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Basic Science Investigations |
1 Service Hospitalier Frédéric Joliot, Department of Medical Research, Division of Life Sciences, French Atomic Agency, Orsay, France
2 Service de Physique, Institut Gustave Roussy, Villejuif, France
| ABSTRACT |
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Key Words: 18F-fluoro-A-85380 PET dosimetry central nicotinic receptors
| INTRODUCTION |
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Imaging of nAChRs using PET could provide useful information on the integrity of the nAChR system in vivo. Therefore, it can be a potentially valuable technique for the diagnosis, follow-up, and study of the pathogenesis of several neurodegenerative diseases.
The development of radiolabeled tracers suitable as PET ligands for imaging nAChRs has been an important goal in the recent years. Among several developed compounds, the halogen derivatives of 3-[2(S)-2-azetidinylmethoxy]pyridine (A-85380) are promising because of both their high affinity for the
4ß2 subtype and their low toxicity and lack of mutagenicity (2,3). 2-18F-Fluoro-3-[2(S)-2-azetidinylmethoxy]pyridine (18F-fluoro-A-85380) is being developed as a PET probe for the study of central nAChRs. This compound has been characterized in rodents and baboons (2,4). As part of phase l studies, this investigation was undertaken to assess the whole-body biodistribution of 18F-fluoro-A-85380 and to calculate the associated radiation absorbed doses in healthy human volunteers.
| MATERIALS AND METHODS |
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Subjects
The Medical Bioethics Committee of the Medical Center at the University of Paris XI approved this study. Three healthy male volunteers, with a mean age of 22 y (range, 2123 y) and a mean weight of 74.2 kg (range, 69.379.8 kg) gave their written informed consent for participation in the study. The subjects were free of illness on the basis of screening by medical history, physical examination, serum chemical analysis, complete blood cell count, and urine analysis. They were nonsmokers as demonstrated by the negative plasma cotinine determination. A standard 12-lead electrocardiogram (ECG) was obtained for screening purposes. Before the start of the experiments, all volunteers were asked to urinate. During the PET experiment, ECG findings and blood pressure were continuously monitored from 10 min before to 10 min after the tracer injection. Serum chemical analysis, complete blood cell count and urine analysis were performed before and within 1 wk after completion of the PET study.
PET Imaging Procedure
During data acquisition, subjects were positioned supine with the arms alongside the body in the ECAT Exact HR+ PET scanner (CTI/Siemens, Knoxville, TN).
For each subject, a whole-body transmission scan was obtained before injection of the radioligand using 3 retractable 68Ge rods (each with approximately 74 MBq). Transmission scans lasted 3 min per bed position (field of view, 15 cm), with 8 or 9 steps according to the height of the subject; they were used for subsequent correction of attenuation of emission scans.
Whole-body emission scans were performed (3-dimensional [3D] mode) after an intravenous bolus injection of 191 ± 50.9 MBq (range, 191238 MBq)that is, 1.73 ± 0.21 nmol of 18F-fluoro-A-85380. One-minute step acquisitions, 8 or 9 steps for 1 scan (from the top the head to the upper part of the thigh), were acquired over 2 h.
Urine Collection
All voided urine from the time of injection until 2 h after injection was collected. The urine was collected in a container, and the volume and time of micturition were recorded for all subjects. Three-milliliter urine aliquots were sampled and radioactivity was counted in an automatic
-counter (model 5000; Packard Instrument Co., Downers Grove, IL). After the counting efficiency of the system had been determined, radioactivity measurements of the samples were corrected for physical decay and multiplied by the urine volume at the micturition time. The amount of radioactivity in the urine at the micturition time was expressed as percentage of the injected radioactivity (%ID). Because the vertebral bodies were clearly seen in all subjects and on all images, the presence of free 18F-fluoride ion in the urine was checked. Five hundred microliters of urine were added to hydroxyapatite (10 mg) and incubated at 37°C for 30 min. The mixture was centrifuged at 3,000 rpm for 2 min. The supernatant was removed and counted. The pellet was washed with 500 µL distilled water and centrifuged again. The water layer and the pellet were counted.
Blood Collection
Twenty-four venous blood samples were taken at designated time points up to 120 min after injection. For each blood sample and each corresponding plasma sample obtained by centrifugation (5 min at 3,000 rpm), the amount of radioactivity in 100-µL aliquots was counted in an automatic
-counter as above. The radioactivity measurements of the samples were corrected for physical decay.
68Ge-Germanium Cylinder and Determination of Calibration Factor
To obtain an accurate factor for the conversion of ECAT counts to megabecquerels of radioactivity, a 68Ge cylinder (radius, 10 cm; length, 20 cm) was imaged with the PET scanner. A volume of 6,283 mL water was mixed with 27.75 MBq 68Ge. An emission scan was acquired for 1 h in 3D mode. Cylinder emission data were reconstructed into a coronal image of the cylinder using the same method as for patient data reconstruction. A region of interest (ROI) was drawn over the entire PET image of the cylinder, and the total counts per second in the cylinder were determined. One count per second was found to be equivalent to 11.5 MBq/mL in 3D mode.
PET Data Analysis
The datasets acquired in 3D mode were corrected for scatter using a model-based correction allowing the simulation of the map of single scatter events. This method uses the map of attenuation coefficients and the image of activity concentration to compute the sinogram of single scatter events using the Klein-Nishima formula (6). Raw positron emission data were reconstructed using the ordered-subsets expectation maximization (OSEM) algorithm in the transaxial format with segmented attenuation correction (7). All reconstructions and image analyses used CAPP software, version 7/1 (CTI/Siemens). Two-dimensional or 3D views were assembled with bed position overlap (12 tomographic slices) and smoothed with a gaussian kernel of 5-mm full width at half maximum. All OSEM reconstructions were performed with 4 iterations and 8 subsets. The images were attenuation corrected using the transmission data collected over the same region of emission imaging.
Because the formalism used to perform absorbed dose calculation is based on the MIRD model (8), all source organs must be first identified from the reconstructed images. ROIs were then drawn over all organs presenting a significant uptake to construct time-activity curves. ROIs were drawn by an experienced investigator on the earliest emission image for liver, abdominal area (including upper and lower large intestine wall as well as small intestine), spleen, kidneys, vertebral bodies, and bone marrow (red); for brain and urinary bladder they were drawn on the emission image obtained 2 h after injection of 18F-fluoro-A-85380. The shapes and sizesthat is, number of pixelswere kept constant for all individual patients. To determine the biologic clearance of 18F-fluoro-A-85380, the activity was decay corrected back to the time of injection and time-activity curves were obtained.
Dosimetry
For dosimetry analysis, using the radioactive concentration (in MBq/mL) extracted from the quantitative images, the total activity contained in each source organ was assessed according to the standard-man model defined by Cristy and Eckerman (9). A new set of data, which depicts the behavior of source organ activity according time, was then generated. Data were fitted (least-square method) as follows: a monoexponential decline of radioactivity for upper large intestine and lower large intestine; a biexponential decline for liver, spleen, and kidneys; an uptake phase followed by a monoexponential decline for the brain and the red bone marrow; a monotonic increase for the bladder followed by a complete micturation at 120 min after injection. For all of these organs, the residence times (in h) were calculated by dividing the area under the time-activity curves by the injected dose. MIRDOSE3 software (10) was then used to estimate the mean absorbed dose by all organs included in the phantom due to the activity contained in the source.
Because healthy volunteers have been used in this study, the concept of effective dose must be used to express the risk encountered. Preliminary calculations demonstrated that kidneys were receiving an absorbed dose as high as the most exposed organ (the liver). Therefore, according the recommendations of International Commission on Radiological Protection (IRCP) Publication 60 (11), a weighting factor, WT, equal to 0.025 was applied to the kidneys (equal to that of the remainder of the body).
| RESULTS |
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Biodistribution and Dosimetry
A whole-body image of 1 subject showing the biodistribution of radioactivity on injection of 18F-fluoro-A-85380 at 92104 min after injection is presented in Figure 1. Ten minutes after injection, high activity was clearly seen in the kidneys, intestines, and liver, and low activity was observed in the brain as well as in the lungs and the heart (Table 1). The images obtained between 1 and 2 h after injection showed that most of the radioactivity was distributed over the kidneys, bladder, liver, and intestines, whereas the uptake in the thalamus (a nAChR-rich region) became more visible at later times. A substantial and rather constant amount (0.4 %ID/100 g tissue from the beginning to the end of the PET acquisition) of radioactivity was seen on the vertebral bodies in all subjects. The radioactivity was rapidly increasing in the urinary bladder, indicating prompt excretion through the renal system. The mean measured urinary excretion at 2 h after injection was 22% ± 8% of the administered activity. No free 18F-fluoride ion was detected in the urine. No clear evidence of biliary excretion of 18F-fluoro-A-85380 was seen on the images.
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Penetration of 18F-fluoro-A-85380 across the blood-brain barrier peaked at 25 min after injection and was followed by a slow clearance (Fig. 2). The average %ID was 0.182 %ID/100 g tissue (range, 0.160.196 %ID/100 g tissue). The thalamus showed the highest radioactivity (Fig. 3).
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| DISCUSSION |
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The biodistribution of intravenously injected 18F-fluoro-A-85380 showed that its main route of elimination is the renal system. This was expected because the tracer is highly hydrophilic (octanol buffer partition coefficient log P = -1.05; M. Bottlaender, unpublished data, 2001). No significant defluorination of the tracer could be detected with the hydroxyapatite method. The amount of 18F-fluoro-A-85380 in the liver and kidneys was initially high (1 %ID/100 g tissue), but the clearance of 18F-fluoro-A-85380 in these organs was also rapid. The amount of 18F-fluoro-A-85380 in the intestine decreased slowly during the first 80 min after injection and then increased slowly, perhaps reflecting the transit into the intestine. The uptake of radioactivity in the vertebral bodies was rather different than that observed after injection of 18F-fluoride ion (12). Therefore, it is possible that 18F-fluoro-A-85380 binds to the
4 nicotinic subunits that are present in the human osteoblasts (13).
Regarding the estimation of energy deposition, the value of the calculated effective dose is in good agreement with the value given in ICRP Publication 80 of the ICPR (14) (1.9 x 10-2 mSv/MBq for adult population), which relates to the use of 18F-FDG. This result can be explained by the fact that 18F has a major contribution in the determination of residence time because of its short physical half-life. So, even when the behavior of the active molecule is significantly different, the impact of its biologic half-life may be less contributive. From the radiation protection point of view, dosimetric estimation for 18F-fluoro-A-85380 remained well within the range of doses acceptable in clinical nuclear medicine studies. On the basis of the average effective dose of 0.0194 mSv/MBq derived from the results of this study, both patients and human volunteers could be investigated with a multiinjection protocol for the quantification of central nAchRs.
Up to 185 MBq 18F-fluoro-A-85380 gives an average effective dose of approximately 4.3 mSv. This amount of radioactivity is adequate for PET imaging and gives an effective dose comparable to that delivered during a typical 18F-FDG examination. In addition, an effective dose equivalent of 5 mSv has been reported as the average effective dose equivalent per patient from nuclear medicine procedures in Europe (15). ICRP Publication 62 (16), which is dedicated to the radiologic protection in biomedical research, defines the level of risk corresponding to a given effective dose. Regarding the dose estimation performed in the framework of this study, the risk due to the administration of 18F-fluoro-A-85380 is then defined as minor to intermediate. For information, the level of natural irradiation in Europe typically ranges between 1 and 5 mSv/y.
| CONCLUSION |
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| ACKNOWLEDGMENTS |
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| FOOTNOTES |
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For correspondence or reprints contact: Héric Valette, MD, Service Hospitalier Frédéric Joliot, Department of Medical Research, Division of Life Sciences, French Atomic Agency, 4 Place du Général Leclerc, F-91406 Orsay, France.
E-mail: valette{at}shfj.cea.fr
| REFERENCES |
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