Journal articles: '99mTc, Mo target, cyclotron'

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Skliarova, Hanna, Sara Cisternino, Gianfranco Cicoria, Mario Marengo, and Vincenzo Palmieri. "Innovative Target for Production of Technetium-99m by Biomedical Cyclotron." Molecules 24, no. 1 (December 21, 2018): 25. http://dx.doi.org/10.3390/molecules24010025.

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Technetium-99m (99mTc) is the most used radionuclide worldwide in nuclear medicine for diagnostic imaging procedures. 99mTc is typically extracted from portable generators containing 99Mo, which is produced normally in nuclear reactors as a fission product of highly enriched Uranium material. Due to unexpected outages or planned and unplanned reactor shutdown, significant 99mTc shortages appeared as a problem since 2008 The alternative cyclotron-based approach through the 100Mo(p,2n)99mTc reaction is considered one of the most promising routes for direct 99mTc production in order to mitigate potential 99Mo shortages. The design and manufacturing of appropriate cyclotron targets for the production of significant amounts of a radiopharmaceutical for medical use is a technological challenge. In this work, a novel solid target preparation method was developed, including sputter deposition of a dense, adherent, and non-oxidized Mo target material onto a complex backing plate. The latter included either chemically resistant sapphire or synthetic diamond brazed in vacuum conditions to copper. The target thermo-mechanical stability tests were performed under 15.6 MeV proton energy and different beam intensities, up to the maximum provided by the available GE Healthcare (Chicago, IL, USA) PET trace medical cyclotron. The targets resisted proton beam currents up to 60 µA (corresponding to a heat power density of about 1 kW/cm2) without damage or Mo deposited layer delamination. The chemical stability of the proposed backing materials was proven by gamma-spectroscopy analysis of the solution obtained after the standard dissolution procedure of irradiated targets in H2O2.

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Matei, L., G. McRae, R. Galea, D. Niculae, L. Craciun, R. Leonte, G. Surette, et al. "A new approach for manufacturing and processing targets to produce 99mTc with cyclotrons." Modern Physics Letters A 32, no. 17 (May 9, 2017): 1740011. http://dx.doi.org/10.1142/s0217732317400119.

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The most important radioisotope for nuclear medicine is [Formula: see text]Tc. After the supply crisis of [Formula: see text]Mo starting in 2008, the availability of [Formula: see text]Tc became a worldwide concern. Alternative methods for producing the medical imaging isotope [Formula: see text]Tc are actively being developed around the world. The reaction [Formula: see text]Mo(p, 2n)[Formula: see text]Tc 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 [Formula: see text]Mo and the foundation for the subsequent commercial separation and purification of the [Formula: see text]Tc produced. Two designs of targets are presented. The targets used to produce [Formula: see text]Tc 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 [Formula: see text]Tc. 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.

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Skliarova, Hanna, Paolo Buso, Sara Carturan, Carlos Rossi Alvarez, Sara Cisternino, Petra Martini, Alessandra Boschi, and Juan Esposito. "Recovery of Molybdenum Precursor Material in the Cyclotron-Based Technetium-99m Production Cycle." Instruments 3, no. 1 (February 13, 2019): 17. http://dx.doi.org/10.3390/instruments3010017.

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A closed-loop technology aiming at recycling the highly 100Mo-enriched molybdenum target material has been developed in the framework of the international research efforts on the alternative, cyclotron-based 99mTc radionuclide production. The main procedure steps include (i) 100Mo-based target manufacturing; (ii) irradiation under proton beam; (iii) dissolution of 100Mo layer containing 9×Tc radionuclides (produced by opened nuclear reaction routes) in concentrated H2O2 solution; and (iv) Mo/Tc separation by the developed radiochemical module, from which the original 100Mo comes as the “waste” alkaline aqueous fraction. Conversion of the residual 100Mo molybdates in this fraction into molybdic acids and MoO3 has been pursued by refluxing in excess of HNO3. After evaporation of the solvent to dryness, the molybdic acids and MoO3 may be isolated from NaNO3 by exploiting their different solubility in water. When dried in vacuum at 40 °C, the combined aqueous fractions provided MoO3 as a white powder. In the last recovery step MoO3 has been reduced using a temperature-controlled reactor under hydrogen overpressure. An overall recovery yield of ~90% has been established.

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Richards, Vernal, and Suzanne Lapi. "Evaluation of new target materials for cyclotron production of 186Re and 99mTc." Nuclear Medicine and Biology 41, no. 7 (August 2014): 647. http://dx.doi.org/10.1016/j.nucmedbio.2014.05.111.

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Koźmiński, Przemysław, Magdalena Gumiela, Rafał Walczak, Kamil Wawrowicz, and Aleksander Bilewicz. "A semi-automated module for the separation and purification of 99mTc from simulated molybdenum target." Journal of Radioanalytical and Nuclear Chemistry 328, no. 3 (April 27, 2021): 1217–24. http://dx.doi.org/10.1007/s10967-021-07710-2.

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AbstractA semi-automated purification module for the cyclic separation of 99mTc was designed for production of [99mTc]TcO4– from γ irradiated 100Mo target. The separation process was carried out by using a 3-column purification system and the final product, [99mTc]TcO4–, was obtained in a total volume of 7 mL. To confirm proper separation achieved for 99mTc, a radio-labeling procedure using DTPA chelator was performed. The radiochemical purity was higher than 95%, which meets the strict radiopharmaceutical requirements. The yielded 99mTc can be separated with high efficiency from Mo in a quick and repeated way. Loss of 99mTc radioactivity during such a three-column separation process was not larger than 10%.

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Kambali, Imam, Indra Saptiama, and Hari Suryanto. "Residual Radioisotopes Generated from Neutron Irradiated Aluminum Capsules." Aceh International Journal of Science and Technology 6, no. 3 (December 31, 2017): 104–10. http://dx.doi.org/10.13170/aijst.6.3.8116.

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Aluminum (Al) is often used to house a molybdenum oxide (MoO3) target for neutron or proton-produced technetium-99m (99mTc) radioisotope. During neutron or proton bombardment of an Al body, residual radioisotopes could be generated following nuclear reactions between the incoming particles and the Al body. In this research, residual radioisotopes produced following nuclear reactor based-neutron irradiation of Al body were experimentally measured using a portable gamma ray spectroscopy system; whereas TALYS 2015 calculated data were used to evaluate various nuclear reactions for the by-product identification. As a comparison, Al body used in a cyclotron-based 99mTc production was also analyzed. Experimental data indicated that relatively long-lived radioisotopes such as 26Al, 22Na and 24Na were identified in the Al body following nuclear reactor-based 99mTc production, whereas the presence of 27Mg radioisotope was, for the first time, experimentally detected in both the Al bodies for nuclear reactor-based and cyclotron-based 99mTc production. A special safety attention should be paid to the radiation workers when producing 99mTc using a nuclear reactor since it generates 26Al (half life = 716,600 years).

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Skliarova, Hanna, Sara Cisternino, Gianfranco Cicoria, Mario Marengo, Emiliano Cazzola, Giancarlo Gorgoni, and Vincenzo Palmieri. "Medical Cyclotron Solid Target Preparation by Ultrathick Film Magnetron Sputtering Deposition." Instruments 3, no. 1 (March 13, 2019): 21. http://dx.doi.org/10.3390/instruments3010021.

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Magnetron sputtering is proposed here as an innovative method for the deposition of a material layer onto an appropriate backing plate for cyclotron solid targets aimed at medical radioisotopes production. In this study, a method to deposit thick, high-density, high-thickness-uniformity, and stress-free films of high adherence to the backing was developed by optimizing the fundamental deposition parameters: sputtering gas pressure, substrate temperature, and using a multilayer deposition mode, as well. This method was proposed to realize Mo-100 and Y-nat solid targets for biomedical cyclotron production of Tc-99m and Zr-89 radionuclides, respectively. The combination of all three optimized sputtering parameters (i.e., 1.63 × 10−2 mbar Ar pressure, 500 °C substrate temperature, and the multilayer mode) allowed us to achieve deposition thickness as high as 100 µm for Mo targets. The 50/70-µm-thick Y targets were instead realized by optimizing the sputtering pressure only (1.36 × 10−2 mbar Ar pressure), without making use of additional substrate heating. These optimized deposition parameters allowed for the production of targets by using different backing materials (e.g., Mo onto copper, sapphire, and synthetic diamond; and Y onto a niobium backing). All target types tested were able to sustain a power density as high as 1 kW/cm2 provided by the proton beam of medical cyclotrons (15.6 MeV for Mo targets and 12.7 MeV for Y targets at up to a 70-µA proton beam current). Both short- and long-time irradiation tests, closer to the real production, have been realized.

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Pawlak, D. W., W. Wojdowska, L. J. Parus, and R. Mikołajczak. "Application of AnaLig resin for 99mTc separation from 100Mo target irradiated in cyclotron." Applied Radiation and Isotopes 113 (July 2016): 75–78. http://dx.doi.org/10.1016/j.apradiso.2016.04.021.

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9

Szkliniarz, Katarzyna, Mateusz Sitarz, Jerzy Jastrzębski, Jarosław Choiński, Andrzej Jakubowski, Kamil Kapinos, Maciej Kisieliński, et al. "Production efficiency and radioisotopic purity of 99mTc formed using the (p,2n) reaction on a highly enriched 100Mo target." Modern Physics Letters A 32, no. 17 (May 18, 2017): 1740012. http://dx.doi.org/10.1142/s0217732317400120.

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The [Formula: see text]Tc isomer was produced using the [Formula: see text] reaction on highly enriched [Formula: see text]Mo samples. The Thick Target Yields were determined in the energy range from 16 MeV to 26 MeV and compared with the values calculated using the most recent cross-section recommendations from the literature. The generated impurities were also determined. It was shown that for 99.815 ± 0.010% enriched samples, only reactions induced on [Formula: see text]Mo are of importance. The ratio of the number of atoms of [Formula: see text]Tc to all produced Tc nuclei was studied as a function of irradiation time and bombarding energy.

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Febrian, Muhamad Basit, Duyeh Setiawan, and Hilda Hidayati. "Synthesis and Characterization of Molybdenum Phthalocyanine as Target Material for High Specific Activity Molybdenum-99 Production." Indonesian Journal of Chemistry 19, no. 3 (May 29, 2019): 556. http://dx.doi.org/10.22146/ijc.33218.

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High specific activity is a necessity in the fabrication of 99Mo/99mTc radioisotope generators. Recoil reaction, or the Szilard-Chalmers effect, is a method that could be used as an alternative method for increasing specific activity in radioisotope production in light of tightening regulation of highly enriched uranium (HEU) irradiation. Phthalocyanine compounds are usually used as the target material in recoil reactions for the production of high specific radioisotope activity via the (n,γ) reaction. Molybdenum phthalocyanine (Mo-Pc) could be a promising target material in recoil reactions for producing high specific activity of 99Mo. Mo-Pc was synthesized via solid-state reaction between ammonium heptamolybdate and phthalonitrile in a reflux system at 300 °C for 3 h. This optimum condition was identified after performing several variations of temperature and time of reaction, considering FTIR spectra, the yield of product and melting point of the product. XRD measurement showed that Mo-Pc synthesized at optimum condition was free from MoO2, phthalimide and unreacted molybdenum. Mo-Pc has UV-vis properties of Q-band absorption between 600 and 750 nm when dissolved in tetrahydrofuran, dimethylformamide and trifluoroacetic acid. Splitting at absorption peak in tetrahydrofuran and dimethylformamide solution indicated that protonation had occurred. This split peak did not appear in a trifluoroacetic acid solution. In the preliminary study of irradiation of 1 g Mo-Pc at 3.5x1012 n cm–2 s–1 neutron flux, followed by dissolution in tetrahydrofuran and extraction of Mo-99 into NaOH, we obtained Mo-99 solution with a specific activity of 682.35 mCi/g Mo, this being 254.61 times higher than in the regular MoO3 target.

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YANG, Z. H., X. M. CHEN, Y. P. ZHANG, A. X. ZHANG, Y. T. ZHAO, Y. CUI, H. Q. ZHANG, et al. "X-RAYS EMISSION OF HYDROGEN-LIKE AND HELIUM-LIKE ARGON IN INTERACTION WITH Mo METALLIC SURFACE." International Journal of Modern Physics B 19, no. 15n17 (July 10, 2005): 2433–37. http://dx.doi.org/10.1142/s0217979205031109.

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14-GHz electron cyclotron resonance ion source (ECRIS) at the Heavy Ion Research Facility National Laboratory in Lanzhou has been used to investigate the radiative deexcitation of highly charged Ar 17+ and Ar 16+ ions as they interact with a molybdenum surface. The interaction of Ar 17+ and Ar 16+ ions above Mo Metallic Surface has been studied by looking at the X-rays with a Si ( Li ) detector. ECRIS is used in our work for the first time. As the experimental results, the X-ray spectra of Ar 17+ and Ar 16+ ions interacting with a Mo metal target have been given. The capture of many electrons by Ar 17+ and Ar 16+ ions, at low velocities, near a metallic surface, has been studied. Hollow atoms produced in the interaction of highly charged ions with a Mo metallic surface have been observed.

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Didi, Abdessamad, Ahmed Dadouch, Otman Jai, and Fatima Zahra Bouhali. "Toward for production of Molybdenum-99 by irradiation of MoO3 target in a neutron flux." Bangladesh Journal of Medical Science 17, no. 4 (September 19, 2018): 567–72. http://dx.doi.org/10.3329/bjms.v17i4.38317.

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Background: Molybdenum- 99 is a parent isotope of Technetium-99m (99mTc) as intermediate to diagnosis and radiation treatment. This production is made according to irradiation of Molybdenum-98 with thermal neutrons. The cycle comprises a complex of MoO3 or the percentage of Mo-98 is 24.13%, this compressed mixture in an irradiation capsule of aluminum; the latter is disposed in the central thimble of a nuclear reactor so that the thermal neutron flux is at a maximum in order to generate 98Mo to 99Mo by nuclear reaction of (n, γ) where the crosssection of molybdenum is (0.13 ± 0.0013) barn.Method: The purpose of this study is to validate of MoO3 target that will be used for the production of Molybdenum-99 in the central thimble irradiation position of the TRIGA Mark II research reactor at CNESTEN (Morocco National Center for Nuclear Energy, Sciences and Techniques), The thermal neutron flux used for activity calculation of Mo-99 used reactor of research TRIGA Mark-II is 3.1 1011 n/cm²s at 250 KW, 2.4E+13 n/cm2s at 1.1 MW and 3.01 1013n/cm²s at 2MW, we are using Fortran-90 code for calculate the activity.Result: The result’s finding was validated by other studies.Bangladesh Journal of Medical Science Vol.17(4) 2018 p.567-572

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Osváth, Szabolcs, Jixin Qiao, and Xiaolin Hou. "Preparation of 93Mo solution using proton irradiated Nb." Journal of Radioanalytical and Nuclear Chemistry 322, no. 3 (September 16, 2019): 1833–39. http://dx.doi.org/10.1007/s10967-019-06758-5.

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Abstract 93Mo is an important long-lived radionuclide in nuclear waste, and is required to be measured during the characterization of decommissioning waste. However, no commercial 93Mo solution is available to be calibrated and used as standard in the analysis of nuclear waste. This work presents a method for separation of 93Mo from Nb metal used in cyclotron as a target holder and irradiated with protons for long time. The separation of 93Mo from Nb matrix was implemented by combination of precipitation and chromatographic separation. The Nb matrix was first removed by precipitating oxides-hydroxides of Nb (e.g. Nb2O5) and then by Fe(OH)3 co-precipitation; Mo in the solution was purified using an alumina (Al2O3) column. A decontamination factor of ca. 105 was achieved for Nb. A pure carrier-free 93Mo solution was successfully prepared, and the 93Mo purity was verified by liquid scintillation spectrometry.

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Saptiama, Indra, Herlina Herlina, Sriyono Sriyono, E. Sarmini, Abidin Abidin, and Kadarisman Kadarisman. "PEMBUATAN RADIONUKLIDA MOLIBDENUM-99 (99Mo) HASIL AKTIVASI NEUTRON DARI MOLIBDENUM ALAM UNTUK MEMPEROLEH TEKNESIUM-99m (99mTc)." Urania Jurnal Ilmiah Daur Bahan Bakar Nuklir 22, no. 2 (October 10, 2016). http://dx.doi.org/10.17146/urania.2016.22.2.3094.

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PEMBUATAN RADIONUKLIDA MOLIBDENUM-99 (99Mo) HASIL AKTIVASI NEUTRON DARI MOLIBDENUM ALAM UNTUK MEMPEROLEH TEKNESIUM-99m (99mTc). Pembatasan penggunaan uranium sebagai target untuk produksi 99mTc menyebabkan rumah sakit di Indonesia kesulitan mendapatkan pasokan 99mTc. Saat ini 99mTc diperoleh dari 99Mo hasil fisi (pembelahan uranium). Pembuatan radionuklida 99Mo dari aktivasi neutron molibdenum alam (MoO3) di teras reaktor G.A Siwabessy digunakan sebagai metode alternatif untuk memperoleh 99mTc. Tujuan penelitian ini adalah untuk melakukan pembuatan radionuklida 99Mo dari aktivasi neutron molibdenum alam untuk memperoleh 99mTc. Serbuk MoO3 alam sebanyak 5 gram dikemas dalam ampul kuarsa dan dimasukkan ke dalam inner capsul selanjutnya dikemas menggunakan outer capsul sebagai bahan target. Bahan target diiradiasi di reaktor G.A Siwabessy selama 100 jam. Hasil perhitungan diperoleh aktivitas 99Mo sebesar 65 % dari nilai maksimum yang dapat diperoleh. MoO3 paska iradiasi dilarutkan dengan NaOH 4 M sehingga diperoleh larutan natrium molibdat (Na2MoO4). Radionuklida 99Mo dan 99mTc diukur menggunakan spektrometer gamma. Radionuklida 99Mo terdeteksi dalam produk larutan Na2MoO4 dengan aktivitas jenis 99Mo yang diperoleh sebesar 0,81 Ci 99Mo/g Mo. Radionuklida anak luruh 99mTc dipisahkan dari radionuklida induk 99Mo menggunakan kolom pemisah yang berisi material berbasis zirkonium (MBZ) sebagai penyerap 99Mo. Radionuklida 99mTc hasil pemisahan diperoleh dalam bentuk natrium pertehnetat (Na99mTcO4).dengan recovery yang masih rendah yaitu sekitar 52 hingga 71 %.Kata kunci: Molibdenum, teknesium, radionuklida, pemisahan, iradiasi. PRODUCTION OF ACTIVATED NEUTRON MOLYBDENUM-99 (99Mo) RADIONUCLIDE FROM NATURAL MOLYBDENUM TO OBTAIN TECHNETIUM-99m (99mTc). Uranium usage restriction causes the hospitals in indonesia difficult to obtain the suply of 99mTc. At Present, 99mTc is obtanied from molybdenum as a uranium fission product. Production of 99Mo radionuclide resulted from neutron activated natural molybdenum (MoO3) in G.A Siwabessy reactor could be used as a alternatif method for producing 99mTc. The aim of this research is synthesize of 99Mo radionuclide from neutron activated natural molybdenum (MoO3) to obtain 99mTc. The five grams of MoO3 powder was packed in a quartz ampule and inserted into inner capsule then also inserted into outer capsule as a target material. It was iradiated in G.A Siwabessy reactor for 100hours. Based on theoritical calculation, about 65 % of maximum 99Mo activity could be recovered. After Irradiation, MoO3 was dissolved by NaOH 4 M solution so it was natrium molybdate (Na2MoO4) solution. 99Mo and 99mTc radionuclide were analyzed using gamma spectrometer. 99Mo radionuclide was detected on Na2MoO4 solution as product that had specific activity of 0.81 Ci 99Mo/ g Mo. 99mTc as daughter radionuclide was separated from 99Mo as parent radionuclide using separated column containing zirconium based material (ZBM) as 99Mo adsobent. 99mTc radionuclide has been succesfully separated using ZBM column although recovery of 99mTc was quite low in which approximately 52 to 71 %. The 99mTc radionuclide was recovered in the form of sodium pertechnetate (NaTcO4) solution.Keywords: Molybdenum, technetium, radionuclide, separation, irradiation.

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Zhuikov, Boris, and Stanislav Ermolaev. "Adsorption from liquid metals: an approach for recovery of radionuclides from irradiated targets." Radiochimica Acta, November 16, 2020. http://dx.doi.org/10.1515/ract-2020-0053.

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AbstractAdsorption of radionuclides in no-carrier-added (NCA) amounts from liquid metals оf Rb, Pb, and Ag was investigated. 82Sr may be recovered from metallic irradiated Rb-target via adsorption onto various surfaces. A high chemical yield is achieved at Sr-sorption from molten Rb of big mass directly onto the inner surface of the target shell at about 300 °C. The investigation showed that the formation and dissolution of oxide sol particles of rubidium oxide, where 82Sr is initially adsorbed in SrO form, play an important role in the mechanism of adsorption. The approach is prospective for different modes in “off-line” and “on-line” 82Sr production. Direct sorption of different NCA radionuclides from molten Pb and Ag was also investigated. Chemical nature of the surface (Ta, Ni, Ti, Mo, Al, or quartz) is very critical for sorption of 188,189Ir, 188Pt,198Au,97Ru,185Os,182mRe,99Mo and 99mTc from molten Pb, and for sorption of 100Pd,101mRh,97Ru, 96Tc from molten Ag.

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Wallace, R. L., and W. A. Anderson. "Solution Grown Polysilicon for Flat Panel Displays." MRS Proceedings 424 (1996). http://dx.doi.org/10.1557/proc-424-219.

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AbstractThin-film poly-Si on low-cost substrates is useful for thin-film transistors in flat panel displays or for photovoltaics. The films reported herein were formed at 600°C by d.c. magnetron sputtering from a Si-target onto a SiO2/Mo substrate, pre-coated with Sn or In/Ti to give a liquid phase growth. Poly-Si films have given a preferred (111) orientation, grain size up to 20μm, a carrier mobility exceeding 100cm2/Vs and carrier lifetime of 8μs when using the Sn pre-layer. The Sn pre-layer typically gave smaller grain size than did the In/Ti solvent but the latter gave lower carrier lifetime from Ti incorporation in the film. The film from the Sn pre-layer gave carrier mobility of 140cm2/V-s after hydrogenation by microwave electron cyclotron resonance. Properties of the Si thin-film can be controlled by type of pre-layer, doping of the target, substrate temperature and deposition environment.

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Journal articles on the topic '99mTc, Mo target, cyclotron'

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