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24 protocols using dose calibrator

1

Fluoride Recovery from QMA Cartridge

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Waters QMA-light Sep-Paks were washed sequentially with ethanol (10 mL), 0.5 M preconditioning agent in water (10 mL), and deionized water (10 mL). Aqueous [18F]fluoride (0.5 mL) was passed through a QMA cartridge followed by 2 mL air, and the activity of the QMA cartridge was determined with a Capintec dose calibrator. [18F]Fluoride was then eluted from the QMA cartridge into a 4 mL vial with 0.5 mL eluent solution, followed by 2 mL of air. Activity of the 4 mL vial (eluate) and QMA cartridge (residual [18F]fluoride) were determined with a Capintec dose calibrator. Activity data was used to calculate % fluoride recovery.
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2

Radiosynthesis and Purification of [18F]Fluoride

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[18F]Fluoride was produced by the 18O(p,n)18F reaction using a GE Healthcare PETtrace cyclotron (Uppsala, Sweden). Radioactivity was measured in a dose calibrator (Biodex Medical Systems, Shirley, NY, USA). TLC was performed on Merck F254 silica plates and analyzed on a Bioscan radio-TLC scanner (Washington, D.C., USA). Purification and analysis of the radioligand were performed using HPLC equipped with a semi-preparative column (YMC-Pack C18, 10 × 250 mm, 5 µm) or an analytical column (YMC-Pack C18, 4.6 × 250 mm, 5 µm). The eluent was monitored simultaneously, using UV (254 nm) and NaI(T1) radioactivity detectors.
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3

Radiolabeling and Purification of [64Cu]CuCl2

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[64Cu]CuCl2 was kindly provided by the Korea Institute of Radiological and Medical Sciences (KIRAMS; Seoul, Korea). All buffers and aqueous HPLC eluents used for radiolabeling were pretreated with Chelex 100 resin. Purification of the product was performed by HPLC (Thermo Fisher Scientific, Waltham, MA, USA) equipped with a semi-preparative column (YMC-Pack C18, 5 µm, 10 × 250 mm). The analysis of the radioligand was performed by HPLC (Agilent Technologies, Santa Clara, CA, USA) using an analytical column (YMC-Pack C18, 5 µm, 4.6 × 250 mm). Eluates were monitored simultaneously using NaI(T1) radioactivity and UV (230 nm) detectors. Radioactivity was measured using a dose calibrator (Biodex Medical Systems, Shirley, NY, USA).
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4

Comprehensive Radiochemical Analytical Techniques

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Microtubes, erlenmeyer, beaker, measuring cup, stirring rod, micropipette (Eppendorf), 0.2 and 0.5 mL microcentrifuge tubes, a set of paper chromatography and paper electrophoresis equipment, analytical balance (Metler Toledo), oven (Memmert), incubator 37 °C (Memmert), digital shaking dry bath (Thermo Scientific), laminar airflow cabinet for radioactive (Comecer), refrigerator -20 °C (Samsung), dose calibrator (Biodex), multi-channel analyzer (Canberra), RadioTLC Scanner (Bioscan), and HPLC UV-Vis and radioactive detector (Agilent Technology).
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5

Gadolinium and Copper Chelation by Macrocyclic Derivatives

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Metal ions are complexed with macrocyclam derivatives in acidic condition (Figure 2c). The lyophilized macrocyclam derivatives were dissolved in distilled water. A 100 nmol aliquot of NrMC or ErMC was mixed with gadolinium chloride (Sigma‐Aldrich) or radioactive copper‐64 chloride in sodium acetate buffer (pH 5.0) and incubated for 2 h at 80°C. Unloaded Gd was removed using a PD‐SpinTrap™ G‐25 column (GE Healthcare, Little Chalfont, UK). The loading amount of Gd in each sample was measured by inductively coupled plasma mass spectrometry (ICP‐MS, Varian 820‐MS; Varian, Palo Alto, CA, USA). Gd chelation consists of a reaction between the Gd3+ and arsenazo III dye under acidic conditions to form a blue–purple complex. Radioactivity was measured using a dose calibrator (Biodex Medical Systems, Shirley, NY, USA).
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6

Radiolabeling of NOTA-Conjugated MG7 Antibody with Gallium-68

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All commercially accessible chemicals (biochemical grade) were purchased from Sigma Aldrich (St. Louis, MO, USA) and without further purification. The NOTA-NHS-ester was purchased from Macrocyclis (Dallax, TX, USA). 68Ga was obtained from a 68Ge/68Ga generator (Isotope Technologies Garching GmbH, Garching, Germany). The mouse monoclonal antibody MG7 was produced and purified in State Key Laboratory of Cancer Biology, Institute of Digestive Diseases, Xijing Hospital, Fourth Military Medical University, PRC. NOTA-MG7 was purified and concentrated using an Amicon® Ultra-2 Centrifugal Filter Device (Merck KGaA, Darmstadt, Germany), and it was quantified using a BCA protein assay kit (Pierce, Rockford, IL, USA). The immunofluorescence was performed using laser confocal scanner (Olimpus, Fluoview FV10i, Tokyo, Japan). Radiochemical analysis was performed using a radioactive thin-layer chromatography scanner (radio-TLC) (Bioscan, Fairfield, CT, USA) to determine the radiochemical purities (RCPs) of 68Ga-NOTA-MG7. Radioactivity was measured using a dose calibrator (Biodex Medical Systems, Shirley, NY, USA) and the tissue radioactivity was counted using an automated gamma counter (Rihuan, Shanghai, China). The in vivo imaging was performed by nanoPET/CT (Mediso, Budapest, Hungary) and the IVIS Lumina II (Caliper, MA, Hopkinton).
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7

Automated [18F]Fluoride Radiosynthesis

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Fluorine-18 was produced via the 18O(p,n)18F nuclear reaction using a GE PETTrace cyclotron (40 μA beam for 2 min generated ca. 150 mCi of fluorine-18 as measured by synthesis module detector). The [18F]fluoride was then processed and either employed in manual reactions, or automated syntheses using a TRACERLab FXFN radiochemistry synthesis module, according to methods described in the SI. Total recovered activity at end-of-synthesis was measured with a Capintec dose calibrator.
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8

Astatine-211 Labeling of Trastuzumab

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Astatine‐211 was produced by the 209Bi(α, 2n)211At reaction, as described previously.13 The 211At labeling of trastuzumab was carried out in accordance with a previously described direct astatination procedure.14 The activities of 211At‐trastuzumab pre/post‐isolation were measured using a dose calibrator (Capintec, Ramsey, NJ, USA) and the labeling yield was calculated by dividing the post‐isolation activity by the pre‐isolation activity.
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9

Radiosynthesis of [18F]-3-Fluoro-4-Nitropyridine N-Oxide

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Example 6

Radiochemical synthesis of [18F]-3-fluoro-4-nitropyridine N-oxide ([18F]-9) from 3-bromo-4-nitropyridine N-oxide (8): 100 μL of 3-bromo-4-nitropyridine N-oxide (8) dissolved in DMSO (20 mg/mL) were added to 100 μL of [18F]-TBAF solution (˜10 mCi, ˜370 MBq) in 3 mL microreactor vial and allowed to react for 15 min. 100 μL of this solution with or without reference standard (20 μg) were injected into a semiprep C-18 HPLC column equipped with a variable wavelength UV-Vis detector and a radiation detector (conditions C). The radioactive peaks were collected and the radioactivity of each fraction measured using a Capintec dose calibrator. The radiochemical yield was calculated as radioactivity in the peak corrected for decay over radioactivity injected.

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10

Radiolabeling of Pyridine N-Oxide Derivative

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Example 7

Radiochemical synthesis of [18F]-3-fluoro-4-nitropyridine N-oxide ([18F]-9) from 3-fluoro-4-nitropyridine N-oxide (9) by 19F/18F exchange: 100 μL of 3-fluoro-4-nitropyridine N-oxide (9) dissolved in DMSO (1 mg/mL) was added to 100 μL of [18F]-TBAF solution (˜10 mCi, ˜370 MBq) in 3 mL microreactor vial and allowed to react for 1 min. 100 μL of this solution were injected into a semiprep C-18 HPLC column equipped with a variable wavelength UV-Vis detector and a radiation detector (conditions E). The radioactive peaks were collected and the radioactivity of each fraction measured using a Capintec dose calibrator. The radiochemical yield was calculated as radioactivity in the peak corrected for decay over radioactivity injected.

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