Theranostic Radiopharmaceuticals: Comparison
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Theranostic Radiopharmaceuticals (Radiotheranostics) is a term in the medical field to define the combination of therapeutic and diagnostic techniques by a suitable radiopharmaceutical agent. Radionuclides are isotopes that emit radiation or have excess nuclear energy, making them chemically unstable and tend to change into another atom. Various types of radiation can be emitted by radionuclides e.g. alpha particles, beta particles, and gamma energy. In radiotheranostics, a pharmaceutical agent (drug) is needed to be a carrier molecule that introduces the radionuclide to its target. Radionuclides are then used as a source of radiation in radiotheranostics that are responsible for diagnosing or treating various diseases.

  • radiopharmaceuticals
  • theranostics
  • radionuclide
  • chelator

1. Radionuclides for Diagnosis Purposes

SPECT and PET have become increasingly popular cancer imaging techniques. The radiopharmaceuticals use a gamma (γ) or beta (β+) emitted radionuclide to selectively interact with a target tissue. In PET and SPECT tracers, a variety of radionuclides have been utilized, including isotopes ranging from 11C (t1/2= 20 min) to 124I (t1/2= 4.2 days), as shown in Table 1 [1].
In the PET scan, the annihilation of positron caused by the collision between positron and electron in the body generates gamma rays in two opposite directions which can be detected by the PET scanner to build a radiogram. The acceptable resolution of radiopharmaceuticals should be about ~5 mm. The position of annihilation (collision) varies between the different radionuclides, this is the reason behind the various resolution of the radiogram for each radiopharmaceutical. For example, a positron released by 18F (E+ = 250 keV) travels 1 mm before being annihilated, but a positron emitted by 68Ga (E+ = 830 keV) travels 35 mm before being annihilated. As a result, PET pictures acquired with 68Ga have poorer resolution than those produced with 18F [2][3].
On the other hand, SPECT uses the gamma rays produced by a radioactive isotope to be further screened by the device. Because gamma rays are solitary events, unlike annihilation photons, they must be detected by putting a lead collimator between the source and the detector which then provides information about each source of radiation in the cell of interest [4]. Any photons that interact with the detector must have come from a parrarel source to the detector’s face. The energy of the photon being photographed is an essential factor to consider. Low-energy photons (~70 keV) are strongly attenuated by tissue, resulting in distortions in the pictures. If the photon energy is too great, the demand for similarly thick collimators becomes prohibitive. Photon energies of the order of 140 keV are predicted from these two variables, indicating that 99mTc is widely used for SPECT diagnosis [5].
Table 1. Radionuclides for diagnosis purposes.
Radionuclide Half-Life Mode of Decay Energy (KeV) (%Abundance) Indication (in Radiopharmaceutical Form) References
99mTc 6.02 h γ 140.5 (89%) (l,l-[99mTc]Tc-ECD) Functional imaging of the brain *, [99m Tc-MDP] bone scintigraphy * [6][7][8]
111In 67.3 h EC 171 (90%)

295 (94%)		 (111In-pentetreotide) imaging of neuroendocrine tumors *, (Capromab Pendetide) for metastatic prostate cancer *, and leukocyte marking for invitro purposes * [9][10][11][12][13]
18F 109.7 min β+

EC		 635 (97%)

1655 (EC) 3%		 FDGPET radionuclide for cancer * and Piflufolastat PET radionuclide for protate cancer imaging * [14][15]
11C 20.4 min β+ 960 (100%) Imaging of tyrosine kinase receptor *****, [11C]Flumazenil for GABA **** imaging, [11C]mZIENT for imaging serotonin receptor *****, and 11C-coenzyme Q10 myocardial imaging ***** [16][17]
133Xe 5.27 days γ 81 (38%) Cerebral blood flow, Xe Technegas for lung perfusion imaging ** [18][19]
201Tl 73 h γ 135 and 167 imaging of soft tissue and bone tumors, detection of recurrence in gliomas [20]
51Cr 27.7 days γ 320 (9.8%) Red blood cell labeling, 51-EDTA for GFR measurement *** [21][22]
67Ga 78.3 h EC

γ		 EC (100%)

γ (93 (39%), 300 (17%), and 185 (21%))		 Imaging skeletal infection, 67Ga–Citrate for

CSF flow imaging ****		 [23][24][25]
68Ga 68 min β+ 890 (90%) Diagnosis or imaging of myocardial perfusion use Ga-68 Galmydar ****, pulmonary perfusion ****, and PSMA for prostate cancer *. [26][27]
123I 13 h EC 159 Ioflupane I-123 Injection *

Injection Dopamine transporter for parkinson’s diagnosis		 [28][29]
125I 59.4–60.2 d EC 28.5 Evaluation of glomerular filtration rate and imaging of thyroid, and 125 Iodine Seeds for brachytherapy in solid tumor *. [30][31][32][33][34]
82Rb 75 s β+ 776 82Rb(Rb)+**** for myocardial ischemia and brain tumors imaging. [35][36]
13N 9.97 min β+ 492 (100%) 13N-ammonia * for myocardial perfusion and blood flow imaging in tissue. [37]
166Ho 26.8 h β−

γ		 1.774 (50%)

80.57 (6.6%)		 166Ho-chitosan ***** for diagnosis of liver cancer [38][39]
89Zr 78.4 h β+ 395 (23%) Diagnosis of various types of tumor and cancer (pancreatic, lymphoma, liver, colorectal, and prostate) (89Zr-trastuzumab, 89Zr-J951, 89Zr-lumretuzumab) ***** [40]
61Cu 3.3 h β+

EC

γ		 1220, 1150 (62%); 940, 560 (38%);

380 γ (3%)		 61Cu-ATSM ***** imaging of tumor hypoxia. [41]
64Cu 12.7 h β+

β−

γ		 657 (19%),

141 (38%)

511 (43%),		 64Cu-SAR-bisPSMA *** Imaging for prostate, 64Cu-DOTA-Trastuzumab *** breast cancer, 64Cu-ATSM *** diagnosis of cervical cancer, 64Cu-DOTA-Daratumumab **** multiple myeloma, and 64Cu-Cl2 urological malignancy. [42][43]
Note: * FDA approved. ** Clinical trial phase III. *** Clinical trial phase II. **** Clinical trial Phase I. ***** Pre-clinical Studies.
a.
99m-Technetium
99mTc (t1/2 = 6,02 h, E = 140.5 keV (89%)) is widely used for SPECT, with 99mTc radiopharmaceuticals accounting for more than 85% of all nuclear medicine studies [44]. The emission and half time of 99mTc are almost ideal for convenient preparation of radiopharmaceuticals and imaging applications [45]. Several in vitro studies regarding the toxicity of 99mTc have been performed. The results of studies showed that [99mTc]TcO4− was able to induce DNA damage in breast cancer epithelial cells and reduce cell survival rate when the [99m-Tc]TcO4− was transported into cells. About 30 mBq/cell of cellular concentration of 99m-Tc was required to reduce the survival rate to 37%. Currently, 99mTc is widely used as a radiodiagnostic agent because it has several advantages e.g., widely available, can produce a variety of complexes with desired characteristics due to multi-oxidation state, sufficient half-life (6.02 h) for the preparation of 99mTc radiopharmaceuticals (in hospitals or centralized radiopharmacies), and decays into 99Tc which has low toxicity (weak beta emission and very long half-life) [45][46][47].
99mTc has traditionally been generated via a 99Mo/ 99mTc generator using parent 99Mo created by the fission of highly enriched 235U. The 99Mo is separated from the 99MoO42− and immobilized through the alumina column [46]. By eluting the generator with 0.9% (isotonic) saline solution, 99mTc is produced as 99mTc O4−. Schaffer et al. demonstrated that a biomedical cyclotron could create 7.7 GBq (208 mCi) of 99mTc after 1.5 h of irradiation with an 18 MeV proton beam.
The primary distinctions between rhenium and technetium are their redox behaviors and kinetics. They are found in oxidation levels ranging from +7 to +1 and belong to the same group of transition metals (VIIB) as manganese. Tc(V) and Re(V) produce structurally similar complexes, but the formation circumstances and stability of the resultant products differ, with 188Re complexes being easier to oxidize [47].
A reducing agent, most often SnCl2, chelating (e.g., DTPA, DOTA, and SAR), and a buffer are usually included in a 99mTc kit. The 99mTc O4− solution in saline is simply injected into the vial to make the 99mTc complex [48][49]. Tc(V)-oxo or -dioxo (d2) complexes are formed by reducing 99mTc O4− with SnCl2, yielding square-pyramidal or octahedral complexes, respectively, with tetradentate having higher in vivo stability and simpler chemical modification, and so becoming the popular choice. Amido thioether thiol (AATT) and single amino acid chelate (SAAC) systems are examples of this tetradentate kind of complex [50].
b.
111Indium
111In (t1/2 2.8 d) is the most typical application for cell labeling, which has the advantage of being compatible with SPECT rather than with PET. For the tagging of a wide range of cell types, two compounds have proven especially useful: [111In]In(oxinate)3 and [111In]In(tropolonate)3 with In(oxinate)3 have been the most used in clinic [1]. 111In is a source of gamma radiation used for diagnosis, is also a source of low-energy auger electrons, and has a short distribution range. The presence of electrons outside the cell can be neglected, but when these electrons are inside the cell or around the cell nucleus, they can have a highly toxic effect on the cell’s DNA. A comparative study of dosimetric estimation of 111In showed that 111In was transported into cancer cells in a cumulative concentration range of about 3.7–9.4 mGy/MBq, whereas in the liver 111In had a cumulative concentration range of 0.6–0.4 mGy/MBq. The result of the study indicated that 111In accumulates higher in cancer cells when compared to normal cells and can induce a cytotoxic effect against cancer cells [10].
Proton irradiation of enriched 112Cd targets with the 112Cd(p,2n)111In reaction is the most frequent method for producing 111In. At proton energy of approximately 25 MeV, this reaction can be performed in intermediate energy cyclotrons [50]. Indium, like gallium, has just one stable oxidation state in water: +3. However, due to its much greater size at 62–92 pm for ionic radius (4–8 Å), In(III) achieves coordination numbers of seven and even eight in its complexes. Indium complexes formed by the acyclic chelators EDTA and DTPA are highly thermodynamically stable. The hexadentate chelator in the seven-coordinate In-EDTA structure approximates a pentagonal bipyramidal geometry [51].
c.
67Galium, and 68Gallium
Gallium has a +3 oxidation state in an aqueous solution, which is comparable to 111In. Ga3+ is a hard metal (small and highly charged cation) with an ionic radius of 4–6 CN (0.4–0.6 Å) that prefers to bind chelator with numerous anionic oxygen and/or nitrogen donor sites (e.g., DOTA, NOTA, and HBED) [52][53]. The variation of Ga3+ coordination number from 3 to 6 support octahedral complexes, the most common and the most stable Ga3+-based radiopharmaceuticals. pH sensitivity is a significant problem in Ga3+ labeling; gallium quickly hydrolyzes at pH>3, converting it to insoluble Ga(OH)3. As a result, it is commonly labeled in acidic circumstances (pH 3–4), with the use of an intermediary ligand as an option (e.g., citrate or oxalate) [5][54].
Two radionuclides, 67Ga and 68Ga, have dominated the development of gallium-based radiopharmaceuticals. The low (γ) energy emitter 67Ga (t1/2 = 78.2 h) decays solely via electron capture (EC) [55][56]. Gallium-67 also generates high-energy (6.3 KeV) and long-range Auger electrons, which has spurred interest in 67Ga for treatment purposes [57]. Gallium-67 is commonly made by bombarding a natZn or isotopically enriched 68Zn target with the nuclear reactions 68Zn(p,2n)67Ga (photon energy range between 15 and 30 MeV) and/or 67Zn (p,n)67Ga (photon energy range between 10 and 20 MeV) and/or 67Zn (p,n)67Ga (photon energy range between 10 and 20 MeV [58].
68Ga (t1/2 = 67.7 min) on the other hand, is a (β+) emitter (89%) with a mean (β+) energy of 0.830 MeV, allowing it to be utilized for diagnostic imaging with PET. Gallium-68 is generated by the natGa (p,xn)68Ge nuclear reaction, which is then absorbed on a column containing either an inorganic (e.g., TiO2, Al2O3, and SnO2) or organic (polymeric) stationary phase, and then eluted as 68GaCl3 with 0.1–1 M HCl for further radiolabeling [59][60].
68Ga and 111In are used for inflammatory diagnosis and tumor imaging. Gallium(III) (Ga3+) has comparable properties to Fe-III when in the body to bind to transferrin and lactoferrin and be transported to sites of inflammation. Compared with In(III), Gallium has advantages over indium in imaging osteomyelitis (bone infection) and chronic inflammation due to its ability to bind neutrophil cell membranes. In another utilization, 111In is most suitable with peptides labeled for the somatostatin receptor and antibody receptor for prostate tumor imaging [61][62]. Several recent studies of cytotoxicity of 67Ga have shown that 67Ga caused DNA damage higher than 111In per Bq concentration. The level of cellular radioactivity required by 67Ga to kill 50–90% of breast cancer cells is 1.5–6 times less than 111In. In addition, 67Ga also has a lower level of DNA damage than 111In if the radionuclide was separated from DNA, which caused 67Ga to have a smaller DNA damage effect on non-targeted cells [25].
d.
61Copper and 64Copper
61Cu is produced from the cyclotron (61Ni(p,n)61Cu) whereas 64Cu is produced from 64Ni(d,2n)64Cu with γ emissions (43%) and produced from 64Ni(p,n)64Cu with β+ emissions (19%). The half-life of 61Cu is shorter than 64Cu, making 64Cu the most used for radiodiagnostic development due to its higher stability [63]. The coordination chemistry of copper, which is quite diverse ~4 to 6, makes Cu isotopes stably functional with BFCs. On the other hand, Cu has two states of oxidation, Cu(I) and Cu(II); thus, the complex remains stable and soluble with chelators phosphine-P and thioether-S (weak donor chelator). Because of the d9 configuration, Cu(II) complexes are more kinetically able to dissociate to ligands than Cu(I) with Cu(I) d10 configurations. Therefore, the compatible chelator Cu radionuclides are generally macrocyclic chelators, making Cu(II) complexes stably conjugated with the ligands [64][65]. The cytotoxicity study of 64Cu radionuclide conjugated with carriers and chelators showed that the accumulated concentration of 64Cu was 3.1–6.0 times higher in cancer cell models than in normal cell models. These results indicate higher efficiency of 64Cu in cancer cells. The result shows that 64Cu has the potential to be used as a radionuclide for cancer therapy or diagnosis [63].
e.
89Zirconium
The half-life of Zr-89 (t1/2 = 78.4 h) is the most suitable for antibody-based radiopharmaceuticals, due to their slow pharmacokinetics. It has relatively low positron energy (395 keV), which results in ideal radionuclides for PET with high-resolution imaging and is also more stable and safer in vivo. Hence, 89Zr has more uses than 124I-based agents for clinical applications. In addition, 124I produces different energies, 723 keV (10.4%), 1691 keV (10.9%), and 603 keV (63.0%), which may lead random result to imaging. However, proper handling during high abundance production is necessary to lower the risk of high energy and penetrating photons (909 keV) [40].
f.
18Fluorine
Despite the benefits of 68Ga, such as its ability to be obtained from a generator or its metallic nature of molecules via coordination chemistry, 18F continues to have a privileged position among the radionuclides used in PET imaging. The sensitivity and spatial resolution of 68Ga PET imaging are lower than those of 18F PET. With a bond strength of around 670 kJ/mol, aluminum forms more stable complexes with fluorine than with other halogens. Furthermore, because the Al-F bond is extremely stable in vivo, tiny quantities of the aluminum fluoride complex are compatible with organisms. With a maximum coordination number of six, the Al3+ ion can be complexed by an appropriate chelator and form a ternary complex (fluorine aluminum–chelator) in the presence of fluoride ions. If the ligand’s valency permits it, it prefers to assume an octahedral geometry [66][67].
The relatively fast in vivo pharmacokinetics of peptide bioconjugates are consistent with the fluorine-18 half-life, making them ideal for [18F]AlF radiolabeling. Good labeling yields of up to 74% have also been produced employing a NODA-MPAA-conjugate (IMP485), a pentavalent chelator better suited to [18F]AlF, according to McBride, W.J et al. [68].

2. Radionuclides for Therapy Purposes

High-energy, short-range radiotherapy is thought to be adequately targeted the tumor tissue without inflicting considerable harm to normal tissue. Radiotherapy should have a high tumor-to-background ratio, be selective in its penetration, and be eliminated quickly by the kidneys. Radionuclides that primarily emit (β−) particles, alpha particles, and/or Auger electrons have been used in medicinal radiopharmaceuticals thus far (Table 32) [69]. Auger electrons (mostly in 67Ga) are extremely low-energy electrons (1–10 keV) produced by radionuclides decaying via electron capture. These particles have a high Linear energy transfer (LET) (4–26 keV/m) and a tissue range of less than a single cell diameter (1–20 m), making them ideal for nucleus targeting [70].
Table 32.
 Radionuclides for therapy purposes.
Radionuclide Half-Life Mode of

Decay		 Energy (KeV) Indication (in Radiopharmaceutical Form) References
90Y 64.10 h β−

β+

γ		 2270 (100%)

739 (0.003%)

511 (0.006%)		 90Y-microsphere (TheraSphere® and SIR-Spheres®) * radiotherapy for hepatic metastasis, 90Y-ibritumomab tiuxetan ** for lymphoma, and 90Y-hydroxypatite and 90Y-citrate colloid ** for leukemia PVNS (synovitis). [71][72]
117mSn 13.6 d IT 130

150		 117mSn-DTPA *** for bone tumor treatment and palliative therapy. [71]
131I 8.02 d β−; γ 606 (89.3%); 364 (81.2%) 131I (radioactive iodine therapy) * use for therapy in thyroid cancer, for hyperthyroidism, RIT for NHL, and therapy for malignant pheochromocytoma neuroblastoma [71][73]
153Sm 46.5 h β− 808 (20%); 710 (50%) 153Sm-EDTMP * for painful bone metastasis and synovitis tratment. [71][72][74][75]
177Lu 6.73 d β− 498 (78%) 177Lu-HA **** for synovitis treatment, 177Lu-PSMA-617 (Pluvicto) * for prostate cancer, 177Lu-DOTATATE (Luthatera ®) * for neuroendocrine tumor. [71][72]
225Ac 10 d α 5793 (18.1%)

5830 (50.7%)		 225Ac-PSMA-617 **** for prostate cancer, 225Ac-lintuzumab *** for leukemia, and 225Ac-NOTA-trastuzumab ***** for breast cancer treatment [76]
186Re 3.72 d EC, β− 1965 β− (25.6%) 186Re-HEDP *** for painful skeletal metastasis and painful arthritis [71][72]
188Re 17.00 h β−, γ 2120 (71.1%) 188Re-HEDP *** for painful bone metastasis, rheumatoid arthritis, and treatments for RIT with various cancers [71][72]
223Ra 11.44 d α 5979 (100%) 223Ra-dichloride (Xofigo®) * for bone metastasis [77]
166Ho 26.8 h β−

γ		 1774 (49.9%)

80.57 (6.6%)		 166Ho-chitosan ***** for liver cancer [39]
Note: * FDA approved. ** Clinical trial phase III. *** Clinical trial phase II. **** Clinical trial Phase I. ***** Pre-clinical Studies.
LET is a popular method for predicting the possible harm that a nuclide might produce in a biological system. Particles having a high LET generate ionizing radiation that quickly disperses in tissue. Particles having a low LET, on the other hand, attenuate their energy slowly, allowing them to deposit energy over a wider range of tissue.
a.
186Rhenium and 188Rhenium
188Re has a half-life of about 17 h and emits β– particles (2120.4 keV, 71.1%; and 1965.4 keV, 25.6%), while 186Re has a longer t1/2 (90 h) and emits (β–) particles (1077 keV, 71%; and 939 keV, 22%) resulting in a longer tissue penetration (10–11 mm). Based on physical properties, 188Re isotopes are excellent for radiotherapy of malignant tumors [78]. Some of the chemical properties of 186Re and 186Re are quite similar to 99m-Tc because of their periodic linkage, but 186Re and 188Re have a lower redox state than 99m-Tc, making them incompatible with several BFCA of 99m-Tc. Ram et al. find the BFCA for peptide-based antibody which has a more stable complex for 99m-Tc and 186Re [79].
Based on phase II clinical trials and dosimetry tests of radiopharmaceuticals labeled with 188Re, 188Re-HEDP has effective pain relief in patients with breast or prostate cancer bone metastases (80% of 15 patients), lung cancer bone metastases (46% of 27 patients), renal cancer (50% of 61 patients), and liver cancer (55.56% of 64 patients). The dosimetry test of 188Re-HEDP showed the maximum tolerated dose was 3.3 GBq, and the radiation-absorbed dose in normal bone marrow was still tolerable and did not cause hematological toxicity [79].
b.
225Actinium
Actinium is present naturally in association with uranium. 225Ac [t1/2= 10 d; α emission 5793 keV (18.1%), 5830 keV (50.7%)] is derived from the decay of 233U as well as the transmutation of neutron of 226Ra by successive n, γ capture decay reactions via 227Ac, 228Th, and 229Th. In the clinical trials, 225Ac can be obtained from U.S. Department of Energy, Oak Ridge National Laboratory (ORNL) in Oak Ridge, TN, United States of America, and the Institute for Transuranium Elements in Karlsruhe, Germany. The 225Ac from both places were produced from 233U and the long-term storage was done in ORNL [80].
225Ac is an α emitter that has a recoil event (see Figure 31) as a challenge when it is complexed with a certain BFCA. There are broad techniques offered to deal with those problems; the first method is to use a nano-carrier capacity to hold the recoiling offspring, such as zeolites or liposomes. Piotrowska et al., 2013, utilized zeolites as transporters for 224Ra and found that under circulating blood conditions, the fraction of recoiled daughters (212Bi, 212Pb, and 208Tl) escaped from the zeolites is minimal [81]. The second strategy is to guarantee that the radiopharmaceutical is quickly absorbed by tumor cells and that any residual unabsorbed material is quickly eliminated from the body. Antibodies have received a lot more interest in the field of alpha radionuclide treatment. The third strategy is to place or inject alpha-emitting radionuclides directly into/near the tumor tissue, as Cordier et al. did in Phase I clinical trials using a radiopharmaceutical coded as “213Bi-DOTA-substance P” which was locally injected in gliomas [82].
Figure 31.
 Scheme of complex instability of alpha emitter due to recoil energy effect.
c.
90Yttrium
90Y is in equilibrium with its parent isotope 90Sr and then decays to form the stable 90Z. 90Y is formed from 89Y being bombarded with neutrons in a nuclear reactor. 90Y has a half-life of about 2.67 days and emits a large amount of β− (2.27 MeV) and a little β+ and γ emission, capable to penetrate tissues up to 11 mm. Due to the high energy β− emission by 90Y, the beta particle radiation not only reaches the target but also rapidly reaches the surroundings of the target cell. About 90% of the radiation is absorbed in a path length of 5 mm (about 100–200 cells). The 90Y emitted beta particles can, directly and indirectly, disrupt cell integrity. Directly, beta particles will damage the DNA structure so that it cannot be repaired. Meanwhile, the emitted beta particles can increase the amount of toxic free radicals in the cytosol indirectly (known as a secondary radiation effect) [83][84].
90Y is a good example of both medicinal and diagnostic isotopes being accessible in the same element. It has a lengthy half-life of 2.7 days, which is long enough to achieve radiotherapy’s critical dosage levels. High energy causes the cell to penetrate deeply, which is ideal for solid tumors. Because of its larger tissue penetration range, 90Y was predicted to have a bigger influence on tumor reduction [83].
The strong affinity of unchelated yttrium for bone and liver dominates the bioinorganic chemistry of Y3+, which necessitates the employment of macrocycle chelators and emphasizes the importance of complex stability. Yttrium(III) is much bigger, having an ionic radius of 6–9 Å, giving it the ability to achieve coordination numbers of 7 and 10 in its complexes. The octadentate lanthanide chelator DOTA offers a nearly perfect match with associated high affinity due to the higher coordination number requirement of Y(III) [84][85].
Although (n,γ) reactions on yttrium metal or yttrium oxide can generate yttrium-90, the resultant product has a poor specific activity. It may also be made in a nuclear reactor by the 90Zr(n,p)90Y reaction. After irradiation, the Zr starting material is removed with HNO3 and mandelic acid, yielding a solution comprising the 90Y daughter and the 90Sr parent, which may be removed from the 90Y product by retaining it on a DOWEX cation column [85].
d.
177Lutetium
In the application of radionuclide-based therapy, 177Lu is now becoming the market leader. 177Lu (t1/2 = 6.7 d) is a β− (0.497 MeV), γ (113 keV, 6%) and (208 keV, 10%) emitters. The development of 177Lu to be a theranostic agent is very prospective, its utilities are not only a post-treatment scans be acquired, but patient dosimetry can also be performed [86][87]
In 2018, [177Lu]Lu-DOTATATE (Lutathera) was approved by the FDA for use as a cancer treatment following a phase III clinical trial. Studies regarding PRRT combining [177Lu]Lu-DOTATATE with [90Y]Y-DOTATATE have shown that kidney injury and myelosuppression are rare side effects. Hematotoxicity due to PRRT can occur due to irradiation and destruction of hematopoietic cells. The acceptable dose of PRRT for bone marrow is 2 Gy [88].
There are two methods of 117Lu production, direct and indirect methods. The direct approach uses the 176Lu(n,γ) 177Lu nuclear reaction to irradiate highly enriched 176Lu targets with neutrons. In the reaction 176Yb(n, γ) 177Yb → 177Lu, the indirect approach employs highly enriched 176Yb as a target material and needs chemical separation of 177Lu from excess Yb [89]. Polycarboxylate ligands (DOTA, NOTA, NODAGA, DTPA, and DOTRP) have been demonstrated to be the most successful choice for developing a BFC capable of binding 177Lu and producing a radioconjugate with adequate stability in an aqueous solution and under biological conditions for 177Lu labeling. The chemical bonds produced by the Lu3+ ion have a strong ionic nature, requiring negatively charged hard donor elements such as oxygen for stable coordination. Negative oxygen atoms in polycarboxylate ligands appear to have a function in providing a strong ionic connection with the ionic metallic core. This is an important element in lowering the enthalpy of thermodynamically favorable processes [90].
e.
153Samarium
153Sm has physical properties being beta emission minus 0.71 MeV (50%) and 0.81 MeV (20%) and an emitted gamma emission 103.2 keV (28%). Beta particles from 153Sm can penetrate soft tissue up to a maximum distance of 3 mm and can penetrate bone up to 1.7 mm, so it is used to reduce bone pain and bone loss due to cancer-causing illnesses and is also used for gamma imaging biodistribution [74][75].

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