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Radiation dose from cyclotron-produced 99mTc-radiopharmaceuticals based on their experimentally determined isotopic composition
Abstracts
Now, we started the development of direct production of 99mTc under 18 MeV proton beam from C18 cyclotron, which will be placed and commissioned at YerPhI in summer 2014, via 100Mo(p,2n)99mTc reaction. The aim is to cover the demand of Armenia of 99mTc isotope. Reference [1] Avagyan R, et al. Nucl Med Biol 2014;41(7):648–9.
649
(NH4)3PO4 · 3H2O, temperature and the time of precipitation. The precipitate can be separated after 15 minutes. From performed studies it can be concluded that the proposed process is promising and allows fast separation of macroamounts of Mo from the solution without co-precipitation of 99mTc. After optimization, the lowest concentration of MoO42 − was only 0.37 mg/ml. Additional purification by sorption of 99mTcO4− using ABEC resin, extraction by HDEHP or sorption of 99mTcO4− by nano-ZrO2 may be required to obtain solution with lower concentration of molybdenum.
http://dx.doi.org/10.1016/j.nucmedbio.2014.05.096
http://dx.doi.org/10.1016/j.nucmedbio.2014.05.090
131 Production of high purity 57Co at the Brookhaven Linac Isotope Producer Zachary P. Gotliba, Suzanne V. Smithb
133 Radiation dose from cyclotron-produced 99mTc-radiopharmaceuticals based on their experimentally determined isotopic composition Svetlana V. Selivanovaa, Johan E. van Liera, Éric Turcottea, Roger Lecomtea, Brigitte Guérina, Ondrej Lebedab, Erik J. van Lierc, Alexander Zyuzinc
a
Chemistry Department, Kutztown University of Pennsylvania, Kutztown, PA 19530 b Medical Isotope Research Program, Collider-Accelerator Department, Brookhaven National Laboratory, Upton, NY 11973
a
Sherbrooke University Hospital Research Centre, Canada Nuclear Physics Institute, Czech Republic c Advanced Cyclotron Systems Inc., Canada b
Cobalt-57 (57Co) is an important radioisotope that has ideal characteristics for use in the calibration of a range of instruments, such as point sources, dose calibrators and imaging cameras. We are interested to produce 57Co by degrading high-energy proton beam of the Brookhaven Linac Isotope Producer (BLIP). The challenge to this approach is that degrading the proton energy beam results in straggle of proton energy which can result in varied production yields and introduce undesirable radionuclide contaminates. The current method for purifying 57Co requires large quantities of highly concentrated acids, which can introduce contaminating metal ions into the nickel targets material and therefore potentially introduce contaminating radioisotopes. It is important to consider the “whole of life cycle” in the production of any radionuclide, that is, the purification of the desired radioisotopes as well as the type of solvent used and waste produced. This study will discuss the design of the target array and the development of a new separation process using organic acid mixture. Our aim is to reduce the introduction of contaminating metal ions into the recycled nickel targets, but also decrease process times and amount of hazardous radioactive waste produced. http://dx.doi.org/10.1016/j.nucmedbio.2014.05.118
132 A new simple way separation of 99mTc from 100Mo target M. Gumiela, E. Gniazdowska, P. Koźmiński, A. Bilewicz Institute of Nuclear Chemistry and Technology, Warsaw, Poland There is growing interest in the large scale cyclotron production of 99mTc via the 100Mo(p,2n)99mTc reaction. Adsorption chromatography enables selective elution of sodium pertechnetate from technetium generators, this method of purification is not sufficient for many alternative production methods. Extraction of technetium from irradiated molybdenum may be carried out using either “wet” or “dry” chemical processes such as thermochromatography, ionexchange chromatography. The aim of our studies was to elaborate a simple and fast method for the separation of 99mTc from macroscopic levels of molybdenum targets. We utilized formation of insoluble yellow ammonium molybdenum phosphate in the reaction of ammonium phosphate with molybdate anions. We have optimized four parameters of the process: the concentrations of NH4NO3 and
One of the practical concerns for cyclotron production of 99mTc remains its radioisotopic purity and ensuing impact on radiation dose to patients. Radioisotopic purity of 99mTc-pertechnetate separated from 100Mo targets irradiated with energy drop 20 → 10, 22 → 10, and 24 → 10 MeV for 2 h was evaluated. Targets were made of two different 100Mo quality: 99.03% enrichment, containing 0.07–0.54% other Mo isotopes, and 99.815% enrichment with b0.005% 92Mo–97Mo and 0.17% 98Mo. Based on the 93 -97mTc yield measured experimentally by gamma-ray spectrometry and using biokinetic data in humans, the effective dose was calculated and compared to the dose due to pure 99mTc for selected 99m Tc-radiopharmaceuticals. Estimated dose increase relative to pure 99mTc for 99mTc-pertechnetate produced from 99.03% 100Mo at 20/22/24 MeV was b5/6/7% if injected up to 3 h post-synthesis, and b9/11/14% if injected at expiry (12 h postsynthesis). For 99.815% 100Mo, the increase in effective dose would be b1% and b3%, respectively, even at Ein = 24 MeV. Irradiation of 99.03% 100Mo with Ein ≤20 MeV will result in 99mTc of acceptable radioisotopic purity. Clinical quality 99mTc can be produced from 99.815% 100Mo targets at up to 24 MeV. http://dx.doi.org/10.1016/j.nucmedbio.2014.05.087
134 Microspectrophotometry for detection of metal ion concentration of radioisotopic solutions Hayley Reeda, Suzanne V. Smithb a
Chemistry Department, Muhlenberg College, Allentown, PA 18104 Medical Isotope Research Program, Collider-Accelerator Department, Brookhaven National Laboratory, Upton, NY 11973
b
The ability to determine specific activity of the radioisotope and any contaminating metal ions of radioisotope solution prior to release is challenging. Atomic absorption spectroscopy (AAS) and inductively coupled plasma atomic and optical emission spectroscopy (ICP-AES and ICP-OES) are very sensitive and can analyze for multiple metal ions simultaneously. Unfortunately, they require relatively large quantities (up to 5 mL) of radioactive solutions,
Now, we started the development of direct production of 99mTc under 18 MeV proton beam from C18 cyclotron, which will be placed and commissioned at YerPhI in summer 2014, via 100Mo(p,2n)99mTc reaction. The aim is to cover the demand of Armenia of 99mTc isotope. Reference [1] Avagyan R, et al. Nucl Med Biol 2014;41(7):648–9.
649
(NH4)3PO4 · 3H2O, temperature and the time of precipitation. The precipitate can be separated after 15 minutes. From performed studies it can be concluded that the proposed process is promising and allows fast separation of macroamounts of Mo from the solution without co-precipitation of 99mTc. After optimization, the lowest concentration of MoO42 − was only 0.37 mg/ml. Additional purification by sorption of 99mTcO4− using ABEC resin, extraction by HDEHP or sorption of 99mTcO4− by nano-ZrO2 may be required to obtain solution with lower concentration of molybdenum.
http://dx.doi.org/10.1016/j.nucmedbio.2014.05.096
http://dx.doi.org/10.1016/j.nucmedbio.2014.05.090
131 Production of high purity 57Co at the Brookhaven Linac Isotope Producer Zachary P. Gotliba, Suzanne V. Smithb
133 Radiation dose from cyclotron-produced 99mTc-radiopharmaceuticals based on their experimentally determined isotopic composition Svetlana V. Selivanovaa, Johan E. van Liera, Éric Turcottea, Roger Lecomtea, Brigitte Guérina, Ondrej Lebedab, Erik J. van Lierc, Alexander Zyuzinc
a
Chemistry Department, Kutztown University of Pennsylvania, Kutztown, PA 19530 b Medical Isotope Research Program, Collider-Accelerator Department, Brookhaven National Laboratory, Upton, NY 11973
a
Sherbrooke University Hospital Research Centre, Canada Nuclear Physics Institute, Czech Republic c Advanced Cyclotron Systems Inc., Canada b
Cobalt-57 (57Co) is an important radioisotope that has ideal characteristics for use in the calibration of a range of instruments, such as point sources, dose calibrators and imaging cameras. We are interested to produce 57Co by degrading high-energy proton beam of the Brookhaven Linac Isotope Producer (BLIP). The challenge to this approach is that degrading the proton energy beam results in straggle of proton energy which can result in varied production yields and introduce undesirable radionuclide contaminates. The current method for purifying 57Co requires large quantities of highly concentrated acids, which can introduce contaminating metal ions into the nickel targets material and therefore potentially introduce contaminating radioisotopes. It is important to consider the “whole of life cycle” in the production of any radionuclide, that is, the purification of the desired radioisotopes as well as the type of solvent used and waste produced. This study will discuss the design of the target array and the development of a new separation process using organic acid mixture. Our aim is to reduce the introduction of contaminating metal ions into the recycled nickel targets, but also decrease process times and amount of hazardous radioactive waste produced. http://dx.doi.org/10.1016/j.nucmedbio.2014.05.118
132 A new simple way separation of 99mTc from 100Mo target M. Gumiela, E. Gniazdowska, P. Koźmiński, A. Bilewicz Institute of Nuclear Chemistry and Technology, Warsaw, Poland There is growing interest in the large scale cyclotron production of 99mTc via the 100Mo(p,2n)99mTc reaction. Adsorption chromatography enables selective elution of sodium pertechnetate from technetium generators, this method of purification is not sufficient for many alternative production methods. Extraction of technetium from irradiated molybdenum may be carried out using either “wet” or “dry” chemical processes such as thermochromatography, ionexchange chromatography. The aim of our studies was to elaborate a simple and fast method for the separation of 99mTc from macroscopic levels of molybdenum targets. We utilized formation of insoluble yellow ammonium molybdenum phosphate in the reaction of ammonium phosphate with molybdate anions. We have optimized four parameters of the process: the concentrations of NH4NO3 and
One of the practical concerns for cyclotron production of 99mTc remains its radioisotopic purity and ensuing impact on radiation dose to patients. Radioisotopic purity of 99mTc-pertechnetate separated from 100Mo targets irradiated with energy drop 20 → 10, 22 → 10, and 24 → 10 MeV for 2 h was evaluated. Targets were made of two different 100Mo quality: 99.03% enrichment, containing 0.07–0.54% other Mo isotopes, and 99.815% enrichment with b0.005% 92Mo–97Mo and 0.17% 98Mo. Based on the 93 -97mTc yield measured experimentally by gamma-ray spectrometry and using biokinetic data in humans, the effective dose was calculated and compared to the dose due to pure 99mTc for selected 99m Tc-radiopharmaceuticals. Estimated dose increase relative to pure 99mTc for 99mTc-pertechnetate produced from 99.03% 100Mo at 20/22/24 MeV was b5/6/7% if injected up to 3 h post-synthesis, and b9/11/14% if injected at expiry (12 h postsynthesis). For 99.815% 100Mo, the increase in effective dose would be b1% and b3%, respectively, even at Ein = 24 MeV. Irradiation of 99.03% 100Mo with Ein ≤20 MeV will result in 99mTc of acceptable radioisotopic purity. Clinical quality 99mTc can be produced from 99.815% 100Mo targets at up to 24 MeV. http://dx.doi.org/10.1016/j.nucmedbio.2014.05.087
134 Microspectrophotometry for detection of metal ion concentration of radioisotopic solutions Hayley Reeda, Suzanne V. Smithb a
Chemistry Department, Muhlenberg College, Allentown, PA 18104 Medical Isotope Research Program, Collider-Accelerator Department, Brookhaven National Laboratory, Upton, NY 11973
b
The ability to determine specific activity of the radioisotope and any contaminating metal ions of radioisotope solution prior to release is challenging. Atomic absorption spectroscopy (AAS) and inductively coupled plasma atomic and optical emission spectroscopy (ICP-AES and ICP-OES) are very sensitive and can analyze for multiple metal ions simultaneously. Unfortunately, they require relatively large quantities (up to 5 mL) of radioactive solutions,