Direct and indirect radiolabeling methods are available for single alpha-particle emitters. Since the nuclear recoil effect does not affect the spread of radioactive burden originating from the recoiling radioactive daughters, particularly the 211At, a halogen that uses chemistry similar to iodine is very attractive. Furthermore, the radiometals like 149Tb and several latter decay series members like 213Bi appear to be very promising. Radionuclides decaying by a series of several α decays release radioactive daughter nuclei from the radiopharmaceutical preparations due to the nuclear recoil effect. This effect complicates the labelling strategies and successful dose targeting. In its presence, both the pharmacokinetic properties of the radiopharmaceuticals and the strategies for elimination of the released radioactive burden need to be optimized.
3.1. Nuclear Recoil Effect and the Release of Daughter Nuclei
Due to the momentum conservation law, part of the decay energy is transferred to a daughter nucleus. An approximate value of this energy can be calculated by the mathematical relation:
where
Er is the recoil energy,
mα the rest mass of an α particle,
Mr mass of the recoil and
Q is the decay energy. The energy distribution ratio between the alpha particle and the recoiling atom is typically 98% to 2%. The amount of energy that the recoil atom reaches is some 100 keV and that is not negligible. Such energy is sufficient to break some 10,000 chemical bonds (assuming 10 eV/one bond). An example of such 109 keV recoil is the
219Rn with the range of some 88 nm in a water-like environment (e.g., cells or extracellular matrix). The comparison of LET and ion ranges of α particles and
219Rn recoils originating from
223Ra decay is shown in
Figure 1 and the ranges of
219Rn recoils in various materials are summarized in
Table 2. Simulations were performed using SRIM code [
36]. These factors have a direct impact on radiopharmaceutical stability and purity, as well as on dosimetry and daughter recoils’ distribution in tissues, especially when so called
in vivo generators are employed. In some cases the radioactive recoils are removed from the radiopharmaceutical preparations and their final formulations before use [
37,
38].
To mitigate the consequences of the nuclear recoil effect in the body, we propose three methods based on the corresponding theorems:
Theorem 1. Recoils spread mitigation by time—the spread of daughter radioactive ions takes time, so their spread in the organism would also depend on their half-life.
Proof of Theorem 1. The blood flow measured in terms of red blood cells velocity in capillaries ranges between about 1–3 mm/s [
39]. Taking into account this value as a reference for passive transport of radiopharmaceuticals in extracellular matrix or in a capillary blood stream, one may compare this displacement time and the half-life of the corresponding released daughter nuclide. While only one half of
219Rn atoms (T = 3.96 s) decay roughly in 4 s, the number of atoms of further decay series member
215Po (T = 1.78 ms) decreases to
1/
1000 of its initial amount in 17.8 ms, and it thus has practically no time to escape or to be translocated. Thus, the selection of nuclides with favorable decay properties determines this approach.
Theorem 2. Recoils spread mitigation by nanoconstruct size/material—daughter-recoiling nuclide consumes some of its energy while getting through the nanoconstruct.
Proof of Theorem 2. Depending on the nanoconstruct design the stopping power of various materials affects the recoils range. The material and size of the nanoconstruct thus determine the energy loss of recoils in nanoconstruct material. Not only the atomic structure but also the molecular structure and chemical-bond environment affect the stopping ability of the nanoconstruct as a whole [
36]. Furthermore, the recoil ion range in nanoconstruct material is limited and its energy is significantly decreased. In general, the stopping power increases with various parameters like atomic weight, electronic density, bond structure, etc. The advantage of spherical nanoconstruct geometry in terms of the stopping efficiency of the nanoconstructs is obvious, and the mother nuclide should be preferably placed in the nanoconstruct core. On the other hand, in case of surface-bonded radionuclide, the probability of daughter recoil ion back-implantation into the nanoconstruct is about 50%.
Theorem 3. Recoils spread mitigation by the nanoconstructs number/depot—even though the recoil ion may escape a nanoconstruct, the probability of its back-implantation or its implantation into surrounding nanoconstruct units is relatively high.
Proof of Theorem 3. In cases when time, nanoconstruct material and size are not sufficient to degrade the recoils energy completely, the released ions may be trapped by a depot of surrounding nanoconstructs or even as mentioned in Theorem 2, by the nanoconstruct itself. This proof is also supported by the fact that both surface and intrinsic labelling strategies yielded quite similar data on
in vitro stabilities results in terms of total released activity [
17]. This method is, however, limited to topical applications of radiopharmaceuticals based on larger nanoconstruct aggregates or agglomerates.
3.2. Labelling Chemistry
A fundamental concept of small molecule labelling, e.g., the antibody fragments, peptides and also surface-modified nanocarriers, is based on chelators conjugated throughout a spacer with the vector or the nanocarriers themselves. Spacers are aliphatic or aromatic moieties (C4–C10 or longer) able to establish chemical bonds (e.g., amides, esters, etc.) via nucleophilic substitution, amide formation using carboimides (e.g., dicyclohexylcarbodiimide, diisopropylcarbodiimide) or the Schotten–Baumann reaction of acylhalogenides with amines. The “click reactions” of azides with moieties containing triple bonds play the most important role, e.g., the Huisgen’s 1,3-dipolar addition at elevated temperatures resulting in 1,5- or 1,4-isomers, or Cu(I) catalyzed azide-alkine cycloaddition (preferably resulting in 1,4-product). Cycloaddition reactions help to establish a bond between the spacers and targeted moieties very quickly and efficiently.
Excellent chelators of trivalent metals are the azamacrocyclic ligands based on DOTA, NOTA or TETA analogues (e.g., carboxylic or phosphonic)—see
Figure 2. Most of them are commercially available with various spacer lengths and as protected (e.g.,
t-butyl or benzyl) or unprotected derivatives.
These chelators provide very fast trivalent ions complexation kinetics (e.g., Ga, Lu, Tb, Ac, Bi, etc.) depending on pH and temperature. Most of them are used with coordinated stable metals (e.g., Gd) as contrast agents in magnetic resonance imaging (MRI) and they are very often employed as chelators for diagnostic positron emission tomography (PET) radionuclides (e.g.,
68Ga) as well as beta decaying therapeutical nuclides (e.g.,
177Lu) [
40,
41,
42,
43,
44]. During the past few years macrocyclic ligands were also used in TAT as chelators suitable for
225Ac or
213Bi [
44,
45]. Thus, DOTA/NOTA like bifunctional chelators are fulfilling the theranostic concept according to which one chelator may be employed for multimodal diagnostic purposes or as α/β
− therapeutic agents. Concerning the α emitters, it is interesting that even though the energy released during α decay exceeds several hundred times the Me–C, Me–O or Me–N bond energy (Me—radiometal) and the recoils are released from the carrier,
in vivo experiments indicate that the use of such delivery systems is also feasible [
4,
46].
As already mentioned, labelling procedures proceed quite rapidly, taking dozens of minutes at laboratory or elevated temperatures (up to 95 °C) at pH = 1–5 depending on the central atom and also ligand structure. Several studies indicate that coordination of trivalent gallium by TRAP-Pr at pH = 1–3 and room temperature is more efficient than NOTA, DOTA, TETA analogues under similar conditions. Optimal labelling protocol was established within 10–30 min for
68Ga at pH = 3–4 (acetate or citrate buffer) at elevated temperatures (90–95 °C). It was also observed that the presence of trace metal impurities like Zn
2+, Cu
2+, Fe
3+, Al
3+, Ti
4+ or Sn
4+ does not significantly decrease the radiochemical yield while gallium labelling proceeds [
47,
48]. This ligand is, thus, promising also for other radiometals like
213Bi,
225Ac. However, under certain conditions macrocyclic ligands form mostly in-cage structures. Depending on the reaction conditions and basicity of the ligands, less thermodynamically stable out-of-cage structures may occur usually when the reaction has been performed at lower temperatures. Employing microwave irradiation may also significantly help to ensure faster formation of in-cage complexes. Experimental
225Ac-DOTA-PSMA-617 was synthesized in a microwave reactor at pH = 9 (
TRIS buffer) within 5 min with radiochemical purity over 98% and specific activity 0.17 MBq/nmol. Similar protocols were employed when synthesized
213Bi-DOTATOC and
213Bi-Substance P were synthesized, hexadentate DOTA-peptide conjugate being used [
49,
50]. Both
213Bi and
212Bi are considered for the purpose. A
212Pb-TCMC-trastuzumab conjugate was studied on patients with HER-2 receptor carcinoma and its toxicity, pharmacokinetics and dosimetry were investigated. However, the use of DOTA analogues as chelators of
225Ac or
213Bi did not solve the toxicity of daughter recoils. A very interesting alternative to the presented α emitters is the
149Tb, currently studied in a preclinical immunotherapy. Terbium-149 was separated from isobaric and other impurities including stable zinc by extraction with α-hydroxyisobutiric acid solution (pH = 4) and was directly added to DOTANOC (incubation: 15 min at 95 °C). Subsequent high-performance liquid chromatography (HPLC) confirmed an over 98% purity and high specific activity (5 MBq/nmol) of
149Tb-DOTANOC. A similar approach was used for
149Tb-DOTA-folate (incubation: 10 min at 95 °C) [
51,
52]. Labelling of monoclonal antibody CD20 rituximab with
149Tb in a mixture of ammonium acetate, ascorbic acid and phosphate-buffered saline (PBS) buffer (pH = 5.5) and 10 min incubation at room temperature resulted in 99% yield and specific activity of 1.11 GBq/mg. Conjugate
149Tb-rituximab was prepared using cyclohexane diethylene triamine pentaacetic acid (CHX-A”-DTPA) [
53]. This pentaacetic acid analogue is a very interesting ring-opening chelator used in several studies with
213Bi-HuM195 on patients with human myeloid leukemia. The TCMC and CHX-A”-DTPA chelators are shown in
Figure 3.
While
225Ac,
213Bi,
149Tb and other radionuclides may be easily coordinated using macrocyclic or DTPA chelating agents, efficient chelator for
223Ra, which is currently used in palliative treatment of bone metastasis of prostate cancer, is still not available. Thus, direct sorption of
223Ra onto surface or intrinsic labelling of nanocariers, e.g., nanohydroxyapatites, LaPO
4, SPIONs and others was investigated [
6,
8,
17]. Due to the problematic chemistry of
211At several studies were focused on the possibility of trapping astatine into a nanoconstruct (e.g., gold or silver nanoparticles (NPs),
211[email protected], TiO
2), attached to targeting vector via a linker [
54,
55,
56,
57]. Synthesized nanoconstructs might be stabilised with polyethyleneoxide or polyethylene glycol (PEG). Retention of the α emitter is also significant in liposomes, where about 81%
225Ac retention was observed but the recoil retention was not evaluated [
58]. Whereas both the labelling of nanoconstructs or liposomes and stabilization of recoils are quite efficient in comparison with small molecules, the stability of their dispersions (e.g., the hydrodynamic diameter) may significantly vary depending on used material.
3.3. Targeting and Clearance
Investigation of how to deliver short-range, high LET radiation to target sites is of key importance. Short α particle range in soft tissues favors their use in the therapy of small lesions, metastases or system-spread diseases like some kinds of leukemia. Depending on the biochemical properties of the radiopharmaceuticals, three targeting strategies could be defined:
Taking into account the half-lives of the therapeutic nuclides and the recoiling daughters, their circulation time, biodistribution and clearance play a critical role. Matching radionuclide half-lives and pharmacokinetic profiles of the vehicle systems remains a significant criterion [
61]. Radionuclides with half-lives long enough to allow differential tumor accumulation and possibly cellular internalization of radiolabeled molecules have some advantages in therapeutic application, but their toxicity for non-targeted sites should be minimized. The features of recoils’ distribution in the body was discussed by de Kruijff et al. [
62]. Pharmacokinetics of the injected radiopharmaceutical could be a function of both time and tumor size. As an example, the data of a preclinical study with
213Bi-DOTATATE in animals bearing small and large tumors (50 and 200 mm
3) using two tumor models: H69 (human small cell lung carcinoma) and CA20948 (rat pancreatic tumor) are demonstrated in
Figure 4 [
63].
Different approaches have been explored to inhibit the accumulation of both parent and daughter radionuclides in critical organs or acceleration of their clearance: co-injection of lysine with
213Bi-labelled conjugate can reduce kidney uptake of
213Bi [
64], bismuth citrate pre-treatment blocks renal retention of
213Bi [
65], and oral administration of BaSO
4 known as a coprecipitating agent of radium reduces the
223Ra accumulation in the large intestine [
66]. In some cases only locoregional therapy (not intravenous injection) is suited because of the large size or high hydrophilicity of the delivery agent, e.g., encapsulated liposomes or multi-layered nanoconstructs [
67]. Imaging methods with the potential for
in vivo evaluation of the pharmacokinetics of the radionuclides, such as single-photon emission computed tomography (SPECT)/PET/CT imaging are of great importance for assessing the outcome of the therapy.
3.4. Dosimetry
The absorbed dose is defined as an energy delivered to a unit of mass (see Equation (2)).
where the dose,
D is defined as a ratio of the energy
Ex deposited by the radiation passage to the matter in a unit of mass
mirr. This definition is however quite general and does not reflect the specific situation when α emitters and chain decays are used in TAT. This requires precise and accurate dose estimation on all levels, starting from whole body biodistribution down to subcellular level. The example of
223Ra decay that produces one α particle and recoiling
219Rn ion gives a clear picture of such situation. Let us assume that the cell density equals 1 g/cm
3, the mass
mirr. taken into dose calculation is expressed as the mass of a sphere with the diameter of the
219Rn recoil path, and the energy
Ex equals the recoil total energy deposition (109.5 keV). In the case of α particle, a sphere with the diameter of 20 µm (single cell dimension) and only partial energy deposition calculated on the basis of LET is considered. Thus the absorbed dose
D delivered by the
219Rn recoil corresponds to 40 kGy in such small volume (total deposited energy of 109.5 keV) while for the α particle it amounts only to 70 mGy over its single-cell path (though the total energy deposited by an alpha particle is 1.83 MeV). To compare the dose in the same mass (or volume), e.g., of one cell, the ratio of the doses delivered by a single α particle and
219Rn recoil turns then to 70 mGy to 4 mGy, respectively. Thus the implications for radionuclide targeting on the subcellular level (e.g., internalization into the nucleus or destruction of cell organelles) play an important role and the contribution of recoil ions should not be neglected. In general, the dosimetry should be evaluated separately in the following levels.
3.4.1. Body Level
In vivo whole body scans with α emitters may provide very helpful and quite detailed information on the pharmacokinetic and pharmacodynamic properties of radiopharmaceuticals [
68,
69]. Organ intake values, renal clearance or fecal excretion may be evaluated in this way and the recoil release could be possibly visualized by employing the multiple energetic windows data analysis.
3.4.2. Organ and Sub-Organ Levels
The
ex vivo sample measurements in animal models and also the
in vivo imaging can provide overall information on the biodistribution and organ uptake of radiopharmaceuticals [
12,
70]. Sub-organ distribution may also be visualized and more detailed information on target organ uptake compartments may be gained. Such information is again very important for the estimation of tumor therapy prognosis since some tumors do not express their specific antigens or do not accumulate the targeting vectors in their whole volume.
3.4.3. Cellular and Subcellular Level
Dosimetry on a cellular level should clarify the cell-death mechanisms induced by radiation and damage of cellular compartments including DNA damage. Direct (e.g., DNA double strand breaks) and indirect damage mechanisms (e.g., reactive oxygen species generation) should be considered and further analysis is needed, taking into account also the recoil effects. The standard condition of the radionuclide internalization in the cell need not be necessary. The dose distribution on a subcellular level differs significantly for α particles and for the recoil ion—see
Section 3.1. The studies published so far did not evaluate the complete decay and the energy distribution in decay products even though microautoradiographic techniques, in a combination with immuno-staining methods, are available [
71]. Single α particle-induced damage visualized in real time was also reported [
72] and the stochastic simulation of
223Ra α particle irradiation effects on subcellular level was recently performed [
73]; however, recoils were not taken into account. The cell-to-cell fluctuations in dose deposition ranged up to about 40%. Interesting results were reported in [
74]. In a simplified cellular model, the average number of hits by α particles resulting in a 90% probability of killing exactly one cell was estimated to range from 3.5 to 17.6. However, a better understanding of α particles and the damage induced by the hot recoil atoms is needed to achieve precise proper dose estimation.
Contrary to the efforts of trapping the recoils, an innovative approach that is actually based on the controlled release of recoiling atoms with radioactive nuclei was developed. A novel concept of diffusing α emitter radiation therapy (DaRT) was proposed as a new form of brachytherapy. To treat solid tumors, the method uses α particles employing implantable
224Ra-loaded wire sources that continually release short-lived α particle emitting recoils that spread over a few millimeters inside the tumor [
75]. Immunogenic cell death seems to significantly influence the overall effect of the therapy.