Kenneth R. Buckley

Implementation of Multi-Curie Production of 99mTc by Conventional Medical Cyclotrons

99mTc is currently produced by an aging fleet of nuclear reactors, which require enriched uranium and generate nuclear waste. We report the development of a comprehensive solution to produce 99mTc in sufficient quantities to supply a large urban area using a single medical cyclotron. Methods: A new target system was designed for 99mTc production. Target plates made of tantalum were coated with a layer of 100Mo by electrophoretic deposition followed by high-temperature sintering. The targets were irradiated with 18-MeV protons for up to 6 h, using a medical cyclotron. The targets were automatically retrieved and dissolved in 30% H2O2. 99mTc was purified by solid-phase extraction or biphasic exchange chromatography. Results: Between 1.04 and 1.5 g of 100Mo were deposited on the tantalum plates. After high-temperature sintering, the 100Mo formed a hard, adherent layer that bonded well with the backing surface. The targets were irradiated for 1–6.9 h at 20–240 μA of proton beam current, producing up to 348 GBq (9.4 Ci) of 99mTc. The resulting pertechnetate passed all standard quality control procedures and could be used to reconstitute typical anionic, cationic, and neutral technetium radiopharmaceutical kits. Conclusion: The direct production of 99mTc via proton bombardment of 100Mo can be practically achieved in high yields using conventional medical cyclotrons. With some modifications of existing cyclotron infrastructure, this approach can be used to implement a decentralized medical isotope production model. This method eliminates the need for enriched uranium and the radioactive waste associated with the processing of uranium targets.

Printed sources for positron emission tomography (PET)

We have developed a method that allows manufacturing of /sup 18/F radioactive printed sources using a standard ink-jet printer. Although previously used in printing and imaging single gamma emitter sources, such techniques have not been, to our knowledge, applied to the manufacturing of positron emitting sources. The added complication in the latter instance is a nonzero positron range and, thus, the need for some attenuating material surrounding the positron emitting atoms. The point sources were first imaged on a phosphor imager and then scanned on three different tomographs (Siemens/CTI ECAT 953B, CPS high-resolution research tomograph (HRRT) and Concorde microPET R4) to measure their point spread functions (PSFs). Where appropriate, the resolution agrees with published values. A comparison of the full width and tenth width half maxima of the point source profiles obtained with and without additional attenuating material showed no effect of the additional attenuation material on their values. The presence of the attenuating material however increased the number of counts in the point source image several fold due to a larger fraction of the positrons annihilating in the region close to the printed source. The results show that printed sources either on paper alone or on paper sandwiched between some additional attenuating material provide a practical means to obtain positron emitting sources.

Water-cooled grid support for high-power irradiation with thin target windows.

A new thin window support system for the accelerator production of positron emitters (e.g. 17F, 18F 11C, 15O) has been developed. The integrated support grid and cooling design has been optimized for 6-13 MeV protons or deuterons. The water-cooled support grid regularly operated at > 100 microA of 6 MeV deuterons and protons. The grid performed without failure at > or = 50 microA of 13 MeV protons on a 3.1 MPa gas target using 25.4 microm aluminum target foil. Transmission for the smallest hole grid of 72% based on uniform parallel beam agreed with the measured yield of 71 +/- 1% compared to the theoretical maximum yield.

Radiosynthesis of N-[11C]-methyl-hydroxyfasudil as a new potential PET radiotracer for rho-kinases (ROCKs)

N-[(11)C]-methyl-hydroxyfasudil was synthesized as a new potential radiotracer for rho-kinases (ROCKs) via a two-step one-pot radiosynthesis. The first step was the methylation of the precursor N-Boc-hydroxyfasudil-sodium salt/benzo-15-crown-5 complex with [(11)C]methyl iodide. The second step involved deprotection of the tert-butoxycarbonyl protecting group. The radiochemical and chemical purities of N-[(11)C]-methyl-hydroxyfasudil were >95% and specific radioactivity was 1565-2565mCi/mumol at the end of the synthesis.

Investigation of Subject Motion Encountered During a Typical Positron Emission Tomography Scan

Subject motion has a known detrimental effect on brain Positron Emission Tomography image resolution. Numerous motion compensation techniques exist to address this issue, however prior to their application every effort should be made to limit subject motion. Using a Polaris motion tracking system subject motion was observed under typical scanning conditions for both healthy and Parkinsons disease (PD) volunteers. Motions in the range of 0 to 5 mm were observed for healthy subjects, and 0 to 20 mm for PD subjects. The most common source of motion was due to interaction between the subject and the attending nurse/scanning staff, especially during examination of the subjects symptoms (motions up to 8 mm). Less common activities resulting in significant motions were the use of a bedpan (20 mm), the removal of a cushion from under the subjects legs (5 mm) and leg readjustments (3 mm). Awareness of the effect each of these activities had on head motion can be used to motivate further limitations on these motions. Measured motions were also extrapolated to various regions in the brain, specifically the cerebellum, occipital cortex, and striatum. Subject head rotation about the vertical and horizontal axes resulted in the greatest displacement of regions in the cerebellum, while rotations about the subjects long axis primarily impacted the displacement of the occipital cortex region. This measurement provides motion related information about the expected accuracy of time activity curves for different brain regions.

Molybdenum target specifications for cyclotron production of 99mTc based on patient dose estimates

In response to the recognized fragility of reactor-produced (99)Mo supply, direct production of (99m)Tc via (100)Mo(p,2n)(99m)Tc reaction using medical cyclotrons has been investigated. However, due to the existence of other Molybdenum (Mo) isotopes in the target, in parallel with (99m)Tc, other technetium (Tc) radioactive isotopes (impurities) will be produced. They will be incorporated into the labeled radiopharmaceuticals and result in increased patient dose. The isotopic composition of the target and beam energy are main factors that determine production of impurities, thus also dose increases. Therefore, they both must be considered when selecting targets for clinical (99m)Tc production. Although for any given Mo target, the patient dose can be predicted based on complicated calculations of production yields for each Tc radioisotope, it would be very difficult to reverse these calculations to specify target composition based on dosimetry considerations. In this article, a relationship between patient dosimetry and Mo target composition is studied. A simple and easy algorithm for dose estimation, based solely on the knowledge of target composition and beam energy, is described. Using this algorithm, the patient dose increase due to every Mo isotope that could be present in the target is estimated. Most importantly, a technique to determine Mo target composition thresholds that would meet any given dosimetry requirement is proposed.

A proof of principle for targetry to produce ultra high quantities of 18F-fluoride

The production of 18F-fluoride from a gas target which utilizes the (18)O(p,n)18F reaction is described. Proof-of-principle experiments demonstrate that it is possible to design and build such a target that can be used routinely to produce terabecquerel (curie) quantities of 18F when operated at 100 microA.

Graphical user interface for yield and dose estimations for cyclotron-produced technetium

The cyclotron-based (100)Mo(p,2n)(99m)Tc reaction has been proposed as an alternative method for solving the shortage of (99m)Tc. With this production method, however, even if highly enriched molybdenum is used, various radioactive and stable isotopes will be produced simultaneously with (99m)Tc. In order to optimize reaction parameters and estimate potential patient doses from radiotracers labeled with cyclotron produced (99m)Tc, the yields for all reaction products must be estimated. Such calculations, however, are extremely complex and time consuming. Therefore, the objective of this study was to design a graphical user interface (GUI) that would automate these calculations, facilitate analysis of the experimental data, and predict dosimetry. The resulting GUI, named Cyclotron production Yields and Dosimetry (CYD), is based on Matlab®. It has three parts providing (a) reaction yield calculations, (b) predictions of gamma emissions and (c) dosimetry estimations. The paper presents the outline of the GUI, lists the parameters that must be provided by the user, discusses the details of calculations and provides examples of the results. Our initial experience shows that the proposed GUI allows the user to very efficiently calculate the yields of reaction products and analyze gamma spectroscopy data. However, it is expected that the main advantage of this GUI will be at the later clinical stage when entering reaction parameters will allow the user to predict production yields and estimate radiation doses to patients for each particular cyclotron run.

A fast and simple dose-calibrator-based quality control test for the radionuclidic purity of cyclotron-produced (99m)Tc.

Cyclotron production of 99mTc through the (100)Mo(p,2n)99mTc reaction channel is actively being investigated as an alternative to reactor-based (99)Mo generation by nuclear fission of (235)U. Like most radioisotope production methods, cyclotron production of 99mTc will result in creation of unwanted impurities, including Tc and non-Tc isotopes. It is important to measure the amounts of these impurities for release of cyclotron-produced 99mTc (CPTc) for clinical use. Detection of radioactive impurities will rely on measurements of their gamma (γ) emissions. Gamma spectroscopy is not suitable for this purpose because the overwhelming presence of 99mTc and the count-rate limitations of γ spectroscopy systems preclude fast and accurate measurement of small amounts of impurities. In this article we describe a simple and fast method for measuring γ emission rates from radioactive impurities in CPTc. The proposed method is similar to that used to identify (99)Mo breakthrough in generator-produced 99mTc: one dose calibrator (DC) reading of a CPTc source placed in a lead shield is followed by a second reading of the same source in air. Our experimental and theoretical analysis show that the ratio of DC readings in lead to those in air are linearly related to γ emission rates from impurities per MBq of 99mTc over a large range of clinically-relevant production conditions. We show that estimates of the γ emission rates from Tc impurities per MBq of 99mTc can be used to estimate increases in radiation dose (relative to pure 99mTc) to patients injected with CPTc-based radiopharmaceuticals. This enables establishing dosimetry-based clinical-release criteria that can be tested using commercially-available dose calibrators. We show that our approach is highly sensitive to the presence of 93gTc, 93mTc, 94gTc, 94mTc, 95mTc, 95gTc, and 96gTc, in addition to a number of non-Tc impurities.

Quantitative analysis of relationships between irradiation parameters and the reproducibility of cyclotron-produced 99mTc yields

Cyclotron production of (99m)Tc through the (100)Mo(p,2n) (99m)Tc reaction channel is actively being investigated as an alternative to reactor-based (99)Mo generation by nuclear fission of (235)U. An exciting aspect of this approach is that it can be implemented using currently-existing cyclotron infrastructure to supplement, or potentially replace, conventional (99m)Tc production methods that are based on aging and increasingly unreliable nuclear reactors. Successful implementation will require consistent production of large quantities of high-radionuclidic-purity (99m)Tc. However, variations in proton beam currents and the thickness and isotopic composition of enriched (100)Mo targets, in addition to other irradiation parameters, may degrade reproducibility of both radionuclidic purity and absolute (99m)Tc yields. The purpose of this article is to present a method for quantifying relationships between random variations in production parameters, including (100)Mo target thicknesses and proton beam currents, and reproducibility of absolute (99m)Tc yields (defined as the end of bombardment (EOB) (99m)Tc activity). Using the concepts of linear error propagation and the theory of stochastic point processes, we derive a mathematical expression that quantifies the influence of variations in various irradiation parameters on yield reproducibility, quantified in terms of the coefficient of variation of the EOB (99m)Tc activity. The utility of the developed formalism is demonstrated with an example. We show that achieving less than 20% variability in (99m)Tc yields will require highly-reproducible target thicknesses and proton currents. These results are related to the service rate which is defined as the percentage of (99m)Tc production runs that meet the minimum daily requirement of one (or many) nuclear medicine departments. For example, we show that achieving service rates of 84.0%, 97.5% and 99.9% with 20% variations in target thicknesses requires producing on average 1.2, 1.5 and 1.9 times the minimum daily activity requirement. The irradiation parameters that would be required to achieve these service rates are described. We believe the developed formalism will aid in the development of quality-control criteria required to ensure consistent supply of large quantities of high-radionuclidic-purity cyclotron-produced (99m)Tc.