-compound (PZC) based chromatographic 99mTc generator to be available for clinical application

    International Nuclear Information System (INIS)

    Le Van So

    2006-01-01

    Two procedures - Column post-loading and Column pre-loading procedures - for the preparation of PZC based chromatographic Tc-99m generators were described in detail. In-process documentation, flow-chart of process for the individual procedures, specific Tc-99m generator designs and pictorially illustrative description of Tc-99m generator production process were systematically reported. The column pre-loading procedure was highly evaluated as a competent technology for the preparation of PZC based Tc-99m chromatographic generator of high performance using (n, γ) 99 Mo of low specific radioactivity produced on low power research reactors. (author)

  3. Presentation of test cases TC-2A, TC-2B, TC-2C, TC-2D - Twodimensional, incompressible, wall flows with separation

    DEFF Research Database (Denmark)

    Scheel Larsen, Poul

    1988-01-01

    The four test cases comprise the backfacing step at high Re-number (TC-2A) and low Re-number (TC-2B), a low Re-number boundary layer flow past a thin obstacle, fence-on-wall (TC-2C), and a high Re-number developed channel flow past a squareobstacle (TC-2D). Geometry, test conditions and available...

  4. Tc: chemistry and radiopharmaceuticals: a prospectus

    International Nuclear Information System (INIS)

    Tulip, T.H.

    1987-01-01

    The recent explosion in technetium chemistry evident in this symposium promises to continue unabated. As in the past, radiopharmaceutical applications will lead to new Tc chemistry. In this lecture the author will discuss those areas which appear most fertile based on chemical and radiopharmaceutical criteria. Among these will be new organometallic Tc chemistry (e.g., Tc(CNR) 6 cations), Tc complexes as metabolic tracers (e.g., Tc-analogs to FDG), and peptide-based Tc chelators (e.g., Tc-metallothionein)

  5. Evaluation of preparation and performance of gel column 99Tcm generators based on zirconium molybdate - 99Mo

    International Nuclear Information System (INIS)

    Saraswathy, P.; Sarkar, S.K.; Patel, R.R.; Arora, S.S.; Arjun, G.; Narasimhan, D.V.S.; Ramamoorthy, N.

    1998-01-01

    In view of the importance and relevance of zirconium molybdate (ZrMo) based gel generators for 99 Tc m , developed first by Australian scientists, particularly for developing nations having production capability for neutron activated 99 Mo, work has been carried out in our centre towards optimisation of the preparatory conditions. Appropriate facilities have been set up for safe, reliable and regular manufacture of such 99 Tc m gel generators on a small scale based on our earlier successful attempts on the approach for process standardisation. The results of our extensive evaluation, including for clinical use, are reported here. Following the regular procedure standardised by us earlier, 9 lots of 99 Mo were converted in ZrMo gel adopting aseptic practices and two different techniques for drying the ZrMo cake - heated air at 60-80 deg. C and microwave drying at 385 watts. The ZrMo granules obtained after further processing were loaded onto generator assemblies. 10 g molybdenum was handled in each batch of gel conversion, while typically 2 g Mo was used per generator column, except in the case of demonstration of higher capacity generators. The generator performance was evaluated systematically over nearly 15 days, in terms of rapidity and smoothness of elution, 99 Tc m elution yield and quality of eluted pertechnetate. The consistent results of over 60% (Max. 90%) yield of 99 Tc m , -3 % 99 Mo breakthrough, >98% radiochemical purity of pertechnetate, 99 Tc m compounds etc. indicated satisfactory quality of pertechnetate, comparable to that obtained by conventional generator systems. 12 such generators, containing up to 18.5 GBq 99 Mo, supplied for clinical use and evaluated at two hospital radiopharmacies showed satisfactory generator performance. The applicability for preparing larger capacity generators for centralised radiopharmacies and feasibility to achieve reduced process time and ease of control by using microwave oven drying have been established. (author)

  6. Assessment of the direct cyclotron production of (99m)Tc: An approach to crisis management of (99m)Tc shortage.

    Science.gov (United States)

    Rovais, Mohammad Reza Aboudzadeh; Aardaneh, Khosro; Aslani, Gholamreza; Rahiminejad, Ali; Yousefi, Kamran; Boulouri, Fatemeh

    2016-06-01

    Nowadays, the cyclotron production of technetium-99m ((99m)Tc) has been increased, due to the worldwide (99m)Tc generator shortage. In the present work, an improved strategy for the production of (99m)Tc, using the proton irradiation of the enriched (100)Mo was developed. The performance of this method in terms of the production yield, chemical purity, radiochemical purity, as well as radionuclide purity was evaluated. The average production yield was measured to be 356MBqμA(-1)h(-1). A good agreement was found between the calculated production yield and the experimental one. The radiochemical separation and total recovery yields of (99m)Tc were 92% and 69%, respectively. The radiochemical and the radionuclide purities of the (99m)Tc were 99% and >99.99% at the end of purification, respectively. The results of quality control tests (QC) support the concept that cyclotron-produced (99m)Tc is suitable for preparation of USP-compliant. Copyright © 2016 Elsevier Ltd. All rights reserved.

  7. Substituent-directed structural and physicochemical controls of diruthenium catecholate complexes with ligand-unsupported Ru-Ru bonds.

    Science.gov (United States)

    Chang, Ho-Chol; Mochizuki, Katsunori; Kitagawa, Susumu

    2005-05-30

    A family of diruthenium complexes with ligand-unsupported Ru-Ru bonds has been systematically synthesized, and their crystal structures and physical properties have been examined. A simple, useful reaction between Ru2(OAc)4Cl (OAc- = acetate) and catechol derivatives in the presence of bases afforded a variety of diruthenium complexes, generally formulated as [Na(n){Ru2(R4Cat)4}] (n = 2 or 3; R4 = -F4, -Cl4, -Br4, -H4, -3,5-di-t-Bu, and -3,6-di-t-Bu; Cat(2-) = catecholate). The most characteristic feature of the complexes is the formation of short ligand-unsupported Ru-Ru bonds (2.140-2.273 A). These comprehensive studies were carried out to evaluate the effects of the oxidation states and the substituents governing the molecular structures and physicochemical properties. The Ru-Ru bond distances, rotational conformations, and bending structures of the complexes were successfully varied. The results presented in this manuscript clearly demonstrate that the complexes with ligand-unsupported Ru-Ru bonds can sensitively respond to redox reactions and ligand substituents on the basis of the greater degree of freedom in their molecular structures.

  8. Analysis of 99Mo Production Capacity in Uranyl Nitrate Aqueous Homogeneous Reactor using ORIGEN and MCNP

    Directory of Open Access Journals (Sweden)

    A. Isnaeni

    2014-04-01

    Full Text Available 99mTc is a very useful radioisotope in medical diagnostic procedure. 99mTc is produced from 99Mo decay. Currently, most of 99Mo is produced by irradiating 235U in the nuclear reactor. 99Mo mostly results from the fission reaction of 235U targets with a fission yield about 6.1%. A small additional amount is created from 98Mo neutron activation. Actually 99Mo is also created in the reactor fuel, but usually we do not extract it. The fuel will become spent fuel which is a highly radioactive waste. 99Mo production system in the aqueous homogeneous reactor offers a better method, because all of the 99Mo can be extracted from the fuel solution. Fresh reactor fuel solution consists of uranyl nitrate dissolved in water. There is no separation of target and fuel in an aqueous homogeneous reactor where target and fuel become one liquid solution, and there is no spent fuel generated from this reactor. Simulation of the extraction process is performed while reactor in operation (without reactor shutdown. With an extraction flow rate of 3.6 L/h, after 43 hours of reactor operation the production of 99Mo is relatively constant at about 98.6 curie/hour

  9. Results of four one-day electron-accelerator irradiations of enriched Mo-100 targets for the production of Mo-99

    Energy Technology Data Exchange (ETDEWEB)

    Chemerisov, S. [Argonne National Lab. (ANL), Argonne, IL (United States); Bailey, J. [Argonne National Lab. (ANL), Argonne, IL (United States); Heltemes, T. [Argonne National Lab. (ANL), Argonne, IL (United States); Jonah, C. [Argonne National Lab. (ANL), Argonne, IL (United States); Gromov, R. [Argonne National Lab. (ANL), Argonne, IL (United States); Makarashvili, V. [Argonne National Lab. (ANL), Argonne, IL (United States); Tkac, P. [Argonne National Lab. (ANL), Argonne, IL (United States); Rotsch, D. [Argonne National Lab. (ANL), Argonne, IL (United States); Virgo, M. [Argonne National Lab. (ANL), Argonne, IL (United States); Vandegrift, G. F. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2016-10-01

    A series of four one-day irradiations was conducted with 100Mo-enriched disk targets. After irradiation, the enriched disks were removed from the target and dissolved. The resulting solution was processed using a NorthStar RadioGenix™ 99mTc generator either at Argonne National Laboratory or at the NorthStar Medical Radioisotopes facility. Runs on the RadioGenix system produced inconsistent analytical results for 99mTc in the Tc/Mo solution. These inconsistencies were attributed to the impurities in the solution or improper column packing. During the irradiations, the performance of the optic transitional radiation (OTR) and infrared cameras was tested in high radiation field. The OTR cameras survived all irradiations, while the IR cameras failed every time. The addition of X-ray and neutron shielding improved camera survivability and decreased the number of upsets.

  10. Sideward flow of K+ in Ru+Ru and Ni+Ni reactions sat SIS energies

    International Nuclear Information System (INIS)

    Crochet, P.; Herrmann, N.; Wisniewski, K.

    2000-01-01

    Experimental data on K + and proton sideward flow measured with the FOPI detector at SIS/GSI in the reactions Ru+Ru at 1.69 A GeV and Ni+Ni at 1.93 A GeV are presented. The K + sideward flow is found to be anti-correlated (correlated) with the one of protons at low (high) transverse momenta. When compared to the predictions of a transport model, the data favour the existence of an in-medium repulsive K + -nucleon potential. (author)

  11. Electron correlation in CaRuO3 and SrRuO3

    International Nuclear Information System (INIS)

    Singh, Ravi Shankar; Maiti, Kalobaran

    2005-01-01

    We investigate the role of electron correlation in the electronic structure of 4d transition-metal oxides CaRuO 3 and SrRuO 3 . The photoemission spectra collected at different surface sensitivities reveal qualitatively different surface and bulk electronic structures in these systems. Extracted bulk spectra could be simulated using first principle approaches consistently with their thermodynamic parameters within the same model. The estimated electron correlation strength (U/W ∼ 0.2) is significantly weak as expected in 4d systems and resolves the long-standing issue that arose due to the prediction of large U/W similar to 3d systems. (author)

  12. Preparation of zirconium molybdate gel for 99mTc gel generator

    International Nuclear Information System (INIS)

    Aliludin, Z.; Ohkubo, Masatake; Kushita, Kouhei

    1988-09-01

    Zirconium molybdate gel has excellent characteristics for use as column matrix material of 99m Tc generators. In this work, zirconium molybdate gels were prepared under different conditions; pH's of molybdate solutions from 2.5 to 7.0, Mo:Zr molar ratios from 0.7:1.0 to 1.3:1.0, drying temperatures from an ambient temperature to 200 deg C, and drying times from 1 h to 25 h. Contents of water, nitrate, molybdenum and zirconium were measured to examine the fundamental conditions in gel preparation. The Mo:Zr molar ratio was 1.0:1.0 for the most of gels obtained. A 99m Tc generator was prepared with an amorphous zirconium molybdate containing a tracer level of 99 Mo as column matrix material. Elution of 99m Tc was rapid and the average elution efficiency was 90 % for 6 ml elutions. Contents of radionuclidic impurities, Zr and Mo in the eluates, were low enough to meet the pharmacopoeia requirements for human use. (author)

  13. Magnesium-molybdenum compounds as matrixes of 99m Tc generators

    International Nuclear Information System (INIS)

    Jimenez M, T.S.

    2005-01-01

    In order to finding new production alternatives of 99 Mo/ 99m Tc generators, easy to produce and with high elutriation efficiencies, it is proposed in this work to develop a generator with basis of magnesium and molybdenum that could be irradiated after their synthesis, given the short half life of the only radioisotope produced by the magnesium: 27 Mg (t 1/2 = 9.46 m). It is necessary to mention that have not been reported works in relation to this type of compound, being then important to carry out basic studies on the formation and behavior of these in relation to their matrix functions of those generated of 99 Mo/ 99m Tc. In this work it was determined the effect that has, the magnesium salt used in the synthesis of those molybdenum-magnesium compounds, the molar ratio Mo: Mg, the concentration of the magnesium salt, the pH of the used ammonium molybdates in the synthesis of the final compounds and the washing of the molybdates of synthesized magnesium, in the performance of the 99 Mo/ 99m Tc generators. Parameters like the elutriation efficiency, the radionuclide purity, radiochemical and chemical of the eluates and their pH, were determined in each case, also its were characterized the synthesized compounds using: neutron activation analysis (NAA), X-ray diffraction (XRD) and scanning electron microscopy of high vacuum (SEM), besides of complementary techniques: infrared spectroscopy (IR), and thermal gravimetric analysis (TGA). (Author)

  14. Distributed production system for 99mTc-I: System overview

    International Nuclear Information System (INIS)

    Bennett, R.G.; Terry, W.K.; Grover, S.B.

    1997-01-01

    Technetium-99m is the radioisotope of choice for >80% of all nuclear medical imaging procedures today in the United States. There are > 12 million 99m Tc scans performed in the United States per year. Since the development of fission-based radio nuclide generators for 99 Mo, 99m Tc use has grown steadily over the past 20 yr. Despite the widespread demand for 99m Tc in medicine, a reliable and assured supply of the parent, 99 Mo, does not exist. Construction of Maple-1 and -2, two new Canadian isotope production reactors intended to replace the aging National Research Universal (NRU) reactor, has been approved in an agreement among Atomic Energy of Canada Limited, MDS Nordion, and the Canadian government. However, the project is expensive: The anticipated cost of Maple-1 and -2 is $C140 million. Outlays toward this cost have recently driven the price of 99 Mo up by 40%, even though the Canadian 99 Mo production will continue to be heavily subsidized by an interest-free construction loan. Research and development for an accelerator-based facility has been undertaken and is described

  15. Enhanced 99 Tc retention in glass waste form using Tc(IV)-incorporated Fe minerals

    Energy Technology Data Exchange (ETDEWEB)

    Um, Wooyong; Luksic, Steven A.; Wang, Guohui; Saslow, Sarah; Kim, Dong-Sang; Schweiger, Michael J.; Soderquist, Chuck Z.; Bowden, Mark E.; Lukens, Wayne W.; Kruger, Albert A.

    2017-11-01

    Technetium (99Tc) immobilization by doping into iron oxide mineral phases may alleviate the problems with Tc volatility during vitrification of nuclear waste. Reduced Tc, Tc(IV), substitutes for Fe(III) in the crystal structure by a process of Tc reduction from Tc(VII) to Tc(IV) followed by co-precipitation of Fe oxide minerals. Two Tc-incorporated Fe minerals (Tc-goethite and Tc-magnetite/maghemite) were prepared and tested for Tc retention in glass melt samples at temperatures between 600 – 1,000 oC. After being cooled, the solid glass specimens prepared at different temperatures were analyzed for Tc oxidation state using Tc K-edge XANES. In most samples, Tc was partially oxidized from Tc(IV) to Tc(VII) as the melt temperature increased. However, Tc retention in glass melt samples prepared using Tc-incorporated Fe minerals were moderately higher than in glass prepared using KTcO4 because of limited and delayed Tc volatilization.

  16. Gamma-gamma angular correlation measurement in the 100 Ru

    International Nuclear Information System (INIS)

    Kenchian, G.

    1990-01-01

    An angular correlation automatic spectrometer with two Ge(Li) detectors has been developed. The spectrometer moves automatically, controlled by a microcomputer. The gamma-gamma directional angular correlations of coincidence transitions have been measured in 100 Ru nuclide, following the β + and electron capture of 100 Rh. The 100 Rh source has been produced with 100 Ru(p,n) 100 Rh reaction, using the proton beam of the Cyclotron Accelerator insiding in 100 Ru isotope. (author)

  17. Enhanced anodic Ru(bpy)32+ electrogenerated chemiluminescence by polyphenols

    International Nuclear Information System (INIS)

    Lei Rong; Xu Xiao; Xu Da; Zhu Gang; Li Na; Liu Huwei; Li Kean

    2008-01-01

    Anodic Ru(bpy) 3 2+ electrogenerated chemiluminescence (ECL) can be enhanced by polyphenols in alkaline solution. Spin trapping-electron spin resonance (ESR) experiments verified that reactive oxygen species (ROS) were generated during the electrolysis of Ru(bpy) 3 2+ in alkaline solution, and oxidation of quercetin enhanced Ru(bpy) 3 2+ ECL at anodic potential by producing additional ROS. This ECL enhancement can be used to analyze real sample and evaluate antioxidant activity of polyphenols

  18. Several novel Ru(II) and Ru(III) complexes formed by reduction of (RuO4bipy) and (RuO3phen)2O with hydroquinone and methanol

    International Nuclear Information System (INIS)

    Ishiyama, Toshio

    1975-01-01

    The geometrical isomers, cis-dichloro-trans-(methanol)(hydroquinone)(2,2'-bipyridine)ruthenium(II) and cis-dichloro-cis-(methanol)(hydroquinone)(2,2'-bipyridine)ruthenium(II), [RuCl 2 (MeOH)(QH 2 )bipy] (complex I and II), were synthesized by reduction and substitution reactions of [RuO 4 bipy] and [RuO 2 (OH) 2 bipy] with hydroquinone in hydrochloric acid solution, and methanol. cis-Chloro(hydroquinonato)bis(2,2'-bipyridine)ruthenium(II), cis-[RuCl(QH)(bipy) 2 ], was obtained from the substitution reaction of complex I or II with 2,2'-bipyridine in methanol, and cis-chloro(hydroquinone)bis(2,2'-bipyridine)ruthenium(II) chloride, cis-[RuCl(QH 2 )(bipy) 2 ]Cl, was also obtained from the substitution of cis-trans-[RuCl 2 (MeOH)(QH 2 )bipy] in methanol containing hydrochloric acid. cis-Dihydroxobis(2,2'-bipyridine)ruthenium(II), cis-[Ru(OH) 2 (bipy) 2 ], was obtained by heating an aqueous solution of cis-[RuCl(QH)(bipy) 2 ]. Trihydroxoaquo(1,10-phenanthroline)ruthenium(III), [Ru(OH) 3 (H 2 O)phen] was also synthesized from [RuO 3 phen] 2 O and [Ru(OH) 3 phen] 2 O by reduction reactions similar to those used for [RuCl 2 (MeOH)(QH 2 )bipy]. These complexes were characterized by the infrared, visible and ultraviolet absorption spectra, and also by polarographic and magnetic measurements. The structures are discussed. (auth.)

  19. Tc depression and superconductor-insulator transition in molybdenum nitride thin films

    Science.gov (United States)

    Ichikawa, F.; Makise, K.; Tsuneoka, T.; Maeda, S.; Shinozaki, B.

    2018-03-01

    We have studied that the Tc depression and the superconductor-insulator transition (SIT) in molybdenum nitride (MoN) thin films. Thin films were fabricated by reactive DC magnetron sputtering method onto (100) MgO substrates in the mixture of Ar and N2 gases. Several dozen MoN thin films were prepared in the range of 3 nm < thickness d < 60 nm. The resistance was measured by a DC four-probe technique. It is found that Tc decreases from 6.6 K for thick films with increase of the normal state sheet resistance {R}{{sq}}{{N}} and experimental data were fitted to the Finkel’stein formula using the bulk superconducting transition temperature Tc 0 = 6.45 K and the elastic scattering time of electron τ = 1.6 × 10‑16 s. From this analysis the critical sheet resistance Rc is found about 2 kΩ, which is smaller than the quantum sheet resistance R Q. This value of Rc is almost the same as those for 2D NbN films. The value of τ for MoN films is also the similar value for NbN films 1.0 × 10‑16 s, while Tc 0 is different from that for NbN films 14.85 K. It is indicated that the mechanism of SIT for MoN films is similar to that of NbN films, while the mean free path ℓ for MoN films is larger than that for NbN films.

  20. Nonalloyed carbon-supported PtRu catalysts for PEMFC applications

    NARCIS (Netherlands)

    Papageorgopoulos, D.C.; De Heer, M.P.; Keijzer, M.; Pieterse, J.A.Z.; de Bruijn, F. A.

    2004-01-01

    PtRu(1:1)/C catalysts were prepared by a process that was claimed previously to lead to non-alloyed Pt and Ru particles, using two different precursors, Ru nitrosyl nitrate and Ru chloride hydrate. Both X-ray diffraction and characterization by cyclic voltammetry point toward Pt and Ru being present

  1. Nonalloyed carbon-supported PtRu catalysts for PEMFC applications

    NARCIS (Netherlands)

    Papageorgopoulos, D.C.; Heer, de M.P.; Keijzer, M.; Pieterse, J.A.Z.; Bruijn, de F.A.

    2004-01-01

    PtRu(1:1)/C catalysts were prepared by a process that was claimed previously to lead to nonalloyed Pt and Ru particles, using twodifferent precursors, Ru nitrosyl nitrate and Ru chloride hydrate. Both X-ray diffraction and characterization by cyclic voltammetrypoint toward Pt and Ru being present as

  2. New structural family of ternary molybdates NaA3R(MoO4)5, where A is Mg, Mn, Co or Ni and R is Al, In, Cr or Fe

    International Nuclear Information System (INIS)

    Kozhevnikova, N.M.; Kotova, I.Yu

    1998-01-01

    Ternary NaA 3 R(MoO 4 ) 5 molybdates belonging to a new structural family are produced by crystallization from melted solution and by solid-phase synthesis method. NaMg 3 In(MoO 4 ) 5 , NaNi 3 Al(MoO 4 ) 5 and NaCo 3 Al(MoO 4 ) 5 single crystals are grown. Crystallographic and thermal characteristics of NaA 3 R(MoO 4 ) 5 are determined. Structural similarities in MgMoO 4 , NaIn(MoO 4 ) 2 , Na 2 Mg(MoO 4 ) 6 and NaA 3 R(MoO 4 ) 5 series are revealed [ru

  3. Development of production of {sup 99}Mo from LEU target

    Energy Technology Data Exchange (ETDEWEB)

    Adang, H G; Mutalib, A; Lubis, H [Radioisotope Production Centre, National Atomic Energy Agency, Kawasan Puspiptek, Serpong (Indonesia); and others

    1998-10-01

    {sup 99}TC, the most popular radioisotope in nuclear medicine, is daughter of {sup 99}Mo. {sup 99}Mo is produced in research reactor by irradiating of high enriched uranium (HEU). However, in recent year, strict regulation that has been implemented by USA DOE and NPT has led to the difficulty in getting HEU. Therefore, BATAN has tried to develop the production of {sup 99}Mo by using low enriched uranium (LEU). The research involves the use of LEU in the production of {sup 99}Mo. This research was started in 1994 by joint-research between BATAN and Argonne National Laboratory USA. This program is divided into three research groups. The first group emphasizes its research on fabrication of LEU foil that is going to be irradiated. The second group studies the irradiation`s aspects and physical characteristic of irradiated LEU foils. The third group studies the radiochemical separation process of fission product {sup 99}Mo from solution of irradiated LEU foils. There are five steps that are carried out in studying of radiochemical separation of {sup 99}Mo from irradiated LEU. First is designing a dissolver that is going to be used in dissolving of LEU foil and testing its reliability. Second is dissolving LEU in the new design dissolver. Third is evaluation the modified of Cintichem`s radiochemical separation process of {sup 99}Mo from LEU. Forth is modifying the Cintichem`s radiochemical separation process of {sup 99}Mo from the solution of irradiated LEU. And fifth is using the modified of Cintichem`s radiochemical separation process for separation {sup 99}Mo from solution of irradiated LEU. The first through the forth steps of experiments were already carried out and will be reported in this workshop, whereas the fifth step of experiment is going to be conducted in February 1998. (author)

  4. Dependence of the quasiparticle recombination rate on the superconducting gap and TC

    Science.gov (United States)

    Carr, G. L.; Xi, Xiaoxiang; Hwang, J.; Tashiro, H.; Reitze, D. H.; Tanner, D. B.

    2010-03-01

    The relaxation of excess quasiparticles in a BCS superconductor is known to depend on quantities such as the quasiparticle & phonon density of states, and their coupling (Kaplan et al, Phys. Rev. B 14 4854, 1976). Disorder or an applied field can disrupt superconductivity, as evidenced by a reduced TC. We consider some simple modifications to the quasiparticle density of states consistent with a suppressed energy gap and TC, leading to changes in the intrinsic and effective (measured) rates for excess quasiparticles to recombine into pairs. We review some results for disordered MoGe and discuss the magnetic-field dependence of the recombination process.

  5. High-Tc superconductor applications

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

    There has been much speculation about new products and business opportunities which high-Tc superconductors might make possible. However, with the exception of one Japanese survey, there have not been any recognized forecasts suggesting a timeframe and relative economic impact for proposed high-Tc products. The purpose of this survey is to provide definitive projections of the timetable for high-Tc product development, based on the combined forecasts of the leading U.S. superconductivity experts. The FTS panel of experts on high-Tc superconductor applications, representing both business and research, forecast the commercialization and economic impact for 28 classes of electronic, magnetic, communications, instrumentation, transportation, industrial, and power generation products. In most cases, forecasts predict the occurrence of developments within a 90% statistical confidence limit of 2-to-3 years. The report provides background information on the 28 application areas, as well as other information useful for strategic planners. The panel also forecast high-Tc research spending, markets, and international competitiveness, and provide insight into how the industry will evolve

  6. GASIFICATION TEST RUN TC06

    Energy Technology Data Exchange (ETDEWEB)

    Southern Company Services, Inc.

    2003-08-01

    This report discusses test campaign TC06 of the Kellogg Brown & Root, Inc. (KBR) Transport Reactor train with a Siemens Westinghouse Power Corporation (Siemens Westinghouse) particle filter system at the Power Systems Development Facility (PSDF) located in Wilsonville, Alabama. The Transport Reactor is an advanced circulating fluidized-bed reactor designed to operate as either a combustor or a gasifier using a particulate control device (PCD). The Transport Reactor was operated as a pressurized gasifier during TC06. Test run TC06 was started on July 4, 2001, and completed on September 24, 2001, with an interruption in service between July 25, 2001, and August 19, 2001, due to a filter element failure in the PCD caused by abnormal operating conditions while tuning the main air compressor. The reactor temperature was varied between 1,725 and 1,825 F at pressures from 190 to 230 psig. In TC06, 1,214 hours of solid circulation and 1,025 hours of coal feed were attained with 797 hours of coal feed after the filter element failure. Both reactor and PCD operations were stable during the test run with a stable baseline pressure drop. Due to its length and stability, the TC06 test run provided valuable data necessary to analyze long-term reactor operations and to identify necessary modifications to improve equipment and process performance as well as progressing the goal of many thousands of hours of filter element exposure.

  7. LEU{sub b}ased Fission Mo-99 Process with Reduced Solid Wastes

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Seungkon; Lee, Suseung; Jung, Sunghee; Hong, Soonbog; Jang, Kyungduk; Choi, Sang Mu; Lee, Jun Sig; Lim, Incheol [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    {sup 99m} Tc emits 140 keV of very low gamma-ray radiation energy, as low as conventional diagnostic X-ray, and has short half-life of 6.0058 hours. Therefore, as radioactive tracer, {sup 99m} Tc provides high quality diagnostic images but keeps total patient radiation exposure low. Depending on the tagging pharmaceuticals and procedures, {sup 99m} Tc can be applied for the diagnostics of various target organs and diseases: brain, myocardium, thyroid, lungs, liver, gallbladder, kidneys, skeleton, blood and tumors. More than 95% of {sup 99}Mo is produced through fission of {sup 235}U worldwide because, {sup 99m}o generated from the fission (fission {sup 99}Mo) exhibits very high specific activity (<100 Ci/g). Over 90% of fission {sup 99}Mo producers have been used highly enriched uranium (HEU) targets so far. However, the IAEA recommends the use of low enriched uranium (LEU) to the {sup 99}Mo producers for nonproliferation reason. These days, worldwide {sup 99}Mo supply is not only insufficient but also unstable. Because, most of the main {sup 99}Mo production reactors are about 50 years old and suffered from frequent and unscheduled shutdown. Planned weekly productivity of 2000 Ci fission {sup 99}Mo, in a 6-day reference, will cover 100% domestic demand of Korea, as well as 20% of international market. It is expected to replace 4.3 million USD ($800/Ci) of {sup 99}Mo import for domestic market while exporting 82.8 million USD for world market, annually.

  8. NMR and XAS Study of Fe-Mo Double Perovskites

    International Nuclear Information System (INIS)

    Zajac, D.A.; Kapusta, C.; Borowiec, M.; Sikora, M.; Marquina, C.; Blasco, J.; Ibarra, M.R.

    2005-01-01

    The results of NMR and XAS measurements of the A 2 FeMoO 6 double perovskites (DP) (A 2 =Sr 2 , SrBa, Ba 2 , Ca 2 ) at the Fe and Mo K edges are reported and the information on the individual site electronic and magnetic properties is analysed. The compounds studied belong to the family of materials exhibiting a high field '' colossal '' magnetoresistance as well as a low field '' giant '' magnetoresistance. Magnetoresistive properties of the compounds arise from their half-metallicity, i.e. only one spin direction being populated in the conduction band, which consists of overlapping spin down 3d Fe, 2p O and 4d Mo electron bands. Within the model, a spin-down electron undergoes a fast hopping through unoccupied oxygen 2p orbitals between Fe 3+ (3d 5 - spin up) and Mo 6+ (4d 0 ) ionic cores. This mechanism implicates an anti-parallel coupling of the Fe and Mo spins and leads to non-integer magnetic moments and a metallic character below TC. The interaction, in analogy with the '' double exchange '' (DE) in manganites, is called '' double exchange-like '' interaction. The superexchange interaction (SE) is also expected to be present, resulting also in an anti-parallel coupling of 3d Fe 3+ and 4d Mo 5+ spins through occupied oxygen 2p orbitals. The insulating character of SE is connected with an increase of the tilt angle of the Fe-O-Mo bond, which is related to a change of the structural tolerance factor f and results in structural distortions. The molybdenum NMR measurements revealed the existence of a non-integer magnetic moment at Mo and Fe, which can be attributed to the DE-like interaction. However, experiments using Moessbauer spectroscopy have shown the existence of two Fe ionisation states - with integer (SE) and non integer (DE) magnetic moments. The 95 Mo and 97 Mo NMR measurements on A 2 FeMoO 6 (A 2 =Sr 2 , SrBa, Ba 2 , Ca 2 ) presented in this work show different values of the Mo hyperfine field and the corresponding magnetic moment. This is attributed

  9. 103Ru/103mRh generator

    International Nuclear Information System (INIS)

    Bartos, B.; Kowalska, E.; Bilewicz, A.; Skarnemark, G.

    2009-01-01

    103m Rh is a very promising radionuclide for Auger electron therapy due to its very low photon/electron ratio. The goal of the present work was the elaboration a method for production of large quantities of 103m Rh for generator system. It was found that the combination of solvent extraction with evaporation of 103 RuO 4 followed by decomposition of H 5 IO 6 makes it possible to produce 103m Rh of high radionuclidic and chemical purity. (author)

  10. In situ Ru K-edge EXAFS of CO adsorption on a Ru modified Pt/C fuel cell catalyst

    International Nuclear Information System (INIS)

    Rose, Abigail; Bilsborrow, Robert; King, Colin R.; Ravikumar, M.K.; Qian Yangdong; Wiltshire, Richard J.K.; Crabb, Eleanor M.; Russell, Andrea E.

    2009-01-01

    The Ru-CO bond of CO adsorbed on a Ru modified Pt/C fuel cell catalyst has been directly probed by in situ EXAFS at the Ru K-edge, providing evidence of a CO:metal surface atom ratio greater than 1:1 and that CO is adsorbed at bridging sites associated with Ru atoms at the surface of the catalyst nanoparticles. This result illustrates the limitations of single crystal models as representations of the bonding of adsorbed species at nanoparticle surfaces.

  11. In-depth study of the H - T phase diagram of Sr4Ru3O10 by magnetization experiments

    Science.gov (United States)

    Weickert, F.; Civale, L.; Maiorov, B.; Jaime, M.; Salamon, M. B.; Carleschi, E.; Strydom, A. M.; Fittipaldi, R.; Granata, V.; Vecchione, A.

    2018-05-01

    We present magnetization measurements on Sr4Ru3O10 as a function of temperature and magnetic field applied perpendicular to the magnetic easy c-axis inside the ferromagnetic phase. Peculiar metamagnetism evolves in Sr4Ru3O10 below the ferromagnetic transition TC as a double step in the magnetization at two critical fields Hc1 and Hc2. We map the H - T phase diagram with special focus on the temperature range 50 K ≤ T ≤TC . We find that the critical field Hc1 (T) connects the field and temperature axes of the phase diagram, whereas the Hc2 boundary starts at 2.8 T for the lowest temperatures and ends in a critical endpoint at (1 T; 80 K). We conclude from the temperature dependence of the ratio Hc 1/Hc 2 (T) that the double metamagnetic transition is an intrinsic effect of the material and it is not caused by sample stacking faults such as twinning or partial in-plane rotation between layers.

  12. Q values of the 76Ge and 100Mo double-beta decays

    International Nuclear Information System (INIS)

    Rahaman, S.; Elomaa, V.-V.; Eronen, T.; Hakala, J.; Jokinen, A.; Julin, J.; Kankainen, A.; Saastamoinen, A.; Suhonen, J.; Weber, C.; Aystoe, J.

    2008-01-01

    Penning trap measurements using mixed beams of 76 Ge- 76 Se and 100 Mo- 100 Ru have been utilized to determine the double-beta decay Q-values of 76 Ge and 100 Mo with uncertainties less than 200 eV. The value for 76 Ge, 2039.04(16) keV is in agreement with the published SMILETRAP value, 2039.006(50) keV. The new value for 100 Mo, 3034.40(17) keV is 30 times more precise than the previous literature value, sufficient for the ongoing neutrinoless double-beta decay searches in 100 Mo. Moreover, the precise Q-value is used to calculate the phase-space integrals and the experimental nuclear matrix element of double-beta decay

  13. Los Alamos National Laboratory Support for Commercial U.S. Production of 99Mo without the Use of Highly Enriched Uranium

    Energy Technology Data Exchange (ETDEWEB)

    Dale, Gregory E. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-03-04

    There is currently a serious shortage of 99Mo, from which to generate the medically significant isotope 99mTc. Most of the world's supply comes from the fission of highly enriched uranium targets--this is a proliferation concern. This document focuses on the technology involved in two alternative methods: electron accelerator production of 99Mo from the 100Mo(γ,n)99Mo reaction and production of 99Mo as a fission product in a subcritical, DT accelerator-driven low enriched uranium salt solution.

  14. Technology of the sup(99m)Tc generator, Elumatic III made by Commissariat a l'Energie Atomique, France

    International Nuclear Information System (INIS)

    Le Bris, H.; Pasqualini, R.; Reboul, J.

    1982-01-01

    The article describes the choices leading to the development of an ''integrated'' 99 Mo-sup(99m)Tc generator meeting the following requirements: (a) total activity eluted in a volume of 5 ml; (b) adequate radioprotection both for the user and the manufacturer; (c) injectable eluate. (author)

  15. Temperature- and pressure-dependent lattice behaviour of RbFe(MoO4)(2)

    DEFF Research Database (Denmark)

    Waskowska, A.; Gerward, Leif; Olsen, J. S.

    2010-01-01

    Trigonal RbFe(MoO4)(2) is a quasi-two-dimensional antiferromagnet on a triangular lattice below T-N = 3.8 K, The crystal exhibits also a structural phase transition at T-c = 190 K related to symmetry change from Pm1 to P. We present the temperature-and pressure-dependent characteristics...

  16. MoEDAL expands

    CERN Multimedia

    Anaïs Schaeffer

    2011-01-01

    The MoEDAL collaboration deployed a test array of 18 plastic Nuclear Track Etch Detector (NTD) stacks – covering an area of 1 m2 – in the MoEDAL/VELO cavern at Point 8 of the LHC ring in November 2009. This small array was supplemented by a further 110 stacks this past January. The MoEDAL test array, which now covers an area of 8 m2, will reveal its secrets early in 2013. The full MoEDAL detector will be installed in the next long shutdown of the LHC in 2013.   View of the MoEDAL detectors installed at Point 8 of the LHC ring in January 2011. MoEDAL (Monopole and Exotics Detector At the LHC), the seventh LHC experiment, was approved by the CERN Research Board at the end of 2009. Its goal is to search for very specific exotics such as highly ionising massive stable (or pseudo-stable) particles with conventional electrical charge and magnetic monopoles. “The main LHC experiments are designed to detect conventionally charged particles, with conventional ionisation patte...

  17. Studies on sup(99m)Tc-pertechnetate from the MEK solvent extraction generator

    International Nuclear Information System (INIS)

    Mohammad, R.; Moore, D.E.; Maddalena, D.J.; Boyd, R.E.

    1984-12-01

    Analysis by gas chromatography-mass spectrometry and high performance liquid chromatography has revealed organic residues in sup(99m)Tc-pertechnetate obtained from 99 Mo-molybdate by extraction, using the organic solvent methylethylketone (MEK). The organic residues have been identified as either (i) low molecular weight carbonyl compounds such as formaldehyde, acetaldehyde and acetone, presumably caused by the effects of γ-radiation on MEK, or (ii) condensation products resulting from the action of strong alkali on MEK during the extraction process. The quantities of organic residues varied from batch to batch of extracted pertechnetate; up to 40 μ mL -1 was found. When these compounds were tested, in rats, by addition to a pyrophosphate bone-seeking radiopharmaceutical, the tissue distribution was not significantly different from that in the control, which contained no added compound. Assay for 99 Tc in MEK-derived pertechnetate indicated up to 10 μg mL -1 of 99 Tc carrier. An assessment of the biological effect of 99 Tc carrier was obtained by (i) red blood cell labelling, where 6 ng mL -1 of 99 Tc was sufficient to reduce labelling efficiency; and (ii) pyrophosphate tissue distribution, where a significant effect was obtained in the presence of 10 μ mL -1 of 99 Tc carrier

  18. Supercapacitive performance of hydrous ruthenium oxide (RuO2 ...

    Indian Academy of Sciences (India)

    2016-08-26

    SO4 electrolyte. RuO2.H2O film showed maximum specific capacitance of 192 F.g-1 at a scan rate of 20 mV.s-1. The charge–discharge studies of RuO2.H2O carried out at 300 A.cm-2 current density revealed the specific ...

  19. NOVEL RU-NI-S ELECTRODE CATALYST FOR PEMFC

    Science.gov (United States)

    The expected results from this project include: a new formula and preparation procedures for Ru-Ni-S catalyst; demonstration of CO and S tolerance of the new catalyst; a small size PEMFC with Ru-Ni-S catalyst and good performance; an...

  20. bond activation and catalysis by Ru -pac complexes

    Indian Academy of Sciences (India)

    and their reactivity towards oxidation of a few organic compounds. Keywords. Kinetics; catalysis; -O–O- bond activation; Ru-pac complex; oxidation. 1. Introduction. Ru-pac complexes exhibit catalytic properties,1 in homogeneous conditions in the presence of oxygen atom donors, that mimic the biological enzymatic oxi-.

  1. Comparative study on catalytic behavior of polynuclear Mg-Mo-complex and FeMo-co-factor of nitrogenase in reactions with C2H2, N2 and CO

    International Nuclear Information System (INIS)

    Bardina, N.V.; Bazhenova, T.A.; Petrova, G.N.; Shilova, A.K.; Shilov, A.E.

    2006-01-01

    Catalytic reduction kinetics of C 2 H 2 in the presence of the Mg-Mo-cluster {[Mg 2 Mo 8 O 22 (MeO) 6 (MeOH) 4 ] 2- [Mg(MeOH) 6 ] 2+ }·6MeOH 1 is studied. Several interdependent coordinating centers are active in reference to substrates and inhibitors in the polynuclear Mg-Mo-complex, as in the reduced by europium amalgam (μ 6 -N)MoFe 7 S 9 ·homocitrate (FeMoco, 2). Comparison of regularities in reduction mechanism of C 2 H 2 , N 2 and CO with the participation of synthetic polynuclear complex 1 and natural cluster 2 is conducted. Regularities of the studied reactions in the systems involving natural catalytic cluster FeMoco and the synthetic Mg-Mo-complex modelling of its effect are noted to be similar. The main variations the systems show as regards to the reaction with molecular nitrogen [ru

  2. High-Density Stacked Ru Nanocrystals for Nonvolatile Memory Application

    International Nuclear Information System (INIS)

    Ping, Mao; Zhi-Gang, Zhang; Li-Yang, Pan; Jun, Xu; Pei-Yi, Chen

    2009-01-01

    Stacked ruthenium (Ru) nanocrystals (NCs) are formed by rapid thermal annealing for the whole gate stacks and embedded in memory structure, which is compatible with conventional CMOS technology. Ru NCs with high density (3 × 10 12 cm −2 ), small size (2–4 nm) and good uniformity both in aerial distribution and morphology are formed. Attributed to the higher surface trap density, a memory window of 5.2 V is obtained with stacked Ru NCs in comparison to that of 3.5 V with single-layer samples. The stacked Ru NCs device also exhibits much better retention performance because of Coulomb blockade and vertical uniformity between stacked Ru NCs

  3. Two crystalline modifications of RuO4

    International Nuclear Information System (INIS)

    Pley, Martin; Wickleder, Mathias S.

    2005-01-01

    RuO 4 was prepared by oxidation of elemental ruthenium. Two different modifications were obtained and investigated by X-ray single crystal diffraction. RuO 4 -I has cubic symmetry (P4; - 3n,Z=8,a=8.509(1)A), and two independent tetrahedral molecules are present in the unit cell. Within the standard uncertainties in both molecules the distances Ru-O are 1.695A. The second modification, RuO 4 -II, is monoclinic (C2/c,Z=4,a=9.302(4)A,b=4.3967(10)A,c=8.454(4)A,β=116.82(3) o ) and isotypic with OsO 4 . There is one independent molecule in the unit cell, which shows distances Ru-O of 1.697 and 1.701A, respectively

  4. Tc-99m imaging agents

    International Nuclear Information System (INIS)

    Weininger, J.; Trumper, J.

    1984-01-01

    A wide range of pharmaceuticals for labeling with Tc-99m, developed by the Soreq Radiopharmaceuticals Department, is described. Details of the production and quality control of 13 kits are given, as well as the range of results required for consistently high quality imaging agents

  5. Ru486: del aborto químico a la contracepción de emergencia

    Directory of Open Access Journals (Sweden)

    Lucio Romano

    2009-06-01

    Full Text Available El uso del mifepriston (RU486, en combinación con análogos de las prostaglandinas, en la inducción del aborto químico requiere una específica reflexión en relación a los principales aspectos farmacológicos y toxicológicos. La actual dialéctica bioética y biopolítica, a menudo ideologizada, impone aún más un tratamiento riguroso basado en evidencias científicas, para aclarar sobre todo los mecanismos de acción y de los eventos adversos. Estos últimos a veces también subvalorados o minimizados. Considerada la iniquidad del aborto voluntario, el artículo se propone también el objetivo de aclarar cómo, a la luz de una reciente bibliografía, el recurso al RU486 representa un significativo riesgo para la salud de las mujeres. Una particular atención está reservada a la aclaración etiopatogenética de las hemorragias y de las sepsis, en las cuales se han evidenciado también distintos decesos. En el artículo están presentes, además, los más actuales desarrollos de la investigación con RU486 sea para el tratamiento experimental de patologías –ginecológicas y no– como para el uso de la molécula de la contracepción hormonal y la “contracepción de emergencias”.

  6. Magnetic, electrical and structural properties of the Re-doped ruthenocuprate Ru1−xRexSr2GdCu2Oy

    International Nuclear Information System (INIS)

    Corredor, L.T.; Albino Aguiar, J.; Landínez Téllez, D.A.; Pureur, P.; Mesquita, F.; Roa-Rojas, J.

    2015-01-01

    Highlights: • We investigated the effect of the dilution of magnetic Ru sub-lattice of RuSr 2 GdCu 2 O 8 . • We synthesized the doped compound Rui x Re x Sr 2 GdCu 2 O y , for 3%, 6%, 9% and 12% Re. • Re would affect the electron coupling: just 3 and 6% samples were superconductor. • Superconductivity emergence strongly affects magnetic properties of 3 and 6% samples. • A weak ferromagnetic component is consistent with a globally antiferromagnetic system. - Abstract: Despite the discovery of new superconductors classes, high-Tc oxides continue to be a current topic, because of their complex phase diagrams and doping-dependant effects (allowing one to investigate the interaction between orbitals), as well as structural properties such as lattice distortion and charge ordering, among many others. Ruthenocuprates are magnetic superconductors in which the magnetic transition temperature is much higher than the critical superconducting temperature, making them unique compounds. With the aim of investigating the dilution of the magnetic Ru sub-lattice, we proposed the synthesis of the Ru 1−x Re x Sr 2 GdCu 2 O y ruthenocuprate-type family, adapting the known two-step process (double perovskite + CuO) by directly doping the double perovskite, thus obtaining the perovskite compound Sr 2 GdRu 1−x Re x O y , which represents a new synthesis process to the best of our knowledge. Our samples were structurally characterized through X-ray diffraction, and the patterns were analysed via Rietveld refinement. A complete magnetic characterization as a function of temperature and applied field, as well as transport measurements were carried out. We discuss our results in the light of the two-lattice model for ruthenocuprates, and a relation between RuO 2 (magnetic) and CuO 2 (superconductor) sub-lattices can clearly be observed

  7. Interaction in the NaIn(MoO4)2 - AMoO4 (A = Mg, Mn) systems

    International Nuclear Information System (INIS)

    Kotova, I.Yu.; Kozhevnikova, N.M.

    2001-01-01

    The results of investigation into NaIn(MoO 4 ) 2 - AMoO 4 (A = Mg, Mn) quasibinary cross-sections by means of X-ray diffraction and differential thermal analysis are presented. Conducted researches revealed that compounds NaMg 3 In(MoO 4 ) and NaMn 3 In(MoO 4 ) melting incongruently at 990 Deg C and 940 Deg C accordingly were formed in the NaIn(MoO 4 ) - AMoO 4 (A = Mg, Mn) systems. The data of initiation of X-ray diffraction pattern of NaMg 3 In(MoO 4 ) 5 are presented. The temperature dependences of conductivity, dielectric permeability and tangent of dielectric losses indicative on ionic-electronic nature conductivity are determined. Activation energy of conductivity in the Mg - Mn row changes moderately - from 9.91 till 5.71 eV [ru

  8. Methanol electro-oxidation on Pt-Ru-P/C and Pt-Ru-P/MWCNT in acidic medium

    CSIR Research Space (South Africa)

    Modibedi, M

    2009-06-01

    Full Text Available . The electro-catalytic activity towards methanol oxidation in acidic medium was studied by cyclic voltammetry and linear sweep voltammetry. Pt-Ru-P/MWCNT showed excellent activity compared to that of Pt-Ru-P/C. This may be attributed to the effectiveness...

  9. Our experience with B.A.R.C. sup(99m)Tc generator

    International Nuclear Information System (INIS)

    Padmanabhan, V.; Pandurengan, N.; Lakshmanan, A.V.

    1980-01-01

    sup(99m)Tc has been eluted from its parent 99 Mo by solvent extraction method. It is pointed out that there is considerable variation in the eluted activity in day to day practice and any administration of the isotope to the patient must be measured in an isotope calibrator. Operator dose levels have been recorded which are quite within the permissible levels. (auth.)

  10. Tc7, a Tc1-hitch hiking transposon in Caenorhabditis elegans.

    OpenAIRE

    Rezsohazy, R; van Luenen, H G; Durbin, R M; Plasterk, R H

    1997-01-01

    We have found a novel transposon in the genome of Caenorhabditis elegans. Tc7 is a 921 bp element, made up of two 345 bp inverted repeats separated by a unique, internal sequence. Tc7 does not contain an open reading frame. The outer 38 bp of the inverted repeat show 36 matches with the outer 38 bp of Tc1. This region of Tc1 contains the Tc1-transposase binding site. Furthermore, Tc7 is flanked by TA dinucleotides, just like Tc1, which presumably correspond to the target duplication generated...

  11. Oxidation study of Cr-Ru hard coatings

    Energy Technology Data Exchange (ETDEWEB)

    Chen, Yung-I, E-mail: yichen@mail.ntou.edu.tw; Kuo, Yu-Chu; Chen, Sin-Min

    2012-01-01

    Cr-Ru alloy coatings with Cr content ranging from 47 to 83 at.% were deposited at 400 Degree-Sign C by direct current magnetron co-sputtering with a Ti interlayer on silicon substrates. With a total input power of 300 W, the Cr content in the Cr-Ru coatings increased linearly with the increasing input power of Cr. The intermetallic compound phase Cr{sub 2}Ru with columnar structure was identified for the as-deposited Cr{sub 56}Ru{sub 44} and Cr{sub 65}Ru{sub 35} coatings, resulting in an increase of hardness up to 15-16 GPa. To evaluate the performance of Cr-Ru coatings as a protective coating on glass molding dies, the annealing treatment was conducted at 600 Degree-Sign C in a 50 ppm O{sub 2}-N{sub 2} atmosphere. The outward diffusion and preferential oxidization of Cr in the Cr-Ru coatings resulted in the variations of the crystalline structure, chemical composition distribution, and surface hardness after annealing. X-ray diffraction and transmission electron microscopy (TEM) proved that an oxide scale consisting of Cr{sub 2}O{sub 3} formed on the free surface. Scanning electron microscopy and TEM observed the surface morphology and structural variation. The chemical composition depth profiles were analyzed by Auger electron microscopy, verifying the presence of a Cr-depleted zone beneath the oxide scale. The hardness of Cr{sub 56}Ru{sub 44} and Cr{sub 65}Ru{sub 35} coatings decreased to 11-12 GPa after annealing, accompanied by the replacement of the Cr{sub 2}Ru phase by the Ru phase. - Highlights: Black-Right-Pointing-Pointer We prepared crystalline Cr-Ru alloy coatings by direct current magnetron sputtering. Black-Right-Pointing-Pointer Cr-Ru coatings were annealed at 600 Degree-Sign C for 2 h in a 50 ppm O{sub 2}-N{sub 2} atmosphere. Black-Right-Pointing-Pointer Cr diffused outwardly and oxidized to form a stable and protective oxide scale. Black-Right-Pointing-Pointer The original columnar grains recrystallized to polycrystalline grains.

  12. APPLIED SCIENTOMETRICS: ELIBRARY.RU VS GOOGLE

    Directory of Open Access Journals (Sweden)

    А В Юрков

    2015-12-01

    Full Text Available The practical issues associated with searching reliable information about the publication activity of Russian scientist are discussed in the article. The examples in [1] show that the effective solution of this problem requires the using of different scientometric services: both the domestic eLIBRARY.RU and its Russian Science Citation Index, and the Google Scholar as an alternative. At the time the work is published comparison was not in favor of the domestic resource. However, due to the RSCI project within a short period the eLibrary’s tools for building database of scientific publications have grown significantly and the opportunities to improve the quality of scientometric information become real. The article gives the examples.

  13. Single hole spectroscopic strength in 98Ru through the 99Ru(d,t) reaction

    International Nuclear Information System (INIS)

    Rodrigues, M.R.D.; Borello-Lewin, T.; Horodynski-Matsushigue, L.B.; Duarte, J.L.M.; Rodrigues, C.L.; Barbosa, M.D.L.; Silva, G.B. da; Ukita, G.M.

    2002-01-01

    The 99 Ru(d,t) 98 Ru reaction was measured for the first time at 16 MeV incident energy with the Sao Paulo Pelletron-Enge-spectrograph facility employing the nuclear emulsion technique. In all, up to 3.5 MeV, 23 levels were detected, eight of them new; angular distributions are presented for all of them. Least squares fits of distorted wave Born approximation one-neutron pickup predictions to the rather well structured experimental angular distributions enabled the determination of l transfers and of the corresponding spectroscopic factors for 19 of these states, some being tentative attributions. Only transfers of l=0, 2, and 4 were observed. Several states were populated through single l transfers. A pure l=2 transfer is associated with the 2 1 + level and with several other states which are considered collective, as well as with the (4 + ) state at 2.277 MeV, which presents the highest spectroscopic strength. Considering five valence neutrons above the N=50 core, only 41% of the spectroscopic strength expected for 99 Ru was detected

  14. Proton-fission for the accelerator production of Mo-99

    International Nuclear Information System (INIS)

    Lagunas-Solar, M.C.; Jungerman, J.A.; Castaneda, C.M.

    1993-01-01

    The production of Mo-99 (66.0 h) via de U-238(p,f) Mo-99 fission reaction is proposed as a non-reactor source of this essential precursor of 6.6-h Tc-99m, an isotope of wide use of diagnostic nuclear medicine applications. Measurements of the total excitation function for the U-238(p,f) reaction indicated a maximum and fairly constant cross section of 1.4 barns at > 30 MeV. Combining the advances of high-current (mA) H-accelerators with dual beam (dual target) operation, and assuming a 5% fission yield, estimates of Mo-99 reaches 5 to 14 Ci/h at 1 mA. The proton fission production of Mo-99 appears to more advantageous than the reactor produced via evaporation neutron-induced fission. An accelerator method could allow securing ample supply of Mo-99 independently of the current scarce reactor operation, while also simplifying the associated waste management problems as well as some of the environmental concerns

  15. Enhanced99Tc retention in glass waste form using Tc(IV)-incorporated Fe minerals

    OpenAIRE

    Um, W; Luksic, SA; Wang, G; Saslow, S; Kim, DS; Schweiger, MJ; Soderquist, CZ; Bowden, ME; Lukens, WW; Kruger, AA

    2017-01-01

    © 2017 Elsevier B.V. Technetium ( 99 Tc) immobilization by doping into iron oxide mineral phases may alleviate the problems with Tc volatility during vitrification of nuclear waste. Because reduced Tc, Tc(IV), substitutes for Fe(III) in the crystal structure by a process of Tc reduction from Tc(VII) to Tc(IV) followed by co-precipitation of Fe oxide minerals, two Tc-incorporated Fe minerals (Tc-goethite and Tc-magnetite/maghemite) were prepared and tested for Tc retention in glass melt sample...

  16. Magnesium-molybdenum compounds as matrixes of {sup 99m} Tc generators; Compuestos de magnesio-molibdeno como matrices de generadores de {sup 99m} Tc

    Energy Technology Data Exchange (ETDEWEB)

    Jimenez M, T S

    2005-07-01

    In order to finding new production alternatives of {sup 99}Mo/ {sup 99m}Tc generators, easy to produce and with high elutriation efficiencies, it is proposed in this work to develop a generator with basis of magnesium and molybdenum that could be irradiated after their synthesis, given the short half life of the only radioisotope produced by the magnesium: {sup 27} Mg (t{sub 1/2} = 9.46 m). It is necessary to mention that have not been reported works in relation to this type of compound, being then important to carry out basic studies on the formation and behavior of these in relation to their matrix functions of those generated of {sup 99} Mo/ {sup 99m} Tc. In this work it was determined the effect that has, the magnesium salt used in the synthesis of those molybdenum-magnesium compounds, the molar ratio Mo: Mg, the concentration of the magnesium salt, the pH of the used ammonium molybdates in the synthesis of the final compounds and the washing of the molybdates of synthesized magnesium, in the performance of the {sup 99} Mo/ {sup 99m} Tc generators. Parameters like the elutriation efficiency, the radionuclide purity, radiochemical and chemical of the eluates and their pH, were determined in each case, also its were characterized the synthesized compounds using: neutron activation analysis (NAA), X-ray diffraction (XRD) and scanning electron microscopy of high vacuum (SEM), besides of complementary techniques: infrared spectroscopy (IR), and thermal gravimetric analysis (TGA). (Author)

  17. Home brew technetium : clinical scale desktop plasma fusion neutron source to produce Tc99m as an alternative to industrial scale fission reactor sources

    International Nuclear Information System (INIS)

    Bosi, S.G.; Khachan, J.; Oborn, B.M.

    2011-01-01

    Full text: Tc-99m (decay product of Mo-99) accounts for ∼ 90% of world's production of radiopharmaceuticals. Recent unexpected shutdowns of two fission reactors and routine maintenance closures .e created a global shortage of Tc-99m, hence the large global effort to find alternative sources. This project aims to design and produce a novel prototype Mo-99/Tc-99m source. An operational desktop neutron source is available at the University of Sydney, employing a deuterium fusion-plasma to create 2.45 MeV neutrons. These neutrons will be used to activate Mo-98 thin an activation vessel. In one embodiment, the activation vessel contains an aqueous slurry or gel containing Mo-98 which converts to 0-99 upon activation. The decay product Tc-99m could then be milked, similar to existing Tc-99m generators. Monte Carlo will be :ed to assess yield versus size and geometry for various vessel designs. The neutron source filled with deuterium operating at 250 W, produces 3 x 106 neutrons continuously. The neutron flux can be increased ∼ 100-fold if the fill gas is 50% tritium and by another ∼ 100-1000-fold by increasing the power. This is being designed for local use, perhaps on the scale f one or a few hospitals, so the yield would not need to be industrial ;ale as with fission reactor sources. This device is low cost <$300 K) compared with cyclotrons and fission reactors.

  18. Status of the study on PZC based Tc-99m generator and potential of its commercial production in VIETNAM

    International Nuclear Information System (INIS)

    Dong, Duong Van

    2007-01-01

    Tc-99m is the most widely used radioisotope in nuclear medicine. It has been almost produced from the decay of its parent 99 Mo by using the (n,γ) nuclear reaction with natural molybdenum. The technology requirement for this processing is simple, and is used in the most developing countries operating research reactor. Under the framework of Forum for Nuclear Cooperation in Asia (FNCA) cooperation program, the PZC based technology for production of Tc-99m generator has been studied at Dalat Nuclear Research Institute (DNRI) in the past several years. Some main activities and results of the study on PZC based Tc-99m generator at DNRI so far are given, and the estimation of future applications of PZC-type Tc-99m generator in Vietnam is also discussed in this report. (author)

  19. Neutronic analysis for the fission Mo99 production by irradiation of leu targets in TRIGA 14 MW reactor

    International Nuclear Information System (INIS)

    Dulugeac, S. D.; Mladin, M.; Budriman, A. G.

    2013-01-01

    Molybdenum production can be a solution for the future in the utilization of the Romanian TRIGA, taking into account the international market supply needs. Generally, two different techniques are available for Mo 99 production for use in medical Tc 99 generation.The first one is based on neutron irradiation of molybdenum targets of natural isotopic composition or enriched in Mo 98 . In a second process, Mo 99 is obtained as a result of the neutron induced fission of U 235 according to U 235 (n,f) Mo 99 . The objectives of the paper are related to Mo 99 production as a result of fission. Neutron physics parameters are determined and presented, such as: thermal flux axial distribution for the critical reactor at 10 MW inside the irradiation location; reactivity introduced by three Uranium foil containers; neutron fluxes and fission rates in the Uranium foils; released and deposited power in the Uranium foils; Mo 99 activity in the Uranium foils. (authors)

  20. Quatenary Na//F, Cl, CO3, MoO4 system

    International Nuclear Information System (INIS)

    Kochkarov, Zh.A.; Lok''yaeva, S.M.; Shurdumov, G.K.; Gasanaliev, A.M.; Trunin, A.S.

    1999-01-01

    Perspective in applied respect quatenary system (NaF) 2 -(NaCl)-Na 2 CO 3 -Na 2 MoO 4 being element of narrowing of more complex six-membered mutual Na//F, Cl, CO 3 , MoO 4 (WO 4 ) system is investigated by differential thermal analysis with the use of projection-thermographic method for the first time. Crystallization tree of Na//F, Cl, CO 3 , MoO 4 system is established. It is shown that this system by tetrahedrating (NaF) 2 -Na 2 CO 3 -Na 3 ClMoO 4 section is triangulated on two stable system: (NaF) 2 -Na 3 ClMoO 4 -Na 2 CO 3 -(NaCl) 2 and (NaF) 2 -Na 3 ClMoO 4 -Na 2 CO 3 -Na 2 MoO 4 . Phase single units are determined too. Coordinates of desired quatenary nonvariant points are calculated on analytical models of surfaces by mutual crystallization of two phases and are refined by differential thermal analysis [ru

  1. Magnetic properties of the filled skutterudite-type structure compounds GdRu4P12 and TbRu4P12 synthesized under high pressure

    OpenAIRE

    Sekine, C; Uchiumi, T; Shirotani, I; Matsuhira, kazuyuki; Sakakibara, T; Goto, T; Yagi, T

    2000-01-01

    We have succeeded in synthesizing filled skutterudite-type structure compounds GdRu4P12 and TbRu4P12 under high pressure. The magnetic properties of GdRu4P12 and TbRu4P12 have been studied by means of electrical resistivity, magnetic susceptibility, and magnetization measurements. Magnetic experiments suggest that the Gd and Tb ions in the compounds have trivalent state. The compound GdRu4P12 displays features that suggest the occurrence of antiferromagnetic ordering below TN=22 K. In TbRu4P1...

  2. Preparation of PtRu/Carbon hybrid materials by hydrothermal carbonization: A study of the Pt:Ru atomic ratio

    International Nuclear Information System (INIS)

    Tusi, Marcelo Marques; Brandalise, Michele; Correa, Olandir Vercino; Oliveira Neto, Almir; Linardi, Marcelo; Spinace, Estevam Vitorio; Villalba, Juan Carlo

    2009-01-01

    PtRu/Carbon materials with different Pt:Ru atomic ratios (30:70, 50:50, 60:40, 80:20 and 90:10) and 5 wt% of nominal metal load were prepared by hydrothermal carbonization using H 2 PtCl 6.6 H 2 O and RuCl 3. xH 2 O as metals sources and catalysts of the carbonization process and starch as carbon source and reducing agent. The obtained materials were treated at 900 deg C under argon and characterized by EDX, XRD and cyclic voltammetry. The electro-oxidation of methanol was studied by cyclic voltammetry and chronoamperometry using thin porous coating technique. The PtRu/Carbon materials showed Pt:Ru atomic ratios obtained by EDX similar to the nominal ones. XRD analysis showed that Pt face-cubic centered (FCC) and Ru hexagonal close-packed (HCP) phases coexist in the obtained materials. The average crystallite sizes of the Pt (FCC) phase were in the range of 8-12 nm. The material prepared with Pt:Ru atomic ratio of 50:50 showed the best performance for methanol electro-oxidation. (author)

  3. Field induced phase transition in layered honeycomb spin system α-RuCl3 studied by thermal conductivity

    Science.gov (United States)

    Leahy, Ian; Bornstein, Alex; Choi, Kwang-Yong; Lee, Minhyea

    α -RuCl3, a quasi -two-dimensional honeycomb lattice is known to be a candidate material to realize the Heisenberg-Kitaev spin model of a highly anisotropic bond-dependent exchange interaction. We investigate in-plane thermal conductivity (κ) as a function of temperature (T) and in-plane applied field (H). At H = 0 , the onset of a strong increase in κ marks the spontaneous long range ordering temperature, Tc = 6 . 5 K , corresponding to ``zigzag'' antiferromagnetic ordering. A broad peak appearing below Tc in κ was found to be suppressed significantly as H increases up to ~ 7 T , implying the system undergoes a field-induced transition from ordered to a new spin-disordered state analogous to the transverse-field Ising model. Further increasing H above 7 . 1 T , the large field seems to begin polarizing spins thus increasing the phonon mean free path, resulting in a significant rise in κ. This tendency is clearly shown in the field dependence of κ below Tc, which has a pronounced minimum at Hmin = 7 . 1 T . We will discuss our scaling analysis to characterize this field-induced phase transition and compare to the transverse-field Ising spin system. Work at the University of Colorado was supported by the US DOE Basic Energy Sciences under Award No. DE-SC0006888.

  4. Adsorption and diffusion of Ru adatoms on Ru(0001)-supported graphene: Large-scale first-principles calculations

    Energy Technology Data Exchange (ETDEWEB)

    Han, Yong; Evans, James W. [Department of Physics and Astronomy, Iowa State University, Ames, Iowa 50011, USA and Ames Laboratory—U.S. Department of Energy, Iowa State University, Ames, Iowa 50011 (United States)

    2015-10-28

    Large-scale first-principles density functional theory calculations are performed to investigate the adsorption and diffusion of Ru adatoms on monolayer graphene (G) supported on Ru(0001). The G sheet exhibits a periodic moiré-cell superstructure due to lattice mismatch. Within a moiré cell, there are three distinct regions: fcc, hcp, and mound, in which the C{sub 6}-ring center is above a fcc site, a hcp site, and a surface Ru atom of Ru(0001), respectively. The adsorption energy of a Ru adatom is evaluated at specific sites in these distinct regions. We find the strongest binding at an adsorption site above a C atom in the fcc region, next strongest in the hcp region, then the fcc-hcp boundary (ridge) between these regions, and the weakest binding in the mound region. Behavior is similar to that observed from small-unit-cell calculations of Habenicht et al. [Top. Catal. 57, 69 (2014)], which differ from previous large-scale calculations. We determine the minimum-energy path for local diffusion near the center of the fcc region and obtain a local diffusion barrier of ∼0.48 eV. We also estimate a significantly lower local diffusion barrier in the ridge region. These barriers and information on the adsorption energy variation facilitate development of a realistic model for the global potential energy surface for Ru adatoms. This in turn enables simulation studies elucidating diffusion-mediated directed-assembly of Ru nanoclusters during deposition of Ru on G/Ru(0001)

  5. Pd-RuSe/C as ORR specific catalyst in alkaline solution containing methanol

    Energy Technology Data Exchange (ETDEWEB)

    Maheswari, S.; Sridhar, P.; Pitchumani, S. [CSIR-Central Electrochemical Research Institute-Madras Unit, CSIR Complex, Chennai 600 113 (India)

    2012-12-15

    Carbon supported RuSe (RuSe/C) catalyst in varying atomic ratios of Ru to Se, namely, 1:1, 2:1, and 3:1 were prepared and their performances were compared with carbon supported Ru (Ru/C). Based on the performance, Palladium was incorporated into as prepared RuSe(2:1)/C and heat treated HTRuSe(2:1)/C. Ru/C, RuSe/C, and Pd-RuSe/C were characterized by X-ray diffraction (XRD) and transmission electron microscopy techniques. The XRD analyses of Ru/C, RuSe/C and Pd-HTRuSe/C show the formation of the hcp structure of Ru particles and the mean particle size was obtained from Ru(101) peak. The electrochemical characterizations of Ru/C, RuSe/C, Pd-HTRuSe(2:1)/C and Pd-RuSe(2:1)/C were conducted by cyclic voltammetry. Linear Sweep Voltammetric studies showed that incorporation of Pd in HTRu-Se(2:1)/C resulted in better catalytic activity toward oxygen reduction with resistance to methanol oxidation. The quantity of hydrogen peroxide produced was obtained from rotating ring disk electrode studies. (Copyright copyright 2012 WILEY-VCH Verlag GmbH and Co. KGaA, Weinheim)

  6. New bisaminoethanethiol (BAT) ligands which form two interconvertible Tc-99m complexes

    Energy Technology Data Exchange (ETDEWEB)

    Oya, Shunichi; Kung, Mei-Ping; Frederick, Dana; Kung, Hank F

    1995-08-01

    Most commonly used radiopharmaceuticals in diagnostic nuclear medicine are labeled with Tc-99m. This is due to its superior physical characteristics (T{sub (1(2))} = 6 h and gamma energy 140 KeV) and convenient availability from the {sup 99}Mo/{sup 99mm}Tc generator. In an attempt to fine tune the properties of Tc-99m complexes, the synthesis and radiolabeling of two novel N{sub 2}S{sub 2} ligands, N,-2-mercaptobenzyl-N'-(1-oxo-2-mercapto-2-methyl)propyl ethylenediamine,8, and N,-2-methylthiobenzyl-N'-(1-oxo-2-mercapto-2-methyl)propyl ethylenediamine, 11, with an ionizable SH or unionizable SMe group, respectively, for the formation of complexes with Tc{sup v}O center cores, have been examined. Both ligands initially formed one apparently stable, lipophilic and neutral complex (HPLC, Rt = 7 min, reverse-phase column, acetonitrile: buffer, pH 7.0; (55(45)); V/V; partition coefficient between 1-octanol and buffer of 410 and 335, respectively) with [{sup 99m}Tc]pertechnetate in the presence of stannous chloride. After treatment with a reducing agent, NaCNBH{sub 3}, the initial [{sup 99m}Tc]8 and 11 complexes were reduced; the reduced complexes were less lipophilic (shorter retention time, Rt = 5 min, on the same reversed phase HPLC). However, only the oxidized form showed sufficient stability. The reduced forms of both [{sup 99m}Tc]8 and 11 were readily and completely converted back to the oxidized forms by a stream of air. Biodistribution studies in rats demonstrated that the [{sup 99m}Tc]8 (oxidized form) penetrated the blood-brain barrier (0.67% dose/organ at 2 min postinjection), but washed out from the brain quickly (0.29% dose/organ at 30 min postinjection). On the contrary, [{sup 99m}Tc]11 (oxidized form) did not show any brain uptake (0.03% dose/organ at 2 min postinjection), despite its higher lipophilicity. The disparity between these two Tc-99m complexes may be related to the relative instability of [{sup 99m}Tc]11 (oxidized form) by the introduction of the

  7. New bisaminoethanethiol (BAT) ligands which form two interconvertible Tc-99m complexes

    International Nuclear Information System (INIS)

    Oya, Shunichi; Kung, Mei-Ping; Frederick, Dana; Kung, Hank F.

    1995-01-01

    Most commonly used radiopharmaceuticals in diagnostic nuclear medicine are labeled with Tc-99m. This is due to its superior physical characteristics (T (1(2)) = 6 h and gamma energy 140 KeV) and convenient availability from the 99 Mo/ 99mm Tc generator. In an attempt to fine tune the properties of Tc-99m complexes, the synthesis and radiolabeling of two novel N 2 S 2 ligands, N,-2-mercaptobenzyl-N'-(1-oxo-2-mercapto-2-methyl)propyl ethylenediamine,8, and N,-2-methylthiobenzyl-N'-(1-oxo-2-mercapto-2-methyl)propyl ethylenediamine, 11, with an ionizable SH or unionizable SMe group, respectively, for the formation of complexes with Tc v O center cores, have been examined. Both ligands initially formed one apparently stable, lipophilic and neutral complex (HPLC, Rt = 7 min, reverse-phase column, acetonitrile: buffer, pH 7.0; (55(45)); V/V; partition coefficient between 1-octanol and buffer of 410 and 335, respectively) with [ 99m Tc]pertechnetate in the presence of stannous chloride. After treatment with a reducing agent, NaCNBH 3 , the initial [ 99m Tc]8 and 11 complexes were reduced; the reduced complexes were less lipophilic (shorter retention time, Rt = 5 min, on the same reversed phase HPLC). However, only the oxidized form showed sufficient stability. The reduced forms of both [ 99m Tc]8 and 11 were readily and completely converted back to the oxidized forms by a stream of air. Biodistribution studies in rats demonstrated that the [ 99m Tc]8 (oxidized form) penetrated the blood-brain barrier (0.67% dose/organ at 2 min postinjection), but washed out from the brain quickly (0.29% dose/organ at 30 min postinjection). On the contrary, [ 99m Tc]11 (oxidized form) did not show any brain uptake (0.03% dose/organ at 2 min postinjection), despite its higher lipophilicity. The disparity between these two Tc-99m complexes may be related to the relative instability of [ 99m Tc]11 (oxidized form) by the introduction of the unionizable methylated thiol group as one of the donor

  8. Studies of post-elution concentration of 99m-Tc eluted from a gel type chromatographic generator

    International Nuclear Information System (INIS)

    Suzuki, Katia N.; Osso Junior, Joao Alberto

    2007-01-01

    The radiopharmaceuticals most used in Diagnostic Nuclear Medicine are those labeled with the metastable technetium ( 99m Tc) due to its ideal physical properties of decay (t 1/2 6.01 h, Eγ 140 keV), low cost and availability facilitated through the commercial generator 99 Mo / 99m Tc. This radionuclide is formed by the β - decay of 99 Mo adsorbed on an alumina column of the generator and collected in the form of sodium pertechnetate (Na 99m TcO 4 ) by elution with saline solution (0.9%). The Radiopharmacy Center (CR) of the IPEN-CNEN/SP developed a gel type chromatographic generator of MoZr with 99 Mo produced by 98 Mo(n, γ) 99 Mo reaction that occurs in IEA-R1 Nuclear Reactor. The gel is composed of zirconium molybdate with elution volume of 12 ml with an activity of 11100 MBq (300 mCi) producing a radioactive concentration of 925 MBq (34 mCi) / ml. The fission generator gives a higher radioactive concentration around 1850 MBq (69 mCi) / ml. The aim of this work is to study a system of post-elution concentration using ion exchange cartridges in tandem (cation - anion) for the attainment of a high enough radioactive concentration to meet the demand of market, with a proved quality. This system of concentration will be made based in the technique of solid phase extraction (SPE) using commercial cartridges of extraction, which contains the solid phase and eluent saline solution (0.9%). As the eluent results of this system used in the gel generator of MoZr will be compared with the fission generator currently produced by IPEN-CNEN/SP. (author)

  9. Studies of post-elution concentration of {sup 99m}-Tc eluted from a gel type chromatographic generator

    Energy Technology Data Exchange (ETDEWEB)

    Suzuki, Katia N.; Osso Junior, Joao Alberto [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)]. E-mail: norisuzuki6@yahoo.com.br; jaosso@ipen.br

    2007-07-01

    The radiopharmaceuticals most used in Diagnostic Nuclear Medicine are those labeled with the metastable technetium ({sup 99m}Tc) due to its ideal physical properties of decay (t{sub 1/2} 6.01 h, E{gamma} 140 keV), low cost and availability facilitated through the commercial generator {sup 99}Mo /{sup 99m}Tc. This radionuclide is formed by the {beta}{sup -} decay of {sup 99}Mo adsorbed on an alumina column of the generator and collected in the form of sodium pertechnetate (Na{sup 99m}TcO{sub 4}) by elution with saline solution (0.9%). The Radiopharmacy Center (CR) of the IPEN-CNEN/SP developed a gel type chromatographic generator of MoZr with {sup 99}Mo produced by {sup 98}Mo(n, {gamma}){sup 99}Mo reaction that occurs in IEA-R1 Nuclear Reactor. The gel is composed of zirconium molybdate with elution volume of 12 ml with an activity of 11100 MBq (300 mCi) producing a radioactive concentration of 925 MBq (34 mCi) / ml. The fission generator gives a higher radioactive concentration around 1850 MBq (69 mCi) / ml. The aim of this work is to study a system of post-elution concentration using ion exchange cartridges in tandem (cation - anion) for the attainment of a high enough radioactive concentration to meet the demand of market, with a proved quality. This system of concentration will be made based in the technique of solid phase extraction (SPE) using commercial cartridges of extraction, which contains the solid phase and eluent saline solution (0.9%). As the eluent results of this system used in the gel generator of MoZr will be compared with the fission generator currently produced by IPEN-CNEN/SP. (author)

  10. Development of 99mTc-labelled the d,1-diasteroisomer of HM-PAO for cerebral blood flow imaging

    International Nuclear Information System (INIS)

    Lun Xiao.

    1989-10-01

    The d,1-diastereoisomer of hexamethyl propyleneamine oxime (HM-PAO) was selected as the preferred ligand for Tc-99m as a radiotracer for cerebral perfusion imaging. Further improvement of the synthesis and isolation method of HM-PAO resulted in pure d,1-HM-PAO and pure meso-HM-PAO. The neutral, lipophilic Tc-99m complexes of d,1-HM-PAO and meso-HM-PAO were formed in high yield by stannous reduction of Mo-99/Tc-99m generator eluate, respectively. Two minutes following i.v. administration of Tc-99m-d,1-HM-PAO in mice, 2.24% of the injected dose appears in the brain. Little washout of the tracer is observed up to 24-hour post injection. Two minutes following i.v. administration of Tc-99m-meso-HM-PAO in mice, 1.9% of the injected dose appears in the brain. The radioactivity of Tc-99m-meso-HM-PAO declined faster than that of Tc-99m-d,1-HM-PAO did in the brain up to 24-hour post injection. 12 refs, 5 figs, 5 tabs

  11. Surface studies by low energy ion beams: Cu/Ru(0001) and Cu/O/Ru(0001)

    Energy Technology Data Exchange (ETDEWEB)

    Shen, Y G; O` Connor, D J; MacDonald, R J [Newcastle Univ., NSW (Australia). Dept. of Physics; Wandelt, H [Institut fur Physikalische und Theoretische Chemie der Universitat Bonn, Bonn (Germany).; Zee, H van [Eindhoven University of Technology, Eindhoven (Netherlands) Dept. of Physics

    1994-12-31

    The surface structure of Cu on Ru(OOO1) has been studied by low energy Li{sup +} ion scattering. It was found that Cu forms pseudomorphic islands for two layers. The effects of Cu on an O-precovered RU(OOO1) surface has also been investigated using keV He{sup +} ions. The results show that during the deposition of Cu, O is displaced from the Ru surface and migrated onto the top of the surface of the growing overlayer. The floated out O has been tested, showing a disordered overlayer. 5 refs., 3 figs.

  12. Surface studies by low energy ion beams: Cu/Ru(0001) and Cu/O/Ru(0001)

    Energy Technology Data Exchange (ETDEWEB)

    Shen, Y.G.; O`Connor, D.J.; MacDonald, R.J. [Newcastle Univ., NSW (Australia). Dept. of Physics; Wandelt, H. [Institut fur Physikalische und Theoretische Chemie der Universitat Bonn, Bonn (Germany).; Zee, H. van [Eindhoven University of Technology, Eindhoven (Netherlands) Dept. of Physics

    1993-12-31

    The surface structure of Cu on Ru(OOO1) has been studied by low energy Li{sup +} ion scattering. It was found that Cu forms pseudomorphic islands for two layers. The effects of Cu on an O-precovered RU(OOO1) surface has also been investigated using keV He{sup +} ions. The results show that during the deposition of Cu, O is displaced from the Ru surface and migrated onto the top of the surface of the growing overlayer. The floated out O has been tested, showing a disordered overlayer. 5 refs., 3 figs.

  13. Anelastic characterization and superconducting properties of RuSr2GdCu2O8+δ

    Directory of Open Access Journals (Sweden)

    Jurelo, A. R.

    2008-08-01

    Full Text Available Since the discovery of the high Tc superconductors, many researches have been carried out on the different properties of these materials, especially on the transition temperature into the superconducting state. The rutheno-cuprates belong to a new class of composites, which were synthesized for the first time by Bauernfeind in 1995. Bernhard and collaborators discovered, in 1999, the coexistence of the ferromagnetism and the superconductivity in this phase, which is known as antagonistic phenomenon in the electromagnetism due to spin-charge interactions established in these states. However, the physical nature of the superconducting and magnetic states is still very obscure. The non-stoichiometric (interstitial oxygen is considered as a possible cause for the non-uniformity of the sample properties. In this paper, results of mechanical spectroscopy in Ru-1212 samples are presented showing complex anelastic spectra, which were attributed to the mobility of the interstitial oxygen atoms in the Ru-1212 lattice.Desde el descubrimiento de los superconductores de alta Tc, muchas investigaciones han sido realizadas sobre las diferentes propiedades de estos materiales, especialmente sobre la temperatura de transición dentro del estado superconductor. Los cupratos de rutenio pertenecen a una nueva clase de compositos, los cuales fueron sintetizados por primera vez por Bauernfeind en 1995. Bernhard y colaboradores descubrieron, en 1999, la coexistencia del ferromagnetismo y la superconductividad en esta fase, lo cual es conocido como un fenómeno antagonistico en el electromagnetismo debido a las interacciones spin-carga establecidas en estos estados. Sin embargo, la naturaleza física de los estados superconductores y magnéticos aun no son muy claros. El oxigeno no-estequiométrico (intersticial es considerado como una causa de la no-uniformidad de las propiedades de la muestra. En este articulo, los resultados de espectroscopia mecánica en muestras

  14. An investigation of the Pd-Ag-Ru-Gd quaternary system phase diagram

    International Nuclear Information System (INIS)

    Zhang Kanghou; Xu Yun

    2005-01-01

    On the basis of the Ag-Pd-Gd, Ag-Ru-Gd and Pd-Ru-Gd ternary systems, the partial phase diagram of Pd-Ag-Ru-Gd (Gd 3 Gd and Ag 51 Gd 14 ; five two-phase regions: Pd(Ag) + (Ru), Pd(Ag) + Ag 51 Gd 14 (Ru) + Ag 51 Gd 14 , Pd(Ag) + Pd 3 Gd and (Ru) + Pd 3 Gd; three three-phase regions: Pd(Ag) + Pd 3 Gd + (Ru), Pd(Ag) + Ag 51 Gd 14 + (Ru) and (Ru) + Ag 51 Gd 14 + Pd 3 Gd; one four-phase region Pd(Ag) + (Ru) + Ag 51 Gd 14 + Pd 3 Gd. No new quaternary intermetallic phase has been found

  15. Optimum Pt and Ru atomic composition of carbon-supported Pt-Ru alloy electrocatalyst for methanol oxidation studied by the polygonal barrel-sputtering method

    International Nuclear Information System (INIS)

    Hiromi, Chikako; Inoue, Mitsuhiro; Taguchi, Akira; Abe, Takayuki

    2011-01-01

    Highlights: → The sputtered Pt and Ru form the Pt-Ru alloy nanoparticles on the carbon support. → The deposited Pt-Ru alloy particles have uniform Pt:Ru atomic ratios. → The optimum Pt:Ru ratio of the Pt-Ru/C for methanol oxidation is 58:42 at.% at 25 deg. C. → The optimum Pt:Ru ratio of 58:42 shifts to 50:50 at.% at 40 and 60 deg. C. → The polygonal barrel-sputtering method is useful to prepare the DMFC anode catalyst. - Abstract: The optimum Pt and Ru atomic composition of a carbon-supported Pt-Ru alloy (Pt-Ru/C) used in a practical direct methanol fuel cell (DMFC) anode was investigated. The samples were prepared by the polygonal barrel-sputtering method. Based on the physical properties of the prepared Pt-Ru/C samples, the Pt-Ru alloy was found to be deposited on a carbon support. The microscopic characterization showed that the deposited alloy forms nanoparticles, of which the atomic ratios of Pt and Ru (Pt:Ru ratios) are uniform and are in accordance with the overall Pt:Ru ratios of the samples. The formation of the Pt-Ru alloy is also supported by the electrochemical characterization. Based on these results, methanol oxidation on the Pt-Ru/C samples was measured by cyclic voltammetry and chronoamperometry. The results indicated that the methanol oxidation activities of the prepared samples depended on the Pt:Ru ratios, of which the optimum Pt:Ru ratio is 58:42 at.% at 25 deg. C and 50:50 at.% at 40 and 60 deg. C. This temperature dependence of the optimum Pt:Ru ratio is well explained by the relationship between the methanol oxidation reaction process and the temperature, which is reflected in the rate-determining steps considered from the activation energies. It should be noted that at 25-60 deg. C, the Pt-Ru/C with Pt:Ru = 50:50 at.% prepared by our sputtering method has the higher methanol oxidation activity than that of a commercially available sample with the identical overall Pt:Ru ratio. Consequently, the polygonal barrel-sputtering method

  16. Synthesis and thermoelectric properties of RuO2 nanorods

    International Nuclear Information System (INIS)

    Music, Denis; Basse, Felix H.-U.; Schneider, Jochen M.; Hassdorf, Ralf

    2010-01-01

    We have explored the effect of the O/Ru ratio on the morphology and the Seebeck coefficient of RuO 2 nanorods (space group P4 2 /mnm) synthesized by reactive sputtering. At an O/Ru ratio of 1.69, a faceted surface is observed, while nanorod formation occurs at O/Ru ratios of 2.03 and 2.24. Using classical molecular dynamics with the potential parameters derived in this work, we show that volatile species enable nanorod formation. Based on ab initio calculations, two effects of the nanorod formation on the Seebeck coefficient are observed: (i) increase due to additional states in the vicinity of the Fermi level and (ii) decrease due to oxygen point defects (volatile species). These two competing effects give rise to a moderate increase in the Seebeck coefficient upon nanorod formation.

  17. Fingerprint elements scatter analysis on ancient chinese Ru porcelains samples

    International Nuclear Information System (INIS)

    Gao Zhengyao; Wang Jie; Chen Xiande

    1997-01-01

    Altogether 28 samples, mainly including glazes and bodies of ancient Chinese Ru porcelain, were analyzed by NAA technique and the contents of 36 elements were compared. The scatter analysis for nine fingerprint-elements indicates that almost all ancient Chinese Ru porcelain samples had nearly identical and long-term stable source of raw materials although they were fired in different kilns, at varying time and with distinct colors, and moreover, the source of raw materials for modern Ru porcelain seems to approach that for ancient one. The close provenance relation between ancient Jun porcelain and ancient Ru porcelain is also preliminarily verified. The glaze material of Jingdezhen white porcelain is totally different from all other samples. It shows that the former came from a separate source

  18. Gamma-gamma angular correlation for transitions in 101Tc and 76Se nuclei

    International Nuclear Information System (INIS)

    Zamboni, C.B.

    1988-01-01

    The technique of directional γ-γ angular correlation has been used the β - decay of 101 Mo (T 1/2 = 14,6 min) to levels in 101 Tc and 76 Hs (T 1/2 = 26,3 h) to levels in 76 Se. The angular correlation of coincident γ-transitions, in both nuclei, have been measured using HPGe-HPGe and HPGe-NaI(Tl) spectrometers. Measurements have been carried out for fifteen gamma-cascades in 101 Tc and twenty four cascades in 76 Se resulting in the determination of multipole mixing ratios δ(E2/M1), for fourteen γ-transitions in 101 Tc and sexteen γ-transitions in 76 Se. In the case of 101 Tc these measurements were realized for the first time and in the case of 76 Se the present results confirmed some of the mixing ratios determined In the earlier studies od nuclear orientation and angular correlation. Present results together with the results of earlier studies also permitted definite assigments of spins to the majority of levels in 101 Tc and 76 Se involved in the present study. The experimental results are discussed in terms of nuclear models and a comparasion of some of the properties of the Technetium odd mass nuclei with A = 95-103 and Selenium even mass nuclei with A = 76-82 has been made in order to ilustrate the systematic variation of these properties with mass number. (author) [pt

  19. Isomer spectroscopy in 92Ru and 95Pd

    International Nuclear Information System (INIS)

    Gorska, M.; Rejmund, M.; Schubart, R.; Grawe, H.; Heese, J.; Maier, K.H.; Spohr, K.; Fitzgerald, J.B.; Fossan, D.B.

    1996-01-01

    The parity changing γ-transitions like E1, M2, E3 in 92 Ru and 95 Pd nuclei have been investigated to probe the purity of the Shell Model. Two isomers of 92 Ru and 95 Pd have been produced in the 58 Ni + 40 Ca heavy ion reaction at 58 Ni beams energy 215 MeV. The gamma-ray transition strength have been deduced

  20. RDM Lifetime measurement in "1"0"0Ru

    International Nuclear Information System (INIS)

    Gupta, C.K.; Rohilla, Aman; Chamoli, S.K.; Singh, R.P.; Murlithar, S.; Chakraborty, S.; Sharma, H.P.; Rai, S.; Kumar, A.; Govil, I.M.

    2016-01-01

    The energy level sequences of nuclei in A ∼ 100 mass region show an interesting interplay between single-particle and collective degrees of freedom. The measured transition probabilities in "9"8Ru suggest that the nucleus has both single-particle and vibrational character. To see how the nature of this nucleus changes with addition of 2 neutrons, we performed RDM lifetime measurement in yrast sequence of "1"0"0Ru at Inter University Accelerator Center (IUAC), New Delhi

  1. Alkali promotion of N-2 dissociation over Ru(0001)

    DEFF Research Database (Denmark)

    Mortensen, Jens Jørgen; Hammer, Bjørk; Nørskov, Jens Kehlet

    1998-01-01

    Using self-consistent density functional calculations, we show that adsorbed Na and Cs lower the barrier for dissociation of N2 on Ru(0001). Since N2 dissociation is a crucial step in the ammonia synthesis reaction, we explain in this way the experimental observation that alkali metals promote th...... the ammonia synthesis reaction over Ru catalysts. We also show that the origin of this effect is predominantly a direct electrostatic attraction between the adsorbed alkali atoms and the dissociating molecule....

  2. Experimental study of the rearrangements of valence protons and neutrons amongst single-particle orbits during double-β decay in 100Mo

    Science.gov (United States)

    Freeman, S. J.; Sharp, D. K.; McAllister, S. A.; Kay, B. P.; Deibel, C. M.; Faestermann, T.; Hertenberger, R.; Mitchell, A. J.; Schiffer, J. P.; Szwec, S. V.; Thomas, J. S.; Wirth, H.-F.

    2017-11-01

    The rearrangements of protons and neutrons amongst the valence single-particle orbitals during double-β decay of 100Mo have been determined by measuring cross sections in (d ,p ), (p ,d ), (3He,α ), and (3He,d ) reactions on Mo,10098 and Ru,102100 targets. The deduced nucleon occupancies reveal significant discrepancies when compared with theoretical calculations; the same calculations have previously been used to determine the nuclear matrix element associated with the decay probability of double-β decay of the 100Mo system.

  3. Quaternary system LiF-LiCl-LiVO3-Li2MoO4

    International Nuclear Information System (INIS)

    Anipchenko, B.V.; Garkushin, I.K.

    2000-01-01

    Interactions in the LiF-LiCl-LiVO 3 -Li 2 MoO 4 system are studied by differential thermal analysis. Rate of heating/cooling of the samples comprised 15 Grad/min, mass of sample composed 0.2 g. The system was investigated in the 300-650 Deg C range. X-ray diffraction method was used for determination of purity of the reagents. Composition and temperature of quaternary component eutectics are determined: 16.5 mol. % of LiF, 47.0 mol. % of LiCl, 28.8 mol. % of LiVO 3 , 7.6 mol. % of Li 2 MoO 4 ; 387 Deg C. Mean value of melting enthalpy of quaternary eutectics mixture in the LiF-LiCl-LiVO 3 -Li 2 MoO 4 system on the results of the tests was in the range of 222 kJ/kg [ru

  4. Superconductivity in Weyl semimetal candidate MoTe{sub 2}

    Energy Technology Data Exchange (ETDEWEB)

    Qi, Yanpeng; Naumov, Pavel; Rajamathi, Catherine; Barkalov, Oleg; Wu, Shu-Chun; Shekhar, Chandra; Sun, Yan; Suess, Vicky; Schmidt, Marcus; Schwarz, Ulrich; Schnelle, Walter; Felser, Claudia; Medvedev, Sergey [Max Planck Institute for Chemical Physics of Solids, Dresden (Germany); Ali, Mazhar; Cava, Robert [Department of Chemistry, Princeton University, Princeton (United States); Hanfland, Michael [European Synchrotron Radiation Facility, Grenoble (France); Pippel, Eckhard; Werner, Peter; Hillebrand, Reinald; Parkin, Stuart [Max Planck Institute of Microstructure Physics, Halle (Germany); Foerster, Tobias; Kampert, Erik [Dresden High Magnetic Field Laboratory, Dresden (Germany); Yan, Binghai [Max Planck Institute for Chemical Physics of Solids, Dresden (Germany); Max Planck Institute for the Physics of Complex Systems, Dresden (Germany)

    2016-07-01

    In this work, we investigate the sister compound of WTe{sub 2}, MoTe{sub 2}, which is also predicted to be a Weyl semimetal and a quantum spin Hall insulator in bulk and monolayer form, respectively. We find that MoTe{sub 2} exhibits superconductivity with a resistive transition temperature T{sub c} of 0.1 K. The application of a small pressure is shown to dramatically enhance the T{sub c}, with a maximum value of 8.2 K being obtained at 11.7 GPa (a more than 80-fold increase in Tc). This yields a dome-shaped superconducting phase diagram. Further explorations into the nature of the superconductivity in this system may provide insights into the interplay between superconductivity and topological physics.

  5. Development of industrial-scale fission {sup 99}Mo production process using low enriched uranium target

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Seung Kon; Lee, Jun Sig [Radioisotope Research Division, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Beyer, Gerd J. [Grunicke Strasse 15, Leipzig (Germany)

    2016-06-15

    Molybdenum-99 ({sup 99}Mo) is the most important isotope because its daughter isotope, technetium-99m ({sup 99}mTc), has been the most widely used medical radioisotope for more than 50 years, accounting for > 80% of total nuclear diagnostics worldwide. In this review, radiochemical routes for the production of {sup 99}Mo, and the aspects for selecting a suitable process strategy are discussed from the historical viewpoint of {sup 99}Mo technology developments. Most of the industrial-scale {sup 99}Mo processes have been based on the fission of {sup 235}U. Recently, important issues have been raised for the conversion of fission {sup 99}Mo targets from highly enriched uranium to low enriched uranium (LEU). The development of new LEU targets with higher density was requested to compensate for the loss of {sup 99}Mo yield, caused by a significant reduction of {sup 235}U enrichment, from the conversion. As the dramatic increment of intermediate level liquid waste is also expected from the conversion, an effective strategy to reduce the waste generation from the fission {sup 99}Mo production is required. The mitigation of radioxenon emission from medical radioisotope production facilities is discussed in relation with the monitoring of nuclear explosions and comprehensive nuclear test ban. Lastly, the {sup 99}Mo production process paired with the Korea Atomic Energy Research Institute's own LEU target is proposed as one of the most suitable processes for the LEU target.

  6. What is wise in the production of 99Mo? A comparison of eight possible production routes

    International Nuclear Information System (INIS)

    Bert Wolterbeek; Jan Leen Kloosterman; Danny Lathouwers; Martin Rohde; August Winkelman; Lodewijk Frima; Frank Wols

    2014-01-01

    The present paper addresses eight possible routes of producing 99 Mo, and discusses both yield and 99 Mo specific activities (SA) in the context of anticipated worldwide demand. Target dimensions are modelled by considering both limits set by cooling and by inside-target radiation attenuation characteristics. Energy deposition profiles are set up by MCNP6, reaction probabilities are taken from TALYS/TENDL and JANIS codes, and both are used in arriving at the produced 99 Mo. The outcomes suggest that U neutron-fission may remain one of the most relevant and efficient means of producing 99 Mo at the world-demand level, but that within this domain new developments may surface, such as ADSR or AHR production modes. Accelerator-based 99 Mo production is discussed as asking for developments in both target cooling and new concepts in post-EOB upgrading of 99 Mo SA, and/or new concepts for 99 Mo/ 99m Tc-generators, the latter possibly in both volumes (mass) and 99 Mo capacities. (author)

  7. Development of Industrial-Scale Fission 99Mo Production Process Using Low Enriched Uranium Target

    Directory of Open Access Journals (Sweden)

    Seung-Kon Lee

    2016-06-01

    Full Text Available Molybdenum-99 (99Mo is the most important isotope because its daughter isotope, technetium-99m (99mTc, has been the most widely used medical radioisotope for more than 50 years, accounting for > 80% of total nuclear diagnostics worldwide. In this review, radiochemical routes for the production of 99Mo, and the aspects for selecting a suitable process strategy are discussed from the historical viewpoint of 99Mo technology developments. Most of the industrial-scale 99Mo processes have been based on the fission of 235U. Recently, important issues have been raised for the conversion of fission 99Mo targets from highly enriched uranium to low enriched uranium (LEU. The development of new LEU targets with higher density was requested to compensate for the loss of 99Mo yield, caused by a significant reduction of 235U enrichment, from the conversion. As the dramatic increment of intermediate level liquid waste is also expected from the conversion, an effective strategy to reduce the waste generation from the fission 99Mo production is required. The mitigation of radioxenon emission from medical radioisotope production facilities is discussed in relation with the monitoring of nuclear explosions and comprehensive nuclear test ban. Lastly, the 99Mo production process paired with the Korea Atomic Energy Research Institute's own LEU target is proposed as one of the most suitable processes for the LEU target.

  8. Reduction of RuVI≡N to RuIII-NH3 by Cysteine in Aqueous Solution.

    Science.gov (United States)

    Wang, Qian; Man, Wai-Lun; Lam, William W Y; Yiu, Shek-Man; Tse, Man-Kit; Lau, Tai-Chu

    2018-05-21

    The reduction of metal nitride to ammonia is a key step in biological and chemical nitrogen fixation. We report herein the facile reduction of a ruthenium(VI) nitrido complex [(L)Ru VI (N)(OH 2 )] + (1, L = N, N'-bis(salicylidene)- o-cyclohexyldiamine dianion) to [(L)Ru III (NH 3 )(OH 2 )] + by l-cysteine (Cys), an ubiquitous biological reductant, in aqueous solution. At pH 1.0-5.3, the reaction has the following stoichiometry: [(L)Ru VI (N)(OH 2 )] + + 3HSCH 2 CH(NH 3 )CO 2 → [(L)Ru III (NH 3 )(OH 2 )] + + 1.5(SCH 2 CH(NH 3 )CO 2 ) 2 . Kinetic studies show that at pH 1 the reaction consists of two phases, while at pH 5 there are three distinct phases. For all phases the rate law is rate = k 2 [1][Cys]. Studies on the effects of acidity indicate that both HSCH 2 CH(NH 3 + )CO 2 - and - SCH 2 CH(NH 3 + )CO 2 - are kinetically active species. At pH 1, the reaction is proposed to go through [(L)Ru IV (NHSCH 2 CHNH 3 CO 2 H)(OH 2 )] 2+ (2a), [(L)Ru III (NH 2 SCH 2 CHNH 3 CO 2 H)(OH 2 )] 2+ (3), and [(L)Ru IV (NH 2 )(OH 2 )] + (4) intermediates. On the other hand, at pH around 5, the proposed intermediates are [(L)Ru IV (NHSCH 2 CHNH 3 CO 2 )(OH 2 )] + (2b) and [(L)Ru IV (NH 2 )(OH 2 )] + (4). The intermediate ruthenium(IV) sulfilamido species, [(L)Ru IV (NHSCH 2 CHNH 3 CO 2 H)(OH 2 )] 2+ (2a) and the final ruthenium(III) ammine species, [(L)Ru III (NH 3 )(MeOH)] + (5) (where H 2 O was replaced by MeOH) have been isolated and characterized by various spectroscopic methods.

  9. Effect of the structural characteristics of binary Pt-Ru and ternary Pt-Ru-M fuel cell catalysts on the activity of ethanol electrooxidation in acid medium.

    Science.gov (United States)

    Antolini, Ermete

    2013-06-01

    In view of their possible use as anode materials in acid direct ethanol fuel cells, the electrocatalytic activity of Pt-Ru and Pt-Ru-M catalysts for ethanol oxidation has been investigated. This minireview examines the effects of the structural characteristics of Pt-Ru, such as the degree of alloying and Ru oxidation state, on the electrocatalytic activity for ethanol oxidation. Copyright © 2013 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

  10. RoMo

    DEFF Research Database (Denmark)

    Pedersen, Esben Warming; Hornbæk, Kasper

    2011-01-01

    In TUIs, physical/digital conflicts can occur when the digital model does not match the model implied by the spatial lay- out of tangibles. We show how tangible tabletop interfaces (TTI) can be modified to allow robot movement of tangi- bles, thereby avoiding conflicts. We present RoMo, an open...... source Java library that allow existing TTI applications to perform robot movement, and demonstrate its functionality with three applications....

  11. Hydrogen-induced room-temperature plasticity in TC4 and TC21 alloys

    DEFF Research Database (Denmark)

    Yuan, Baoguo; Jin, Yongyue; Hong, Chuanshi

    2017-01-01

    In order to reveal the effect of hydrogen on the room-temperature plasticity of the titanium alloys TC4 and TC21, compression tests have been carried out at room temperature. Results show that an appropriate amount of hydrogen can improve the room-temperature plasticity of both the TC4 and TC21...... alloys. The ultimate compression strain of the TC4 alloy containing a hydrogen concentration of 0.5 wt.% increases by 39% compared to the untreated material. For the TC21 alloy the ultimate compression strain is increased by 33% at a hydrogen concentration of 0.6 wt.%. The main reason for the improvement...... of hydrogen-induced room-temperature plasticity of the TC4 and TC21 alloys is discussed....

  12. Microbial reduction of 99Tc (as TcO4-) in anaerobic alkaline conditions

    International Nuclear Information System (INIS)

    Khizhnyak, T.; Simonoff, M.; Sergeant, C.; Simonoff, G.; Medvedeva-Lyalikova, N.N.

    2003-01-01

    The ability of bacteria to reduce pertechnetate in alkaline conditions was investigated using halophilic bacteria isolated from soda-lakes environments. Anaerobic halophilic bacteria were able to reduce as much as 0.25 mM pertechnetate, whereas no reduction took place without bacteria or in the presence of heat-killed bacteria. The results obtained showed reduction of Tc(VII)O 4 - to the Tc(V) and Tc(IV) at pH 10 in the carbonate-bicarbonate medium. About 57% of the total technetium was determined to be Tc(IV), 1-3% as a Tc(V) and 17-20% as a Tc(VII) after 1-3 days of incubation with bacteria. The microbial reduction of Tc(VII) in alkaline conditions has been suggested as a potential mechanism for the removal of Tc from contaminated environments or waste streams. (author)

  13. Pt and Ru X-ray absorption spectroscopy of PtRu anode catalysts in operating direct methanol fuel cells.

    Science.gov (United States)

    Stoupin, Stanislav; Chung, Eun-Hyuk; Chattopadhyay, Soma; Segre, Carlo U; Smotkin, Eugene S

    2006-05-25

    In situ X-ray absorption spectroscopy, ex situ X-ray fluorescence, and X-ray powder diffraction enabled detailed core analysis of phase segregated nanostructured PtRu anode catalysts in an operating direct methanol fuel cell (DMFC). No change in the core structures of the phase segregated catalyst was observed as the potential traversed the current onset potential of the DMFC. The methodology was exemplified using a Johnson Matthey unsupported PtRu (1:1) anode catalyst incorporated into a DMFC membrane electrode assembly. During DMFC operation the catalyst is essentially metallic with half of the Ru incorporated into a face-centered cubic (FCC) Pt alloy lattice and the remaining half in an amorphous phase. The extended X-ray absorption fine structure (EXAFS) analysis suggests that the FCC lattice is not fully disordered. The EXAFS indicates that the Ru-O bond lengths were significantly shorter than those reported for Ru-O of ruthenium oxides, suggesting that the phases in which the Ru resides in the catalysts are not similar to oxides.

  14. A model system for carbohydrates interactions on single-crystalline Ru surfaces

    Energy Technology Data Exchange (ETDEWEB)

    Nguyen, Thanh Nam

    2015-07-01

    In this thesis, I present a model system for carbohydrate interactions with single-crystalline Ru surfaces. Geometric and electronic properties of copper phthalocyanine (CuPc) on top of graphene on hexagonal Ru(0001), rectangular Ru(10 anti 10) and vicinal Ru(1,1, anti 2,10) surfaces have been studied. First, the Fermi surfaces and band structures of the three Ru surfaces were investigated by high-resolution angle-resolved photoemission spectroscopy. The experimental data and theoretical calculations allow to derive detailed information about the momentum-resolved electronic structure. The results can be used as a reference to understand the chemical and catalytic properties of Ru surfaces. Second, graphene layers were prepared on the three different Ru surfaces. Using low-energy electron diffraction and scanning tunneling microscopy, it was found that graphene can be grown in well-ordered structures on all three surfaces, hexagonal Ru(0001), rectangular Ru(10 anti 10) and vicinal Ru(1,1, anti 2,10), although they have different surface symmetries. Evidence for a strong interaction between graphene and Ru surfaces is a 1.3-1.7 eV increase in the graphene π-bands binding energy with respect to free-standing graphene sheets. This energy variation is due to the hybridization between the graphene pi bands and the Ru 4d electrons, while the lattice mismatch does not play an important role in the bonding between graphene and Ru surfaces. Finally, the geometric and electronic structures of CuPc on Ru(10 anti 10), graphene/Ru(10 anti 10), and graphene/Ru(0001) have been studied in detail. CuPc molecules can be grown well-ordered on Ru(10 anti 10) but not on Ru(0001). The growth of CuPc on graphene/Ru(10 anti 10) and Ru(0001) is dominated by the Moire pattern of graphene. CuPc molecules form well-ordered structures with rectangular unit cells on graphene/Ru(10 anti 10) and Ru(0001). The distance of adjacent CuPc molecules is 15±0.5 Aa and 13±0.5 Aa on graphene/Ru(0001

  15. Hot Cell Facility modifications at Sandia National Laboratories to support 99Mo production

    International Nuclear Information System (INIS)

    Vernon, M.; Philbin, J.; Berry, D.

    1997-01-01

    In September, 1996, following the completion of an extensive Environmental Impact Statement (EIS), a record of decision (ROD) was issued by DOE selecting Sandia as the facility to take on the 99 Mo production mission. 99 Mo is the precursor to 99m Tc which is used in 36,000 medical procedures per day in the US. to meet US 99 Mo medical demands, 20 kCi of 99 Mo must be delivered to the pharmaceutical companies each week. This could be accomplished by the processing of twenty-five targets (total fission product of 15 kCi/target) each week within the SNL Hot Cell Facility (HCF). To accomplish this new mission, significant modifications to the HCF will have to be undertaken. This paper presents a brief history of the HCF, and describes modifications necessary to achieve DOE directives

  16. Tc(V)-DMS tumour imaging agent

    International Nuclear Information System (INIS)

    Horiuchi, K.; Yomoda, I.; Yokoyama, A.; Endo, K.; Torizuka, K.

    1986-01-01

    The data obtained by the authors provide good evidence of Tc(V)-DMS as a stable, large-molecular-size Tc-complex or polynuclear Tc-complex, comparable to Tc-cit and Ga-cit. A role for this polynuclear configuration in the generation of Tc-species with affinity for neoplastic cells was demonstrated using the dilution method as a promoter of Tc(V)-DMS dissociation. The concurrent Ehrlich ascites tumour cell uptake studies with TLC analysis revealed the chromatographically detected changes well traced by the biological cell utilization. The biological implications of dilution as one of the factors regulating radiopharmaceutical delivery to the tumour cell tissue were better demonstrated in the biodistribution studies carried out with Erhlich ascites-bearing mice. If, on the basis of the present data, the authors may take their postulate one step further, a more dissociated Tc-species, defined speculatively as TcO/sub 4//sup 3-/, might constitute an active Tc- species within the cell interacting with some tumour-specific substance or site. Research to find evidence of its presence is currently in progress

  17. Measurement of the Ru surface content of electrodeposited PtRu electrodes with the electrochemical quartz crystal microbalance: implications for methanol and CO electrooxidation

    NARCIS (Netherlands)

    Frelink, T.; Visscher, W.; Veen, van J.A.R.

    1996-01-01

    To obtain the surface content of Ru in rough electrocodeposited PtRu electrodes, the mass change of a Pt electrode during Ru deposition was measured with the electrochemical quartz crystal microbalance (EQCMB). It is shown that there is a correlation between the potential of the surface oxide

  18. Reactivity toward alcohols of (Ru/sup IV/ = O/sup 2-/) unit in trans-(RuCl(O)(py)/sub 4/)/sup +/

    Energy Technology Data Exchange (ETDEWEB)

    Aoyagi, Kimitake; Nagao, Hirotaka; Yukawa, Yasuhiko; Ogura, Mariko; Kuwayama, Akito; Howell, F S; Mukaida, Masao; Kakihana, Hidetake

    1986-12-01

    The reactivity with alcohol of trans-(RuCl(O)(py)/sub 4/)/sup +/ was investigated. In MeOH, trans-(RuCl(OH)(py)/sub 4/)/sup +/ was confirmed to exist as a precursor in the formation of trans-(RuCl(OMe)(py)/sub 4/)/sup +/. The reaction progress was traced by spectrometrical and /sup 18/O-labelling experiments.

  19. Using Tc-Re chemical analogy to synthesize and identify new 99mTc complexes

    International Nuclear Information System (INIS)

    Gambino, D.; Kremer, C.; Cartesio, S.; Leon, A.; Kremer, E.

    1989-01-01

    The strong chemical resemblance between Tc and Re is applied to design and evaluate experiments with 99m Tc complexes. A combination of spectrophotometric and electrophoretic techniques allows to propose the formula [TcO 2 (amine) 2 ] + for compounds prepared by reduction of 99m TcO 4 - with Zn (solid phase) in presence of several (bidentate) amines. (author) 10 refs.; 2 figs.; 4 tabs

  20. Superconductivity in the W-Tc and W2C-Tc systems

    International Nuclear Information System (INIS)

    Giorgi, A.L.

    1985-01-01

    A series of compositions in the W-Tc, W 2 C-Re and W 2 C-Tc systems were prepared and examined for superconductivity. The crystal structure, lattice parameters and superconducting transition temperatures of the W 2 C-Tc are reported for the first time. Similar measurements were made on the W-Tc and W 2 C-Re systems and the results compared with previous published results for these systems. 7 refs., 2 figs., 2 tabs

  1. PNRI Pioneering the Establishment and Operation of the Tc-99m Generator Production Facility for Nuclear Medicine Applications

    International Nuclear Information System (INIS)

    Bulos, Adelina DM.; Borras, Ma. Teresa L.; Ciocson, Gregory R.; Mascariñas, Rommel D.C.; Nuñez, Ivy Angelica A.; Dela Rosa, Alumanda M.

    2015-01-01

    In response to the increasing demand in the nuclear medicine sector in the Philippines, the Philippine Nuclear Research Institute (PNRI) initiated the establishment of a radioisotope production facility. To date, the most commonly used radioisotope in nuclear medicine, Technetium-99m or Tc-99m has been successfully produced in the new laboratory, the PNRI facility has already obtained a license to operate from the Philippine FDA. The new facility is envisioned to meet the country’s requirements for all the major medical radioisotope starting with the local production of Tc-99m and the most commonly used Tc-99m radiopharmaceuticals. At present, all radioisotope supplies in the country are sourced overseas at price that varies accordingly. With the establishment of the PNRI’s laboratories, we now have a GMP-grade Tc-99m generator facility capable of producing 50 Tc-99m generators per batch. Instead of Tc-99m being imported, it will be the parent Mo-99m that will be transferred to PNRI facility from Mo-99 processing facilities overseas, contained in specialized transport containers and via airfreight arrangements so it can be processed locally to make Tc-99m generators. But, to make radiopharmaceuticals, the other non-radioactive components are needed to be sourced from abroad. Thus, it has become imperative to also locally produce these non-radioactive components. All of these components, radioactive and non-radioactive, from the radiopharmaceutical finished products which are utilized in nuclear medicine caters for the diagnosis and detection of critical and non-critical human illnesses. The completion of this program is foreseen as another concrete validation on the capacity of the Philippine as a country that is at par with advanced nations on competency and expertise in the research and development of nuclear medicine application for better healthcare delivery and management. (author)

  2. Thermal conduction properties of Mo/Si multilayers for extreme ultraviolet optics

    Science.gov (United States)

    Bozorg-Grayeli, Elah; Li, Zijian; Asheghi, Mehdi; Delgado, Gil; Pokrovsky, Alexander; Panzer, Matthew; Wack, Daniel; Goodson, Kenneth E.

    2012-10-01

    Extreme ultraviolet (EUV) lithography requires nanostructured optical components, whose reliability can be influenced by radiation absorption and thermal conduction. Thermal conduction analysis is complicated by sub-continuum electron and phonon transport and the lack of thermal property data. This paper measures and interprets thermal property data, and their evolution due to heating exposure, for Mo/Si EUV mirrors with 6.9 nm period and Mo/Si thickness ratios of 0.4/0.6 and 0.6/0.4. We use time-domain thermoreflectance and the 3ω method to estimate the thermal resistance between the Ru capping layer and the Mo/Si multilayers (RRu-Mo/Si = 1.5 m2 K GW-1), as well as the out-of-plane thermal conductivity (kMo/Si 1.1 W m-1 K-1) and thermal anisotropy (η = 13). This work also reports the impact of annealing on thermal conduction in a co-deposited MoSi2 layer, increasing the thermal conductivity from 1.7 W m-1 K-1 in the amorphous phase to 2.8 W m-1 K-1 in the crystalline phase.

  3. [Population Council responsible for RU486 clinical trials in USA].

    Science.gov (United States)

    Aguillaume, C J

    1993-04-01

    As a result of the sudden political change that came with the Clinton Administration, RU-486's manufacturer, Roussel-Uclaf, and the Population Council agreed on April 20, 1992, on the manufacture and distribution of RU-486 in the US. In the US, there are less than 1.6 million induced abortions annually. From now on, US women will be able to have a choice between medical and surgical abortion. The Population Council and Roussel-Uclaf have had a contract since 1982. The Council is solely responsible for the phase 2 clinical trial of RU-486 in the US and other countries. It must present to the US Food and Drug Administration (FDA) an amendment allowing it to begin phase 3 clinical trials. The Council will also lead the US medical facilities in this study. It will identify partners for future production of RU-486 and its distribution in the US. It will also submit to FDA a New Drug Application (NDA). FDA will review the scientific literature on RU-486 and evaluate all data submitted by the Population Council. There are still obstacles to be surmounted. The Population Council must demonstrate good judgment when selecting the criteria for choosing a pharmaceutical firm before a Technical Committee which will be part of a group of players promoting women's health, scientific experts, and other interested parties. It must find the necessary funds to conduct the clinical trials and prepare the NDA. Phase 3 clinical trials in the US must have at least 2000 women. They will test RU-486's efficacy, safety, and acceptability among women choosing medical abortion over surgical abortion. Since the Council operates in almost all countries in the world, has innovated contraceptive research and development activities, and has been endorsed by the UN, product approval of RU-486 in the US will affect policy in all countries concerned about abortion.

  4. Phase formation in K2O(K2CO3)-CdO-MoO3 system

    International Nuclear Information System (INIS)

    Tsirenova, G.D.; Tsybikova, B.A.; Bazarova, Zh.G.; Solodovnikov, S.F.; Zolotova, E.S.

    2000-01-01

    Phase formation in K 2 O(K 2 CO 3 )-CdO-MoO 3 system are studied by the methods of x-ray diffraction, thermal and crystal optical analyses. Three potassium-cadmium molybdates are detected: K 4 Cd(MoO 4 ) 3 with a new structure, alluodite-like K 4-2x Cd 1+x (MoO 4 ) 3 (0.26≤x≤0.38 at 470 Deg C) and K 4 CdMo 4 O 15 of K 4 MnMo 4 O 15 type. First of them decomposes in solid phase at 580 Deg C, and others melt incongruently at 720 and 515 Deg C correspondingly. It is established that K 4-2x Cd 1+x (MoO 4 ) 3 compound undergoes phase transition of the second type in the temperature interval of 500-550 Deg C. Phase diagram of quasibinary cross section K 2 MoO 4 -CdMoO 4 is plotted [ru

  5. Prospects of zero Schottky barrier height in a graphene-inserted MoS2-metal interface

    Science.gov (United States)

    Chanana, Anuja; Mahapatra, Santanu

    2016-01-01

    A low Schottky barrier height (SBH) at source/drain contact is essential for achieving high drive current in atomic layer MoS2-channel-based field effect transistors. Approaches such as choosing metals with appropriate work functions and chemical doping are employed previously to improve the carrier injection from the contact electrodes to the channel and to mitigate the SBH between the MoS2 and metal. Recent experiments demonstrate significant SBH reduction when graphene layer is inserted between metal slab (Ti and Ni) and MoS2. However, the physical or chemical origin of this phenomenon is not yet clearly understood. In this work, density functional theory simulations are performed, employing pseudopotentials with very high basis sets to get insights of the charge transfer between metal and monolayer MoS2 through the inserted graphene layer. Our atomistic simulations on 16 different interfaces involving five different metals (Ti, Ag, Ru, Au, and Pt) reveal that (i) such a decrease in SBH is not consistent among various metals, rather an increase in SBH is observed in case of Au and Pt; (ii) unlike MoS2-metal interface, the projected dispersion of MoS2 remains preserved in any MoS2-graphene-metal system with shift in the bands on the energy axis. (iii) A proper choice of metal (e.g., Ru) may exhibit ohmic nature in a graphene-inserted MoS2-metal contact. These understandings would provide a direction in developing high-performance transistors involving heteroatomic layers as contact electrodes.

  6. Diffusion barrier performances of thin Mo, Mo-N and Mo/Mo-N films between Cu and Si

    International Nuclear Information System (INIS)

    Song Shuangxi; Liu Yuzhang; Mao Dali; Ling Huiqin; Li Ming

    2005-01-01

    In this work, we have studied the diffusion barrier performances of Mo, Mo-N and Mo/Mo-N metallization layers deposited by sputtering Mo in Ar/N 2 atmospheres, respectively. Samples were subsequently annealed at different temperatures ranging from 400 to 800 deg C in vacuum condition. The film properties and their suitability as diffusion barriers and protective coatings in silicon devices were characterized using four-point probe measurement, X-ray diffractometry, scanning electron microscopy, Auger electron spectroscopy and transmission electron microscopy analyses. Experimental results revealed that the Mo (20 nm)/Mo-N (30 nm) layer was able to prevent the diffusion reaction between Cu and Si substrate after being annealed at 600 deg C for 30 min. The adhesion between layers and the content of N atoms are the key parameters to improve the properties of Mo-based barrier materials. The Mo layer interposed between Cu and Mo-N diluted the high nitrogen concentration of the barrier and so enhanced the barrier performances

  7. Scavenging of Tc(V) formed by I.T. in 95mTcO4- solutions

    International Nuclear Information System (INIS)

    Ianoz, E.; Colin, M.; Kosinski, M.

    1988-01-01

    The chemical effects of the I.T. of 95m Tc in 95m TcO 4 - have been studied in chelating ligand solutions. At high pH and at high concentration of 1,4,8,11-tetraazacyclotetradecane and 1,4-dithia-8, 11-diazacyclotetradecane, the retention of 95g Tc is about 20% and the unretained 95g Tc appears preponderantly (ca. 73%) as [TcO 2 L] + complexes. In glucoheptonate solution, the 95g Tc retention remains practically the same (22%) but the unretained 95g Tc is found in high proportion (73%) as [TcObis(glucoheptonate)] - . The added ligands are very good scavengers for 95g Tc(V). A comparison is made between 95g Tc species formed by the I.T. in 95m TcO 4 - and 99m Tc species resulting from the chemical reduction of 99m TcO 4 - . (orig.)

  8. Solubility study of Tc(IV) oxides

    International Nuclear Information System (INIS)

    Liu, D.J.; Fan, X.H.

    2005-01-01

    The deep geological disposal of the high level radioactive wastes is expected to be a safer disposal method in most countries. The long-lived fission product 99 Tc is present in large quantities in nuclear wastes and its chemical behavior in aqueous solution is of considerable interest. Under oxidizing conditions technetium exists as the anionic species TcO 4 - whereas under the reducing conditions, expected to exist in a deep geological repository, it is generally predicted that technetium will be present as TcO 2 ·nH 2 O. Hence, the mobility of Tc(IV) in reducing groundwater may be limited by the solubility of TcO 2 ·nH 2 O under these conditions. Due to this fact it is important to investigate the solubility of TcO 2 ·nH 2 O. The solubility determines the release of radionuclides from waste form and is used as a source term in radionuclide migration analysis in performance assessment of radioactive waste repository. Technetium oxide was prepared by reduction of a technetate solution with Sn 2 + . The solubility of Tc(IV) oxide has been determined in simulated groundwater and redistilled water under aerobic and anaerobic conditions. The effects of pH and CO 3 2- concentration of solution on solubility of Tc(IV) oxide were studied. The concentration of total technetium and Tc(IV) species in the solutions were periodically determined by separating the oxidized and reduced technetium species using a solvent extraction procedure and counting the beta activity of the 99 Tc with a liquid scintillation counter. The experimental results show that the rate of oxidation of Tc(IV) in simulated groundwater and redistilled water is about (1.49-1.86) x 10 -9 mol/(L·d) under aerobic conditions, but Tc(IV) in simulated groundwater and redistilled water is not oxidized under anaerobic conditions. Under aerobic or anaerobic conditions the solubility of Tc(IV) oxide in simulated groundwater and redistilled water is equal on the whole after centrifugation or ultrafiltration. The

  9. Present status of the use of LEU in aqueous reactors to produce Mo-99

    International Nuclear Information System (INIS)

    Ball, Russell M.; Pavshook, V.A.; Khvostionov, V.Ye.

    1998-01-01

    An operating aqueous homogeneous reactor, the ARGUS at Kurchatov Institute, has been used to produce fission product molybdenum-99 (Mo-99), widely used in nuclear medicine to produce technetium-99m (Tc-99m). The Mo-99 has been extracted from the sulfate solution using an organic sorbent after operation at 1 kW/liter. after purification, the material has been assayed and the result is well within required specification of the USPharmacopaeia. Operation calculation are presented to show the sources and quantity of alpha activity when LEU is used. (author)

  10. Acoustic properties of TiNiMoFe base alloys

    International Nuclear Information System (INIS)

    Gyunter, V.Eh.; Chernyshev, V.I.; Chekalkin, T.L.

    2000-01-01

    The regularity of changing the acoustic properties of the TiNi base alloys in dependence on the alloy composition and impact temperature is studied. It is shown that the oscillations of the TiNiMoFe base alloys within the temperature range of the B2 phase existence and possible appearance of the martensite under the load differ from the traditional materials oscillations. After excitation of spontaneous oscillations within the range of M f ≤ T ≤ M d there exists the area of long-term and low-amplitude low-frequency acoustic oscillations. It is established that free low-frequency oscillations of the TH-10 alloy sample are characterized by the low damping level in the given temperature range [ru

  11. Syntheses, structures, and physicochemical properties of diruthenium compounds of tetrachlorocatecholate with metal-metal bonded Ru(3+)(mu-OR)(2)Ru(3+) and Ru(3.5+)(mu-OR)(2)Ru(3.5+) cores (R = CH(3) and C(2)H(5)).

    Science.gov (United States)

    Miyasaka, H; Chang, H C; Mochizuki, K; Kitagawa, S

    2001-07-02

    Metal-metal bonded Ru(3+)(mu-OR)(2)Ru(3+) and Ru(3.5+)(mu-OR)(2)Ru(3.5+) (R = CH(3) and CH(3)CH(2)) compounds with tetrachlorocatecholate (Cl(4)Cat) have been synthesized in the corresponding alcohol, MeOH and EtOH, from a nonbridged Ru(2+)-Ru(3+) compound, Na(3)[Ru(2)(Cl(4)Cat)(4)(THF)].3H(2)O.7THF (1). In alcohol solvents, compound 1 is continuously oxidized by oxygen to form Ru(3+)(mu-OR)(2)Ru(3+) and Ru(3.5+)(mu-OR)(2)Ru(3.5+) species. The presence of a characteristic countercation leads to selective isolation of either Ru(3+)(mu-OR)(2)Ru(3+) or Ru(3.5+)(mu-OR)(2)Ru(3.5+) as a stable adduct species. In methanol, Ph(4)PCl and dibenzo-18-crown-6-ether afford Ru(3+)(mu-OMe)(2)Ru(3+) species, [A](2)[Ru(2)(Cl(4)Cat)(4)(mu-OMe)(2)Na(2)(MeOH)(6)] ([A](+) = Ph(4)P(+) (2), [Na(dibenzo-18-crown-6)(H(2)O)(MeOH)](+) (3)), while benzo-15-crown-5-ether provides a Ru(3.5+)(mu-OMe)(2)Ru(3.5+) species, [Na(benzo-15-crown-5)(2)][Ru(2)(Cl(4)Cat)(4)(mu-OMe)(2)Na(2)(MeOH)(6)] (4). The air oxidation of 1 in a MeOH/EtOH mixed solvent (1:1 v/v) containing benzo-15-crown-5-ether provides a Ru(3.5+)(mu-OMe)(2)Ru(3.5+) species, [Na(benzo-15-crown-5)(H(2)O)][Ru(2)(Cl(4)Cat)(2)(mu-OMe)(2)Na(2)(EtOH)(2)(H(2)O)(2)(MeOH)(2)].(benzo-15-crown-5) (5). Similarly, the oxidation of 1 in ethanol with Ph(4)PCl provides a Ru(3.5+)(mu-OEt)(2)Ru(3.5+) species, (Ph(4)P)[Ru(2)(Cl(4)Cat)(4)(mu-OEt)(2)Na(2)(EtOH)(6)] (7). A selective formation of a Ru(3+)(mu-OEt)(2)Ru(3+) species, (Ph(4)P)(2)[Ru(2)(Cl(4)Cat)(4)(mu-OEt)(2)Na(2)(EtOH)(2)(H(2)O)(2)] (6), is found in the presence of pyrazine or 2,5-dimethylpyrazine. The crystal structures of these compounds, except 2 and 7, have been determined by X-ray crystallography, and all compounds have been characterized by several spectroscopic and magnetic investigations. The longer Ru-Ru bonds are found in the Ru(3+)(mu-OR)(2)Ru(3+) species (2.606(1) and 2.628(2) A for 3 and 6, respectively) compared with those of Ru(3.5+)(mu-OMe)(2)Ru(3.5+) species (2.5260(6) A and 2

  12. Standard enthalpies of formation of selected Ru{sub 2}YZ Heusler compounds

    Energy Technology Data Exchange (ETDEWEB)

    Yin, Ming, E-mail: myin1@hawk.iit.edu; Nash, Philip

    2015-06-15

    Highlights: • Standard enthalpies of formation of Ru{sub 2}YZ were measured using a drop calorimeter. • Result of L2{sub 1} structured compounds agrees with first principles data. • Lattice parameters and related phase relationships were consistent with literature data. • Ru{sub 2}HfSn, Ru{sub 2}TiSn, Ru{sub 2}VGa, Ru{sub 2}VSi, Ru{sub 2}VSn of L2{sub 1} structure were reported for the first time. - Abstract: The standard enthalpies of formation of selected ternary Ru-based Heusler compounds Ru{sub 2}YZ (Y = Fe, Hf, Mn, Ti, V; Z = Al, Ga, In, Si, Ge, Sn) were measured using high temperature direct reaction calorimetry. The measured enthalpies of formation (in kJ/mole of atoms) of the Heusler compounds are, Ru{sub 2}FeGe (−19.7 ± 3.3); Ru{sub 2}HfSn (−24.9 ± 3.6); Ru{sub 2}MnSi (−46.0 ± 2.6); Ru{sub 2}MnGe (−29.7 ± 1.0); Ru{sub 2}MnSn (−20.6 ± 2.4); Ru{sub 2}TiSi (−94.9 ± 4.0); Ru{sub 2}TiGe (−79.1 ± 3.2); Ru{sub 2}TiSn (−60.6 ± 1.8); Ru{sub 2}VSi (−55.9 ± 1.7);for the B2-structured compounds, Ru{sub 2}FeSi (−28.5 ± 0.8); Ru{sub 2}HfAl (−70.8 ± 1.9); Ru{sub 2}MnAl (−32.3 ± 1.9); Ru{sub 2}MnGa (−25.3 ± 3.0); Ru{sub 2}TiAl (−62.7 ± 3.5); Ru{sub 2}VAl (−30.9 ± 1.6); Ru{sub 2}ZrAl (−64.5 ± 1.5). Values were compared with those from published first principles calculations and the OQMD (Open Quantum Materials Database). Lattice parameters of these compounds were determined using X-ray diffraction analysis (XRD). Microstructures were identified using scanning electron microscopy (SEM) and Energy Dispersive Spectroscopy (EDS)

  13. Precision measurement of the half-life of {sup 90m}Nb and {sup 99m}Tc

    Energy Technology Data Exchange (ETDEWEB)

    Kikunaga, H.; Fujisawa, H.; Ooe, K. [Osaka Univ., Toyonaka (Japan). Graduate School of Science] [and others

    2011-07-01

    We have produced {sup 90m}Nb and {sup 99m}Tc in the reactions of {sup nat}Zr(p, xn){sup 90m}Nb and {sup 100}Mo({gamma}, n){sup 99}Mo, followed by disintegration to {sup 99m}Tc, respectively, and measured the halflives of these nuclides by using a reference source method. In order to determine the short half-lives of {sup 90m}Nb precisely, an on-line gas-jet system has been employed. As a result, the half-lives of these nuclides were determined with good precision on the order of magnitude of 0.1%. (orig.)

  14. The utilization and performance of poly zirconium chloride (PZC) as chromatographic column for 99mTc generator

    International Nuclear Information System (INIS)

    Wan Anuar Wan Awang; Zulkifli Mohd Hashim; Saaban Kassim

    2004-01-01

    We report on the performance test of column 99m Tc generator utilizing poly zirconium chloride as an adsorbent. Natural molybdenum trioxide was irradiated for 2 hrs at a neutron flux of about 1.5 x 10 12 n/cm 2 /s. A total fourteen generators have been prepared from the experiments. Yield of 99m Tc has been 60-93% and measured 99 Mo content in eluates is 0.20-0.44 %. The adsorption efficiency of 99 Mo on PZC column is between 85 - 92 %. The flow rates from the elution are relatively very poor and take about 5 minutes to finish the elution of 1 ml saline. (author)

  15. Neutron diffraction study of single crystalline ErCo10Mo2

    International Nuclear Information System (INIS)

    Janssen, Y.; De Boer, F.R.; Brueck, E.; Tegus, O.; Ma, L.; Buschow, K.H.J.; Reehuis, M.

    1999-01-01

    Complete text of publication follows. The ferrimagnetic intermetallic compound ErCo 10 Mo 2 (Tc = 600 K) crystallizes in the tetragonal ThMn 12 -type structure (space group 14/mmm). The Co and Mo atoms may share three crystallographic sites (8f, 8i and 8j). Earlier neutron powder diffraction experiments show that Mo has a strong preference for the 8i-site and that the magnetic ordering at low temperature is planar. Furthermore ErCo 10 Mo 2 has been reported to show one [2] or more [3] spin-reorientation transitions from planar to axial magnetic ordering. Recently we succeeded in growing a single-crystalline sample of ErCo 10 Mo 2 . Magnetic measurements in 1T show one spin-reorientation transition at about 135 K. Neutron diffraction experiments were performed to investigate a possible link between the magnetic properties and the site occupation by Mo. Our results show that our sample has the Mo atoms exclusively occupying half the 8i-sites. There is no evidence for a crystallographic superstructure. Furthermore, below 150 K some reflections strongly increase due to the growing Er magnetic moment. (author)

  16. Dynamical spin structure factors of α-RuCl3

    Science.gov (United States)

    Suzuki, Takafumi; Suga, Sei-ichiro

    2018-03-01

    Honeycomb-lattice magnet α-RuCl3 is considered to be a potential candidate of realizing Kitaev spin liquid, although this material undergoes a phase transition to the zigzag magnetically ordered state at T N ∼ 7 K. Quite recently, inelastic neutron-scattering experiments using single crystal α-RuCl3 have unveiled characteristic dynamical properties. We calculate dynamical spin structure factors of three ab-initio models for α-RuCl3 with an exact numerical diagonalization method. We also calculate temperature dependences of the specific heat by employing thermal pure quantum states. We compare our numerical results with the experiments and discuss characteristics obtained by using three ab-initio models.

  17. Growth model of Au films on Ru(001)

    International Nuclear Information System (INIS)

    Canessa, E.; Calmetta, A.

    1992-06-01

    In an attempt to find generic features on the fractal growth of Au films deposited on Ru(001), a simple simulation model based on irreversible diffusion-limited aggregation (DLA) is discussed. Highly irregular two-dimensional dentritic islands of Au particles that gradually grow on a larger host lattice of Ru particles and have fractal dimension d f approx. 1.70 each, are generated via a multiple had-hoc version of the DLA algorithm for single aggregates. Annealing effects on the islands morphology are reproduced assuming different sticking probabilities at nearest-neighbour lattice sites of Au films on Ru(001). Using simulation data, islands growth are described in analogy to diffusion-limited, precipitate growth with soft impingement of precipities. This leads to analyse thin film island growth kinetics in such fractal systems and to predict a main peak in scattering intensity patterns due to interisland interference. (author). 12 refs, 4 figs

  18. On the solubility of yttrium in RuO2

    International Nuclear Information System (INIS)

    Music, Denis; Zumdick, Naemi A.; Hallstedt, Bengt; Schneider, Jochen M.

    2011-01-01

    We have investigated the solubility of Y in rutile RuO 2 using experimental and theoretical methods. Nanostructured Ru-Y-O thin films were synthesized via combinatorial reactive sputtering with an O/metal ratio of 2.6 and a Y content of 0.3 to 12.6 at. %. A solubility limit of 1.7 at. % was identified using x-ray photoelectron spectroscopy and x-ray diffraction. Based on ab initio and thermodynamic modeling, the solubility of Y can be understood. Smaller Y amounts are incorporated into the lattice, forming a metastable film, with local structural deformations due to size effects. As the Y content is increased, extensive local structural deformations are observed, but phase separation does not occur due to kinetic limitations. Nanostructured RuO 2 alloyed with Y might lead to enhanced phonon scattering and quantum confinement effects, which in turn improve the thermoelectric efficiency.

  19. Accumulation, elimination and retention of 99Tc by duckweed

    International Nuclear Information System (INIS)

    Hattink, J.; Weltje, L.; Wolterbeek, H.Th.; Goeij, J.J.M. de

    2004-01-01

    Accumulation dynamics of the long-lived fission product technetium ( 99 Tc) in duckweed is studied. Duckweed serves as model for aquatic plants, because of its representative foliar uptake for 99 Tc. 99 Tc is irreversibly accumulated and distributed over cytoplasm, chloroplasts and mitochondria. Autoradiography showed that 99 Tc was not transported to new biomass. Irreversible storage of 99 Tc in plant biomass means that steady-state situations cannot be interpreted as a balance between uptake and elimination of 99 Tc, but that 99 Tc continuously builds up in each single duckweed plant and overall Tc concentrations are averaged over new biomass. (author)

  20. Development of more efficacious Tc-99m organ imaging agents for use in nuclear medicine by analytical characterization of radiopharmaceutical mixtures. Progress report, May 1, 1982-April 30, 1983

    International Nuclear Information System (INIS)

    Heineman, W.R.; Deutsch, E.A.

    1982-11-01

    A procedure based on high performance liquid chromatography (HPLC) has been developed for separating individual Tc-diphosphonate complexes in skeletal-imaging radiopharmaceuticals prepared by reduction of TcO 4 - with NaBH 4 in the presence of methylene diphosphonate (MDP). Seven different Tc-MDP complexes have been detected and isolated in pure form. Significant differences in skeletal uptake and blood clearance are exhibited by the three complexes tested thus far by biodistribution studies in test animals. The relative quantities of these complexes present in a radiopharmaceutical preparation are dramatically influenced by the pH of the reaction mixture. Thus, control of pH is a simple means of forming in high yield the single, most efficacious Tc-MDP complex for skeletal imaginG. An HPLC method with electrochemical detection has been developed for the analytical determination of total TcO 4 - (/sup 99m/Tc + 99 Tc). Concentrations of TcO 4 - as low as 9 x 10 -9 M can be detected. The method is being evaluated for monitoring total TcO 4 - in 99 Mo//sup 99m/Tc generators

  1. Development of more efficacious /sup 99m/Tc organ imaging agents for use in nuclear medicine by analytical characterization of radiopharmaceutical mixtures. Progress report, May 1, 1983-January 1, 1986

    International Nuclear Information System (INIS)

    Heineman, W.R.

    1986-01-01

    The formation of many different technetium complexes in the Tc(NaBH 4 )-HEDP, Tc(NaBH 4 )-MDP, and Tc(NaBH 4 )-DMAD systems has been clearly demonstrated by HPLC-separation of reaction mixtures. The dramatically different biodistributions exhibited by the various complexes strongly suggests that an improved skeletal radiopharmaceutical would result if the single technetium complex which exhibits the optimum biodistribution properties is administered to the patient. The influence of pH, time, concentrations of TcO 4 - and ligand, and the nature of reductant on the relative amounts of the different complexes formed were investigated. Electrochemical reduction offers a means of possibly generating a desired complex in very high yield due to the precision with which redox potential can be controlled. Additionally, we have developed HPLC methods with uv and electrochemical detection for the determination of total TcO 4 - in eluents from the 99 Mo//sup 99m/Tc radionuclide generator. The inadequacy of current theory to accurately predict total TcO 4 - in generator eluents was demonstrated in that the concentration of total TcO 4 - is a major factor determining the yield of individual Tc-diphosphonate complexes. Spectroelectrochemistry proved an effective technique to study the redox properties of Tc-complexes. 18 refs., 10 figs., 1 tab

  2. Estimation of internal exposure to 99Mo in nuclear medicine patients

    International Nuclear Information System (INIS)

    Dantas, B.M.; Silva, C.O.A. da; Dantas, A.L.A.; Lucena, E.A.; Souza, W.O.

    2008-01-01

    99m Tc is the most widely used radionuclide in nuclear medicine. It is obtained by elution of 99 Mo- 99m Tc generators. Depending on the quality of the generator and its integrity, 99 Mo might be extracted from the column during the elution process, becoming a radionuclidic impurity in the 99m Tc eluate. This fact would impart an undesired dose to the patients submitted to diagnostic procedures using 99m Tc. The aims of this work are: to evaluate the incorporation of 99 Mo as a radionuclidic impurity using in vivo and in vitro techniques; to estimate the internal effective doses in nuclear medicine patients and; to provide additional information about the metabolic behavior of molybdenum in humans. A methodology based on in vivo measurements and urine sampling was developed to determine retention and excretion patterns of molybdenum in the human body. In vivo measurements were performed in IRD whole body counter using a NaI(Tl) 8”x4” scintillation detector. The detector is located inside a shielded room with internal dimensions of 2.5 x 2.5 x 2.65 meters. In vitro analysis was based on the collection of urine samples from the patients and was performed in IRD bioassay laboratory using a High Purity Germanium (HPGe) detection system. Four patients have been monitored by in vivo and in vitro measurements showing detectable activities of 99 Mo in whole body and urine samples. Bioassay results were interpreted by using AIDE software version 6. Estimated values of 99 Mo incorporation were compared to predicted values based on the standard metabolic model of molybdenum established by the International Commission of Radiological Protection (ICRP). Internal effective doses were estimated in the order of micro sieverts per examination. Based on the data obtained in this work it is suggested to implement a routine quality control program of radionuclidic impurity of 99 Mo in 99m Tc eluates to be conducted by radiopharmacy laboratories of nuclear medicine centers. (author)

  3. Separation of fission 99Mo by alpha-benzoin oxime precipitation in nitric medium

    International Nuclear Information System (INIS)

    Yamaura, Mitiko; Freitas, Antonio A.; Egute, Nayara dos S.; Camilo, Ruth L.; Araujo, Izilda C.; Forbicini, Christina A.L.G. de O.

    2011-01-01

    Since 2009, the production of generators 99 Mo/ 99 mTc suffers a crisis of global supply due to technical problems of the two reactors which account for 64% of world production of fission 99 Mo. By the project of Brazilian Multipurpose Reactor (RMB), the Brazilian government invests in the construction of the first multipurpose reactor suitable for the domestic production of 99 Mo from LEU targets in order to supply of fission 99 Mo in the coming decades. The IPEN started the research of the technology and production of fission 99 Mo from acid and alkaline dissolutions of Low Enriched Uranium (LEU) targets as well as other used radioisotopes in nuclear medicine. This work is part of the research of the technology of the fission 99 Mo from acid dissolution of the LEU targets that is being developed at the IPEN. In this study the separation of the Mo by precipitation with alpha-benzoin oxime in nitric medium and the recovery by dissolution were investigated. The precipitation studies were performed by batch assays with nitric solution of Mo(VI), containing 99 Mo tracer, and uranyl ions. Influence of concentration of permanganate from 0.03 to 2.5%, dissolution temperature at 30 deg C and 150 deg C and the uranium concentration from 74 g.L -1 to 115 g.L -1 was studied. Results indicated that the precipitation of Mo with alpha-benzoin oxime from nitric medium is highly efficient, and its recovery by dissolution with basic solution of H 2 O 2 gave a high yield. (author)

  4. Pristine Basal- and Edge-Plane-Oriented Molybdenite MoS2 Exhibiting Highly Anisotropic Properties.

    Science.gov (United States)

    Tan, Shu Min; Ambrosi, Adriano; Sofer, Zdenĕk; Huber, Štěpán; Sedmidubský, David; Pumera, Martin

    2015-05-04

    The layered structure of molybdenum disulfide (MoS2 ) is structurally similar to that of graphite, with individual sheets strongly covalently bonded within but held together through weak van der Waals interactions. This results in two distinct surfaces of MoS2 : basal and edge planes. The edge plane was theoretically predicted to be more electroactive than the basal plane, but evidence from direct experimental comparison is elusive. Herein, the first study comparing the two surfaces of MoS2 by using macroscopic crystals is presented. A careful investigation of the electrochemical properties of macroscopic MoS2 pristine crystals with precise control over the exposure of one plane surface, that is, basal plane or edge plane, was performed. These crystals were characterized thoroughly by AFM, Raman spectroscopy, X-ray photoelectron spectroscopy, voltammetry, digital simulation, and DFT calculations. In the Raman spectra, the basal and edge planes show anisotropy in the preferred excitation of E2g and A1g phonon modes, respectively. The edge plane exhibits a much larger heterogeneous electron transfer rate constant k(0) of 4.96×10(-5) and 1.1×10(-3)  cm s(-1) for [Fe(CN)6 ](3-/4-) and [Ru(NH3 )6 ](3+/2+) redox probes, respectively, compared to the basal plane, which yielded k(0) tending towards zero for [Fe(CN)6 ](3-/4-) and about 9.3×10(-4)  cm s(-1) for [Ru(NH3 )6 ](3+/2+) . The industrially important hydrogen evolution reaction follows the trend observed for [Fe(CN)6 ](3-/4-) in that the basal plane is basically inactive. The experimental comparison of the edge and basal planes of MoS2 crystals is supported by DFT calculations. © 2015 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

  5. Fuel management simulation for CANFLEX-RU in CANDU 6

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Chang Joon; Suk, Ho Chun [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1997-12-31

    Fuel management simulations have been performed for CANFLEX-09% RU fuel in the CANDU 6 reactor. In this study, the bi-directional 4-bundle shift fuelling scheme was assumed. The lattice cell and time-average calculation were carried out. The refuelling simulation calculations were performed for 600 full power days. Time-averaged results show good axial power profile with the CANFLEX-RU fuel. During the simulation period, the maximum channel and bundle power were maintained below the licensing limit of CANDU 6 reactor. 7 refs., 4 figs. (Author)

  6. Role of steps in N-2 act