177Lu was produced with a specific activity of approximately 70-80 mCi/mg and radionuclidic purity of 99.98% by irradiation of natural Lu2O3 (99.999% purity from Aldrich Co., UK) targeted at a thermal neutron flux of approximately 4-1013 n.cm-2.sec-1 for 5 days at Tehran Research Reactor (TRR). Whatman No. 3 paper was obtained from Whatman Company (UK). Radio-chromatography was performed by using a Bioscan AR-2000 radio TLC scanner instrument (Bioscan, France). A high purity germanium (HPGe) detector coupled with a Canberra™ (model GC1020-7500SL, Canberra Industries, Inc. CT, U.S.A.) multichannel analyzer and a dose calibrator ISOMED 1010 (Elimpex-Medizintechnik, Austria) was used for counting distributed activity in rat organs. All other chemical reagents were purchased from Merck Company (Germany).
Calculations were performed based on the 112 keV peak for 177Lu. All values were expressed as mean ± standard deviation and the data were compared using Student’s t-test. Animal studies were performed in accordance with the United Kingdom Biological Council’s Guidelines on the Use of Living Animals in Scientific Investigations (1987). The approval of NSTRI Ethical Committee was obtained for conducting this research.
The wild-type rats (NMRI), weighing 180-200 g, were purchased from Pasteur Institute of Iran (Karaj), and acclimatized at proper rodent diet and 12 h/12 h day/night light/darkness.
Production and quality control of 177LuCl3 solution
177Lu was produced by neutron irradiation of 1 mg natural Lu
2O
3, according to the reported procedures (
10) at TRR (General Atomics, USA). The irradiated target was dissolved in 200 µL of 1.0 molL
-1M HCl, for the preparation of
177LuCl
3 and then diluted to the appropriate volume with ultra pure water for the production of a stock solution of final volume of 5 mL (0.04 molL
1). The mixture was filtered through a 0.22 µm filter (Waters, USA) for the purpose of sterilization. The radionuclidic purity of the solution was determined for the presence of other radionuclides using purity germanium (HPGe) spectroscopy, through the detection of various interfering gamma emitting radionuclides. The radiochemical purity of the
177LuCl
3 was evaluated using 2-solvent systems for instant thin layer chromatography (ITLC) [A: 10 mmolL
-1 diethylenetriamine pentaacetic acid (DTPA), pH = 5 and B: 10% ammonium acetate:methanol mixture (1:1)].
Synthesis of EDTMP
EDTMP was synthesized from phosphorous acid, ethylenediamine and formaldehyde in the presence of HCl by a modified Mannich-type reaction (
11). To the stirring mixture of phosphorous acid (33.66 g, 0.5 mole) and concentrated HCl (33.44 g) under N
2 atmosphere, ethylenediamine dihydrochloride (5 g, 0.08 moles) was added drop wise and the mixture was heated to reflux. Aqueous solution of formaldehyde (37 %) was then added drop wise to the mixture. Reflux (at 100 °C) continued for 4 h and the boiling suspension was evaporated under vacuum. The residue was recrystallized from water/methanol mixture [m.p. 214-215°C; IR (KBr, ν cm
-1): 3308, 2633, 2311, 1668, 1436, 1356;
1H-NMR (D
2O, δ ppm): 3.53 (d, J = 12.3 Hz, 8H,-N-CH
2-P=O), 3.85 (s, 4H, -N-CH
2-);
13C NMR (D
2O, δ ppm): 51.63, 52.73;
31P NMR (D
2O, δ ppm): 10.52].
Radiolabeling of EDTMP with 177LuCl3
A stock solution of EDTMP was prepared by dissolving in 1 molL-1 NaOH and diluted to the appropriate volume with ultra pure water, in order to produce a solution of 50 mg.mL-1. For labeling, an appropriate amount of the 177LuCl3 solution (0.1 mL, 50 mCi) containing the required activity was added to the desired amount of EDTMP solution (0.3 mL, 1 to 5 mg.mL-1). The complex solution was then kept at room temperature for 60 min. The final solution was passed through a 0.22 µm membrane filter and the pH was adjusted to 7-8.5 with 0.05 molL-1 phosphate buffer (pH = 5.5). The radiochemical purity was determined using Whatman 3 MM chromatography paper or ITLC-SG, eluted with NH4OH (56%): methanol (%100): water (%100) (0.2:2:4; v/v/v) mixture.
Sterility and Apyrogenicity of the radiopharmaceutical
Sterility was controlled on a random sampling following the decay of radioactivity. The Limulus Amoebocyte Lysate (LAL) test was used for the validation of radiopharmaceutical production method according to European protocol (
12).
Stability of 177Lu-EDTMP in final formulation
Stability of 177Lu-EDTMP in the final preparation was determined by storing the final solution at 25 °C for 2 days and performing frequent ITLC analysis for the determination of radiochemical purity using Whatman 3 MM chromatography paper or ITLC-SG, eluted with NH4OH (56%):methanol (%100):water (%100) (0.2:2:4; v/v/v) mixture.
Stability of 177Lu-EDTMP in presence of human serum
Final 177Lu-EDTMP solution (200 µCi, 50 µL) was incubated in the presence of freshly prepared human serum (300 µL) (Purchased from Iranian Blood Transfusion Organization, Tehran, Iran) at 37 °C for 2 days. The stability was determined by performing frequent ITLC analysis using the above-mentioned chromatography system.
Biodistribution studies
The biodistribution of free Lu3+ cation as well as of 177Lu-EDTMP was determined in wild-type rats. For each radiochemical compound, 100 µL (150 µCi) radioactive solution was injected directly to normal rat through caudal vein. The animals (n = 3) were sacrificed at predetermined times following the injection (2 h to 7 days) and the percentage of the injected dose in the tissues was then determined with a ©-ray scintillation or a dose calibrator.
Single photon emission computed tomography (SPECT) imaging of 177Lu-EDTMP in wild-type rats
For imaging studies, 177Lu-EDTMP solution (7.4 MBq, 200 µL) was injected intravenously to rats through their tail veins, followed by the injection of propofol-xylazine mixture for anaesthetization. The images were taken after administration of the radiopharmaceutical by a single-head SPECT system (Siemens, Germany) based on 112 keV peak (15% energy window). The rat-to-septa distance was 12 cm.