Production of highly purified no-carrier-added 177Lu for radioimmunotherapy

A multi-stage COF membrane column system for enhanced Yb/Lu separation

This study introduces an innovative multi-stage membrane column separation system that combines membrane and column separation technologies, utilizing a COF membrane as the packing material. This approach achieves a superior separation factor and a reduced elution volume for Yb3+/Lu3+ separation, offering a new approach to address challenges in column separation.

Preparation and Biodistribution Assessment of 177Lu-curcumin as a Possible Therapeutic Agent

Purpose

Curcumin as a potent anti-inflammatory and cancer-prevention molecule was labeled with n.c.a 177Lu. The combination of 177Lu as a theranostic agent and curcumin as an anti-cancer can be considered for nuclear medicine.

Methods

First, n.c.a 177Lu (specific activity = 48 Ci/mg) was prepared using the extraction chromatography method. Then, semi-empirical quantum chemical calculations were applied to get a deeper insight into the complexation reaction between Lu+ 3 and curcumin ligand. UV-Vis spectrophotometry was used for the determination of the metal-to-curcumin ratio. Subsequently, a mixture of (111-333 MBq) n.c.a 177Lu, 50 µL curcumin solution in ethanol, and 450 µL acetate buffer at pH = 5 was incubated for 1 h at 95 ºC. The Lu-curcumin complex chemical structure was characterized using IR spectroscopy. Finally, the prepared complex was analyzed by different quality control tests.

Results

Complexometry using UV-Vis studies showed a 1:2 ratio for Lutetium: curcumin complex which is in agreement with theoretical calculations. The IR-spectra analysis also confirmed the complex formation. The radiochemical purity of n.c.a 177Lu -curcumin was more than 95% as determined by radio-TLC. The stability of up to 48 h was observed for the prepared complex in serum. The partition coefficient was calculated for the compound (log P = -0.31). Evaluating biodistribution in tumoral mice exhibited high tumor uptake (%ID/gtissue = 2.03).

Conclusion

The promising results showed that n.c.a 177Lu-curcumin can be considered as a possible radiopharmaceutical agent for therapeutic applications.

Comparative evaluation of radionuclide therapy using 90Y and 177Lu

OBJECTIVE

Both ⁹⁰Y and ¹⁷⁷Lu are attractive β-emitters for radionuclide therapy and have been used in clinical practice. Nevertheless, comparative evaluation between ⁹⁰Y- and ¹⁷⁷Lu-labeled molecules has not been fully conducted. Thus, in this study, the features of ⁹⁰Y and ¹⁷⁷Lu for radionuclide therapy were assessed in tumor-bearing mice.

METHODS

Two tumor cell lines with different growth rates were used. Biodistribution studies of ¹⁷⁷Lu-labeled antibodies (¹⁷⁷Lu-Abs) were conducted in each tumor-bearing mouse model. Subsequently, the therapeutic effect of ⁹⁰Y- and ¹⁷⁷Lu-Ab were assessed in tumor-bearing mice. The absorbed radiation dose for the tumor was estimated using the Monte Carlo simulation.

RESULTS

¹⁷⁷Lu-Abs demonstrated high tumor accumulation in both tumor-xerograph. In the fast-growing tumor model, ⁹⁰Y-Ab showed a better therapeutic effect than ¹⁷⁷Lu-Ab, reflecting a higher absorbed radiation dose of ⁹⁰Y-Ab than that of ¹⁷⁷Lu-Ab. In the slow-growing tumor model, both ⁹⁰Y- and ¹⁷⁷Lu-Ab showed an excellent therapeutic effect; however, ¹⁷⁷Lu-Ab had a longer efficacy period than ⁹⁰Y-Ab, which could be attributed to the longer half-life and better dose uniformity of ¹⁷⁷Lu than those of ⁹⁰Y.

CONCLUSIONS

To accomplish a maximum therapeutic effect, selecting ⁹⁰Y or ¹⁷⁷Lu, to depend on the growth rate of individual cancer, would be helpful.

Investigation of radiolabeling efficacy by enhancement of the chemical form of no carrier added 177Lu isolated by electro amalgamation process

BACKGROUND

Due to the suitable nuclear decay characteristics, 177Lu is an attractive radionuclide for various therapeutic applications. The non-carrier added form of 177Lu has drawn many attention because of its high specific activity needed in radiolabeling studies. There have been several separation methods for NCA 177Lu production.

OBJECTIVES

Among the various separation methods, the electro-amalgamation separation method has got a large potential for large scale production. Li presence is a significant problem in this separation method, which seriously affects the radiolabeling efficiency.

METHOD

In this study, Li was separated from the final product of electro-amalgamation separation by adding an ion-exchange chromatography column to the separation process.

RESULTS

NCA 177Lu was obtained by 84.09% ELM separation yield, 99.9% radionuclide purity and, 65 Ci/g specific activity. Then, 177Lu (177LuCl3 chemical form) was separated from Li using the ion exchange chromatography method by a separation yield of 94%. The obtained results of the radiolabeling efficacy studies showed that the radiochemical purity and radio-complex stability were significantly increased by separating of NCA 177Lu from Li.

CONCLUSION

This new separation setup consisting of two steps allows using 177Lu of such a favorable quality for labeling studies.

Radionuclide generator-based production of therapeutic 177Lu from its long-lived isomer 177mLu

Background

In this work, a lutetium-177 (¹⁷⁷Lu) production method based on the separation of nuclear isomers, ^177mLu & ¹⁷⁷Lu, is reported. The ^177mLu-¹⁷⁷Lu separation is performed by combining the use of DOTA & DOTA-labelled peptide (DOTATATE) and liquid-liquid extraction.

Methods

The ^177mLu cations were complexed with DOTA & DOTATATE and kept at 77 K for periods of time to allow ¹⁷⁷Lu production. The freed ¹⁷⁷Lu ions produced via internal conversion of ^177mLu were then extracted in dihexyl ether using 0.01 M di-(2-ethylhexyl) phosphoric acid (DEHPA) at room temperature. The liquid-liquid extractions were performed periodically for a period up to 35 days.

Results

A maximum ¹⁷⁷Lu/^177mLu activity ratio of 3500 ± 500 was achieved with [^177mLu]Lu-DOTA complex, in comparison to ¹⁷⁷Lu/^177mLu activity ratios of 1086 ± 40 realized using [^177mLu]Lu-DOTATATE complex. The ¹⁷⁷Lu-^177mLu separation was found to be affected by the molar ratio of lutetium and DOTA. A ¹⁷⁷Lu/^177mLu activity ratio up to 3500 ± 500 was achieved with excess DOTA in comparison to ¹⁷⁷Lu/^177mLu activity ratio 1500 ± 600 obtained when lutetium and DOTA were present in molar ratio of 1:1. Further, the ¹⁷⁷Lu ion extraction efficiency, decreases from 95 ± 4% to 58 ± 2% in the presence of excess DOTA.

Conclusion

The reported method resulted in a ¹⁷⁷Lu/ ^177mLu activity ratio up to 3500 after the separation. This ratio is close to the lower end of ¹⁷⁷Lu/^177mLu activity ratios, attained currently during the direct route ¹⁷⁷Lu production for clinical applications (i.e. 4000–10,000). This study forms the basis for further extending the liquid-liquid extraction based ^177mLu-¹⁷⁷Lu separation in order to lead to a commercial ^177mLu/¹⁷⁷Lu radionuclide generator.

Electronic supplementary material

The online version of this article (10.1186/s41181-019-0064-5) contains supplementary material, which is available to authorized users.

Measurement of neutron capture cross section of 187W for production of 188W

Tungsten-188 (t_1/2 = 69.4 d) is routinely produced by double neutron capture using highly enriched ¹⁸⁶W target, ¹⁸⁶W(n,γ)¹⁸⁷W(n,γ)¹⁸⁸W reaction, at the ORNL 85 MWt High Flux Isotope Reactor. While the thermal neutron cross section for the first reaction, ¹⁸⁶W(n,γ)¹⁸⁷W, is well known, the single reported 64 b cross-section for the second reaction, ¹⁸⁷W(n,γ)¹⁸⁸W, cannot be validated by experimental results that yield lower than expected activities of ¹⁸⁸W. In this study, we report a new value for the thermal neutron capture cross section of ¹⁸⁷W. After confirming the neutron capture cross section of ¹⁸⁶W (σ⁰ = 37.8 ± 1.8 b for thermal and I⁰ = 476 ± 25 b for resonance integrals with σ⁰/I⁰ = 12.6 ± 0.4) in two short irradiations, longer irradiations (1-10 d) were performed to obtain a value of 6.5 ± 0.8 b for the σ⁰ of ¹⁸⁷W, which is lower than the adopted value by a factor of 10. Due to the short half-life of ¹⁸⁷W (t_1/2 = 23.7 d), the σ⁰ for ¹⁸⁷W was obtained empirically by comparing the ¹⁸⁸W experimental yields with the theoretical yields generated by code IsoChain and varying the ¹⁸⁷W cross section while keeping all other parameters constant.

Feasibility study for production and quality control of Yb-175 as a byproduct of no carrier added Lu-177 preparation for radiolabeling of DOTMP

Skeletal uptake of β^- emitters of DOTMP complexes is used for the bone pain palliation. In this study, two moderate energy β^- emitters, ¹⁷⁷Lu (T_1/2 = 6.7 days, E_βmax = 497 keV) and ¹⁷⁵Yb (T_1/2 = 4.2 days, E_βmax = 480 keV), are considered as potential agents for the development of the bone-seeking radiopharmaceuticals. Since the specific activity of the radiolabelled carrier molecules should be high, the non-carrier-added (NCA) radionuclides have an effective role in nuclear medicine. Many researchers have presented the synthesis of NCA ¹⁷⁷Lu. Among these separation techniques, extraction chromatography has been considered more capable than other methods. In this study, a new approach, in addition to production of NCA ¹⁷⁷Lu by EXC procedure is using pure ¹⁷⁵Yb that was usually considered as a waste material in this method but because of high radionuclidic purity of ¹⁷⁵Yb produced by this method we used it for radiolabeling as well as NCA ¹⁷⁷Lu. To obtain optimum conditions, some effective factors on separation of Lu/Yb by EXC were investigated. The NCA ¹⁷⁷Lu and pure ¹⁷⁵Yb were produced with radionuclidic purity of 99.99 and 99.97% respectively by irradiation of enriched ¹⁷⁶Yb target in thermal neutron flux of 5 × 10¹³ n/cm² s for 14 days. ¹⁷⁷Lu-DOTMP and ¹⁷⁵Yb-DOTMP were obtained with high radiochemical purities (> 95%) under optimized reaction conditions. Two radiolabeled complexes exhibited excellent stability at room temperature. Biodistribution studies in rats showed favorable selective skeletal uptake with rapid clearance from blood along with insignificant accumulation of activity in other non-target organs for two radiolabelled complexes.

Production and quality control 177Lu (NCA)-DOTMP as a potential agent for bone pain palliation

Skeletal uptake of radiolabeled-1, 4, 7, 10-tetraazacyclododecane-1, 4, 7, 10-tetramethylene phosphoric acid (e.g., 177Lu-DOTMP) complex, is used for bone pain palliation. The moderate energy of β-emitting 177Lu (T½ = 6.7 d, Eβmax = 497keV) has been considered as a potential radionuclide for development of the bone-seeking radiopharmaceutical. Since the specific activity of the radiolabeled carrier molecules should be high, the "no-carrier-added radionuclides" have sig-nificant roles in nuclear medicine. Many researchers illustrated no-carrier-added 177Lu production; among these separation techniques such as ion exchange chromatography, reversed phase ion-pair, and electrochemical method, extraction chromatography has been considered more capable than other methods. In order to optimize the conditions, some effective factors on separation of Lu/Yb were investigated by EXC. The NCA 177Lu, produced by this method, was mixed with 300 μl of DOTMP solution (20 mg in 1 mL of 0.5 M NaHCO3, pH = 8) and incu-bated under stirring at room temperature for 45 min. Radiochemical purity of the 177Lu-DOTMP complex was determined using radio-thin-layer chromatography (RTLC) method. The complex was injected to wild-type rats and biodistribution was then studied for seven days. The NCA 177Lu was produced with specific activ-ity of 48 Ci/mg and with a radinuclidic purity of 99.99% through irradiation of enriched 176Yb target (1 mg) in a thermal neutron flux of 4 × 1013 n.cm-2.s-1 for 14 days. 177Lu-DOTMP was obtained with high radiochemical purities (> 98%) under optimized reaction conditions. The radiolabeled complex exhibited excellent stability at room temperature. Biodistribution of the radiolabeled complex studies in rats showed favorable selective skeletal uptake with rapid clearance from blood along with insignificant accumulation within the other nontargeted organs.