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Clinical Investigations |
1 Division of Nuclear Medicine, Johns Hopkins School of Medicine, Baltimore, Maryland
2 Department of Environmental Health Sciences, Johns Hopkins School of Public Health, Baltimore, Maryland
3 General Electric Medical Systems, Milwaukee, Wisconsin
| ABSTRACT |
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Key Words: 18F-FDG PET CT attenuation correction PET/CT
| INTRODUCTION |
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Recently, combined PET/CT scanners have been developed, and their routine clinical use is now beginning (711). CT images obtained with such a combined scanner should be more usable for image fusion, because the CT and PET are done in close temporal sequence, ideally with no motion of the patient between sequential studies. Further, the CT data from such a combined scanner can also potentially be used for PET attenuation correction. Attenuation correction has traditionally been performed by generating transmission data from an external radionuclide source, such as 68Ge, which, through positron annihilation, generates 511-keV photons. Rapid transmission images of high statistical quality are an important potential advantage of a combined PET/CT scanner, because the CT acquisition time is much shorter than the radionuclide transmission acquisition time (35 s in our scanner for CT vs. 1835 min for transmission using 68Ge) and because the CT data are of higher spatial resolution and much lower noise (8). Although careful basic studies have been performed using CT attenuation maps (12), and the first PET/CT scanner produced satisfactory images using a CT attenuation correction algorithm, there have been only a few preliminary reports about differences between PET images corrected using CT versus 68Ge attenuation maps (1315). Differences might be expected because the energy of the x-rays from CT is not monoenergetic and is much lower than that of an external positron-emitting radionuclide source, necessitating use of a transforming formula to convert CT attenuation values to those appropriate for 511-keV photons. If such a conversion is not accurate, the quantitative analysis that has been one of the advantages of PET may be compromised. Accordingly, the objective of this study was to evaluate the quantitative differences between emission PET images reconstructed with CT-based and germanium-based attenuation correction.
| MATERIALS AND METHODS |
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Data Acquisition
18F-FDG was synthesized by the method of Hamacher et al. (16). For whole-body imaging, PET was performed using a commercial combined PET/CT scanner (Discovery LS; General Electric Medical Systems, Waukesha, WI). The system permitted the simultaneous acquisition of 35 transaxial PET emission images per field of view with an interslice spacing of 4.25 mm. Axial and transaxial resolution using a ramp filter was approximately 4.5 mm in full width at half maximum. The field of view was 50 cm, and the pixel size of the reconstructed images for registration was 3.906 mm; that is, a 128 x 128 matrix size was used. This PET/CT scanner has an integrated 4-slice multidetector helical CT scanner. Technical parameters used for CT imaging were as follows: a detector row configuration of 4 x 5 mm, a pitch of 6:1 (high-speed mode), a gantry rotation speed of 0.8 s, a table speed of 30 mm per gantry rotation, 140 kVp, and 80 mA. After at least a 4-h fast, patients received an intravenous injection of approximately 555 MBq (15 mCi) 18F-FDG. Approximately 60 min later, CT scanning was performed from the meatus of the ear to the mid thigh for 35 s without breath-holding, and a whole-body emission scan for the same axial coverage was obtained, with 5 min per bed position. Finally, a radionuclide transmission scan was obtained using 2 rotating 68Ge rod sources, with 3 min per bed position.
Image Reconstruction
The CT images were created in a matrix size of 512 x 512 but were reduced to a 128 x 128 matrix to correspond to the PET emission images. The resulting CT pixel values in Hounsfield units were transformed into linear attenuation coefficients in cm-1 at 511 keV by a bilinear function "hinged" at the CT value of water (Fig. 1). These attenuation images were forward-projected according to the PET scanner geometry, and the calculated line integrals were put in exponential form to obtain the attenuation correction factors. The resulting sinograms were smoothed with an 8-mm gaussian filter to adjust the correction data to the PET resolution. These attenuation correction factors were then applied to the emission data, and the attenuation-corrected emission images were reconstructed with an ordered-subset expectation maximization (OSEM) iterative reconstruction algorithm (2 iterations, 28 subsets). For the conventional 68Ge correction, segmented attenuation correction (SAC) was used. The reconstructed 68Ge transmission map was automatically segmented into tissue classes of differing average attenuation, and the average attenuation coefficient within each class was substituted for the raw pixel-by-pixel values. Thus, 2 different PET datasets were produced, one representing attenuation correction based on the transmission data from CT, the other based on the transmission data from 68Ge.
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Image Analysis
Identical ROIs were placed over the same locations in the 2 PET images (Fig. 2), and the mean and maximum values (in Bq/mL) were obtained. We also evaluated the corresponding CT value (in Hounsfield units) by placing the same ROIs on the CT images. The exact corresponding location was obtained using the commercial fusion software on the scanners workstation (eNTEGRA; Elgems, Haifa, Israel).
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Statistical Analysis
The differences in individual ROI values between the 2 images were compared using the paired t test. To assess the intrasubject variability of all values, the percentage difference (%Diff) across organs or suspected tumors was calculated using the following formula:
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| RESULTS |
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Table 1 compares the ROI values for the same areas in normal organs between CT-corrected and germanium-corrected images in varying tissues. In evaluating mean and maximum values, the values in CT-corrected images were significantly higher than in germanium-corrected images in all tissues except lung (P < 0.01). Table 2 compares the quantitative values of tumor uptake and tumor-to-background ratios. Tumor ROI values were significantly higher in CT-corrected images than in germanium-corrected images (P < 0.01). Of note, there was a significant difference in the discrepancy between CT-corrected and germanium-corrected values when the lesion was osseous versus nonosseous, for both mean values (11.0% vs. 2.3%, P < 0.05) and maximum values (11.1% vs. 2.1%, P < 0.01).
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| DISCUSSION |
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To investigate potential discrepancies caused by the difference of energy between the CT and 68Ge source attenuation images, we assessed quantitative tracer uptake values in normal organs and tumors in emission PET images that have been corrected for attenuation through CT or 68Ge sources. Our data indicate that CT-corrected images produced modestly but significantly higher uptake values than did germanium-corrected images, both in tumors and in normal organs (except the lung). In addition, we observed a marked discrepancy between CT-based and germanium-based lesion uptake values depending on whether the lesion was located in bone.
The water-containing phantom study showed only a borderline difference of 1.6% between the CT-based and germanium-based radioactivity concentration values, whereas considerably larger differences were observed in many organs and tumors. This finding means that the observed differences in patient datasets were highly unlikely to have been caused by errors in the conversion of CT numbers to 511-keV attenuation coefficients for tissues similar to water. However, the considerable difference in discrepancy depending on whether a lesion was located in bone may explain the differences between CT-based and germanium-based ROI values. At the lower CT energies, the 2 primary processes by which photons interact with tissues are the photoelectric effect, which depends on effective atomic number raised to the fourth power, and Compton scattering, which depends on electron density. In contrast, at 511 keV, the primary photon interaction mechanism is Compton scattering. The effective atomic number of bone is significantly higher than that of other tissues. Electron density is quite similar across tissues, including bone. Thus, scaling nonbone CT values to 511-keV attenuation coefficients is, in theory, more straightforward than scaling bony values. Attenuation maps from CT to be used for PET attenuation correction would be expected to be more accurate in nonbone regions than in bone. We thus believe that the differences between CT-based and germanium-based ROI values, and the discrepancies between bony and nonbony lesions, are mainly caused by errors in the conversion of bone CT values to 511-keV attenuation values.
Other factors are likely contributing to our observations as well. Among the normal organs, we did not see significant differences between CT-based and germanium-based values in the lung. In the lung, 18F-FDG uptake is usually low. Small absolute differences in 18F-FDG uptake can thus contribute to larger relative differences. In contrast, in the hepatic S8 segment, %Diff was considerable. Respiratory movement influences this area because it is just below the diaphragm. The upper part of the liver is scanned by CT for a few seconds, whereas 68Ge required 3 min in this study. These scan time differences and respiratory motion may contribute to differences between the 2 corrections in regions near the diaphragm.
In the current study, images were acquired with the arms at the patients side. Arms-down imaging attenuates photon flux from the patient but likely reduces arm-motion artifacts. Because of the range of attenuation coefficients at CT energies among tissues, arms-down scanning is more likely to influence the apparent radioactivity values in the chest, abdomen, and pelvis. This influence may partly explain the wide range of %Diff values in normal thoracic and abdominal organs (Fig. 3), compared with the temporal lobe and cerebellum, although respiratory or bowel movement in the abdomen and pelvis can also have an effect.
A weak positive correlation was found between CT Hounsfield units and %Diff. This finding is consistent with the larger difference found for bone lesions than nonbone lesions and is consistent with our hypothesis that errors exist in the conversion of high CT values to 511-keV attenuation coefficients. In contrast, a significant correlation was not observed between %Diff and tumor size or the average measured activity of the 2 images, although the number of lesions that could be evaluated on CT was limited for assessing the relationship between tumor size and %Diff.
In the current investigation, CT-corrected images were produced with measured attenuation correction (MAC) using a CT transmission scan, whereas germanium-corrected images were produced with SAC, with substitution of the average attenuation coefficient within each segment or tissue compartment. Visvikis et al. (19) showed an 8.7% underestimation of average standardized uptake value in filtered backprojection SAC reconstruction, compared with filtered backprojection MAC, when transmission and emission acquisition times were 3 min and 5 min, respectivelyscanning times identical to ours. Therefore, differences between MAC and SAC per se might have contributed to the difference in our observations between CT-corrected (with MAC) and germanium-corrected (with SAC) standardized uptake values. Also, Visvikis et al. reported that OSEM, compared with filtered backprojection reconstruction, possibly underestimates standardized uptake values. Therefore, if we wish to more directly address error, we may want to use filtered backprojection-based germanium-corrected images as a standard. However, in clinical practice, whole-body PET images are now widely reconstructed by OSEM SAC, and this is our routine as well. Because we wanted to compare CT-based attenuation correction with our preexisting routine approach, we believed it most appropriate to directly compare CT-MAC and germanium-SAC images reconstructed by OSEM.
| CONCLUSION |
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| FOOTNOTES |
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For correspondence or reprints contact: Richard L. Wahl, MD, Division of Nuclear Medicine, 601 N. Caroline St., Room 3223A, Baltimore, MD 21287-0817.
E-mail: rwahl{at}jhmi.edu
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