Research Article | Open Access
Alejandro Amor-Coarasa, Andrew Milera, Denny Carvajal, Seza Gulec, Anthony J. McGoron, "Lyophilized Kit for the Preparation of the PET Perfusion Agent [68Ga]-MAA", International Journal of Molecular Imaging, vol. 2014, Article ID 269365, 7 pages, 2014. https://doi.org/10.1155/2014/269365
Lyophilized Kit for the Preparation of the PET Perfusion Agent [68Ga]-MAA
Rapid developments in the field of medical imaging have opened new avenues for the use of positron emitting labeled microparticles. The radioisotope used in our research was 68Ga, which is easy to obtain from a generator and has good nuclear properties for PET imaging. Methods. Commercially available macroaggregated albumin (MAA) microparticles were suspended in sterile saline, centrifuged to remove the free albumin and stannous chloride, relyophilized, and stored for later labeling with 68Ga. Labeling was performed at different temperatures and times. 68Ga purification settings were also tested and optimized. Labeling yield and purity of relyophilized MAA microparticles were compared with those that were not relyophilized. Results. MAA particles kept their original size distribution after relyophilization. Labeling yield was 98% at 75°C when a 68Ga purification system was used, compared to 80% with unpurified 68Ga. Radiochemical purity was over 97% up to 4 hours after the labeling. The relyophilized MAA and labeling method eliminate the need for centrifugation purification of the final product and simplify the labeling process. Animal experiments demonstrated the high in vivo stability of the obtained PET agent with more than 95% of the activity remaining in the lungs after 4 hours.
Starting in 1964, several efforts have been made to find an agent for perfusion and embolization [1, 2]. A lyophilized kit for the preparation of 99mTc-MAA was created in 1974 for Single Photon Emission Tomography (SPECT) imaging. With the arrival of Positron Emission Tomography (PET) the formulation of an analogue drug with a positron emitter was needed. Among the available PET isotopes 68Ga is easily obtained from its parent nuclide 68Ge by chromatographic column separation with different inorganic exchangers. The long lived parent allows the construction of a generator that can last up to two years  compared to a 99mTc/99Mo generator which lasts only for 1-2 weeks. MAA was first successfully labeled with 68Ga in 1989  but never used, probably due to unreliability of the existing 68Ge/68Ga generators and low availability of PET imaging cameras. Revived interest has been shown recently [5, 6], and the first PET lung perfusion studies in humans have been performed [7, 8].
Selective internal radiation treatment (SIRT), a technique used to treat metastatic liver cancer, could also benefit from a PET perfusion tracer. During the planning stage, a 99mTc-MAA perfusion scan is performed to assess the allocation in lung and gastrointestinal tract. It is also used to calculate tumor to normal liver allocation ratio . The distribution acts as a predictor of the treatment safety and effectiveness. A PET perfusion agent (e.g., 68Ga-MAA) could provide valuable, quantifiable information to calculate precise doses, which could potentially improve the treatment outcome. Initial work with 68Ga-MAA for SIRT planning has already been performed .
All reported 68Ga labeling of MAA has been done using a commercial MAA kit for 99mTc (mainly Pulmolite kit, no longer on the market). All kits contain approximately 100 μg stannous chloride and free albumin; hence the particles need to be washed with saline before 68Ga labeling. The maximum reported labeling yield using the Pulmolite kit is around 80% . Elimination of the free 68Ga via centrifugation is therefore necessary. The purification process is also required to eliminate traces of the long half-life 68Ge that are eluted from the generator (required only if 68Ge ≥ 0.001% of the 68Ge/68Ga generator activity or 0.5 μCi for a 50 mCi generator). A new 68Ga specific MAA lyophilized kit is needed for labeling. Further, it needs to be combined with a prepurification system that assures prior elimination of 68Ge traces and provides pure, preconcentrated 68Ga for labeling.
2. Materials and Methods
2.1. MAA Lyophilized Kit Preparation
Macroaggregated albumin (MAA) was obtained from Triad Isotopes (DraxImage kit). The content was reconstituted with 0.9% saline solution, separated into two 15 mL centrifuge tubes (to match the original 4 · 106 number of particles present in the Pulmolite kit for comparison purposes), centrifuged (Eppendorf, Germany), and the supernatant discarded (“washed MAA”) . The particles were then relyophilized overnight and stored for labeling (“relyophilized MAA”). Size and morphology analysis was performed on reconstituted MAA using an optical microscope (Micromaster, Fisher-Sci, USA) and a hemacytometer (Reichert, USA) before and after relyophilization.
2.2. 68Ge/68Ga Radioisotopic Generator
The 68Ge/68Ga generator used was the 50 mCi IGG-100 (Eckert & Ziegler, Germany), based on the TiO2 resin technology, eluted with 5 mL of 0.1 M ultrapure HCl (Sigma-Aldrich, USA) solution.
2.3. Purification System
A combination of chromatographic exchange resins was used . Two Luer-fitting column beds were prepared. First, mg of AG-50Wx8 cation exchange (Eichrom, USA) column is connected to a three-way stopcock. Next, mg of UTEVA anion exchange (Eichrom, USA) resin in a column is positioned. Finally, another three-way stopcock is located at the end. The system was designed to be used in four simple steps: elution (from the generator, 5 mL of 0.1 M HCl); cleaning (1 mL of 0.1 M HCl); purification (1 mL of 5 M HCl); extraction (1 mL of Millipore Water) (Figure 2).
2.4. MAA Labeling
Both, washed MAA and relyophilized MAA, were labeled (using the original Green’s method [4, 5]) with either purified or unpurified 68Ga solution. The unpurified 68Ga solution was obtained directly from the generator (5 mL, pH = 1, A ≈ 10 mCi). The purified 68Ga elution (1 mL, pH = 0.6, A ≈ 10 mCi) was obtained from the purification system. Both were buffered using 0.3 mL of 3 N ultrapure sodium acetate (Sigma-Aldrich, USA). The solution was added to the 15 mL centrifuge tube containing the MAA. Labeling was performed using a thermomixer with a heating block for 15 mL centrifuge tubes and stirring at 750 rpm (Eppendorf, Germany). Labeling temperature was 25 (room temperature), 50, 75, and 95 degrees Celsius. Labeling time was set at 15 minutes based on previous reports of MAA-68Ga labeling kinetics [4, 5]. Particles were separated from the supernatant by centrifugation. The particles and supernatant were measured separately using an Atomlab 100 dose calibrator (Biodex, USA). Final particles were resuspended in 5 mL saline solution with a vortex mixer (Fisher-Sci, USA).
2.5. Animal Experiments
Sprague Dawley rats (200–225 grams, 2 per time point) were obtained from Harlan Laboratories (Harlan, USA). Animals were weighed before the procedure and anesthetized using an Ohmeda Isotec 3 isoflurane vaporizer (GE Healthcare, USA). Isoflurane levels were kept ≤3% at all times. Once completely anesthetized, animals were restrained in the supine position and a torso X-Ray was obtained (Belmont Acuray 071A, USA). Later, 100 μL of the labeled MAA (8,000–10,000 particles) with an activity ranging from 50 to 100 μCi (1.85–3.7 MBq) was injected through the lateral tail vein. Animals were euthanized at 2 or 4 hours. For either time points their lungs, liver, spleen, heart, kidneys, ribs, and 0.2 mL of blood and urine were collected, weighed, and activity measured using a Cobra 5000 well counter (Packard, USA). Uncollimated autoradiography images (in the unaltered supine position the X-Ray was obtained) were also taken at 1, 2, 3, and 4 hours (Packard Phosphorimager, Perkin Elmer, USA). Free 68Ga was injected as a control. Additionally, imaging and organ collection were also performed with 99mTc-MAA and reduced Na 99mTcO4 (sodium pertechnetate) for comparison purposes 99mTc-MAA and Na 99mTcO4 were purchased from a local pharmacy (Triad Isotopes, USA). Approximately 5 mCi of sodium pertechnetate in 5 mL of saline (pH ≈ 5.5) was reduced with 100 μg of stannous chloride (Sigma-Aldrich, USA) before injection. The obtained X-Rays and the autoradiography images were superimposed to provide anatomical and functional data.
3. Results and Discussion
3.1. MAA Relyophilization
The elimination of the excess free albumin is a necessary step prior to successful labeling with 68Ga (“washed MAA”) [4, 5]. Resuspension of the particles was fast using a vortex mixer; manual shaking of the vial was also efficient. Relyophilization of the MAA did not change either the particle’s size distribution or morphology (Figure 1).
3.2. Purification System
The assembly of the purification system is simple and easy to use (Figure 2).
The optimized and simple four-step purification process is as follows. (1) Elution of the generator using a 0.1 M HCl solution. During this step the gallium is trapped with most of the metal impurities in the cation exchanger. Most of the 68Ge contamination is removed in this step. (2) Cleaning is performed with one extra mL of 0.1 M HCl through the syringe dock to remove the excess solution coming from the generator. One mL of air is then vented to the system. (3) Purification is performed with slow elution using 1 mL of 5 M HCl. The Ga3+ forms a complex so it is released from the cation exchanger and absorbed onto the anion exchanger. One mL of air is also used to vent the system. All the metal impurities are eliminated in this step (especially Fe, Ti, and Zn). (4) Extraction is done using 1 mL of Millipore water in which the gallium complex is destroyed and released from the anion exchanger into the labeling vial. One mL of air is pushed through the system to remove most of the 68Ga (Figure 3). The purification system retrieves approximately 85% of the eluted gallium activity after 10 minutes of processing. It provides pure, preconcentrated 68Ga in slightly acidic solution that is buffered by adding 0.3 mL of 3 N ultrapure sodium acetate . All the 68Ge is eliminated in the process; consequently radio-nuclide impurities are eliminated from the labeling process.
The purification system can be reused for times without altering its performance. However to maintain sterility it is recommended to be used once and disposed.
3.3. MAA Labeling
Labeling yield of MAA with unpurified 68Ga was % after 15 minutes at 75°C, similar to that reported by other investigators . A labeling yield of % was obtained at 50°C (Figure 4). Better labeling yield (%) was obtained at 95°C; however the particle quality control showed important changes. Smaller particles were detected and in higher concentration, apparently due to the rupture of bigger macroaggregates. The labeling yield at room temperature was %. Radiochemical purity tests were conducted for all the products showing more than 97% “in vitro” stability in all cases after 4 hours.
The introduction of the 68Ga purification system improved the labeling yield significantly (). An % labeling yield was obtained at room temperature (25°C). This yield is higher than the maximum yield obtained at 75°C with unpurified 68Ga. However, if room temperature labeling is performed, postlabeling purification is still needed to assure a final radiochemical purity >90%. In the particular case of MAA, labeling at up to 75°C has been proven to not damage the particles. Nevertheless, synthesis near room temperature or elimination of the heating step all together is obviously desirable. Good labeling yield of % was obtained at 50°C. When labeling at this temperature, purification is still recommended since nearly 10% of free 68Ga will be present in the final product.
The labeling of MAA with purified 68Ga yielded the best results at 75°C (Figure 4). A labeling yield of % was obtained after 15 minutes of reaction. Particle distribution and morphology remained well within specifications and a >95% radiochemical purity was obtained. Labeling at this temperature eliminates the need for a purification step, rendering the final product ready for injection immediately. Experiments with purified 68Ga-MAA at 95°C were not performed because of the previously observed particle change at that temperature.
Relyophilized MAA labeling with purified 68Ga showed no significant difference from the results obtained with the washed MAA (). The elimination of the free albumin and the stannous chloride from the original formulation followed by relyophilization of the MAA does not compromise either resuspension or morphology (and size distribution) of the particles. The relyophilized MAA (or MAA prepared without SnCl2 and free albumin), in combination with the 68Ga purification system, allows for the preparation of a single-use lyophilized kit for the preparation of 68Ga-MAA. This kit can be used for Positron Emission Tomography in lung perfusion studies, selective internal radiation treatment (for liver cancer) planning, and other applications requiring perfusion imaging.
Since terminal studies were conducted, sterility of the final product was not a concern. However sterility of the final product is very important to have a successful kit. To maintain 68Ga-MAA sterility, 68Ga needs to be filtered through a 0.22 μm filter before labeling. In the same way, the MAA kit must be produced albumin and SnCl2 free for 68Ga labeling and its sterility must be guaranteed. Final product sterility cannot be assured by filtration (since MAA particles are in the μm range); therefore a parametric release is needed. All labeling procedures for human use must be conducted in a clean room.
3.4. Animal Experiments
More than 90% of the injected 68Ga-MAA activity was detected in the lungs after tail vein injection (seen in the image taken after 10 minutes, not shown) and until at least 4 hours after injection (Table 1). Less than 2% of ID/o activity was measured in any organ other than lungs after 2 and 4 hours. Most of the free 68Ga (>60%) remains in the blood after 4 hours (presumably as 68Ga-native transferrin complex). The remaining activity was extracted by the kidneys to the bladder (13%) or absorbed by the liver (15%). The in vivo radiochemical purity of 68Ga-MAA was greater than 97% during the studied period.
The behavior and “in vivo” radiochemical purity of 99mTc MAA was different than that of 68Ga-MAA. 99mTc was slowly released from the MAA and extracted by the kidneys into the urine ( after 2 hours and after 4 hours). Only % of the decay corrected activity was found in the lungs after 2 hours, decreasing to % at 4 hours.
Hydrolyzed 99mTc (reduced with SnCl2) allocates mainly in the lungs and liver. The % ID/o did not change over the study period. 68Ga-MAA exhibited better “in vivo” stability than 99mTc-MAA (Table 1 and Figure 5). The autoradiography images clearly showed the preferential allocation of 68Ga-MAA in the lungs over the period studied (Figure 6). The drug-product in-vivo half-life was determined using regions of interest in the autoradiography images. A square cell of 40 40 mm was used to count the activity in the lung region for each time point (Figure 6). For 99mTc-MAA biological half-live was found to be hours. This is consistent with the previously reported value of hour biological half-life . The biological half-life of 99mTc-MAA is not to be confused with the MAA biological half-life. These are equal only if 100% “in vivo” radiochemical purity of 99mTc-MAA is assumed. The assumption was reinforced by the fact that injected hydrolyzed99mTc behaves differently than that released from the MAA (Table 1 and Figure 6). The only feasible explanation is that injected hydrolyzed 99mTc forms nanocolloids with the SnCl2, being absorbed by the liver and lungs, while 99mTc released from the MAA is quickly absorbed by the kidneys. Furthermore, it is very unlikely that some form of degraded 99mTc-albumin will be absorbed by the kidneys for excretion rather than be degraded in the liver. For over 40 years MAA half-life was considered to be in the 6–12-hour range [1, 12]. However if MAA half-life happened to be so short, degradation would have been observed in the 68Ga-MAA experiments. The stronger 68Ga-MAA binding, with superior “in vivo” stability, proves that MAA half-life is much longer than previously assumed .
The assumption of a shorter MAA half-life (MAA biological decomposition) has little or no implication in lung perfusion studies or probe guided surgery. However questionable implication is present when using the radiolabeled MAA in planning for liver cancer SIRT. The radio-microsphere technique is based on several planning steps. One of them is a particle distribution assessment using 99mTc-MAA, mainly to determine lung and gastrointestinal (GI) allocation after hepatic artery injection. If only liver allocation is found (less than 20% lung allocation and no GI allocation), then the radio-microsphere treatment is administered after 48 hours since the MAA is assumed to have been cleared from the vessels (assuming a MAA half-life of 6–12 hours). Despite this wrong assumption, the treatment is successful. Therefore, it must be concluded that the effectiveness of the treatment does not require the complete decay of the treatment planning microparticles. Because they are injected in small numbers, enough arterioles seem to still be available for the allocation of the therapy particles. However, whether or not the treatment could benefit from the use of fast degrading planning particles (faster than MAA) remains an open question. Nevertheless, a precise determination of MAA half-life is needed and can probably be measured by combining the strong gallium binding with a longer radioactive half-life (e.g., 67Ga-MAA).
The relyophilization of washed MAA was a first approach to show the feasibility of a lyophilized kit specifically for 68Ga-MAA. In a production facility the pharmaceutical development would need to be different from that of the 99mTc-MAA kit. Free albumin and SnCl2 would not need to be added to the final product. The high labeling yield obtained during the preparation of 68Ga-MAA eliminates the need for final centrifugation for purification. What seems to be the apparent elimination of a single step has major implications. In these conditions the purification/labeling scheme can be easily automated using one of the available modular labs for PET synthesis (e.g., Modular-Lab PharmTracer, Eckert and Ziegler, Germany), or it could easily be accomplished in a nuclear medicine hot-lab in a hospital.
A Gallium specific lyophilized kit for 68Ga-MAA production was created. The kit is comprised of a vial containing MAA (relyophilized DraxImage kit), a 68Ga purification system, and working solutions in the following syringes: 5 mL of 0.1 M HCl (elution), 1 mL 0.1 of M HCl (cleaning), 1 mL of 5 M HCl (purification), 1 mL of Millipore water (extraction), and 0.3 mL of 3 N NaAc solution (buffer). The purification system can also be used for labeling of most 68Ga imaging agents (e.g., DOTANOC and DOTATOC) with a small variation in the buffer amount. Labeling of MAA at 75°C for 15 minutes is recommended for labeling yields higher than 95% with no further purification necessary. Room temperature labeling is possible for producing 80% labeling yield but postlabeling purification is needed. Lung perfusion PET images are recommended to be acquired within the first hour after injection because of the short half-life of the 68Ga. The “in vivo” stability of the obtained 68Ga-MAA drug product is superior to that of 99mTc-MAA. Use of 68Ga-MAA in SIRT planning is also possible, likely to benefit from superior imaging/quantification and more accurate dosimetric calculations.
|PET:||Positron Emission Tomography|
|SIRT:||Selective Internal Radiation Treatment|
|SPECT:||Single Photon Emission Tomography.|
Conflict of Interests
The authors declare that there is no conflict of interests regarding the publication of this paper.
The authors acknowledge the NIH Grant no. 1 R21 CA159073-01A1 and the Rinker Family Foundation.
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