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Aydia MI, El-Said H, El-Sadek AA, El-Azony KM. Preparation and characterization of zirconium silico 188W-tungstate as a base material for 188W/ 188Re generator. Appl Radiat Isot 2018; 142:203-210. [PMID: 30408724 DOI: 10.1016/j.apradiso.2018.09.026] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 10/12/2017] [Revised: 09/11/2018] [Accepted: 09/20/2018] [Indexed: 11/18/2022]
Abstract
Zr:W:Si. The optimum gel was prepared using the molar ratio 1:1:7 at pH 8. The ZrSiW gel was investigated by FTIR, XRD, thermal analysis (TGA and DTA), FESEM, XRF, and NAA. Then, XRF and NAA techniques were used to estimate the proportion of the constituents of the gel according to the molecular formula [ZrO2(Si(WO4)2)16H2O]. 188W/188Re generator was prepared based on the selected ZrSi188W gel, which gives the highest tungsten content (393.3 mg W/g gel) with 75 ± 3% elution yield of 188Re. Quality control was studied on the 188Re to make sure its validity for clinical applications.
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Affiliation(s)
- M I Aydia
- Radioactive Isotopes and Generators Department, Hot Labs. Center, Atomic Energy Authority, P.O. Box 13759, Cairo, Egypt
| | - H El-Said
- Radioactive Isotopes and Generators Department, Hot Labs. Center, Atomic Energy Authority, P.O. Box 13759, Cairo, Egypt
| | - A A El-Sadek
- Radioactive Isotopes and Generators Department, Hot Labs. Center, Atomic Energy Authority, P.O. Box 13759, Cairo, Egypt
| | - K M El-Azony
- Radioactive Isotopes and Generators Department, Hot Labs. Center, Atomic Energy Authority, P.O. Box 13759, Cairo, Egypt.
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2
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Nano-technology contributions towards the development of high performance radioisotope generators: The future promise to meet the continuing clinical demand. Appl Radiat Isot 2017; 129:67-75. [DOI: 10.1016/j.apradiso.2017.08.012] [Citation(s) in RCA: 12] [Impact Index Per Article: 1.5] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 03/30/2017] [Revised: 07/21/2017] [Accepted: 08/07/2017] [Indexed: 11/17/2022]
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Boschi A, Martini P, Uccelli L. 188Re(V) Nitrido Radiopharmaceuticals for Radionuclide Therapy. Pharmaceuticals (Basel) 2017; 10:ph10010012. [PMID: 28106830 PMCID: PMC5374416 DOI: 10.3390/ph10010012] [Citation(s) in RCA: 15] [Impact Index Per Article: 1.9] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Download PDF] [Figures] [Journal Information] [Subscribe] [Scholar Register] [Received: 12/07/2016] [Revised: 01/09/2017] [Accepted: 01/16/2017] [Indexed: 11/27/2022] Open
Abstract
The favorable nuclear properties of rhenium-188 for therapeutic application are described, together with new methods for the preparation of high yield and stable 188Re radiopharmaceuticals characterized by the presence of the nitride rhenium core in their final chemical structure. 188Re is readily available from an 188W/188Re generator system and a parallelism between the general synthetic procedures applied for the preparation of nitride technetium-99m and rhenium-188 theranostics radiopharmaceuticals is reported. Although some differences between the chemical characteristics of the two metallic nitrido fragments are highlighted, it is apparent that the same general procedures developed for the labelling of biologically active molecules with technetium-99m can be applied to rhenium-188 with minor modification. The availability of these chemical strategies, that allow the obtainment, in very high yield and in physiological condition, of 188Re radiopharmaceuticals, gives a new attractive prospective to employ this radionuclide for therapeutic applications.
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Affiliation(s)
- Alessandra Boschi
- Department of Morphology, Surgery and Experimental Medicine, University of Ferrara, Ferrara 44121, Italy.
| | - Petra Martini
- Department of Morphology, Surgery and Experimental Medicine, University of Ferrara, Ferrara 44121, Italy.
- Italy and Legnaro National Laboratories, Italian National Institute for Nuclear Physics (LNL-INFN), Legnaro (PD) 35020, Italy.
| | - Licia Uccelli
- Department of Morphology, Surgery and Experimental Medicine, University of Ferrara, Ferrara 44121, Italy.
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4
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Azadbakht B, Afarideh H, Ghannadi-Maragheh M, Asgari M, Bahrami-Samani A. Development of an electrochemical 188W/ 188Re generator as a technique for separation and purification of 188Re in radiopharmaceutical applications. Appl Radiat Isot 2016; 118:331-337. [PMID: 27750109 DOI: 10.1016/j.apradiso.2016.09.027] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 07/16/2016] [Revised: 09/06/2016] [Accepted: 09/07/2016] [Indexed: 10/20/2022]
Abstract
In this study, a simple electrochemical procedure adaptable for using low specific activity 188W for separation and purification of 188Re from 188W to obtain no carrier added (NCA) 188Re is developed. The electrochemical parameters were optimized to maximize the 188Re electrodeposition yield with minimal 188W contamination. Two cycle electrolysis procedure was developed. The first electrochemical cell was used for separation of 188Re and in the second electrochemical cell, separation and purification of 188Re with >90% deposition yield of 188Re and minimal contamination of 188W (<10-4%) was achieved. The overall electrodeposition yield of 188Re was >90% with >99% radionuclidic purity and >99% radiochemical purity suitable for radiopharmaceutical applications. Furthermore, the performance of the generator remained consistent during a period of 69 days, one half-life of 188W, when the electrochemical separation procedure was performed frequently, at least once in 5 days.
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Affiliation(s)
- Bakhtiar Azadbakht
- Department of Energy Engineering and Physics, Amirkabir University of Technology, 15875-4413 Tehran, Iran
| | - Hossein Afarideh
- Department of Energy Engineering and Physics, Amirkabir University of Technology, 15875-4413 Tehran, Iran.
| | | | - Mehdi Asgari
- Nuclear Science and Technology Research Institute (NSTRI), P.O. Box:14395-836, Tehran, Iran
| | - Ali Bahrami-Samani
- Nuclear Science and Technology Research Institute (NSTRI), P.O. Box:14395-836, Tehran, Iran
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Zaidi JH, Wasim M, Arif M, Mushtaq A. Development of radiochemistry in Pakistan – 1960 to 2010. RADIOCHIM ACTA 2014. [DOI: 10.1524/ract.2012.1952] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
Abstract
Abstract
With the inception of Pakistan Atomic Energy Commission (PAEC) in 1956, peaceful uses of atomic energy commenced for the benefit of scientific community as well as masses of Pakistan. Radiochemistry played a vital role right from the beginning. The research and development in this field accelerated soon after the criticality of the first research reactor named as Pakistan Research Reactor (PARR- 1) at the Pakistan Institute of Nuclear Science and Technology (PINSTECH), Islamabad. The first radioisotope produced at PARR-1 for application in nuclear medicine was 131I. Later on, many other radioisotopes were prepared and radiopharmaceuticals were synthesised for their use in industry and hospitals. Besides providing pure radioactive tracers for nuclear medicine, radiochemistry also enhanced the detection limit of impurities at all stages of nuclear fuel cycle for power generation. In 1983, research in the field of nuclear data measurement began. The main aim was to identify suitable conditions for the production of radionuclides for cancer diagnostics, treatment and therapy. With the establishment of a second research reactor (PARR-2) at PINSTECH, research in neutron activation analysis, radioisotope production and separation studies gained more momentum and many research articles were published. Solvent extraction, adsorption and ion-exchange were the main routes of separation in those studies. Separation of heavy metals and treatment of waste generated in a nuclear power plant are other important aspects related to environmental restoration and nuclear waste management, where radiochemistry is required. In future, work in radiochemistry will be continued on similar lines to develop novel radiopharmaceuticals, identify indigenous schemes for nuclear waste management and work out intelligent procedures for material characterization for benefit to mankind, especially the people of Pakistan.
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Affiliation(s)
- J. H. Zaidi
- Pakistan Institute of Nuclear Science and Technology, P.O. Nilore, Islamabad, Pakistan
| | - M. Wasim
- Pakistan Institute of Nuclear Science and Technology, P.O. Nilore, Islamabad, Pakistan
| | - M. Arif
- Pakistan Institute of Nuclear Science and Technology, P.O. Nilore, Islamabad, Pakistan
| | - A. Mushtaq
- Pakistan Institute of Nuclear Science and Technology, P.O. Nilore, Islamabad, Pakistan
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Chakravarty R, Dash A. Nanomaterial-based adsorbents: the prospect of developing new generation radionuclide generators to meet future research and clinical demands. J Radioanal Nucl Chem 2013. [DOI: 10.1007/s10967-013-2823-1] [Citation(s) in RCA: 8] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]
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7
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Iller E, Wawszczak D, Konior M, Polkowska-Motrenko H, Milczarek JJ, Górski L. Synthesis and structural investigations of gel metal oxide composites WO3–ZrO2, WO3–TiO2, WO3–ZrO2–SiO2, and their evaluation as materials for the preparation of 188W/188Re generator. Appl Radiat Isot 2013; 75:115-27. [DOI: 10.1016/j.apradiso.2013.01.038] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 06/13/2012] [Revised: 01/22/2013] [Accepted: 01/31/2013] [Indexed: 10/27/2022]
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Chakravarty R, Shukla R, Ram R, Venkatesh M, Tyagi AK, Dash A. Exploitation of Nano Alumina for the Chromatographic Separation of Clinical Grade 188Re from 188W: A Renaissance of the 188W/188Re Generator Technology. Anal Chem 2011; 83:6342-8. [DOI: 10.1021/ac201232m] [Citation(s) in RCA: 18] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
Affiliation(s)
- Rubel Chakravarty
- Radiopharmaceuticals Division and ‡Chemistry Division, Bhabha Atomic Research Centre, Mumbai 400 085, India
| | - Rakesh Shukla
- Radiopharmaceuticals Division and ‡Chemistry Division, Bhabha Atomic Research Centre, Mumbai 400 085, India
| | - Ramu Ram
- Radiopharmaceuticals Division and ‡Chemistry Division, Bhabha Atomic Research Centre, Mumbai 400 085, India
| | - Meera Venkatesh
- Radiopharmaceuticals Division and ‡Chemistry Division, Bhabha Atomic Research Centre, Mumbai 400 085, India
| | - Avesh Kumar Tyagi
- Radiopharmaceuticals Division and ‡Chemistry Division, Bhabha Atomic Research Centre, Mumbai 400 085, India
| | - Ashutosh Dash
- Radiopharmaceuticals Division and ‡Chemistry Division, Bhabha Atomic Research Centre, Mumbai 400 085, India
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Molybdenum-99/technetium-99m management: race against time. Ann Nucl Med 2011; 25:677-9. [DOI: 10.1007/s12149-011-0512-0] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 05/20/2011] [Accepted: 06/13/2011] [Indexed: 10/18/2022]
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Qazi QM, Ahmad M. Preparation and evaluation of hydrous titanium oxide as a high affinity adsorbent for molybdenum (99Mo) and its potential for use in 99mTc generators. RADIOCHIM ACTA 2011. [DOI: 10.1524/ract.2011.1817] [Citation(s) in RCA: 16] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
Abstract
Abstract
Hydrous titanium oxide was prepared and its affinity as an adsorbent for molybdenum ( 99Mo) and its potential for use in 99mTc generators were evaluated. Adsorption behavior of molybdate on hydrous titanium oxide was studied at boiling water bath temperature (∼100 °C) using radiotracer technique. Various parameters affecting the adsorption of molybdenum, such as pH, amount of molybdenum, incubation period etc. , were determined. Technetium-99m generators were prepared by adsorbing low specific activity Molybdenum-99 (∼230 mg) on 1 g hydrous titanium oxide. Elutions were carried out with normal saline. Performance of the generators, such as 99Mo breakthrough, titanium content, pH, elution profile, radiochemical purity and labeling efficiency of kits, was checked.
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Affiliation(s)
- Q. M. Qazi
- Pakistan Institute of Nuclear Science and Technology, Isotope Production Division, P.O. Nilore, Islamabad, Pakistan
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Chakravarty R, Shukla R, Ram R, Tyagi AK, Dash A, Venkatesh M. Practicality of Tetragonal Nano-Zirconia as a Prospective Sorbent in the Preparation of 99Mo/99mTc Generator for Biomedical Applications. Chromatographia 2010. [DOI: 10.1365/s10337-010-1754-z] [Citation(s) in RCA: 36] [Impact Index Per Article: 2.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/05/2022]
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12
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Nanocrystalline zirconia: A novel sorbent for the preparation of 188W/188Re generator. Appl Radiat Isot 2010; 68:229-38. [DOI: 10.1016/j.apradiso.2009.10.031] [Citation(s) in RCA: 27] [Impact Index Per Article: 1.8] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 03/24/2009] [Revised: 08/28/2009] [Accepted: 10/16/2009] [Indexed: 11/20/2022]
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13
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Abstract
Because of the high content of inactive molybdenum in neutron irradiated MoO3, large columns containing alumina or gel are needed to produce chromatographic 99Mo→99mTc generator. This results in large elution volumes containing relatively high 99Mo breakthrough and low concentrations of 99mTcO4
-. The decrease in specific volume of 99mTc places a limitation on reconstitution of some kits for 99mTc radiopharmaceuticals applied in diagnostic nuclear medicine. Hence concentration technique is mandatory for effective utilization of (n,γ) produced 99Mo/99mTc generators at the start of its life whereas in case of fission 99Mo/99mTc generator the technique may be quite useful at the end of first week of its life. We report post elution concentration of 99mTc using in house prepared Pb column. The high bolus volumes (10–60 ml saline) can conveniently be concentrated in ∼1 ml of saline.
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Mushtaq A, Bukhari TH, Khan IU. Extraction of medically interesting 188Re-perrhenate in methyl ethyl ketone for concentration purposes. RADIOCHIM ACTA 2009. [DOI: 10.1524/ract.2007.95.9.535] [Citation(s) in RCA: 10] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
Abstract
The high bolus volumes (20–40mL) of the generator-produced Rhenium-188 require post elution concentration of the eluate for the preparation of a dissolved β− source and radiopharmaceuticals labeled with Re-188 for radiotherapy. Solvent extraction of 188Re in methyl ethyl ketone was studied. With the increase of organic phase volume, extraction of 188Re was enhanced while mixing time of aqueous and organic phases did not show any significant effect on the extractability of 188Re in the organic phase. Almost 80% of 188Re was extracted in methyl ethyl ketone at a volume ratio of 1:2 for aqueous and organic phases. By evaporation/distillation of methyl ethyl ketone, 188Re was concentrated and dissolved in the desired volume of physiological saline.
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Chakravarty R, Dash A, Kothari K, Pillai MRA, Venkatesh M. A novel 188W/188Re electrochemical generator with potential for medical applications. RADIOCHIM ACTA 2009. [DOI: 10.1524/ract.2009.1612] [Citation(s) in RCA: 18] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
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16
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Bokhari TH, Mushtaq A, Khan IU. Lead cation exchange and alumina columns for concentration of 99mTc-pertechnetate. J Radioanal Nucl Chem 2008. [DOI: 10.1007/s10967-007-7264-2] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
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17
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Mushtaq A, Haider I. Sodium sulfate as an eluant for concentrated solution of pertechnetate. Appl Radiat Isot 2008; 66:1079-82. [PMID: 18280744 DOI: 10.1016/j.apradiso.2008.01.004] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 08/23/2007] [Revised: 12/06/2007] [Accepted: 01/04/2008] [Indexed: 11/27/2022]
Abstract
Fission molybdenum-99 based technetium-99m chromatography generators are the most widely employed generator systems in the field of diagnostic nuclear medicine. In the first week these generators provide high specific volume activity Na99mTcO4, but in the second week the radioactive concentration of the eluate (99mTc) becomes 17% of that at the beginning of the first week. Low specific volume activity limits the clinical procedures (e.g. 99mTc-DTPA for lung ventilation scanning, 99mTc-sestamibi for myocardial perfusion studies, 99mTc-ECD for brain imaging and 99mTc-red cells for testicles) that can be performed at the beginning of the second week. To overcome such limitations sodium sulfate was used as an eluant, which provides>80% of 99mTc radioactivity in 2 ml solution, while 0.9% NaCl provides only 40-45% 99mTc in first 2 ml solution.
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Affiliation(s)
- A Mushtaq
- Isotope Production Division, Pakistan Institute of Nuclear Science and Technology, P.O. Nilore, Islamabad, Pakistan.
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