- freely available
Appl. Sci. 2013, 3(3), 593-613; doi:10.3390/app3030593
Abstract: 89Zr has emerged as a useful radioisotope for targeted molecular imaging via positron emission tomography (PET) in both animal models and humans. This isotope is particularly attractive for cancer research because its half-life (t1/2 = 3.27 days) is well-suited for in vivo targeting of macromolecules and nanoparticles to cell surface antigens expressed by cancer cells. Furthermore, 89Zr emits a low-energy positron (Eβ+,mean = 0.40 MeV), which is favorable for high spatial resolution in PET, with an adequate branching ratio for positron emission (BR = 23%). The demand for 89Zr for research purposes is increasing; however, 89Zr also emits significant gamma radiation (Γ15 keV = 6.6 R∙cm2/mCi∙h), which makes producing large amounts of this isotope by hand unrealistic from a radiation safety standpoint. Fortunately, a straightforward method exists for production of 89Zr by bombarding a natural Y target in a biomedical cyclotron and then separation of 89Zr from the target material by column chromatography. The chemical separation in this method lends itself to remote processing using an automated module placed inside a hot cell. In this work, we have designed, built and commissioned a module that has performed the chemical separation of 89Zr safely and routinely, at activities in excess of 50 mCi, with radionuclidic purity > 99.9% and satisfactory effective specific activity (ESA).
The isotope 89Zr is one of several positron-emitting radiometals that are increasing in popularity as radiolabels for positron emission tomography (PET) [1,2,3,4,5]. A search of the PubMed database  found over 55 publications with 89Zr mentioned in the title, 75% of which had been published since 2009. In particular, 89Zr holds significant potential for immunoPET [4,7,8,9,10], a growing technique that uses radiolabelled antibodies, antibody fragments, and peptides for the in vivo molecular imaging of antigens using PET [7,11,12,13,14]. 89Zr is well-suited for this technique because it is a positron-emitter with a half-life (t1/2 = 3.27 days) that is long enough to accommodate the targeting time for these relatively large imaging agents, which is on the order of days. So far, the most prevalent application for 89Zr has been cancer imaging, which is the focus of the majority of publications that used 89Zr for in vivo PET imaging. The information that is obtained using 89Zr-immunoPET can be useful for cancer staging, therapy planning, and treatment monitoring, making 89Zr a potentially valuable tool for personalized medicine.
There are several properties of 89Zr that make it an attractive radiolabel for immunoPET. Most importantly, the half-life of 89Zr matches the biological half-life of antibodies. Additionally, 89Zr emits positrons with a sufficient branching ratio (y = 23%) and provides good PET spatial resolution because it emits positrons at a low average energy (Eβ+,avg = 396 keV), and therefore a lower positron range (1.2 mm ) compared to several other PET isotopes. Unfortunately, 89Zr also emits a high energy (909 keV) gamma ray with a high branching ratio (99.0%). Thus, 89Zr has a high gamma factor, Γ15 keV = 6.6 R∙cm2∙mCi−1∙h−1 (weighted average of all gamma rays emitted) , meaning that the dose rate for this isotope is significant. The Zr4+ ion prefers a coordination state of 6 to form a stable complex, and, so far, the most prevalent chelator of 89Zr is desferrioxamine (DFO) [8,17]. Table 1 summarizes chemical and nuclear decay properties of 89Zr, including a simplified decay scheme.
The vast majority of medical centers capable of producing medical isotopes do so using a low-energy “biomedical” cyclotron capable of bombarding a target with protons with energy (Ep) < 20 MeV (and alternatively deuterons with energy (Ed) <10 MeV). For these particles and energies, the highest cross-section is the (p,n) reaction with a peak cross-section of ~0.8 b at Ep~14 MeV. The (p,n) reaction uses 89Y target material, which is 100% naturally abundant and thus relatively inexpensive. For the above reasons, the natY(p,n)89Zr reaction is the most common reaction route for 89Zr production . However, contaminants can also be produced in a natY foil via the following common low-energy positron reactions: (p,n)89mZr, (p,2n)88Zr, (p,pn)88Y, as shown in the Electronic Supplementary Information (ESI). Fortunately, high radionuclidic purity can still be achieved using ~15 MeV protons because 89mZr has a short half-life (t1/2 = 4.2 m) and a high degree of isomeric transition (IT = 93.8%) and because the (p,2n) and (p,pn) reactions require greater proton beam energies, so they have low cross-sections at Ep~15 MeV—less than 0.2 and 0.02 b, respectively . The important characteristics of 89Zr production in general are summarized in Table 2, and the parameters and results from eight publications [20,21,22,23,24,25,26,27] about 89Zr production are shown in the ESI.
|Nuclear Decay:||Simplified decay scheme:|
|Half-life, t1/2||3.27 days|
|Daughter isotope||100% 89Y (stable)|
|Decay modes||23% β+|
|β+ energy, Eβ+, avg (range in water)||396 keV (1.2 mm)|
|γ-ray energy, Eγ (intensity)||909 keV (99.0%)|
|Gamma factor, Γ15 keV||6.6 R∙cm2∙mCi−1∙h−1|
|Theoretical specific activity||40 Ci∙μmol−1|
The gamma factor in the table accounts for gamma ray energies ≥15 keV. The decay scheme displays all gamma-rays with intensity (y) >1%. Percentages indicate the overall intensity of each transition. DFO: desferrioxamine; EC: electron capture; IT: isomeric transition; β+: positron emission; γ: gamma-ray; ε: EC+β+ transition [15,16,19,23].
|Target (natural abundance)||natY (100% 89Y)|
|Production reaction||(p,n)89Zr (t1/2 = 3.27 days)|
|Peak cross-section and energy, σ (Eβ+)||~0.8 b (~15 MeV)|
|Reaction threshold, Q||3.7 MeV|
|Stopping range of 14.7 MeV protons||1.02 mm|
|Other possible reactions||(p,n)89mZr (t1/2 = 4.2 m)|
|(p,2n)88Zr (t1/2 = 83.4 days)|
|(p,pn)88Y (t1/2 = 107 days)|
|Optimum beam energy, Ep||13 MeV|
|Target preparation||hot-rolled natY metal foil|
Out of eight papers that used the (p,n) reaction for 89Zr production, five used Y foil targets [20,21,23,26,27], two used sputtered Y onto Cu [24,25], and one used Y2O3 pellets . Although the sputtered targets provided superior heat transfer and therefore allowed for higher beam currents, we chose to use Y foil for ease of use. For a hypothetical irradiated Y foil that contains 100 mCi of 89Zr, <0.3 μg of 89Zr atoms are present in the foil, and these product atoms must be extracted chemically to give the desired product—a solution containing 89Zr4+ ions. This separation has been performed with mixed results using several different techniques , including solvent extraction [21,22,26,27,37], solid cation exchange [21,22], solid anion exchange [22,26,27,38], and solid hydroxamate resin [23,24,25,39,40]. Hydroxamate resin separation has emerged as the preferred method following the publication of a standardized method for producing and separating 89Zr by Holland, et al. . This separation can produce high recovery, radionuclidic purity, and effective specific activity (ESA). Our work does not contribute new separation chemistry; rather, the objective for this work was to automate the process that was reported by Holland, et al.  based on chemistry that was developed by Verel, et al. , Meijs, et al. , and Herscheid, et al. .
Automation is an important part of isotope production in particular and nuclear medicine in general because automated modules enable production centers to separate large activities of isotopes while still meeting institutional and federal regulations for radiation dose. Automated modules are ubiquitous at many PET centers, where they are typically used in good manufacturing practice (GMP) facilities for synthesizing patient doses of radiopharmaceuticals, such as [18F]fluoro-deoxy-glucose ([18F]FDG). Automated modules are essential to such processes because these syntheses are for human injection and because the radiolabels for these compounds have short half-lives, high activities, and high gamma factors. Therefore, automated modules are used to make the synthesis clean, reproducible, fast, and safe to production personnel. Although most PET radiometals are still at the research stage, automated separation modules are still useful for many of the same reasons, but principally to minimize dose to personnel. Several groups have published on custom-made automated modules for various radiometals, including 64Cu [41,42,43,44], 124I , 99mTc , 86Y , and 89Zr [48,49]. In this work, we have designed, built and commissioned a module that has performed the chemical separation of 89Zr safely and routinely, at activities in excess of 50 mCi, with high radionuclidic purity and satisfactory ESA.
2. Experimental Section
natY foil (99.9% purity) was purchased from Alfa Aesar (Ward Hill, MA, USA), and Nb metal (99.8%) was purchased in rod form from A.D. Mackay (Denver, NC, USA). A silica-based weak cation exchange resin was purchased from Waters (Milford, MA, USA). Trace metals grade water purchased from Sigma-Aldrich (St. Louis, MO, USA) was used for all liquids in the automated chemical separations. Ultrapure (~18 MΩ) water was purified in a Millipore system (Billerica, MA, USA) and was used for all other purposes, including cleaning the automated module before each use and making solutions for DFO titrations. DFO-NCS was purchased from Macrocyclics (Dallas, TX, USA), and all other chemicals were purchased from Sigma-Aldrich.
2.2. Cyclotron Production
Discs with diameter 9.5 mm were punched from 0.64 mm thick natY foil (disc mass ~0.2 g). Nb metal target holders were machined, consisting of a base and a screw-on lid with a centered, circular hole to expose the target foil to the cyclotron beam. Nb was selected because of its high melting temperature (Tm = 2,468 °C) and high chemical inertness . A single natY disc was placed inside the target holder, as shown in Figure 1. Due to activation, many target holders were machined to allow residual activity to decay before reuse. Before each target holder was reused, it was scrubbed by hand using a cotton swab dipped in a slurry made from Al2O3 powder and water, if deemed necessary. The target holder was placed in 6 M HCl for 1–4 h for cleaning and dried in an oven. The target assembly was mounted in the CS-15 cyclotron (The Cyclotron Corporation, Berkeley, CA, USA) at the Mallinckrodt Institute of Radiology (MIR) and bombarded with protons (Ep ≈ 14.7 MeV) to produce 89Zr via the natY(p,n)89Zr reaction. The beam exit energy was Ep ≈ 7.9 MeV, based on calculations performed using The Stopping Range of Ions in Matter (SRIM) software , which implements the Bethe formula for stopping power. After Ep was degraded by the Y foil, the beam stopped in the base of the Nb target holder, as calculated with Transport of Ions in Matter (TRIM) module within the SRIM package (see ESI). During bombardment, the target holder assembly was cooled on the beam side by a He gas jet and on the reverse side by flowing chilled water (T ≈ 2.2 °C). Following irradiation, the target remained in the solid target station for a few hours to allow for the decay of short-lived contaminants, especially 89mZr in the Y foil. Then, the target assembly was removed by hand, and other short-lived contaminants were allowed to decay overnight while the target was in a shielded location. On the following morning, chemical separation was performed in the hot cell that contained the automated module.
2.3. Separation Chemistry
Figure 2 summarizes the general steps in our production process. A stock of hydroxamate resin was made by functionalizing the weak cation exchange resin with hydroxamate groups according to a procedure published in Holland, et al. , based on chemistry developed by others [24,25,39]. Chemical separation of 89Zr from the natY foil was performed in an in-house built automated module installed inside a lead hot cell (Comecer, Castel Bolognese, Italy), typically on the day after bombardment. During setup for each separation of 89Zr, 100 mg of hydroxamate resin from this stock was loaded between two polyethylene (PE) frits (Grace, Deerfield, IL, USA), which were between two small pieces of glass wool, and loaded into a custom-blown glass column reservoir that was then incorporated into the system with air-tight connections. The entire irradiated target assembly—target holder and target foil—was quickly dropped into a Teflon dissolution vessel mounted on the automated system. This transfer was performed manually, the door to the hot cell was then closed, and the remaining steps in the purification process were performed remotely. Work is underway on a system that will automate the transfer of the target from a custom-made transport safe to the dissolution vessel in the automated module.
Using a custom software program made in LabVIEW (National Instruments, Austin, TX, USA) running on a laptop outside the hot cell (see Section 2.4), 10 mL 2 M HCl was added to the dissolution vessel to dissolve the natY target. After waiting ~1 h for complete dissolution, the dissolved target was transferred to the column through tubing using compressed air. Then, the Y was eluted from the column in 10 mL 2 M HCl and collected in a waste vial, leaving the 89Zr bound on the column. The column was rinsed with 10 mL water, which was collected in the same waste vial, and then the 89Zr was eluted in 1 mL 1 M oxalic acid and collected in a product vial as 89Zr chelated by the oxalate ions (89Zr-oxalate). Although other studies have achieved greater recovery and activity per volume by collecting multiple fractions from the column [23,24,25], we currently have automated the collection for only one elution of the product for simplicity in the automated module. However, to compensate for collecting a single fraction, we increased slightly the volume of eluent to 1 mL. After collection of 89Zr in the product vial, the product was retrieved from the hot cell manually and then dispensed in 2 mL skirted microcentifuge tubes for distribution within our institution and/or shipping to extramural researchers.
2.4. Automated Module
An automated module was designed and built to perform Zr-Y separation protocol remotely inside a lead hot cell. The frame for this module (h × w × d = 21 × 18 × 11 in. = 0.53 × 0.46 × 0.28 m) was constructed of extruded Al modular framing, to which walls were attached that were made of ultra high-molecular weight polyethylene. Various system components were mounted on these plastic walls, as pictured in Figure 2. The front panel of the module was hinged to allow easy access to the components and wiring inside the module. All liquids were pushed through the system by compressed air through C-Flex® flexible tubing and through needles made of polyetheretherketone (PEEK™) tubing. The compressed air was delivered to various parts of the system through polytetrafluoroethylene (PTFE) tubing. All liquid and most gas connections were assembled using non-metallic connectors, which reduced exposure to metals that may have compromised ESA. Many of the liquid connection pieces were designed for high pressure liquid chromatography (HPLC) systems and were made of ethylene-tetrafluoroethylene (ETFE, Tefzel®); gas connections were made using stainless steel Swagelok® tube fittings (Swagelok, Solon, OH, USA). The path of fluids (liquids and air) through the system was controlled by solenoid-actuated isolation valves, and, as a fail-safe, solenoid-actuated pinch valves prevented liquids from flowing through the flexible tubing at inappropriate times or in the opposite direction. Solenoid valves were manufactured by NResearch (West Caldwell, NJ, USA). Solvents only came in contact with polymers and glass in the system. The compressed air was adjusted by a pressure regulator (Swagelok). The flow of compressed air was precisely controlled by a hot wire anemometer mass flow controller (Pneutronics) that received commands from the computer. Before each separation, all liquid solvents were pre-loaded into the system by hand in glass vials capped with silicone rubber septa that allowed for insertion of two PEEK needles—one connected to compressed air and one for transporting the liquid. The vials were then clipped onto the front of the module, and during the separation each liquid was extracted from its vial using positive pressure from the PEEK needle that was connected to compressed air. The general schematic of the entire system is shown in Figure 3.
A computer located outside of the hot cell was used to control the entire chemical separation process. A program was created on the LabVIEW platform that featured a graphical user interface (GUI) that provides instructions and controls for production personnel. Users could follow a step-by-step procedure with a pre-programmed control scheme and, if necessary, intervene by controlling individual valves in the event of a problem in the system. Using the GUI, the user can easily and precisely change the flow through the mass flow controller and thereby the speed at which liquids were pushed through the system, most importantly the speed of solvents through the column. We found that to improve recovery, the final eluent was allowed to sit on the column for ~20 min. and then slowly pushed through the column at ~0.2–1 mL/min. The GUI also included a live video feed from a mini color camera (ApexCCTV, Allen, TX, USA) providing an up-close view of the liquid on the column, as well as real-time graphs that reported the radiation dose measured by four Si PIN-type photodiode detectors (Carroll & Ramsey, Berkeley, CA, USA). These detectors were strategically placed close to the dissolution vessel, resin column, waste vial, and product vial (see Figure 3), allowing the user to monitor the movement of radioactivity through the system in real time. A screenshot of the GUI near the end of a separation process is shown in Figure 4.
2.5. Product Characterization
The final product was characterized for activity amount, radionuclidic purity, and ESA. The amount of activity that was recovered was measured using a dose calibrator (Capintec, Ramsey, NJ, USA) using a dial setting of 465. The radionuclidic purity was characterized using a high-purity Ge detector (Canberra, Meriden, CT, USA) connected to a digital spectrum analyzer (Canberra). The product was diluted in 2 mL skirted microcentrifuge tubes, and a 10 m scan of the product was performed within one half-life of the original bombardment. To search for longer-lived contaminants, an aliquot of one production was allowed to decay for ~3 half-lives and then scanned for 12 h. Gamma ray peaks were identified based on characteristic gamma-rays, which are summarized in Table S2. DFO titration was used to determine ESA—the activity per total amount of metals—as per Holland, et al. . To minimize non-specific binding of other metals by the DFO, the DFO was challenged by 50 mM DTPA. The titration was carried out by thin layer chromatography (TLC) on pure cellulose blotting paper that was developed in 50 mM DTPA and scanned using a radio-TLC imaging scanner (Bioscan, Washington, DC, USA).
3. Results and Discussion
The methods described in this work have been used successfully for several months for the cyclotron production and chemical separation of 89Zr. Typically, after the chemical separation was completed using the automated module, a dose calibrator was used to measure the activity of 89Zr collected in the product and waste vials. To reduce radiation dose, the system was allowed to decay for one week before measuring the dissolution vessel, which still contained the irradiated Nb target holder, and the intact column assembly, which still included the resin, frits, and glass wool. The radioactivity measured for all four major module components was decay-corrected to the end-of-bombardment (EOB) time for each production. The decay-corrected activities were summed to give an estimated total radioactivity of 89Zr produced in each cyclotron bombardment. This estimate neglects any activity that was lost in tubing, valves, etc., but it allows us to compare the performance of the automated chemical separation for productions with different starting activities. The majority (74% ± 16%) of 89Zr was collected in the product vial and the largest loss of activity was to the column (18% ± 15%), which was greater than either the waste vial (4% ± 10%) or the dissolution vessel (3% ± 3%), as shown in Figure 5. The percentage of 89Zr activity collected in the product vial is the recovery rate of the chemical separation that was carried out using the automated module and is an important performance indicator for the separation process. Our average recovery was significantly lower than other publications about 89Zr production (see ESI). In some cases this may be a result of us only collecting one elution instead of multiple fractions; otherwise, it may be because the stock of hydroxamate resin became less effective at binding Zr if it was stored for too long. We chose to make a stock of the resin for simplicity to avoid functionalizing a new batch of resin for each production.
Characteristics for ten selected productions are shown in Table 3, including cyclotron parameters, predicted and estimated yields from the cyclotron, and ESA. All targets were bombarded with ~14.7 MeV protons. In this current work, Nb was selected as the material for the target holder primarily because of its chemical inertness toward HCl and its high melting temperature. The Nb target holders have been irradiated up to 15 μA without significant alterations of target or target holder. Since the same beam current, beam energy, and foil thickness were used for all productions in this work, the bombardment time (t) was the only bombardment parameter that was adjusted to control the amount of activity produced in the cyclotron. The maximum bombardment time in this work was 4 h, which was equivalent to 60 μA∙h. The parameters for comparable publications varied widely. Excluding the Y2O3 pellet targets, only one publication  used a foil that was close to ours in thickness. Also, the beam current, bombardment time, and μA∙h all varied widely across publications. Not surprisingly, the Y2O3 targets used lower currents, presumably because of reduced heat transfer, while the sputtered targets received high beam current for long bombardment times.
|Bombardment Time||Predicted Activityfrom Cyclotron||Estimated Total Activity||Effective Specific Activity|
|h (μA∙h)||mCi||mCi (% of Predicted)||mCi∙μmol−1 (% of TSA)|
|4 (60)||79||62 (78%)||353 (0.88%)|
|2 (30)||40||30 (74%)||250 (0.63%)|
|2 (30)||40||30 (76%)||134 (0.33%)|
|2 (30)||40||29 (74%)||87 (0.22%)|
|2 (30)||40||27 (68%)||73 (0.18%)|
|2 (30)||40||30 (75%)||63 (0.16%)|
|4 (60)||79||37 (47%)||59 (0.15%)|
|2 (30)||40||20 (50%)||25 (0.06%)|
|2 (30)||40||29 (72%)||21 (0.05%)|
|1 (15)||20||15 (75%)||15 (0.04%)|
Constants: beam energy, Ep = 14.7 MeV; beam current, I = 15 μA; target thickness, ttarget = 0.64 mm; theoretical specific activity, TSA = 40 Ci∙μmol−1. All activities have been decay-corrected to the end-of-bombardment time for each production.
The predicted activity produced from each cyclotron bombardment is given in Table 1 and was calculated using published empirical cross-section data for the natY(p,n)89Zr reaction [29,30,31,32,33,34,35,36] (see ESI) and the theoretical stopping ranges of protons in Y metal. The former data were accessed through the NNDC database  and the latter from calculations performed using the SRIM software . By geometry, we estimated that 37% of the beam was lost on the lid of the target holder, instead of irradiating the exposed Y foil. The reaction rate (R) was calculated, followed by the activity (A), using the equation A = R(1−e−λt) , where λ is the decay constant for 89Zr. The predicted values were also used to evaluate the total activity in the automated module as a percentage, also shown in Table 1.
To confirm the radionuclidic purity of the solution in the product vial, gamma spectroscopy was performed. Typically, a short (10 m) scan of a diluted aliquot from the product vial was performed on the same day as each chemical separation, (see spectra in the ESI). For one production, a long (12 h) scan was performed after waiting for several half-lives (~22 days) of 89Zr to allow it to decay relative to longer-lived potential radiocontaminants, making them easier to detect by gamma spectroscopy. This spectrum indicated a radionuclidic purity of 89Zr equal to 99.998% of total activity (99.95% of total atoms) and identified 88Zr as the only radiocontaminant. Even though our recovery percentage was less than most other studies, our radionuclidic purity was on par with other publications, only one of which had a radionuclidic purity <99%. This is likely because of the minimal overlap of the excitation function for the natY(p,n)89Zr reaction with other natY(p,x) reactions, especially the natY(p,2n)88Zr reaction at these irradiation energies. For most productions of 89Zr in this work, ESA was determined by DFO titration . ESA accounts for the presence of any metal isotope (stable or radioactive) that can be chelated by the selected chelator, in this case, DFO. For each production, the results of the DFO titration were plotted and fit with a sigmoidal dose-response curve to produce an EC50 value (see ESI), which was used to calculate ESA in mCi∙μmol−1. ESA was also expressed as a percentage of TSA, with absolute and relative ESA values shown in Table 1. Our results for ESA as a percentage of TSA were very low, although we expect when we produce and recover larger activities of 89Zr this will improve. Only one other publication  reported ESA values, and our values were significantly less than their results, although typically our production activities were less as well. We did observe an improvement in ESA with increasing size of production batches, and we are saving samples to analyze for metal contaminants that would diminish the ESA. Elemental analysis will be performed on these samples by ion-coupled plasma mass spectrometry (ICP-MS).
In this work, we present the cyclotron production of 89Zr using a biomedical cyclotron and the chemical separation of 89Zr from a Y foil target using an automated module. This module dissolved the Y foil in acid and then separated the 89Zr from Y using a hydroxamate resin column. Our methods reduced radiation dose to production personnel as the separation was carried out inside a lead hot cell, while the module was controlled by a laptop outside. The progress of the separation was monitored using radiation detectors in the module, and the final result for each production was a 89Zr4+-oxalate solution, and this solution was characterized for recovery of activity, radionuclidic purity, and ESA. Our 89Zr products had very high purity, similar to other published production methods. However, our productions had lower recovery percentages than other studies, possibly because we only collected one fraction from the column. Our ESA values were also lower than the only other paper that reported ESA, but that may improve with higher production activities. The procedures described in this work have been used for several months to routinely produce 89Zr for users at our institution and for shipping to other institutions. Lessons learned from production of 89Zr will be adapted for routine cyclotron production and chemical separation of other radiometals from solid targets.
The authors acknowledge G.G. Gaehle for advice in designing the automated module; W.H. Margenau and J.W. Linders for constructing certain components of the system; the Washington University School of Medicine Instrument Machine Shop and J.W. Linders for machining the Nb target holders; W.H. and P.M. Margenau for operation of the cyclotron; and O.F. Ikotun and B.V. Marquez for general advice on 89Zr separation and chelation chemistries. The authors have no competing financial interests to disclose. A.L. Wooten was supported in part by a training grant from NIBIB/NIH (T32EB014855-01). This work was funded by the U.S. Department of Energy, Office of Science, Nuclear Physics Isotope Program under grant DESC0008657.
Conflict of Interest
The authors declare no conflict of interest.
Electronic Supplementary Information
|Y Foil Thickness||Bombardment Parameters||Target Holder Description||Target Cooling Description||Activity/ (μA × h)||% Recovery||Radionuclidic Purity||ESA|
|mm||μA × h||mCi/ (uA x h)||% of total activity||mCi∙μmol−1 (% of TSA)|
|This Work||2013||0.64||15 × 4 § = 60||Machined Nb||Chilled water (2.2 °C); He jet (beam side)||3.67-15||93% †||99.998%||5-353 (0.01%–0.88%)|
|Walther, et al. ||2011||0.15||12 × 2 = 24||Aluminum||Chilled water; He jet (beam side)||0.338||97.5%||>95%||-|
|Dutta, et al. ||2009||0.009||0.54 × 2.3 = 1.3||-||-||-||-||-||-|
|Kandil, et al. ||2007||13 (Y2O3 pellet diam.)||2 × 5 = 10||Covered with Al foil||Chilled water (13 °C)||0.754||97.5%||99.9%||-|
|Holland, et al. ||2005||0.10||15 × 5 = 75||10° slant||Chilled water (25 °C)||1.52||99.5% ‡||99.9%||470-1195 (1.2%–3.0%)|
|Verel, et al. ||2003||0.035 (sputtered)||80 × 3 = 240||onto Cu plate||-||0.002||97% ‡||99.9%||-|
|Meijs, et al. ||1994||0.025 (sputtered)||100 × 1 = 100||onto Cu plate||-||0.069||98% ‡||-||-|
|DeJesus and Nickles ||1990||0.127 and 0.6||10 × 2 = 20||-||Chilled water||43 and 100||95%||87%||-|
|Link, et al. ||1986||-||10 × 0.66 = 6.7||-||-||10.51||25%–80%||99%||-|
ESA: effective specific activity TSA: theoretical specific activity, (40 Ci∙μmol−1 for 89Zr). We selected the highest recovery from the productions that are presented in this table.§ longest bombardment; † average recovery; ‡ total recovery from multiple fractions.
|Reaction||Product||Half-Life||Decay Mode(s)||Daughter (Yield%)||Gamma Ray Energyand Intensity||Radionuclidic Purity|
|t1/2||Eγ keV (y%)||% of total activity(% of atoms)|
|(p,n)||89Zr||3.3 days||100% ε (77.3% EC, 22.7% β+)||89Y(100%, stable)||909 (99.0%)||99.998% (99.95%)|
|(p,n)||89mZr||4.2 m||93.8% IT, 6.2% ε (4.7% EC, 1.5% β+)||89Zr(93.8%), 89Y(6.2%, stable)||588 (89.6%)||Not Observed|
|(p,2n)||88Zr||83.4 days||100% ε (100% EC)||88Y(100%)||393 (97.3%)||0.002% (0.05%)|
|(p,pn)||88Y||106.6 days||100% ε (100% β+)||88Sr(100%, stable)||1836 (99.2%)||Not Observed|
89Y is 100% naturally abundant. Isomers were excluded if they had a half-life less than 1 s with exactly 100% decay by isomeric transition. Yield is the percentage of all parent nuclei that decay to the specified daughter isotope. The decay of all radioactive daughter isotopes were described elsewhere. For each isotope, this table displays the three signature gamma rays (if applicable) with the highest intensities that are at least 0.1%. Radionuclidic purity was based on a single 12 h scan of the product solution from an 89Zr production, 21 days after its cyclotron bombardment. All data were accessed via BNL/NNDC .
|Product Vial||Waste Vial||Column||DissolutionVessel||EstimatedTotal Activity|
|mCi (%)||mCi (%)||mCi (%)||mCi (%)||mCi|
|14.2 (97%)||0.1 (0.5%)||0.0 (0%)||0.3 (2%)||14.6|
|14.6 (93%)||0.4 (2.5%)||0.4 (2%)||0.4 (2%)||15.8|
|13.7 (84%)||0.0 (0.0%)||2.3 (14%)||0.3 (2%)||16.3|
|24.7 (84%)||3.8 (12.9%)||0.1 (0%)||0.9 (3%)||29.4|
|23.3 (82%)||0.1 (0.3%)||3.6 (13%)||1.6 (5%)||28.6|
|16.0 (79%)||1.4 (6.9%)||2.6 (13%)||0.2 (1%)||20.1|
|48.1 (78%)||0.2 (0.2%)||7.7 (12%)||6.0 (10%)||62.0|
|20.2 (74%)||0.1 (0.3%)||6.5 (24%)||0.5 (2%)||27.3|
|21.5 (71%)||0.0 (0.1%)||7.4 (24%)||1.4 (5%)||30.4|
|9.1 (61%)||0.2 (1.2%)||5.5 (36%)||0.3 (2%)||15.0|
|16.4 (56%)||0.1 (0.5%)||12.7 (43%)||0.3 (1%)||29.6|
|15.1 (50%)||0.1 (0.3%)||14.6 (48%)||0.4 (1%)||30.1|
|16.4 (44%)||13.8 (37%)||4.5 (12%)||2.5 (7%)||37.2|
Percentages represent the percent of total activity.
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