Abstract
Immuno-PET as a quantitative imaging procedure before or concomitant with radioimmunotherapy is an attractive option to improve confirmation of tumor targeting and especially assessment of radiation dose delivery to both tumor and normal tissues. General information about PET, PET systems, and quantification is provided in this review. The requirements for an appropriate positron emitter and characteristics of the most attractive candidate emitters for immuno-PET are discussed. An overview of preclinical and clinical immuno-PET studies reported in the literature is provided.
Cancer treatment with radioimmunotherapy (RIT), consisting of radionuclides coupled to monoclonal antibodies (mAbs), has been the focus of research for more than 2 decades. The concept that mAbs could maximize the targeting of radiation to tumors while minimizing dose delivery to normal tissues has proven its worth only in recent years. Currently, 2 RIT procedures, 90Y-ibritumomab tiuxetan (Zevalin; IDEC Pharmaceuticals) and 131I-tositumomab (Bexxar; Corixa Corp.) have received approval by the U.S. Food and Drug Administration, and several radioimmunoconjugates are entering advanced-stage clinical trials. Although RIT appears to be successful in treatment of hematologic cancer types, treatment of solid tumors remains a challenge.
Important issues complicating successful application of RIT are the small therapeutic window (with bone marrow being the dose-limiting organ) and interpatient variations in pharmacokinetics and tumor uptake of the radioimmunoconjugate. Most radioimmunoconjugates currently in use are administered with some level of dose adjustment based on the patient’s body weight or body surface area. These dosing schemes, although easy to implement, do not address the often substantial physiologic variability in mAb pharmacokinetics and target antigen accessibility among patients.
Performing radioimmunoscintigraphy (RIS) with trace-labeled mAbs before RIT enables the confirmation of tumor targeting and estimation of radiation dose delivery to both tumor and normal tissues. This approach can be used for in vivo characterization of new RIT candidate mAbs, as well as for the selection of RIT candidate patients, as is routine in both the Zevalin and Bexxar treatment regimens. In the Zevalin treatment regimen, a tracer amount of 111In-ibritumomab tiuxetan is administered 7 to 9 d before therapy with 90Y-ibritumomab tiuxetan, to rule out patients with unfavorable biodistribution. Dosimetry results from this diagnostic procedure have not been shown to correlate with toxicity (1). The Bexxar treatment schedule consists of a dosimetric dose of 131I-tositumomab followed by a therapeutic dose of the same conjugate within 7 to 14 d. Patient-specific doses are administered on the basis of the calculated total-body residence time of dosimetric 131I-tositumomab (2).
Detection of the γ-ray-emitting radionuclides 111In and 131I involves planar imaging with a γ-camera or SPECT. These procedures, however, have intrinsic limitations with respect to quantification, primarily because of insufficient correction for scatter and partial absorption of γ-photons in tissue. Because of more accurate scatter and attenuation corrections, PET is better qualified for tracer quantification. In addition, PET provides better spatial and temporal resolution and sensitivity than SPECT.
IMMUNO-PET: IMAGING AND QUANTIFICATION
Immuno-PET is based on annihilation coincidence detection after labeling of a mAb or mAb fragment with a positron-emitting radionuclide. The emitted positron (a positively charged β-particle) will travel a distance of a few millimeters, depending on the initial positron energy and the density of the surroundings. After having lost its kinetic energy, combining with an electron leads to the so-called annihilation process, yielding 2 photons each with an energy of 511 keV emitted simultaneously in opposite directions (Fig. 1). After administration of a PET conjugate to a patient, the distribution of the compound is monitored by detection of the annihilation photon pairs with a PET camera. A PET camera consists of a ring of detectors placed around the body of the patient. If 2 photons are registered by detectors on opposite sides of the body within a very short time, it is assumed that somewhere along the line between the 2 detectors an annihilation event has taken place. By calculating the crossing of all the lines of response (LORs), the location of the radiation source can be determined.
For dosimetry purposes, immuno-PET must provide reliable quantitative information. All photon pairs with energies that fall within the PET acquisition energy window (typically 350–650 keV) and that are detected in coincidence within a certain time period (coincidence time window, approximately 5–15 ns) are called coincidences. In addition to true coincidences, the gross coincidence rate can include scatter coincidences, random coincidences, and spurious true coincidences (Fig. 2). Spurious true coincidences can occur when an annihilation photon is registered together with an emitted single γ-photon from the same decay event (prompt γ-photon) and with an energy that falls within the PET acquisition energy window. In contrast to scatter and random coincidences, the occurrence of spurious true coincidences depends on the positron emitter used. For all 3, however, the LOR is not representative of the annihilation location and degrades the image quality. In addition, some portion of the annihilation photons will not be detected as a result of attenuation and dead time. Attenuation is the loss of true coincidences through Compton processes and absorption within tissue, causing 1 or both of the annihilation photons to fall outside the PET acquisition energy window or coincidence time window. The probability of a true coincidence detection is the product of the probabilities of each of the 2 annihilation photons escaping the body without interaction. For this reason, the amount of attenuation along a specific LOR is the same, independent of the location of the event on the LOR. This holds true even if the event took place outside the body. This fact is used in attenuation correction and requires an additional transmission scan in which the body is scanned with a rotating external radioactive point or line source. Dead time losses result from the system’s inability to process an infinite number of photons at the same time. Dead time losses can be minimized by using a system with many independent detectors, fast scintillators, and fast processing electronics. To arrive at a quantitative image, the raw PET data must be corrected for the aforementioned disturbing effects.
After correction of raw PET data, the only factor influencing quantitative PET analysis of radioactivity is resolution related. Because of limited spatial resolution, the spread of locoregional radioactivity to surrounding areas must be considered. With small objects, the true radioactivity concentration of a hot object in cold surroundings will be underestimated in the PET image, whereas that of a cold object in hot surroundings will be overestimated (Fig. 3). The loss of radioactivity from the object into the surroundings and the contribution of near-surrounding spillover radioactivity into the object are called partial-volume effects. These partial-volume effects can be corrected for when the correction factors are known from test measurements and if the true volume of the object is known by anatomic imaging (3,4). Quantitative imaging in immuno-PET is challenging because of the relatively low object (e.g., tumor)-to-background radioactivity uptake ratios.
DEVELOPMENT IN CLINICAL PET IMAGING SYSTEMS
In 1975, the first PET scanner with thallium-doped sodium iodide (NaI[Tl]) detectors that could form true tomographic images was developed by Phelps et al. (5). Since then, the PET scanner has undergone several developments with respect to scintillation crystals and system design.
Over the years, the hexagonal and octagonal designs of the first PET systems were followed by circular designs. Today, most PET scanners contain bismuth germanate as scintillation material because of its greater efficiency for detecting 511-keV photons (6). In recent years, 2 promising new scintillation crystals, cerium-doped gadolinium oxyorthosilicate and cerium-doped lutetium oxyorthosilicate, have been applied in PET scanners, and several other detector materials are under investigation. It is expected that advances in this area will further improve PET sensitivity and resolution (7).
To facilitate accurate interpretation of PET images and dosimetry, it has been proposed that PET be combined with anatomic imaging by CT or MR imaging to provide simultaneous registration of both biologic function and anatomy. In only a few years, hybrid PET/CT scanners were developed and marketed commercially and now account for more than 65% of all PET sales. An extensive description of the current state of PET/CT has been published (8). Although combining PET with MR imaging is technologically more challenging because of the strong magnetic fields restricting the use of certain electronic components, the first MR imaging-compatible PET scanner has been developed. The availability of anatomic data not only provides landmarks for PET image interpretation but also can be used for attenuation correction, reduction of image noise, and partial volume correction.
POSITRON EMITTERS FOR IMMUNO-PET
For a positron emitter to be appropriate for immuno-PET, several aspects must be considered. The applicability of a positron emitter is dependent on the availability of methods to obtain it in pure and sufficient amounts, the time period available for transportation and labeling, the availability of procedures for its stable coupling to the mAb with maintenance of the antibody’s in vivo biodistribution characteristics, and identification of undesirable components in its decay scheme that could compromise image quality and quantification accuracy. The predominant factor for determining a positron emitter’s suitability for immuno-PET is its physical half-life. This must be compatible with the time needed for a mAb or mAb fragment to achieve optimal tumor-to-nontumor ratios (typically 2–4 d for intact mAbs and 2–6 h for mAb fragments). Thus far, radiolabeled intact mAbs have been used in tumor detection and treatment planning, as well as in RIT, whereas the application of mAb fragments has been restricted for the most part to tumor detection. Although the use of shorter-lived positron emitters (with half-lives of hours) for immuno-PET with mAb fragments is an option, the kinetics of intact mAbs demand the use of long-lived positron emitters (half-lives of days) to allow imaging at later time points for obtaining maximum information.
Given these considerations, the application of positron emitters with half-lives of minutes, such as the bioradionuclides 15O, 13N, and 11C, is out of the question. The positron emitters that have been evaluated in preclinical and clinical immuno-PET studies are listed in Table 1. On the basis of their half-lives, most of these radionuclides are better suited for use in combination with mAb fragments (in particular 94mTc, 68Ga and 18F, and, to a lesser extent, 64Cu, 86Y, and 76Br). The 2 positron emitters that are suitable for imaging of mAb fragments as well as intact mAbs are 124I and 89Zr. The half-lives of these radionuclides offer an advantage with respect to the logistics of radiolabeling and transportation but a potential disadvantage with respect to the radiation burden to the patient, especially when coupled to compounds with long biologic half-lives, such as intact mAbs. This disadvantage might be overcome by the introduction of the latest generation of high-resolution PET scanners with higher sensitivity, allowing lower doses of injected radioactivity for comparable images.
Other aspects of a positron emitter to be considered are the presence of prompt single γ-photons causing spurious true coincidences (86Y, 76Br, and 124I), high β+-energy resulting in an intrinsic resolution loss (94mTc, 68Ga, 76Br, and 124I), and the presence of radionuclidic impurities or radioisotopes of the same element generated during cyclotron production (94mTc and 64Cu). Except for the production of 76Br and 89Zr, all positron emitters listed in Table 1 require enrichment of the target material, a process that is expensive while 100% enrichment is never reached. The positron emitters 68Ga, 18F, 64Cu, 86Y, and 89Zr need indirect labeling methods with bifunctional chelates, but 94mTc, 76Br, and 124I can also be coupled directly to mAbs.
EXPERIENCES WITH IMMUNO-PET
Although several positron emitters have been suggested for mAb labeling, immuno-PET research is still in its infancy. Most immuno-PET studies have focused on animal models, and clinical evaluations are rare. This is mainly the result of the limited availability of suitable positron emitters, a lack of robust labeling methods, and, until recently, the relatively small number of PET cameras in operation. An application that shows considerable potential is the use of quantitative PET in combination with RIT. For this purpose, the radioimmunoconjugates used for immuno-PET and RIT should demonstrate a similar biodistribution, and, therefore, radionuclides (and, if required, chelates) with comparable chemical properties must be chosen.
Because PET is believed to be superior to SPECT with respect to quantification, several PET radioisotopes have been suggested as substitutes for γ-emitting radionuclides used in RIS. At least in theory, this could enable easy conversion from a SPECT to a PET procedure. Examples of PET/SPECT radioisotope pairs are 94mTc/99mTc, 67Ga/68Ga, and 124I/123I, and examples of PET/RIT radioisotope pairs are 64Cu/67Cu, 86Y/90Y, and 124I/131I. However, PET/RIT surrogate pairs also can be considered, such as 94mTc/186Re, 94mTc/188Re, 124I/186Re, 124I/188Re, 76Br/131I, and 89Zr/90Y.
At the present time, 18F-FDG is by far the most widely available and most widely applied clinical PET tracer. The application of 18F in immuno-PET, however, is limited to mAb fragments because of the tracer’s short half-life (1.83 h). Although several conjugates have been evaluated in biodistribution studies in xenograft-bearing mice, no quantitative preclinical or clinical PET studies have been performed (23,24).
Other short-lived positron emitters are 94mTc and 68Ga. The imaging agent carcinoembryonic antigen (CEA)-scan, supplied as an instant kit containing lyophilized NP-4 F(ab′) for labeling with 99mTc, has been used for coupling to 94mTc instead (25). Although 94mTc and 99mTc are isotopes of the same element, labeling results were different because NP-4 F(ab′) contained much more reoxidized NP-4 F(ab′)2 as a result of 94mTc labeling. No in vivo evaluation of these conjugates was performed. 68Ga coupled to small mAb fragments or for use in so-called pretargeting strategies has been investigated. Pretargeted PET with 68Ga has been evaluated in mice bearing CD44v6- and MUC1-expressing tumors and in patients with breast cancer (26,27). In the latter study, patients received anti-MUC1/anti-Ga-chelate bispecific antibody (Bs-mAb), followed 18 h later by a blocker to remove residual circulating Bs-mAb from the blood and another 15 min later by the chelate labeled with 230–300 MBq 68Ga. PET was started 60–90 min after injection of the 68Ga-chelate. In 10 patients, 14 of 17 known breast lesions, ranging from 10 to 80 mm in size, were clearly visualized with PET as foci with increased activity. No false-positive readings were obtained. Detection of axillary lymph node metastases was hampered by a high activity in blood vessels near the lymph nodes. It was concluded that PET offered better sensitivity for the detection of breast cancer at low tumor contrast than conventional RIS.
Smith-Jones et al. (28) have demonstrated the potential of 68Ga-immuno-PET for quantitative imaging of HER2 expression modulation. Tumor-bearing mice were treated with 17-allylaminogeldanamycin, a heat shock protein 90 inhibitor that causes degradation of the HER2 receptor. A 68Ga-labeled F(ab′)2 fragment of the anti-HER2 antibody herceptin was used for PET of HER2 expression. A linear correlation (R2 = 0.97) was found between tracer uptake quantified by direct assessment of resected tumors by γ-counter and tracer uptake estimated by PET.
Positron emitters suggested for immuno-PET with half-lives of several hours (but less than 1 d) are 64Cu, 86Y, and 76Br. 64Cu has been coupled to the intact anticolorectal murine mAb 1A3 for immuno-PET in patients with suspected advanced primary or metastatic colorectal cancer (29). After injection of the conjugate (5–20 mg mAb; 370 MBq), PET was performed once or twice (at 4 h or at 4 and 36 h). All 36 patients entered in this study underwent CT or MR imaging, and 18 patients were also studied with 18F-FDG PET. In 29 patients, 1 or more tumor sites (40 of 56 total) were identified on immuno-PET, absence of tumor was confirmed in 5 patients, and tumor status was not confirmed in 2 patients. All 17 primary and recurrent sites were clearly visualized, but only 23 of 39 metastatic sites (59%) were detected. The sensitivity of immuno-PET was best in abdomen and pelvis. In these regions 11 occult small tumor lesions were detected, including 9 small foci <2 cm in diameter that were not detected by CT or MR imaging. For detection of abdominal-pelvic tumors, immuno-PET exhibited better sensitivity than CT or MR imaging, and appeared as sensitive as 18F-FDG PET. In contrast, detection of metastatic disease of liver and lung was difficult because of high blood-pool activity at the early imaging time points, which were chosen because of the half-life of 64Cu (12.7 h). Detection of liver metastases was also hampered by nontarget background activity, caused by 64Cu residualizing in the liver after catabolism of the conjugate.
In another study, the genetically engineered anti-CEA T84.66/GS18 minibody was labeled with 64Cu via the 1,4,7,10-tetraazacyclododecane-N,N′,N″,N‴-tetraacetic acid (DOTA) chelate, and PET of colorectal carcinoma xenograft-bearing nude mice was performed (30). Tumors of 25-395 mg were visualized within a few hours after injection of the tracer. With these 64Cu-conjugates high retention of activity in the liver was also observed, resulting in tumor-to-liver uptake ratios <1. Such retention would restrict the detection of hepatic lesions. 64Cu has also been used in a pretargeting strategy, consisting of the antiepithelial cell adhesion molecule mAb NR-LU-10 conjugated with streptavidin and a 64Cu-DOTA-biotin ligand (31). In mice bearing colorectal carcinoma xenografts, a maximum tumor uptake was reached with this strategy at 1 h after injection. The tumor-to-blood ratio of areas under the curve was 14 times higher for pretargeted 64Cu-DOTA-biotin than for conventionally labeled 64Cu-DOTA-NR-LU-10. Although no PET was performed in this study, superior PET contrast might be expected when using the pretargeting strategy. Also in this study, increased uptake of 64Cu in the liver was observed, but uptake levels were much lower than in tumor.
The positron emitter 86Y has been coupled to the anti-Lewis Y humanized mAb (hMAb) hu3S193 and the anti-HER2 hMAb herceptin, and their biodistributions were compared with those of their respective 111In-labeled mAbs (15,32). The rational for this comparison was that PET with 86Y-mAb might be better qualified for predicting 90Y-mAb localization and dose delivery in RIT studies than 111In-mAb SPECT. Although biodistribution data from both studies indicated that this might be the case, accurate quantitation of 86Y with PET still remains a challenge because of the prompt single γ-photons emitted by this positron emitter (32). 76Br has been coupled to the anti-CEA mAb 38S1 by Lövqvist et al. (33), and biodistribution studies and PET were performed in colon carcinoma xenograft-bearing nude rats. The authors hypothesized that 76Br might be an interesting alternative to 124I as a PET radionuclide substitute for the iodine radioisotopes used in RIS and RIT. To this end, 76Br-38S1 and 125I-38S1 were prepared by direct labeling, and their biodistribution compared in nude rats carrying human colon xenografts. Although all tumors could be identified readily by PET, the concentrations of 76Br radioactivity in tumor, blood, and normal tissues were higher than corresponding 125I concentrations at all time points. This was mainly the result of catabolism of radiolabeled mAb, resulting in free radiohalides, of which 76Br− was retained in the blood pool in contrast to the rapidly excreted 125I− ion. These data suggest that 76Br cannot be used as a PET radionuclide substitute for iodine radioisotopes.
124I and 89Zr are long-lived positron emitters. In the 1990s, several studies were performed with 124I-labeled mAbs in animals and patients. Snook et al. (34) evaluated the biodistribution of 124I-labeled H17E2 in HEp2 xenograft-bearing nude mice, without comparison with 131I-labeled H17E2 and without performing PET. Similar studies were performed with 124I-labeled rat mAb ICR12 for the targeting of human breast carcinoma xenografts overexpressing the c-erb B2 proto-oncogene product (35). PET was performed (but without quantitative analyses), and tumor xenografts of 6-mm diameter were successfully delineated with high resolution at 24, 48, and 120 h after injection. Clinical immuno-PET studies with 124I-labeled mAbs have been performed in only a small numbers of patients (36,37). Wilson et al. (37) used PET with 124I-labeled mMAb HMFG1 for tumor detection in 7 breast cancer patients and for quantitative measurement of conjugate uptake in tumors. In only 2 of 7 patients the tumor uptake of the specific antibody was higher than that seen with the nonspecific antibody, and therefore mMAb HMFG1 was not further studied in immuno-PET. After almost a decade, interest in 124I-labeled mAbs has been renewed. The complementarity-determining region grafted hMAb A33 was labeled with 124I, and colon xenograft-bearing mice were imaged (38). Biodistribution studies revealed excellent tumor uptake of 50.0 ± 0.7 %ID/g, with maximum uptake at 4 d after injection. PET detected antigen-positive tumors (range, 0.2–0.7 g) by 4 h after injection, and high-resolution images were obtained by 24 h after injection. In these studies, PET was not exploited for quantitative measurements. The potential of 124I-labeled genetically engineered antibody fragments for tumor detection was confirmed by Sunderesan et al. (39), who demonstrated high resolution images and specific localization (compared with 18F-FDG) with anti-CEA T84.66 minibody and diabody in nude mice bearing colon carcinoma xenografts. The potential of 124I-labeled mAbs for pretherapy PET was demonstrated by Verel et al. (40). To this end, the scouting performance of 124I-labeled chimeric mAb (cMAb) U36 was evaluated in a biodistribution experiment on coinjection with 131I-labeled cmAb U36, and by PET in nude mice bearing head and neck cancer xenografts. 124I- and 131I-labeled cmAb U36 produced fully concordant tissue uptake values, whereas selective tumor uptake was confirmed with immuno-PET with visualization of all 15 tumors.
Recently, the positron emitter 89Zr has been coupled to cmAb U36 via the bifunctional derivative of the chelate desferrioxamine B, and the in vivo behavior of the conjugate was evaluated by biodistribution and PET studies in nude mice bearing head and neck cancer xenografts (18). These studies demonstrated selective tumor targeting of 89Zr-labeled cmAb U36 and visualization of small tumors in the range of 19–154 mg on PET images (Fig. 4). To examine the applicability of 89Zr-labeled mAb as a scouting procedure for 90Y-mAb RIT, cmAb U36 was labeled with 89Zr and 88Y (as substitute for 90Y) (4). The radioimmunoconjugates were coinjected in xenograft-bearing nude mice, and biodistribution was determined at 3, 24, 48, 72, and 144 h after injection. The radioimmunoconjugates showed similar uptake in tumor, blood, and other organs, except for sternum and thigh bone at later time points. Small differences were found in kidney and liver. Quantitative imaging performance of 89Zr approximated that of 18F, whereas, after correction for partial-volume effects, a good correlation was found between image-derived 89Zr tumor radioactivity and γ-counter 89Zr radioactivity values of excised tumors (R2 = 0.79). These data are in line with the previously discussed data of Smith-Jones et al. (28) and confirm the accuracy of PET for noninvasive estimation of mAb tissue accumulation. Because of the encouraging results obtained with 89Zr immuno-PET, 89Zr-labeled cmAb U36 is currently being evaluated for its capacity to detect primary tumors and metastases in patients with operable head and neck small-cell cancer. Preliminary data showed that tumor deposits can be visualized clearly after administration of 74 MBq 89Zr (Fig. 5). A smooth interpretation of images, however, is hampered by high activity in blood vessels resulting from the long residence time of intact mAbs. To deal with this problem, combining immuno-PET with anatomic imaging seems an interesting future approach.
CONCLUSION
Immuno-PET combines the high resolution and quantitative aspects of PET with the high specificity and selectivity of mAbs. This makes immuno-PET an attractive imaging modality for tumor detection. Moreover, immuno-PET has the potential to supersede γ-camera imaging in combination with RIT, because it enables the sensitive confirmation of tumor targeting and a more reliable estimation of radiation dose delivery to both tumor and normal tissues. Improved assessment of mAb biodistribution permits the optimization of RIT (and other antibody-based therapies), as well as the individualization of RIT with respect to dose planning and selection of patients with the best chance to benefit from RIT.
Acknowledgments
This study was supported by grants from the European Union FP6, LSHC-CT-2003–5032, STROMA. The publication reflects only the authors view. The European Commission is not liable for any use that may be made of the information contained.
Footnotes
Received Apr. 6, 2004; revision accepted Oct. 21, 2004.
For correspondence or reprints contact: Guus A. van Dongen, MS, PhD, Department of Otolaryngology/Head and Neck Surgery, VU University Medical Center, De Boelelaan 1117, P.O. Box 7057, 1007 MB Amsterdam, The Netherlands.
E-mail: gams.vandongen{at}vumc.nl