Abstract

1. Introduction

The development of new radiopharmaceuticals for positron emission tomography (PET) in the aspect of personalized medicine is characterized by incredible progress in recent years [1,2,3]. The number of new compounds highly specific to certain biological processes is constantly increasing [4]. The incredible success of radiopharmaceuticals based on gallium-68 boosted the renaissance of radiopharmaceuticals based on metal radionuclides in general [5,6,7,8,9,10,11]. Labeled peptides with fast accumulation in target organs (comparable to the half-life of gallium-68 (T_½ = 67.8 min) and similar radionuclides) were particularly effective [6]. However, some highly specific molecules have a sufficiently high molecular weight and, as a result, a long retention in the bloodstream (e.g., monoclonal antibodies [12]). Therefore, researchers focus on radionuclides such as zirconium-89, yttrium-86, gallium-66, scandium-44, and copper-64 [13,14,15,16]. Zirconium-89, with a half-life of 78.42 h, is recently of particular interest. During the decay of zirconium-89, positrons with maximum energy E_β+ = 0.902 MeV are formed (yield 22.8%). By this positron emission and via electron capture (76.2%), zirconium-89 decays producing yttrium-89m (T_½ = 15.8 s), which in turn decays to stable yttrium-89 emitting photons (E_γ = 909 keV, 99.03%) [17]. The nuclear-physical properties of zirconium-89 make it an extremely promising radionuclide to study processes with a long-term kinetics using PET [18]. Zirconium-89 has several advantages compared to other similar radionuclides. The main advantage is its production feature: to produce zirconium-89 with a cyclotron, an isotopically enriched target is not required, since the starting material of the target is yttrium, which is a monoisotopic element [19]. Another advantage of zirconium-89 is that it has one of the lowest maximum energies of emitted positrons (after fluorine-18, copper-64 and carbon-11), which makes it possible to obtain PET images with high resolution [18,20]. According to the modeling results, which are in good agreement with the published experimental data, ⁸⁹Y(p,n)⁸⁹Zr reaction is considered to be the best for producing zirconium-89, and optimum energy for proton bombardment is 14 MeV [21,22,23,24]. The reaction can be successfully performed using small biomedical cyclotrons (<20 MeV); even 11 MeV cyclotrons are suitable [25,26,27].

There are several thorough reviews on radiopharmaceutical preparations based on zirconium-89 [18,28,29]. One of the earliest studies (it is also probably the first one published) on the distribution of zirconium-89 in human body was performed in 1957. Mealey studied the dynamics of excretion of zirconium-89 from the bloodstream and its distribution between plasma proteins [30]. He reported the possibility of the application of zirconium-89 for the “external localization of human brain tumors”. Zirconium-89 was prepared and administered in the form of [⁸⁹Zr]Zr-citrate (formulated in 1% sodium citrate, pH 6–7). The irradiated target was dissolved in 12 M HCl, passed through an anion exchange resin (Dowex); zirconium-89 was eluted from the resin with 5 M HNO₃, nitric acid was then evaporated, and zirconium-89 activity was dissolved in in 1% sodium citrate; the solution was filtered to remove colloidal zirconium-89.

Preclinical studies have demonstrated the effectiveness of [⁸⁹Zr]Zr-oxine in studying the distribution of stem cells and leukocytes (including the evaluation the effectiveness of cell therapy) [31], various cancer cells [32], and bone marrow cells after implantation [33]. Park et al. assessed the suitability of [⁸⁹Zr]Zr-oxalate as a PET tracer for the diagnosis of tumor and inflammatory processes, as well as rheumatoid arthritis in an animal model [34]. However, as mentioned above, most zirconium-89 radiopharmaceuticals used and under development today are labeled monoclonal antibodies [35,36]. These radiopharmaceuticals show high suitability in the diagnosis of various oncological diseases using PET. The growing interest in zirconium-89 together with very encouraging data from preclinical and clinical studies can ensure its rapid introduction into routine clinical practice, provided the availability of the radionuclide itself. The long half-life of zirconium-89 makes it possible to effectively implement the concept of its centralized production and delivery to medical institutions, which eliminates the need for a cyclotron-radiochemical complex in the medical institution itself. Thus, the development of effective methods for isolating zirconium-89 and formulating it in solutions that are most convenient for preparing radiopharmaceuticals is an extremely important obstacle on the way of introducing zirconium-89 into medical practice.

For the isolation of zirconium-89 from the irradiated target, cation- [37,38,39] and anion-exchange [23,40,41] chromatography methods, and extraction [38,41,42] were proposed. A typical procedure for processing the target is as follows: The irradiated target is dissolved in concentrated hydrochloric acid (9–12 M HCl). Next, the resulting solution is evaporated and/or diluted to the required concentration of HCl (≥8 M) and passed through an ion exchange column (Dowex 1 × 8, 2 × 8). Desorption of zirconium-89 is carried out with 1–2 M HCl or with combined solutions containing nitric, oxalic or hydrofluoric acid. The yield of zirconium-89 for this purification method ranges from 60% to 98%, depending on the volume and composition of the eluent. The chemical and radionuclide purity of the solutions obtained also varies widely.

In 1965, Baroncelli and Grossi found that hydroxamic acids have high specific affinity for zirconium and form very stable complexes with it [43]. Later, it was shown that hydroxamates have very specific and high affinity for Zr-ions even at high acid concentrations (in contrast to Fe, Al and Y) [44,45]. Thus, these compounds are suitable for a one-step separation of radiozirconium (^88/89Zr) from the bulk quantities of yttrium and other metal ions present in the target material. Meijs et al. described the first separation of zirconium-89 from yttrium with an in house prepared hydroxamate resin by eluting the no carrier added radiozirconium with 1.0 M oxalic acid [46]. Holland et al. showed that [⁸⁹Zr]Zr-oxalate in the form of 1.0 M oxalic acid solution obtained using hydroxamate resin has high chemical and radionuclide purity, and is suitable for obtaining complexes with deferoxamine with high molar activity (there was no effect of oxalic acid concentration on the yield of the complexation) [47].

Pandya et al. showed that it is possible to obtain zirconium-89 complexes with tetraazamacrocyclic ligands. In that study, [⁸⁹Zr]Zr-DOTA complex showed “extraordinary stability” [48]. It is particularly interesting that the authors demonstrated the effect of the nature of the initial zirconium-89 solution on the complexation efficiency: the use of [⁸⁹Zr]Zr-chloride (solution in 1 M HCl after reconstitution method [47]) when preparing zirconium-89 complexes with various ligands is preferable over the use of [⁸⁹Zr]Zr-oxalate.

It is important to note that hydroxamate resins mentioned in the vast majority of publications are in house prepared. Hence, there may be differences in the experimental data obtained by various scientific groups. ZR-resin (TrisKem International) is probably the only commercially available hydroxamate resin today [49]. According to the data provided by the manufacturer, this resin has a high selectivity for Zr in a wide range of HCl concentrations (0.01–10 M) and in HNO₃ solutions with concentrations up to 5 M. At the same time, the resin has a low affinity for Y, as well as for Fe(III) in solutions of 1–6 M HCl, and therefore can be effective for the isolation of zirconium-89 from the irradiated target. It is important that zirconium-89 can be eluted from the resin with a solution of oxalic acid with a concentration of 0.05–0.1 M in a small volume (1–1.5 mL). Thus, using this resin, it is possible to decrease the concentration of oxalic acid in the eluent by an order of magnitude with generally accepted methods [46,47]. Unfortunately, today, there are few papers describing the processes of using ZR-resin to isolate zirconium-89. Noteworthy is the work of Graves et al., who carried out the evaluation of the suitability of tributylphosphate(TBP)-impregnated solid-phase resin (TrisKem International) for the isolation of zirconium-89 [50]. As a comparison, a ZR-resin was used. Using TBP-resin, zirconium-89 was obtained in the form [⁸⁹Zr]Zr-chloride (0.1 M HCl). In the case of ZR-resin, zirconium-89 eluted with 1.0 M H₂C₂O₄ (although the manufacturer indicated a concentration of 0.05–0.1 M) and then reconstitution of [⁸⁹Zr]Zr-oxalate to [⁸⁹Zr]Zr-chloride was carried out using the method described in [47]. With TBP-resin zirconium-89 recovery efficiency in 1.0 mL of 0.1 M HCl was 89 ± 3%. At the same time, the content of metallic impurities (Y and Fe) was higher than when using ZR-resin. It is important to note that the preparation of zirconium-89 in dilute hydrochloric acid solutions has a significant drawback. It is known that, in the case of microconcentrations (10⁻⁹–10⁻¹¹ M ⁹⁵Zr) in solutions of saline, nitric, and perchloric acids, a noticeable hydrolysis of Zr⁴⁺ ion is observed at concentrations of hydrogen ion below ~2 g-ion/L [51]. The hydrolysis proceeds in steps with the formation of hydroxocations of the formula [Zr(OH)_x]^4−x (x < 3), the monomolecular hydroxide Zr(OH)₄, and also mixed complex cations and neutral molecules. Obviously, with increasing pH, the depth of the hydrolysis of zirconium-89 in such solutions will increase. The same applies to the reformulation of zirconium-89 in saline. Thus, the preparation of zirconium-89 in solutions of carboxylic acids is preferable in terms of their stability and suppression of zirconium hydrolysis with increasing pH. In addition to ZR-resin, we were also interested in the possibility of using Chelex-100 resin for the formulation of zirconium-89 solutions. The data presented by El-Sweify et al. allow evaluating the suitability of Chelex-100 for reconstitution in carboxylic acids solutions with pH close to neutral [52].

Based on the above, the aim of our work was to find a suitable method for obtaining zirconium-89 solutions in a form convenient for radiopharmaceutical purposes: low acidity, long term stability, suitable for further synthesis of various conjugates, and low or zero (replacement by another suitable intermediate) concentration of oxalic acid.

2. Results

2.1. Radio-TLC Systems for Analysis of Zirconium-89 Preparations

To date, several radio-TLC systems used for analysis of radiochemical purity of [⁸⁹Zr]Zr-labeled radiopharmaceuticals are mentioned in the literature. These systems are mainly used to analyze [⁸⁹Zr]Zr-labeled monoclonal antibodies to determine unbound zirconium-89 content.

Since iTLC-SG/50 mM DTPA pH 7.0 system is most often mentioned in the literature for analyzing [⁸⁹Zr]Zr-radiopharmaceutical preparations ([⁸⁹Zr]Zr-DFO and [⁸⁹Zr]Zr-DFO-mAb—Rf = 0; unbound zirconium-89—Rf = 1) [32,47,53,54,55,56,57,58], we decided to use this system (further referred to as Method 1) as a control in all experiments. In addition, according to literature data, zirconium forms more stable complexes with DTPA than those with EDTA (stability constants for [Zr(EDTA)]⁰, [Zr(EDTA)₂]⁴⁻, [Zr(DTPA)]⁻ and [ZrH₈(DTPA)₂]²⁺ are 27.9 ± 0.1, 54.4 ± 0.2, 35.3 ± 0.3 and 70.3 ± 0.4, correspondingly [59]).

At the same time, it was interesting for us to find a system capable of separating zirconium-89 in the form of an oxalate (or another auxiliary ligand) complex from [⁸⁹Zr]Zr-chloride and its hydrated forms. As a result of a large comparative study, we found a system that is probably the most satisfactory for this purpose. In iTLC-SG/CH₃OH-H₂O (1:1), 4% TFA (v/v) system zirconium-89 in the form of oxalate complex moves with a solvent front (Rf = 1). At the same time, samples of zirconium-89 in hydrochloric acid solutions of various concentrations (0.1–1.0 M HCl), prepared without using oxalic acid, remain at the start of the chromatogram completely in this system (Rf = 0) (Table 1; for more detailed information, see Tables S1 and S2 in the Supplementary Materials).

Table 1

Radio-chromatograms of different zirconium-89 preparations with iTLC-SG/CH₃OH-H₂O (1:1), 4% TFA (v/v) system (Method 2).

[89Zr]Zr-Oxalate0.1 M Oxalic Acid	[89Zr]Zr-Oxalate 0.1 M Oxalic Acid (Neutralized to pH~7)	[89Zr]Zr-Oxalate1.0 M Oxalic Acid	[89Zr]ZrCl4 in 1 M HCl	[89Zr]Zr in 0.1 M HCl

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This method (Method 2) was used in all further studies in combination with Method 1. It is important to note that, when using Method 2 for analysis, we observed an interesting effect on various [⁸⁹Zr]Zr-oxalate preparations: depending on the pH value and the concentration of oxalic acid in the preparation, either two peaks with Rf 0.8 and 1.0 or only one of them could be observed. The ratios of the peaks could be different as well. This fact suggests the existence of two dominant forms of zirconium-89 complexes with oxalate anion in these preparations. Based on published data, it can be assumed that probably these forms are [⁸⁹Zr]Zr(oxalate)₄)⁴⁻ and [⁸⁹Zr]Zr(oxalate)₃)²⁻ [60]. A strict correlation between the content of these two forms and the properties of the preparations was not established at current stage of the study. Nevertheless, some regularities in the obtained data were observed:

• The higher was the concentration of oxalic acid in the preparation, the greater the amount of zirconium-89 activity was associated with the peak with Rf = 1.0 in Method 2.

• The higher was the pH value of the preparation (in the range of 1–7), the more zirconium-89 activity was associated with the peak with Rf = 1.0 in Method 2.

There was another interesting effect that we observed in our work when using Method 1. With a decrease in the concentration of hydrochloric acid in zirconium-89 solution, an increasing part of the activity remained on the chromatogram origin (see Supplementary Materials, Figure S1). Thus, Method 1 probably makes it possible to evaluate the relative content of various hydrolyzed forms of zirconium-89 in solutions.

2.3. Refinement of Zirconium-89 Solutions with Chelex-100 Resin

It has been shown that zirconium can be sorbed on a Chelex-100 resin from an oxalic acid solution at low pH values [52]. With pH 0–1, the distribution coefficient of zirconium on Chelex-100 was about 500 mL/g for 0.1 M oxalic acid (about 10 mL/g for citric acid). With pH increasing, the value of the distribution coefficient dropped significantly and reached a value close to 1 mL/g if pH > 2 for citric acid and at pH ≥ 4 for oxalic acid. Based on the data presented, we assumed that zirconium-89 can be effectively sorbed on Chelex-100 resin from oxalic acid solutions (obtained after a hydroxamate resin), and then effectively desorbed with solutions of sodium oxalate or sodium citrate. Experimental data confirmed our assumption and showed that, when [⁸⁹Zr]Zr-oxalate solutions in 0.1 M oxalic acid (obtained after ZR-resin) were passed through a column filled with Chelex-100 resin, 98 ± 1% of the activity remained on the column. Zirconium-89 could then be effectively eluted from the column with 0.1 M sodium oxalate solution (~97%) in 500–600 μL. Moreover, the activity loss at this stage could be reduced to a negligibly small portion (<0.5%) when using 0.1 M oxalic acid to wash the column after zirconium-89 sorption. However, when using 0.1 M HCl for the same purpose, the loss during washing was higher—2–3%.

Experiments on zirconium-89 sorption on Chelex-100 resin in static conditions were carried out at time points of 5, 10, 20, 30, and 60 min. The results show that after 20 min there were no further changes in the distribution of zirconium-89 between the phases. Therefore, the time point of 30 min was chosen for distribution coefficients determination. Experiments on the effect of oxalic acid concentration on the distribution coefficients (Dg) of zirconium-89 on the Chelex-100 showed that this dependency had a maximum, and the highest Dg ~ 700 was reached at 0.5 M oxalic acid concentration (Figure 1).

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Figure 1

Dependence of zirconium-89 distribution coefficients (Dg) on oxalic acid concentration for Chelex-100 resin.

To recover zirconium-89 from Chelex-100, resin solutions of sodium salts of various carboxylic acids were assessed. Experimental data show that the highest yield in activity could be achieved using sodium oxalate and citrate solutions (Figure 2).

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Figure 2

Dependence of zirconium-89 elution efficiency using different sodium carboxylates solutions as eluents with Chelex-100 resin (load from 0.5 M oxalic acid medium: losses at the sorption step—0.7%; losses at the washing step (0.1 M oxalic acid)—0.3%).

When using 0.1 M Na₃Citr as an eluent, 94 ± 2% of sorbed zirconium-89 activity could be obtained in 350–400 μL (see Supplementary Materials, Figure S3).

Figure 3 demonstrates the dependency of zirconium-89 recovery from Chelex-100 on the concentration of sodium citrate in the eluent.

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Figure 3

Dependence of zirconium-89 elution efficiency from Chelex-100 on sodium citrate concentration in eluent.

As it can be seen from the experimental data, when the concentration of sodium citrate in the eluent was 0.05 M elution, efficiency was about 85%. Starting with 0.2 M, it reached its maximum (97 ± 2%) and then plateaued. Bearing in mind the data of El-Sweify et al. [52], it is highly probable that this dependence is actually associated not so much with a change in the actual concentration of sodium citrate, as with a change in the pH value of eluents after being passed through the column. For example, pH of 1.0 M sodium citrate solution was 9.2 before entering the column and 6.8 after leaving the column, and pH of 0.1 M sodium citrate solution was 8.9 before entering the column and 5.1 after leaving the column (given that after [⁸⁹Zr]Zr-oxalate in 0.1 M oxalic acid (obtained after ZR-resin) the column was rinsed with 0.1 M HCl).

In terms of the application of Chelex-100 resin for converting zirconium-89 to the non-oxalate form, washing the resin after passing oxalic acid solutions is important. Comparison of various washing solutions showed that the best results could be obtained using 0.1 M HCl–0.1 M H₃Citr (1:1) for washing the column. Losses of the activity at the washing stage in this case were negligible (≤0.5%) (for more detailed information, see Figure S4 in the Supplementary Materials).

It is important to note that, when [⁸⁹Zr]Zr-citrate preparations in 0.1–1.0 M citric acid obtained after Chelex-100 resin were analyzed using TLC Methods 1 and 2, two features were observed:

(1) When using Method 1, the peak that moved with the solvent front was often characterized by the significant tailing, which complicated the interpretation of the chromatogram (this method is probably not the best one for preparations such as these).

(2) When using Method 2, the chromatographic pattern was sharp enough and no “doubling” of the peak was observed at the solvent front (which took place when evaluating [⁸⁹Zr]Zr-oxalate preparations) (see Supplementary Materials, Table S5).

2.4. Comparison of Zirconium-89 Preparations Obtained with Different Methods

Based on the data presented in this paper, we propose three methods for preparation of zirconium-89 solutions (for more detailed information, see Figure S5 in the Supplementary Materials):

• using ZR-resin only (0.1–0.115 M oxalate anion concentration; 0.5 M oxalic acid is necessary if the combined method is further implemented);

• combination of ZR-resin and Chelex-100 (0.1–0.116 M oxalate-anion concentration); and

• combination of ZR-resin and Chelex-100 (0.1–1.0 M citrate-anion concentration).

For ease of further interpretation of the results, the term “radiochemical impurities” of zirconium-89 solutions for radiopharmaceutical purposes should be introduced, by analogy with other solutions of radionuclides for labeling (e.g., “Gallium (⁶⁸Ga) chloride solution for radiolabeling” or “Yttrium (⁹⁰Y) chloride solution for radiolabeling”; EDQM, Ph. Eur.). “Radiochemical impurities” assumed to be the sum of all zirconium-89 forms that are “inactive”, i.e., cannot participate in labeling reaction (colloidal form).

Bearing in mind that radiochemical purity is the proportion of the total radioactivity in the sample, which is present as the desired radiolabeled species, in the case of zirconium-89 in radiopharmaceutical preparations, radiochemical purity is the proportion of zirconium-89 presented in “active” form. Regardless of method used to prepare a sample of zirconium-89, for a number of the preparations, there is one important stability feature to be noted. If according to Method 1 RCP ≤ 100% and according to Method 2 RCP = 100%, then over time RCP (Method 2) remains equal to 100% while RCP (Method 1) drops to 0%. As soon this situation occurs (RCP (Method 1) = 0%, RCP (Method 2) = 100%), the zirconium-89 activity presented in the solution begins to drop, being settled on the surface of the vial (in our case, Eppendorf polypropylene tubes). In this case, further changes in the chromatographic picture according to both methods were not observed. In 24 h, the amount of zirconium-89 remaining on the surface of the vial (in the case of quantitative transfer of the entire volume of the preparation) is in the 20–40% range.

This settled on the surface activity of zirconium-89 can be easily returned to the solution by adding 0.1 M HCl. As a rule, when formulating preparations of zirconium-89 in an oxalate solution, if the RCP value according to Method 1 was in the range of 95–99%, then its drop in time to 0% was extremely slow (more than 14 days). If this RCP value was in the range of 90–95%, then the drop took about 9–10 days. With RCP less than 90%, the drop took 2–7 days. Thus, for the preparations obtained by each of the proposed methods, the maximum pH value was the one allowing obtaining preparations with RCP (Method 1) ≥ 90%, RCP (Method 2) ≥ 99%. When studying the stability of the preparations, we decided that a preparation could not be stored beyond the moment when the following values were achieved: RCP (Method 1) = 0%, RCP (Method 2) = 100% (and in any case if RCP (Method 2) ≤ 99%). For an example of changing the chromatographic behavior of [⁸⁹Zr]Zr-oxalate preparations, obtained using various methods, during their storage, see Supplementary Materials, Table S6.

It is noteworthy that, unlike [⁸⁹Zr]Zr-oxalate samples obtained using ZR-resin, samples obtained using Chelex-100 resin exhibited chromatographic behavior similar to that of [⁸⁹Zr]Zr-oxalate preparations obtained from the original zirconium-89 solution in HCl by adding oxalic acid with further neutralization (see Supplementary Materials, Table S4). The main characteristics of the proposed processes are presented in Table 3.

Table 3

The main characteristics of the proposed processes for formulating zirconium-89 solutions for radiopharmaceutical preparations.

Formulation Method	Total Yield of 89Zr, %	pHmax.	Shelf Life
ZR-resin only (0.1 M oxalic acid)	90 ± 2%	5.0 ± 0.5	8–9 days
ZR-resin + Chelex-100 (0.1 M sodium oxalate)	93 ± 2%	6.0 ± 0.5	>10 days
ZR-resin + Chelex-100 (0.1 M sodium citrate)	90 ± 1%	5.0 ± 0.5	3–4 days
ZR-resin + Chelex-100 (1.0 M sodium citrate)	94 ± 2%	6.5 ± 0.5	6–7 days

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Over time, only for a zirconium-89 obtained in the form of 0.1 M sodium citrate solution (pH 6.5), the formation of an impurity (colloidal zirconium-89 hydroxide) was observed using Method 2. For all other methods of preparation RCP (Method 2) ~ 100%, no changes in time were observed. It is noteworthy that, with the same concentration of oxalate anions in the solution, the preparations obtained with the combination of ZR-resin + Chelex-100 made it possible to achieve higher pH values (6.5 ± 0.5) in the final solution, compared with the method of using only ZR-resin (pH 5.0 ± 0.5). In addition, these solutions were stable for a much longer time. This effect could be related to the presence of organic impurities. Another possible explanation is the difference between forms of zirconium-oxalate complexes presented in the preparations obtained using ZR and Chelex-100 resins. This is the subject of further research. At this stage of research, the method using ZR-resin only was left solely for comparison.

To assess the suitability of zirconium-89 preparations obtained using the proposed methods for the synthesis of radiopharmaceuticals, we carried out experiments to evaluate the efficiency of complexation of zirconium-89 in these preparations with DFO (estimated using the DFO titration method). The pH of the reaction mixture for each preparation was 5.5 (i to compare the combined methods (ZR-resin + Chelex-100) with ZR-resin only method). The incubation time was 15 min. The volume activity of zirconium-89 in all samples was 4.0 ± 0.5 MBq/mL. The volume of the reaction mixture was 1 mL. The results of the experiment are presented in Figure 4.

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Figure 4

The dependence of [⁸⁹Zr]Zr-DFO complex formation yield on the amount of chelator for various formulations of zirconium-89.

Experimental data show that, for all three zirconium-89 preparations with 5 μg DFO, a quantitative yield of the complexation reaction was observed (99–100%). However, with a decrease in the chelator concentration, the difference in the efficiency of complexation for the three formulations of zirconium-89 became apparent. An amount of 2.5 μg allowed achieving a complexation yield of the zirconium-89 preparation using ZR-resin only procedure (0.1 M oxalic acid) of 94%; for ZR-resin + Chelex-100 procedure (0.1 M sodium oxalate), the complexation yield was 88%; and, for ZR-resin + Chelex-100 procedure (0.1 M sodium citrate), the complexation yield was 99%. In general, zirconium-89 preparations, formulated in 0.1 M sodium citrate, showed greater efficiency of complexation than oxalate preparations. It is noteworthy that, in the preparations of zirconium-89 in oxalate solution, the preparations obtained by the combined ZR-resin + Chelex-100 method (0.1 M sodium oxalate) showed a lower efficiency of complexation than the obtained ZR-resin only procedure (0.115 M oxalic acid). To a certain extent, this is consistent with the resulting difference in the stability of these solutions. One possible explanation may be that the preparations obtained by the combined ZR-resin + Chelex-100 procedure (0.1 M sodium oxalate) and ZR-resin only procedure (0.1 M oxalic acid), even under the same conditions of oxalate concentration and pH values, contain different mixtures of complexes of zirconium-89 and oxalate anion with different stabilities.

According to our data, to achieve a quantitative yield of the [⁸⁹Zr]Zr-DFO formation reaction, a much larger amount of chelator was needed than, for example, presented by Holland et al. [47]. Probably, this difference was due to the non-optimal pH value chosen in our case (pH 5.5, while, according to the literature data, pH ~ 7 is optimal for the formation of [⁸⁹Zr]Zr-DFO complex). Nevertheless, very encouraging results were obtained using zirconium-89 formulated in sodium citrate solutions (0.1–1.0 M). pH 5.5 was used to observe the conditions under which the chromatographic behavior of the applied zirconium-89 solutions is the same.

It is important to note that Method 2 was not suitable for analyzing reaction mixtures in the case of labeling reactions, when one or another chelating agent (for example, DFO) was added to the zirconium-89 solution (see Supplementary Materials, Table S7). In this system, there was no difference in the chromatographic behavior of both the initial solution of zirconium-89 (blank solution) and the reaction mixture with the addition of DFO (no matter how well the complexation proceeded according to the results of the analysis using Method 1). This may be due either to the fact that the [⁸⁹Zr]Zr-DFO complex in it had the same mobility as [⁸⁹Zr]Zr-oxalate (Rf = 1.0), or [⁸⁹Zr]Zr-DFO complex quickly and completely degraded when contacting the eluent (which is less likely).

Another important aspect is the fact that, if [⁸⁹Zr]Zr-oxalate was used for complexation, the data obtained by Method 1 and by iTLC-SA/50 mM EDTA (pH 5) method practically coincide (since Method 2 does not allow evaluating the efficiency of complexation reaction, we decided to supplement the analysis of samples containing DFO with one more method). However, in the case of using [⁸⁹Zr]Zr-citrate solutions, the iTLC-SA/50 mM EDTA system (pH 5) also turned out to be ineffective. Of course, to some extent, yields of [⁸⁹Zr]Zr-DFO formation could be evaluated by the shape of the peak at the start of the chromatogram (which became much narrower), but this was not a sufficient analytical signal. Thus, the question of selecting adequate systems for analyzing various radiopharmaceutical preparations based on zirconium-89 remains a sticking point.

Since today there are publications describing the possibility of synthesizing zirconium-89 complexes with macrocyclic ligands (DOTA, etc.) exhibiting high stability [48,50], and such reactions require heating, we studied the stability of the preparations obtained by using zirconium-89 when heated. From the results, zirconium-89 preparations in 0.1 M sodium citrate solution (pH 6) did not withstand heating, in contrast to 1.0 M sodium citrate solutions and 0.1 M sodium oxalate solutions with the same pH values. After 30 min of incubation at 95 °C, when analyzed by both TLC methods, a large fraction of zirconium-89 activity remained at the start of the chromatogram (~45% in Method 1; ~40% in Method 2). This fact is likely evidence of the hydrolysis of zirconium-89 occurring under the given conditions (for more detailed information, see Table S8 in the Supplementary Materials). In the case of the use of these samples for further labeling of DFO, this fact is not a significant drawback, since the complexation reaction proceeded at room temperature. In general, heating was not possible at all in direct labeling of monoclonal antibodies with zirconium-89. However, in relation to obtaining zirconium-89 complexes with macrocyclic chelators (DOTA, etc.), the procedures for the preparation of zirconium-89 solutions proposed in this study were unsuitable. In this case, it was necessary to use 1.0 M sodium citrate solution. For samples of zirconium-89 formulated in 0.1 M sodium citrate solution, temperature sterilization was also unacceptable.

2.5. Relation between Chromatographic Behavior of [⁸⁹Zr]Zr-Oxalate Preparations and Their Biodistribution

In the course of this work, as noted above, we repeatedly noted a significant difference in the chromatographic behavior of zirconium-89 preparations in various chromatographic systems. The difference between results obtained in Method 1 and Method 2 is of particular interest.

Quite often, especially in the pH range of 5–8 and with low oxalate anion concentrations (≤0.5 M), when analyzing preparations using Method 1, the greater activity peak (up to 100%) was detected at the start of the chromatogram. This should count in favor of the fact that zirconium-89 in the preparation underwent hydrolysis and was not capable of further complexation. At the same time, when analyzing the same samples according to Method 2, all the activity applied to the chromatographic strip moved with the solvent front. The first thing assumed was the idea that Method 1 showed the presence of colloidal zirconium-89 and, in Method 2, the dissolution of these hydrated zirconium-89 forms occurred due to the presence of acid (4% TFA (v/v). This dissolved fraction of zirconium-89 was then transformed into the ionic form. Another assumption was that Method 1, for all its popularity in the scientific literature, did not reflect the nature of zirconium-89 forms in samples adequately, in contrast to Method 2. It is known that if a metal radionuclide in a preparation (in radiopharmaceutical) undergoes hydrolysis to form a colloidal form, there will be two observations to be made during further experiments. Firstly, this form will obviously remain at the start of the radio-chromatogram when analyzed by thin-layer chromatography. Secondly, when administered to animals, there will be an accumulation of the activity in the liver and, less frequently, in the lungs as a result of the seizure of colloids by cells of the reticular-endothelial system.

To establish the correlation between the chromatographic behavior of zirconium-89 preparations and their biodistribution, a series of biological experiments were conducted. Various preparations were introduced to laboratory animals. The result of these experiments allowed assessing the adequacy of the chromatographic systems used.

Table 4 presents the results of the biological distribution of three representative preparations of [⁸⁹Zr]Zr-oxalate.

Table 4

Relation between chromatographic behavior of [⁸⁹Zr]Zr-oxalate preparations and their biodistribution evaluated using ex vivo direct radiometry.

Method	[89Zr]Zr-Oxalate Sample 1		[89Zr]Zr-Oxalate Sample 2		[89Zr]Zr-Oxalate Sample 3
	pH 5.5		pH 7.0		pH 9.0
Chromatography (Radio-TLC)
iTLC-SG/50 mM DTPA (pH 7.0) Method 1
	RCP ~ 100%		RCP ~ 0%		RCP ~ 0%
iTLC-SG/CH3OH-H2O (1:1), 4% TFA (v/v) Method 2
	RCP ~ 100%		RCP ~ 100%		RCP < 30%
Biodistribution (ID/g, %)
Organ/Tissue	Time after Intravenous Administration
	1 h	24 h	1 h	24 h	1 h	24 h
blood	3.57 ± 0.61	2.19 ± 0.30	3.36 ± 0.60	2.15 ± 0.19	0.99 ± 0.12	0.13 ± 0.02
lungs	1.22 ± 0.29	1.14 ± 0.19	1.54 ± 0.35	1.12 ± 0.09	1.05 ± 0.30	0.17 ± 0.08
heart	1.70 ± 0.16	1.09 ± 0.14	1.42 ± 0.39	1.06 ± 0.11	0.05 ± 0.01	0.11 ± 0.03
stomach	0.47 ± 0.16	0.30 ± 0.05	0.39 ± 0.01	0.25 ± 0.02	0.27 ± 0.07	0.04 ± 0.01
liver	0.68 ± 0.20	0.93 ± 0.05	0.77 ± 0.19	0.88 ± 0.07	5.12 ± 1.81	4.88 ± 1.07
kidney	0.59 ± 0.11	1.52 ± 0.24	0.65 ± 0.16	1.19 ± 0.82	0.27 ± 0.11	0.60 ± 0.29
bladder	0.21 ± 0.01	0.32 ± 0.17	0.34 ± 0.11	0.48 ± 0.22	0.11 ± 0.06	0.06 ± 0.02
s. intestine	0.47 ± 0.02	0.42 ± 0.07	0.52 ± 0.15	0.39 ± 0.06	0.22 ± 0.07	0.06 ± 0.02
l. intestine	0.18 ± 0.01	0.55 ± 0.14	0.22 ± 0.15	0.38 ± 0.11	0.06 ± 0.03	0.10 ± 0.01
muscle	0.11 ± 0.05	0.11 ± 0.01	0.22 ± 0.03	0.14 ± 0.03	0.05 ± 0.01	0.02 ± 0.01
femur	0.26 ± 0.08	0.95 ± 0.25	0.37 ± 0.27	0.97 ± 0.17	0.14 ± 0.02	0.27 ± 0.04

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The results of radio-chromatography show that, in Sample 1, according to both methods, all zirconium-89 was in the “active” ionic form and its RCP was about 100%. In Sample 2, according to the results of Method 1, all zirconium was in “inactive” form (highly hydrated, RCP ~ 0%), while Method 2 still indicated RCP of 100% in the preparation. The results of direct radiometry of the mice organs 1 and 24 h after intravenous administration show that the difference in the biological behavior of Samples 1 and 2 was absent (within error margins). No increase in Sample 2 accumulation in the liver was observed compared to Sample 1. In Sample 3, Method 1 chromatography data demonstrate that its RCP was 0%. According to Method 2, ~60% of Sample 3 activity stayed at the origin of chromatogram. This part of zirconium-89 activity could be associated with the presence of zirconium-89 in colloidal form. The direct radiometry data show a significant difference in the biodistribution of this sample compared to Samples 1 and 2. As expected, the accumulation of the preparation occurred mainly in the liver. The accumulation in other organs and tissues for this preparation was significantly lower than that of Samples 1 and 2. This fact suggests that Method 2 gave a real indication of the presence or absence of zirconium in the preparation in the “active” ionic form. The suitability of Method 1 in this case was extremely doubtful.

Another series of experiments (Table 5 and Figure 5) gave a more visual representation in the difference in the biodistribution of zirconium-89 samples, since laboratory animals were studied using μPET. Table 5 presents the chromatographic data of the most representative samples.

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Figure 5

μPET maximum intensity projections of mice after 24 h p.i. of [⁸⁹Zr]Zr-oxalate samples listed at Table 5: (a) Sample 1; (b) Sample 2; (c) Sample 3; and (d) Sample 4.

Table 5

Radio-TLC chromatograms of representative [⁸⁹Zr]Zr-oxalate samples (prepared for in vivo μPET imaging (Figure 5) obtained using both methods.

Method	[89Zr]Zr-Oxalate Sample 1	[89Zr]Zr-Oxalate Sample 2
iTLC-SG/50 mM DTPA(pH 7.0) Method 1
	RCP ~ 100%	RCP ~ 0%
iTLC-SG/CH3OH-H2O (1:1), 4% TFA (v/v) Method 2	RCP ~ 100%	RCP ~ 100%
	[89Zr]Zr-Oxalate Sample 3	[89Zr]Zr-Oxalate Sample 4
iTLC-SG/50 mM DTPA (pH 7.0) Method 1
	RCP ~ 0%	RCP ~ 0%
iTLC-SG/CH3OH-H2O (1:1), 4% TFA (v/v) Method 2
	RCP ~ 90%	RCP ~ 0%

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As in the previous series of experiments, Sample 1 had an RCP of 100% according to both methods. Sample 2 according to the results of Method 1 had an RCP ~ 0%, whereas, according to Method 2, its RCP was 100%. The results of µPET 24 h after administration (Figure 5a,b) of these preparations indicate that there was no difference in the biodistribution of these samples: only the skeleton was visualized on tomograms. The accumulation was increased in the areas of active physiological bone tissue metabolism (bone epiphyses) in both cases. Samples 3 and 4, according to Method 1, had zero RCP. At the same time, the results of Method 2 indicate that in Sample 3 about 10% of zirconium-89 might be presented in hydrolyzed form, and in Sample 4, almost all of it was present in hydrolyzed form.

The results of µPET 24 h after Sample 3 administration (Figure 5c) indicate that most of the accumulated activity was associated with the bone tissue of the animal, but the liver is also clearly visualized on the tomogram. On a tomogram obtained 24 h after Sample 4 administration (Figure 5d), only the liver can be seen.

At this stage, we can confidently say that determining the content of unbound zirconium-89 in radiopharmaceutical preparations ([⁸⁹Zr]Zr-labeled antibodies) using Method 1 did not provide an adequate estimation of unbound zirconium-89 forms. Method 2 gave more complete and adequate estimation of the content of zirconium-89 forms in a preparation. Using this method, the presence of “inactive” hydrolyzed forms of zirconium-89 could be clearly evaluated.

3. Discussion

The implementation of radiopharmaceuticals based on zirconium-89 (especially labeled monoclonal antibodies) into clinical practice will allow us to bring the effectiveness of radionuclide diagnostics of various diseases to a new level. The growing interest in this radionuclide, the development of new chelating agents for it, and preclinical and clinical studies of various [⁸⁹Zr]Zr-based radiopharmaceuticals suggest its high potential for the needs of nuclear medicine. Therefore, the question of obtaining solutions of zirconium-89 in a suitable and convenient form for radiopharmaceutical purposes is extremely important.

Meijs et al. described the first separation of zirconium-89 from yttrium with an in house prepared hydroxamate resin by eluting the n.c.a. radiozirconium with 1.0 M oxalic acid [46]. The authors studied different eluents (oxalic acid, acetate and citrate solutions) for ^88/89Zr removal from the resin, and found oxalic acid to have the best elution efficiency. Increasing the oxalic acid concentration from 0.01 to 1.0 M raised the percentage of zirconium-89 eluted from the column from ~20% to 98% (with oxalic acid concentration of 0.5 M the elution of zirconium-89 was nearly quantitative (95%)). The ability of citrate to remove radiozirconium from “hydroxamate material” was found to be not only concentration- but also pH-dependent: at pH 4.0, transchelation occurred (80% at 1 M), but, at lower pH values, the transchelating capacity was less. It also decreases smoothly with a decrease of citrate concentration in the eluent. Holland et al. showed that [⁸⁹Zr]Zr-oxalate in the form of 1.0 M oxalic acid solutions obtained using hydroxamate resin have high chemical and radionuclide purity, and are suitable for obtaining complexes with deferoxamine with high molar activity (no effect of oxalic acid concentration on the yield of the complexation) [47]. The yield of complexation was close to quantitative at a concentration of deferoxamine higher than 0.03 μg (0.04–0.07 μg). Elution of zirconium-89 from hydroxamate resin was achieved with 99.5% recovery of the radioactivity by transchelation with 1.0 M oxalic acid. Attempts to elute the activity with lower than < 0.5 M had no effect. Only partial recovery of zirconium-89 activity (13–34%) was achieved by using oxalic acid concentrations of 0.5–0.75 M. Later, O’Hara et al. showed that, at 0.8 M H₂C₂O₄, Kd for zirconium-89 was < 2 mL/g and 0.8 M H₂C₂O₄ eluent solution concentration is adequate [61].

ZR-resin (TrisKem International) is probably the only commercially available hydroxamate resin today [49]. It is important that according to the data provided by the manufacturer zirconium-89 can be eluted from the resin with a solution of oxalic acid with a concentration of 0.05–0.1 M (less than in generally accepted methods [46,47]) in a small volume (1–1.5 mL). It should be noted that according to the literature the solution with a sodium oxalate concentration of 1.55% (0.116 M) is isotonic [62,63]. When using a solution of this composition, there is no visible deformation of blood cells or their dysfunction. It has been shown that the use of sodium oxalate solution with a concentration even lower than isotonic (1.1%) does not induce visible deformations of blood cells [64]. Thus, from the physiological point of view, the concentration of sodium oxalate in the hypothetic [⁸⁹Zr]Zr-oxalate preparation should be in the range of 1.1–1.55% (10.1–15.5 mg/mL) in the absence of additional osmolytes. The estimated (theoretical) lethal dose of sodium oxalate for an adult patient is 15–30 g, but the lowest lethal dose reported is 5 g [65]. Healthy volunteers (women) who received 120 mg of sodium oxalate per day for three days did not have any health problems [66]. For a human, sodium oxalate LD₁₀ is 17 mg/kg when administered intravenously [65]. Thus, when 1 mL of [⁸⁹Zr]Zr-oxalate solution with an oxalate ion concentration of 0.1 M is administered to a patient intravenously, the injected amount of oxalate ion will be almost 90 times less than LD₁₀ (assuming an average adult weight is 70 kg). These data are also in favor of using 0.1 M oxalic acid to isolate zirconium-89 and, accordingly, in favor of using ZR-resin. Unfortunately, the results of our experiments showed that the concentration of oxalic acid of 0.1 M is insufficient for the complete elution of zirconium-89 from this resin. Another important feature found in the course of this work was that the samples of [⁸⁹Zr]Zr-oxalate preparations, obtained using ZR-resin, exhibit chromatographic behavior differing from [⁸⁹Zr]Zr-oxalate preparations with the same oxalic acid concentration prepared from the origin solution [⁸⁹Zr]Zr-cloride (Dowex).

Implication of Chelex-100 resin after using ZR-resin allows obtaining [⁸⁹Zr]Zr-oxalate preparations with chromatographic behavior of those obtained without using ZR-resin. At the same time, these samples are stable for a long period of time and can withstand raising the pH up to 6.0 ± 0.5. In the course of this work, we also found conditions that make it easy and effective to reconstitute [⁸⁹Zr]Zr-oxalate to [⁸⁹Zr]Zr-citrate using Chelex-100 resin. [⁸⁹Zr]Zr-citrate solutions obtained (especially those in 1 M sodium citrate) are stable enough and are not affected by the increase of pH up to 6.5 ± 0.5, which is convenient for their use in further processing for obtaining radiopharmaceuticals (labeled antibodies). When comparing [⁸⁹Zr]Zr-oxalate and [⁸⁹Zr]Zr-citrate preparations with the same carboxylic acid concentration it can be seen that [⁸⁹Zr]Zr-citrate is less stable than [⁸⁹Zr]Zr-oxalate. However, [⁸⁹Zr]Zr-citrate shelf life is still long enough for possibility of its centralized supply to clinics. Moreover, when comparing the effectiveness of complexation with DFO, [⁸⁹Zr]Zr-citrate showed higher yield than [⁸⁹Zr]Zr-oxalate. Our results are to some extent consistent with the published data on the determination of the stability constants of zirconium complexes. For example, Kobayashi et al. showed that zirconium oxalate complexes have the stability constants of 11.5, 20.8, 27.2 and 29.7 for [Zr(oxalate)]²⁺, [Zr(oxalate)₂]⁰_aq., [Zr(oxalate)₃]²⁻ and [Zr(oxalate)₄]⁴⁻, respectively [60]. Omar et al. observed the formation of a single complex zirconium-citrate complex with ratio 1:1 [67]. The stability constant of this complex determined by various methods was 7.4–7.6, which is lower than that of zirconium-oxalate complexes. At pH 6.0–7.0, macroscopic Zr⁴⁺ is known to undergo hydrolysis to the tetranuclear complex [Zr₄(OH)₈(OH2)₁₆]⁸⁺ with further polymerization [51]. Therefore, papers on the determination of the stability constants of zirconium complexes where the formation of polynuclear forms is not mentioned cause some concern. On the other hand, in the case of solutions of non-carrier added zirconium radionuclides (microconcentrations), the formation of polynuclear forms is less likely, thus it is acceptable to focus on the published values of the stability constants of mononuclear complexes. It is not clear what causes the difference in the chromatographic behavior and the effectiveness of [⁸⁹Zr]Zr-DFO complex formation. It can be due to the presence of an organic impurity that get into the preparations when using ZR-resin or to the difference in the set of zirconium-89 oxalate complexes in various methods of preparation.

Meijs et al. described the methods for removing oxalic acid from the final solution and evaluated the effect of the method of preparing of radiozirconium solution on the effectiveness of complexation with deferoxamine [46]. With zirconium-89 isolated by hydroxamate method before removal of oxalic acid (the final oxalic acid concentration was 0.2 M), the complexation capacity of deferoxamine was too low to quantitatively form a complex—only about 90% at 10 mM. The authors described lengthy procedures for the production of [⁸⁹Zr]Zr-chloride from purified [⁸⁹Zr]Zr-oxalate involving decarboxylation of the excess oxalic acid with H₂O₂ in 6 M HCl at 80 °C followed by drying of the reaction mixture at room temperature in vacuo or, alternatively, by the use of room temperature vacuum sublimation techniques at 26.7 mPa. The decarboxylation method gave zirconium-89, which was able to form complexes with a very low yield (<60%) only at very high deferoxamine concentration (>10 mM). The sublimation method resulted in zirconium-89, which formed complexes at very low deferoxamine concentrations (yield > 90% at 10 μM of deferoxamine). Interestingly, zirconium-89 isolated with the anion-exchange method (Dowex) leads to quantitative complexation only at high deferoxamine concentrations. Holland et al. also presented a method of reconstitution [⁸⁹Zr]Zr-oxalate to [⁸⁹Zr]Zr-chloride which is much simpler and more convenient [47]. Zirconium-89 can be removed from oxalic acid solution with 100% efficiency by trapping on an activated a Sep-pak QMA strong anion exchange cartridge. No less than 99.8% of the oxalic acid was then removed by washing the cartridge with a large volume of water, and the activity was eluted with 100% recovery of zirconium-89 with 300–500 μL of 1.0 M HCl(aq.). Standard 0.9% saline can also be used to elute zirconium-89 activity, but the recovery of activity was found to be less efficient (22–38% in 500 μL of saline). The acid can be removed rapidly by boiling the eluate at 110 °C under a continuous stream of argon, then reconstituted in 0.9% saline or 0.1 M HCl(aq.) for further labeling. This method allows to find the effect of the nature of the initial zirconium-89 solution on the complexation efficiency with DOTA [48]. When using [⁸⁹Zr]Zr-oxalate (diluted aliquot of 1.0 M H₂C₂O₄) the complexation with DOTA (99 °C, 120 min, pH 7.0–7.5 (1 M Na₂CO₃)) yield was only 65 ± 9.6%, whereas with [⁸⁹Zr]Zr-chloride (90 °C, 45 min, PH 6.9–7.2 (0.5 M HEPES)) it was 100%. Thus, it becomes obvious that methods of preparation of zirconium-89 formulations are able to influence their suitability for further synthesis of radiopharmaceuticals.

A particularly interesting fact discovered during this work is, in our opinion, the demonstrated features of the chromatographic behavior of various zirconium-89 preparations (and, in particular, after reformulation with a QMA-cartridge) and the interrelation of the chromatographic behavior of zirconium-89 preparations and their biodistribution. Undoubtedly, this question needs further, more detailed research. When the chemical form of the zirconium-89 in formulations is not reliably clear, the results of the study of its biodistribution are also very contradictory. For example, according to Holland et al., when [⁸⁹Zr]Zr-chloride is administered intravenously the accumulation of the activity occurs mainly in the liver [47]. The most probable explanation for that is the presence of zirconium-89 in colloidal form. However, in the work of Abou et al., the accumulation of the activity ([⁸⁹Zr]Zr-cloride was administered intravenously as a solution in 0.9% saline, pH 7.2–7.4) was observed in soft tissues, and later on in the skeleton, and the accumulation of the activity in the liver was insignificant [68]. It remains unclear why in one case the hydrolyzed zirconium-89 does not dissolve, and in the other easily goes back to the ionic form. The biodistribution of [⁸⁹Zr]Zr-oxalate is described by Abou et al. as well [68]. The data are similar to our results (Table 4, Sample 1) to a certain degree, taking into account the fact that the parameters of the experiments are not exactly the same. However it can be seen that the pattern of the biodistribution of [⁸⁹Zr]Zr-oxalate preparations in [68] and in Sample 1 (Table 4) is the same: the radioactivity is primarily detected in blood and over time it accumulates in bones. Another example is the comparison of data presented by Bansal et al. [32] with those presented by Abou et al. [68]. According to Abou et al., after the administration of zirconium-89 phosphate within six days, the larger half of the activity was detected in the liver (~60%/g) and the spleen [68]. The data presented by Bansal et al. show that, after the intravenous administration of zirconium-89 phosphate, the larger half of the activity was presented in the liver and the bones [32]. Moreover, seven days post injection, the accumulation in the bones was considerably higher than that in the liver (~60%/g and ~30%/g, respectively). At this stage, it is clear that the use of Method 1 only (which seems to be very popular) is not enough for a real assessment of the radiochemical purity of zirconium-89 preparations. The method of analysis proposed by us (Method 2) gives a more detailed understanding of the speciation of zirconium-89 in the radiopharmaceuticals. Nevertheless, this method also cannot be used independently.

In addition to formulating the final solution of zirconium-89, the effective isolation of zirconium-89 from the irradiated yttrium target is also an important step. We admit the possibility of applying the method described by us to isolate zirconium-89 from the stock solution. The evaluation of the resin suitability for zirconium-89 separation from solutions of an irradiated target was not the goal of this work, and these experiments are in future plans. At the same time, the effectiveness of ZR-resin for the isolation of zirconium-89 from target solutions has already been demonstrated by Graves et al. [50], thus there is no reason to think that the purification in our case can go any other way. We did carry out experiments on metal impurities using model solutions (Y, Cu, and Fe added with the concentration of 25 mg/L) and MP-AES. It was found that with similar model solutions there were no differences in zirconium-89 recovery from Chelex-100 resin and ZR-resin (according to the method prosed in this work). In addition, the results of the quantitative determination of metal impurities showed that using Chelex-100 led to fine (additional) purification from Fe and Cu. Research on this subject are in progress.

4. Conclusions

Zirconium itself is a complex chemical element, and its isotope zirconium-89 is a non-conventional radionuclide for nuclear medicine. Considering that, even for radionuclides that are already firmly established in world clinical practice, for example, ⁶⁸Ga, there are still some ambiguities and features in the analysis of radiochemical purity of their preparations [69], much work remains to be done to optimize the methods and approaches to preparation and the quality control (radiochemical purity) of zirconium-89 based formulations.

5. Materials and Methods

Acknowledgments

Supplementary Materials

The following are available online, Table S1: Radio-chromatograms of different zirconium-89 – oxalic acid preparations with iTLC-SG/CH₃OH-H₂O (1:1), 4% TFA (v/v) system. Table S2: Radio-chromatograms of different zirconium-89 – HCl preparations with iTLC-SG/CH3OH-H2O (1:1), 4% TFA (v/v) system. Figure S1: Radio-chromatograms of different zirconium-89 preparations in HCl (iTLC-SG/50 mM DTPA pH 7.0). Figure S2: Elution profiles of ZR-resin column (50 mg, 50 mm × Ø2.1 mm) with oxalic acid of different concentrations. Table S3: Radio-TLC analysis results of [⁸⁹Zr]Zr-oxalate preparations obtained with ZR-resin and solutions of different oxalic acid concentrations. Table S4: Radio-TLC analysis results for [⁸⁹Zr]Zr-oxalate preparations obtained without and after ZR-resin. Figure S3: Chelex-100 column elution profile using 0.1 M Na₃Citr and 0.1 M Na₂C₂O₄ as eluents. Figure S4: The effect of various solutions used for column wash on recovery efficiency of zirconium-89 with Chelex-100 resin. Table S5: Radio-chromatograms of different [⁸⁹Zr]Zr-citrate preparations. Figure S5: The scheme of methods proposed for preparation of zirconium-89 solutions for radiopharmaceutical purposes. Table S6: Radio-TLC analysis results of [⁸⁹Zr]Zr-oxalate preparations during their storage. Table S7: Examples of analysis of the products of zirconium-89 reactions with DFO. Table S8: The results of the analysis of various preparations of zirconium-89 while keeping the samples at room temperature and when heated. Figure S6: The scheme of zirconium-89 reconstitution from oxalic acid solution into hydrochloric acid solution using Chromafix 30PS-HCO₃ anion-exchange cartridge. Table S9: Radio-TLC results (method 2) of zirconium-89 samples obtained in 1.0 M HCl using oxalate-free technology and using the reconstitution method from oxalic acid solution. Table S10: Radio-chromatograms in various systems. Zirconium-89 samples obtained in 1.0 M HCl using oxalate-free technology and those reconstituted from oxalic acid solution (pH = 6).

Author Contributions

Conceptualization, A.L.; formal analysis, A.L., V.B. and A.M.; investigation A.L., V.B., A.M., M.Z. and A.K.; project administration, G.K.; supervision, A.L. and G.K.; validation, A.L., V.B. and A.M.; visualization A.L., V.B. and A.M.; writing—original draft, A.L., V.B. and A.M.; and writing—review and editing, A.L. and G.K.

Funding

This research was financially supported by Ministry of Education and Science of the Russian Federation—State Contract No. 14.N08.11.0162.

Conflicts of Interest

The authors declare no conflict of interest. The founding sponsors had no role in the design of the study; in the collection, analyses, or interpretation of data; in the writing of the manuscript, and in the decision to publish the results.

Footnotes

References