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.

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.

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.

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)

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

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.

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)

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

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

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.

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).

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.

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.

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.)

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)

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)

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)

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.

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)

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)

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)

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)

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)

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)

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)

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.

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.

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.

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)

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)

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

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)

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)

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)

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

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

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

{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)

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.)

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)

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)

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)

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)

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)

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.

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.

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

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)

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)

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)

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)

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)

'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.

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.)

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.

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)

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)

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)

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.

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

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)

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.

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.

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

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

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.

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)

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

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.)

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.

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.

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)

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

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)

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)

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)

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

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

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)

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.

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)

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)

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)

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.

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.

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.

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

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.

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)

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)

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

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)

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.

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.

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. ...

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)

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)

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)

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

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)

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)

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

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)

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)

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.

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)

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.

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

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

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

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)

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

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)

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)

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

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

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.

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)

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.

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)

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

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)

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).

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)

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.

DFT study of the hexagonal high-entropy alloy fission product system

Energy Technology Data Exchange (ETDEWEB)

King, D.J.M., E-mail: daniel.miks@live.com [School of Electrical Engineering, University of New South Wales, Kensington, 2052, NSW (Australia); Institute of Materials Engineering, Australian Nuclear Science and Technology Organisation, Lucas Heights, NSW (Australia); Burr, P.A.; Obbard, E.G. [School of Electrical Engineering, University of New South Wales, Kensington, 2052, NSW (Australia); Institute of Materials Engineering, Australian Nuclear Science and Technology Organisation, Lucas Heights, NSW (Australia); Middleburgh, S.C. [Westinghouse Electric Sweden AB, SE-721 63, Västerås (Sweden); Department of Materials, Imperial College London, South Kensington, London, SW7 2AZ (United Kingdom); KTH Royal Institute of Technology, Reactor Physics, 106 91 Stockholm (Sweden)

2017-05-15

The metallic phase fission product containing Mo-Pd-Rh-Ru-Tc can be described as a hexagonal high-entropy alloy (HEA) and is thus investigated using atomic scale simulation techniques relevant to HEAs. Contrary to previous assumptions, the removal of Tc from the system to form the Mo-Pd-Rh-Ru analog is predicted to reduce the stability of the solid solution to the point that σ-Mo{sub 5}Ru{sub 3} may precipitate out at typical fuel operating temperatures. The drive for segregation is attributed to the increased stability of the solid solution with the ejection of Mo and Ru. When Tc is included in the system, a single phase hexagonal solid solution is expected to form for a wider range of compositions. Furthermore, when cooled below 700 °C, this single phase solid solution is predicted to transition to a partially ordered structure. Future studies using the Tc-absent analogue will need to take these structural and chemical deliberations into consideration.

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)

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

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)

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

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

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)

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)

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)

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.

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)

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

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

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...

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

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)

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.

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.

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.

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)

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.

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

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)

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)

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

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)

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)

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)

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)

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)

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)

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)

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

Oxidation behaviour of noble-metal inclusions in used UO2 nuclear fuel

International Nuclear Information System (INIS)

McEachern, R.

1997-07-01

The literature on the chemistry of the noble-metal (Mo-Rh-Ru-Pd-Tc) inclusions found in used nuclear fuel has been reviewed. The Mo-Ru-Pd phase diagram is reasonably well understood, and the pseudoternary Mo-(Tc+Ru)-Rh+Pd) system can be used to qualitatively understand the phase chemistry of the noble-metal inclusions. The kinetics of the oxidation reaction are not particularly well understood, but they are of limited applicability to understanding the properties of used fuel. In contrast, it is important to determine the thermodynamic activity of molybdenum in noble-metal inclusions, so that analysis of their molybdenum content can be used as a probe of the local oxygen potential of the used fuel. (author)

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

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

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

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)

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)

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

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.

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)

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.

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.

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)

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)

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).

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)

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)

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)

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)

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).

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)

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.

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

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

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)

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.

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)

Some phase diagram studies of systems with fission product elements for fast reactor fuels

International Nuclear Information System (INIS)

Haines, H.R.; Potter, P.E.; Rand, M.H.

1979-01-01

The results of some experimental studies on the uranium-carbon- and plutonium-carbon-ternary systems with rhenium and technetium are first described. All the systems are characterized by ternary compounds; in particular two new ternary compounds are reported for the U-Tc-C system. Some studies on the Pu-Cr-C system have revealed two ternary compounds whilst there are no such compounds found in the Pu-Ni-C system. In the second part of the paper some calculations of phase diagrams of the binary systems Mo-Tc, Tc-Rh and Tc-Pd together with the ternary systems Mo-Tc-Rh, Mo-Tc-Pd and Mo-Ru-Pd are presented. A regular solution model has been used to describe the thermodynamic properties of the solutions. (orig.) [de

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

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

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).

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)

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

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

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

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

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)

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)

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....

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.)

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)

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

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)

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)

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.)

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

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

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)

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

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)

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)

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)

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.).

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)

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)

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)

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

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.

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.

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)

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)

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.

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.

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

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.

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

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.

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.)

Excretion of biotrace elements using the multitracer technique in mice

International Nuclear Information System (INIS)

Wang, X.; Wu, M.; Yin, X.M.; Zhang, X.; Li, Z.W.; Tian, J.; Sheng, X.L.

1999-01-01

A radioactive multitracer solution obtained from the nuclear reaction of selenium with 25 MeV/nucleon 40 Ar ions was applied to the investigation of the trace elements behavior in feces and urine of mouse. The excretion rates of 23 elements, Na, K, Rb, Mg, Ca, Sr, Ga, As, Sc, V, Cr, Mn, Co, Fe, Zn, Y, Zr, Mo, Nb, Tc, Ru, Ag and In were simultaneously detected under strictly identical experimental conditions, in order to clarify the excretion behavior of the elements in Mice. Fecal and urinary excretion rates of the elements in mice reached the highest value separately at 48 and 24 hours. The total excretion of Mo, Tc and Co within 96 hours were all larger, more than 60%. Accumulative excretion rates of Ca, Nb, Mg, Sr, V, Sc, Na, Cr, Fe, Ag, Mn and Zr were 60-30%. The total rates of Ru, K, As, Zn, Rb, Y, Ga and In were less than 30%, and low excretion. The main excretion pathway of Mo, Co, Mg, Fe and Ag was through urine, and Na, K, As and Rb were eliminated from the body also in urine. But fecal excretion of Tc, Nb, Sr, Y, Ru, and In were larger than urinary excretion, and Ca, Sc, Mn, Zr, Zn were eliminated from the body in feces. (author)

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

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

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.

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

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

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)

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)

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)

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

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

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)

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

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)

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

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

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.)

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

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.

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.

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.

Electrochemical Corrosion Studies for Modeling Metallic Waste Form Release Rates

International Nuclear Information System (INIS)

Poineau, Frederic; Tamalis, Dimitri

2016-01-01

The isotope 99 Tc is an important fission product generated from nuclear power production. Because of its long half-life (t 1/2 = 2.13 ∙ 105 years) and beta-radiotoxicity (β - = 292 keV), it is a major concern in the long-term management of spent nuclear fuel. In the spent nuclear fuel, Tc is present as an alloy with Mo, Ru, Rh, and Pd called the epsilon-phase, the relative amount of which increases with fuel burn-up. In some separation schemes for spent nuclear fuel, Tc would be separated from the spent fuel and disposed of in a durable waste form. Technetium waste forms under consideration include metallic alloys, oxide ceramics and borosilicate glass. In the development of a metallic waste form, after separation from the spent fuel, Tc would be converted to the metal, incorporated into an alloy and the resulting waste form stored in a repository. Metallic alloys under consideration include Tc–Zr alloys, Tc–stainless steel alloys and Tc–Inconel alloys (Inconel is an alloy of Ni, Cr and iron which is resistant to corrosion). To predict the long-term behavior of the metallic Tc waste form, understanding the corrosion properties of Tc metal and Tc alloys in various chemical environments is needed, but efforts to model the behavior of Tc metallic alloys are limited. One parameter that should also be considered in predicting the long-term behavior of the Tc waste form is the ingrowth of stable Ru that occurs from the radioactive decay of 99 Tc ( 99 Tc → 99 Ru + β - ). After a geological period of time, significant amounts of Ru will be present in the Tc and may affect its corrosion properties. Studying the effect of Ru on the corrosion behavior of Tc is also of importance. In this context, we studied the electrochemical behavior of Tc metal, Tc-Ni alloys (to model Tc-Inconel alloy) and Tc-Ru alloys in acidic media. The study of Tc-U alloys has also been performed in order to better understand the nature of Tc in metallic spent fuel. Computational modeling

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

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.

Onderzoek naar de radioactiviteit van neerslag. Resultaten over 1986

NARCIS (Netherlands)

Vaas LH; Mattern FCM; Drost RMS; Glastra P; Koolwijk AC; Ockhuizen A

1989-01-01

De belangrijkste gamma-emitters in 1986 door "Tsjernobyl" te Bilthoven gedeponeerd , waren: Mo-99/mTc-99 (1040 Bq/m2), Ru-103 (8300 Bq/m2), Ru-106 (4100 Bq/m2), I-131 (19000 Bq/m2), Te-132/I-132 (14000 Bq/m2), Cs-134 (1530 Bq/m2), Cs-136 (620 Bq/m2), Cs-137 (3360 Bq/m2) en

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.

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)

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

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

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

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.

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)

{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.

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

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.

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.

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.

Electrochemical Corrosion Studies for Modeling Metallic Waste Form Release Rates

Energy Technology Data Exchange (ETDEWEB)

Poineau, Frederic [Univ. of Nevada, Las Vegas, NV (United States); Tamalis, Dimitri [Florida Memorial Univ., Miami Gardens, FL (United States)

2016-08-01

The isotope ⁹⁹Tc is an important fission product generated from nuclear power production. Because of its long half-life (t_1/2 = 2.13 ∙ 10⁵ years) and beta-radiotoxicity (β⁻ = 292 keV), it is a major concern in the long-term management of spent nuclear fuel. In the spent nuclear fuel, Tc is present as an alloy with Mo, Ru, Rh, and Pd called the epsilon-phase, the relative amount of which increases with fuel burn-up. In some separation schemes for spent nuclear fuel, Tc would be separated from the spent fuel and disposed of in a durable waste form. Technetium waste forms under consideration include metallic alloys, oxide ceramics and borosilicate glass. In the development of a metallic waste form, after separation from the spent fuel, Tc would be converted to the metal, incorporated into an alloy and the resulting waste form stored in a repository. Metallic alloys under consideration include Tc–Zr alloys, Tc–stainless steel alloys and Tc–Inconel alloys (Inconel is an alloy of Ni, Cr and iron which is resistant to corrosion). To predict the long-term behavior of the metallic Tc waste form, understanding the corrosion properties of Tc metal and Tc alloys in various chemical environments is needed, but efforts to model the behavior of Tc metallic alloys are limited. One parameter that should also be considered in predicting the long-term behavior of the Tc waste form is the ingrowth of stable Ru that occurs from the radioactive decay of ⁹⁹Tc (⁹⁹Tc → ⁹⁹Ru + β⁻). After a geological period of time, significant amounts of Ru will be present in the Tc and may affect its corrosion properties. Studying the effect of Ru on the corrosion behavior of Tc is also of importance. In this context, we studied the electrochemical behavior of Tc metal, Tc-Ni alloys (to model Tc-Inconel alloy) and Tc-Ru alloys in acidic media. The study of Tc-U alloys has also been performed in order to better understand the

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

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)

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.

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)

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)

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.

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

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)

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.

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)

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%

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

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

Separation of technetium and rare earth metals for co-decontamination process

International Nuclear Information System (INIS)

Riddle, Catherine; Martin, Leigh

2015-01-01

Poster. In the US there are several technologies under consideration for the separation of the useful components in used nuclear fuel. One such process is the co-decontamination process to separate U, Np and Pu in a single step and produce a Np/ Pu and a U product stream. Although the behavior of the actinide elements is reasonably well defined in this system, the same is not true for the fission products, mainly Zr, Mo, Ru and Tc. As these elements are cationic and anionic they may interact with each other to extract in a manner not predicted by empirical models such as AMUSE. This poster presentation will discuss the initial results of batch contact testing under flowsheet conditions and as a function of varying acidity and flowsheet conditions to optimize recovery of Tc and minimize extraction of Mo, Zr and Ru with the goal of developing a better understanding of the behavior of these elements in the co-decontamination process.

Fate of the Epsilon Phase in the Oklo Natural Reactors

International Nuclear Information System (INIS)

S. Utsunomiya; R.C. Ewing

2005-01-01

In spent nuclear fuel (SNF), the micron- to submicron-sized epsilon phase (Mo-Ru-Pd-Tc-Rh) is an important host of 99 Tc which has a long half life (2.13 x 10 5 years) and can be an important contributor to dose in safety assessments of nuclear waste repositories. In addition, Tc is predominantly present as TcO 4 - under oxidizing conditions at wide range of pH, weakly adsorbed onto mineral surfaces, and unlikely to be incorporated into alteration uranyl minerals. In the Oklo natural reactor (2.0 Ga), essentially all of the 99 Tc has decayed to 99 Ru. Thus, this study focuses on Ru and the other metals of the epsilon phase in order to investigate the occurrence and the fate of the epsilon phase during the corrosion of this natural SNF. Samples from reactor zone (RZ)-10 (836, 819, 687); from RZ-13 (864, 910); were investigated using TEM (transmission electron microscopy). Within the UO 2 matrix, a Bi-Pd particle (40-60 nm), fioodite, PdBi 2 , was observed with trace amounts of As, Fe, and Te surrounded by an amorphous Pb-rich area. (Pd,Rh) 2 As, palladodymite or rhodarsenide, was observed (400-500 nm in size). Ruthenarsinite, (Ru,Ni)As, was identified in most samples: with a representative composition of As, 59.9: Co, 2.5: Ni, 5.2; Ru, 18.6; Rh, 8.4; Pd, 3.1; Sb, 2.4 in atomic percent. The particles diameters are a few hundred nanometers and, in most cases, surrounded by a Pb-rich phase (400-500 nm). Typically, the ruthenarsenite does not occur as single particle but an aggregate of ∼200 nm-sized particles. Some Ru-particles revealed a complex phase separation within the grain such as a Ru-particle (600-700 nm) with Pb at the core of the particle and enrichment of Ni, Co, and As at the rim. Some ruthenarsenite crystals were embedded in chlorite immediately adjacent to uraninite. A few particles were still coated by Pb. These results suggest a history for the epsilon phases: (1) The original epsilon phase was transformed to, in most cases, ruthenarsenite. (2) All

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)

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

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.

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)

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)

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)

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.

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.

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.

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.

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)

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

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.)

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.

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)

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.

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.)

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.

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

Effect of increasing disorder on superconductivity of Mo/Nb superlattices

Science.gov (United States)

Pereiro, Juan; Saerbeck, Thomas; Schuller, Ivan K.

2015-08-01

We investigated the superconducting properties of Nb/Mo superlattices (SLs). The structural changes as a function of Nb and Mo layer thickness allow us to investigate the effect of disorder on the superconducting properties in a controlled fashion. Systematic structural studies provide quantitative measures of disorder parameters, such as roughness, interdiffusion, and strain, which allow separating their effect on the individual superconducting layers. The Mo critical temperature does not change as the layer thickness decreases below its coherence length. Thus, the SL critical temperatures in the presence of disorder and proximity effects can be modeled by considering only the effects of the Nb mean free path and coherence length. With increasing layer thickness, the SL critical temperatures approach Nb bulk values. Contrary to expectations the Tc of Mo remains below the Nb Tc. We discuss the results using existing theories based on Coulomb repulsion or changes in the density of states at the Fermi surface as a function of disorder. Questions about current understanding of the effect of disorder on superconductivity arise from the results.

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

Spent fuel reaction - the behavior of the ε-phase over 3.1 years

International Nuclear Information System (INIS)

Finn, P.A.; Hoh, J.C.; Wolf, S.F.

1996-01-01

The release fractions of the five elements in the ε-phase ( 99 Tc, 97 Mo, Ru, Rh, and Pd) as well as that of 238 U are reported for the reaction of two oxide fuels (ATM-103 and ATM-106) in unsaturated tests under oxidizing conditions. The 99 Tc release fractions provide a lower limit for the magnitude of the spent fuel reaction. The 99 Tc release fractions indicate that a surface reaction might be the rate controlling mechanism for fuel reaction under unsaturated conditions and the oxidant is possibly H 2 O 2 , a product of alpha radiolysis of water

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

NAVAIR Portable Source Initiative (NPSI) Standard for Material Properties Reference Database (MPRD) V2.2

Science.gov (United States)

2012-09-26

of a material to conduct electricity . p-electrical_resisitivity electrical resistivity electrical ohm-m The property of a material...that resists the flow of electrical current. p-magnetic_susceptibility magnetic susceptibility electrical The degree to which a...enumeration Zr enumeration Nb enumeration Mo enumeration Tc enumeration Ru enumeration Rh enumeration Pd enumeration Ag enumeration

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.

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

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

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.

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)

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

Report on the Behavior of Fission Products in the Co-decontamination Process

International Nuclear Information System (INIS)

Martin, Leigh Robert; Riddle, Catherine Lynn

2015-01-01

This document was prepared to meet FCT level 3 milestone M3FT-15IN0302042, 'Generate Zr, Ru, Mo and Tc data for the Co-decontamination Process.' This work was carried out under the auspices of the Lab-Scale Testing of Reference Processes FCT work package. This document reports preliminary work in identifying the behavior of important fission products in a Co-decontamination flowsheet. Current results show that Tc, in the presence of Zr alone, does not behave as the Argonne Model for Universal Solvent Extraction (AMUSE) code would predict. The Tc distribution is reproducibly lower than predicted, with Zr distributions remaining close to the AMUSE code prediction. In addition, it appears there may be an intricate relationship between multiple fission product metals, in different combinations, that will have a direct impact on U, Tc and other important fission products such as Zr, Mo, and Rh. More extensive testing is required to adequately predict flowsheet behavior for these variances within the fission products.

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.

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

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

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.

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)

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

The excretion of biotrace elements using the multitracer technique in tumour-bearing mice.

Science.gov (United States)

Wang, X; Tian, J; Yin, X M; Zhang, X; Wang, Q Z

2000-12-01

A radioactive multitracer solution obtained from the nuclear reaction of selenium with 25 MeV/nucleon 40Ar ions was used for investigation of trace element excretion into the faeces and urine of cancerous mice. The excretion rates of 22 elements (Na, K, Rb, Mg, Ca, Sr, Ga, As, Sc, V, Cr, Mn, Co, Fe, Y, Zr, Mo, Nb, Tc, Ru, Ag and In) were simultaneously measured under strictly identical experimental conditions, in order to clarify the excretion behavior of these elements in cancerous mice. The faecal and urinary excretion rates of Mg, Sr, Ga, As, Sc, V, Cr, Mn, Co, Fe, Y, Zr, Nb, Ru and Mo in cancerous mice, showed the in highest value at 0-8 hours. The accumulative excretion of Ca, Mo, Y and Zr was decreased and Na, Fe, Mn and Co increased in tumour-bearing mice, when compared to normal mice.

The excretion of biotrace elements using the multitracer technique in tumour-bearing mice

Energy Technology Data Exchange (ETDEWEB)

Wang, X.; Tian, J. E-mail: tianjun@public.lz.gs.cn; Yin, X.M.; Zhang, X.; Wang, Q.Z

2000-12-15

A radioactive multitracer solution obtained from the nuclear reaction of selenium with 25 MeV/nucleon {sup 40}Ar ions was used for investigation of trace element excretion into the faeces and urine of cancerous mice. The excretion rates of 22 elements (Na, K, Rb, Mg, Ca, Sr, Ga, As, Sc, V, Cr, Mn, Co, Fe, Y, Zr, Mo, Nb, Tc, Ru, Ag and In) were simultaneously measured under strictly identical experimental conditions, in order to clarify the excretion behavior of these elements in cancerous mice. The faecal and urinary excretion rates of Mg, Sr, Ga, As, Sc, V, Cr, Mn, Co, Fe, Y, Zr, Nb, Ru and Mo in cancerous mice, showed the in highest value at 0-8 hours. The accumulative excretion of Ca, Mo, Y and Zr was decreased and Na, Fe, Mn and Co increased in tumour-bearing mice, when compared to normal mice.

The excretion of biotrace elements using the multitracer technique in tumour-bearing mice

International Nuclear Information System (INIS)

Wang, X.; Tian, J.; Yin, X.M.; Zhang, X.; Wang, Q.Z.

2000-01-01

A radioactive multitracer solution obtained from the nuclear reaction of selenium with 25 MeV/nucleon 40 Ar ions was used for investigation of trace element excretion into the faeces and urine of cancerous mice. The excretion rates of 22 elements (Na, K, Rb, Mg, Ca, Sr, Ga, As, Sc, V, Cr, Mn, Co, Fe, Y, Zr, Mo, Nb, Tc, Ru, Ag and In) were simultaneously measured under strictly identical experimental conditions, in order to clarify the excretion behavior of these elements in cancerous mice. The faecal and urinary excretion rates of Mg, Sr, Ga, As, Sc, V, Cr, Mn, Co, Fe, Y, Zr, Nb, Ru and Mo in cancerous mice, showed the in highest value at 0-8 hours. The accumulative excretion of Ca, Mo, Y and Zr was decreased and Na, Fe, Mn and Co increased in tumour-bearing mice, when compared to normal mice

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

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)

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.

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.)

Synthesis and IR spectral study of MoO2Cl2 molecular complex with acetoacetanilides. Crystal structure of MoO2Cl2 complex with acetoacet-2-toluidine

International Nuclear Information System (INIS)

Abramenko, V.L.; Sergienko, V.S.; Churakov, A.V.

2000-01-01

Certain MoO 2 Cl 2 complexes with acetoacetanilide derivatives were synthesized, two IR spectral study being performed. Crystal and molecular structure of MoO 2 Cl 2 complex with acetoacet-2-toluidine (HL) was determined using X-ray diffraction analysis. The crystals are monoclinic, a = 7.621 (7), b = 9.498 (3), c = 19.980 (9) A, β = 95.16 (7), Z = 4, sp.gr. P2 1 /n. Coordination polyhedron of Mo atom is a distorted octahedron with two O oxoatoms in cis-position, two Cl atom in mutual trans-position and two O(HL) atoms in trans-positions in reference to O(oxo) [ru

Applicability of Sol-Gel Derived Adsorbent for the Production of (n,f) 99Mo Generator

International Nuclear Information System (INIS)

Lee, Jun-Sig; Lee, Jong-Sup; Park, Ul-Jae; Son, Kwang-Jae; Han, Hyon-Soo; Kim, Myung Sic; Koo, Sung Chan; Chung, Young-Ju

2007-01-01

High performance adsorbents as the column material for (n,γ) 99 Mo/ 99 mTc and 188 W/ 188 Re generators have been developed at KAERI. These adsorbents should have enough loading capacities to produce such generators with high activities as the loading isotopes are not carrier-free. In this regard, the adsorbents are synthesized by sol-gel processing in which the ligand density can easily be adjusted and maximized. The marginal capacity of such adsorbents should be higher than 200 mg/g for molybdenum. From the previous works, the sol-gel processing techniques are adequately applied to meet the criteria. Further studies are being undertaken to employ the adsorbents for the production of high capacity (n,f) 99 Mo/ 99 mTc. Domestically, a private company has lined up the production facility of the molybdenum generator in the activity range of 300 ∼ 1,000 mCi/ea. The column elements are composed of manganese oxide doped on silica and alumina at the backup layer. In this column, the manganese oxide is the main reactive layer to retain (n,f) 99 Mo. The sol-gel derived adsorbent, in this study, is employed as the replacement of the manganese oxide doped silica in the column and tested for the loading efficiency of (n,f) 99 Mo, elution of 99 mTc, labeling property of the eluted 99 mTc. The same loading and elution procedures as the commercial production are applied for the tests and quality controls

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

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.)

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)

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)

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

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.

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 )

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)

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

European Union's efforts to sustain the supply of 99Mo

International Nuclear Information System (INIS)

Remigiusz Baranczyk; Stamatios Tsalas; Turquet de Beauregard, G.Y.

2015-01-01

The Molybdenum-99/Technetium-99m ( 99 Mo/ 99m Tc) supply disruptions occurred in the recent years prompted the European Commission and industry to establish in 2012 a European Observatory on the Supply of Medical Radioisotopes, aimed at bringing together all relevant information to the decision makers in the European Union (EU) institutions and national governments in order to assist them in defining strategies as well as policies for their implementation. The Observatory follows the Organisation for Economic Co-operation and Development/Nuclear Energy Agency-OECD/NEA principles established by the High Level Group on the Security of Supply of Medical Radioisotopes (HLG-MR), of which the European Commission is a Member, and focuses on the specificities of their implementation in the EU, recognizing at the same time that the supply is of a global nature and requires broader international cooperation. The Observatory has four general strategic objectives: to support a secure 99 Mo/ 99m Tc supply across the European Union, ensure that the issue of 99 Mo/ 99m Tc supply is given high political visibility, encourage the creation of a sustainable economic structure of the supply chain and establish periodic reviews of the supply capacities and demand. (author)

Uncertainties in the production of p nuclides in thermonuclear supernovae determined by Monte Carlo variations

Science.gov (United States)

Nishimura, N.; Rauscher, T.; Hirschi, R.; Murphy, A. St J.; Cescutti, G.; Travaglio, C.

2018-03-01

Thermonuclear supernovae originating from the explosion of a white dwarf accreting mass from a companion star have been suggested as a site for the production of p nuclides. Such nuclei are produced during the explosion, in layers enriched with seed nuclei coming from prior strong s processing. These seeds are transformed into proton-richer isotopes mainly by photodisintegration reactions. Several thousand trajectories from a 2D explosion model were used in a Monte Carlo approach. Temperature-dependent uncertainties were assigned individually to thousands of rates varied simultaneously in post-processing in an extended nuclear reaction network. The uncertainties in the final nuclear abundances originating from uncertainties in the astrophysical reaction rates were determined. In addition to the 35 classical p nuclides, abundance uncertainties were also determined for the radioactive nuclides 92Nb, 97, 98Tc, 146Sm, and for the abundance ratios Y(92Mo)/Y(94Mo), Y(92Nb)/Y(92Mo), Y(97Tc)/Y(98Ru), Y(98Tc)/Y(98Ru), and Y(146Sm)/Y(144Sm), important for Galactic Chemical Evolution studies. Uncertainties found were generally lower than a factor of 2, although most nucleosynthesis flows mainly involve predicted rates with larger uncertainties. The main contribution to the total uncertainties comes from a group of trajectories with high peak density originating from the interior of the exploding white dwarf. The distinction between low-density and high-density trajectories allows more general conclusions to be drawn, also applicable to other simulations of white dwarf explosions.

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

Downregulation of PTP1B and TC-PTP phosphatases potentiate dendritic cell-based immunotherapy through IL-12/IFNγ signaling.

Science.gov (United States)

Penafuerte, Claudia; Feldhammer, Matthew; Mills, John R; Vinette, Valerie; Pike, Kelly A; Hall, Anita; Migon, Eva; Karsenty, Gerard; Pelletier, Jerry; Zogopoulos, George; Tremblay, Michel L

2017-01-01

PTP1B and TC-PTP are highly related protein-tyrosine phosphatases (PTPs) that regulate the JAK/STAT signaling cascade essential for cytokine-receptor activation in immune cells. Here, we describe a novel immunotherapy approach whereby monocyte-derived dendritic cell (moDC) function is enhanced by modulating the enzymatic activities of PTP1B and TC-PTP. To downregulate or delete the activity/expression of these PTPs, we generated mice with PTP-specific deletions in the dendritic cell compartment or used PTP1B and TC-PTP specific inhibitor. While total ablation of PTP1B or TC-PTP expression leads to tolerogenic DCs via STAT3 hyperactivation, downregulation of either phosphatase remarkably shifts the balance toward an immunogenic DC phenotype due to hyperactivation of STAT4, STAT1 and Src kinase. The resulting increase in IL-12 and IFNγ production subsequently amplifies the IL-12/STAT4/IFNγ/STAT1/IL-12 positive autocrine loop and enhances the therapeutic potential of mature moDCs in tumor-bearing mice. Furthermore, pharmacological inhibition of both PTPs improves the maturation of defective moDCs derived from pancreatic cancer (PaC) patients. Our study provides a new advance in the use of DC-based cancer immunotherapy that is complementary to current cancer therapeutics.

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)

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