Four terbium isotopes 149,152,155,161Tb emitting various types of radiation can be used for both diagnostics and therapy. 152Tb emits positrons and is ideal for PET. 155Tb is considered a promising ...Auger emitter and a diagnostic pair for other terbium therapeutic isotopes. Several methods for the production of 155Tb using charged particle accelerators have been proposed, but they all have significant limitations. The restricted availability of this isotope hinders its medical applications. We have proposed a new method for production of 155Tb, irradiating enriched 155Gd by alpha particles. The possibility of simultaneous production of two isotopes of terbium, 152,155Tb, was also studied for more efficient cyclotron beam use.
Irradiation of 155Gd enriched targets and 155Gd / 151Eu tandem target with alpha-particles with an energy of 54 MeV was carried out at the U-150 cyclotron at the NRC “Kurchatov Institute”. The cross sections of nuclear reactions on enr-155Gd were measured by the stack foil technique, detecting the gamma-radiation of the activation products. The separation of rare earth elements was performed by extraction chromatography with the LN Resin. 155Tb was produced via 155Dy decay.
The cross sections for the 155,156Tb and 155,157Dy production were measured by the irradiation of a gadolinium target enriched with the 155Gd isotope with alpha-particles in an energy range of 54 → 33 MeV. The yield of 155Dy on a thick target at 54 MeV was 130 MBq/μAh, which makes it possible to obtain 1 GBq of 155Tb in 11 h-irradiation with 20 μA beam current. The possibility of simultaneous production of 152,155Tb by irradiation of 155Gd and 151Eu tandem target with medium-energy alpha-particles is implemented. Optimal irradiation energy ranges of alpha -particles as 54 → 42 MeV for 155Tb and 42 → 34 MeV for 152Tb were suggested. Product activity and radionuclidic purity were calculated.
New nuclear data relevant to the production of 155Tb were obtained. The proposed tandem target approach allows for increasing the availability of medical radioisotopes 152,155Tb.
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Separation technique of rhenium radioisotopes from a deuteron-irradiated tungsten target of natural isotopic composition has been developed. The irradiated tungsten powder was dissolved in a mixture ...of H
2
O
2
and NaOH, the solution was passed through a column filled with an extraction chromatographic sorbent TEVA Resin. Rhenium was eluted with 4 M nitric acid. The separation procedure takes approximately 3 h, the radiochemical yield of rhenium is more than 97%.
Modular nanotransporters (MNTs) are promising technology for nuclear medicine of the present time which is based on an engineered polypeptide platform. Emitters of Auger electrons can be used in pair ...with MNTs as short-range cytotoxic agents, and among the most effective ones
Rh with parent nuclide of
Ru (
min and
d respectively) is to be noted. This work provides new experimental data of cumulative yield of
Ru radionuclide for
He-,
He-, proton- and deuteron-induced reactions on ‘‘thick’’ ThO
targets. Data shows that acquired activity of
Ru is sufficient for creation of
Ru/
Rh generator.
The efficiency of employing a beam of intermediate-energy
He particles for the production of the radionuclide
Pa on natural-thorium targets, which is used to obtain a
U therapeutic
emitter was ...estimated. The cross section for the reaction
Pa and the cross sections for the accompanying reactions
Pa and
Pa in the energy range from 39 to 58 MeV were measured. Experimental results were compared with theoretical data from TENDL-2019 library. The present experiment did not confirm a large cross-section values presented in TENDL-2019 library (up to 400 mb for the reaction
Pa). Therefore, this reaction can hardly be viewed as an alternative to proton- and deuteron-induced reactions for production of
Pa. The cross sections for the reactions
Pa and
Pa in TENDL-2019 also differ significantly from the experimental data.
The cumulative cross sections for
232
Th fission products in the energy range of
3
He nuclei of 39‒58 MeV are measured. The measurements are made using the activation technique and the foil stack ...technique. Eighteen cumulative cross sections for the
232
Th fission products by
3
He nuclei with half-lives from one day (
112
Pd,
T
1/2
= 21 h) to 64 days (
95
Zr,
T
1/2
= 64 d) are measured for the first time. Being fundamental constants, the results can supplement the existing libraries of nuclear data.
The paper describes the method developed for obtaining the medical radionuclide 177Lu, which is obtained using an indirect method, namely, by irradiating an ytterbium target with a high degree of ...enrichment in the target isotope 176Yb. This method makes it possible to obtain a radionuclide without a carrier and with a high radionuclide purity for obtaining therapeutic complexes for the purposes of nuclear medicine.
The paper describes the results of work on the creation of a prototype 212Pb generator obtained by the emanation method using the gaseous radionuclide 220Rn. The generator is technologically simple ...and has convenient operational characteristics. The efficiency of 220Rn isolation with this design is more than 90%, which indicates the acceptability of such type of sources for obtaining 212Pb of high radionuclide purity for the needs of nuclear medicine.
Abstract—The work describes the results of the research of radon-220 emanation from a polymer membrane source with complex porous structure with adsorbed parent radionuclide thorium-228. It is shown ...that this type of source can be used for the isolation of target radionuclide lead-212 with high radionuclide purity for various nuclear-medicine applications.
This article reports the first measurements of the yield of the radioisotopes
230,232,233
Pa on irradiation of thick ThO
2
targets by
1,2
H and
3.4
He. The experimental yield was compared with the ...computed yield using constants from the TENDL-2019 library and the SRIM computer code was used to calculate the travel distance. Most experimental values differ from the computed values. It is shown that the highest yield of
230
Pa – 3.47 MBq/(μA∙h) – can be obtained by irradiating with a proton beam a thorium dioxide target in the U-150 cyclotron at the NRC Kurchatov Institute. It is concluded that
230
U with activity sufficient for clinical use can be produced using the cyclotron.
At present, the radioisotope
U is considered as one of the most promising
-emitters for application in immunotherapy. In order to refine nuclear data and to evaluate the efficiency of
U production, ...the cross sections for the reactions
Th(
He,
)
U and
Th(
He,
)
U, as well as the cross sections for the accompanying reactions
Th(
He,
)
Pa and
Th(
He,
)
Pa, were measured for the first time in the range of energies of
He nuclei between 30 and 62 MeV. The activation technique was used to measure the reaction cross sections. The experimental cross sections were compared with data from the TENDL-2021 library. The results give grounds to conclude that the reactions
Th(
He,
)
U and
Th(
He,
)
U cannot ensure efficient production of
U at the U-150 cyclotron of National Research Center Kurchatov Institute. Therefore, they cannot be viewed as an alternative to proton- and deuteron-induced reactions producing
U.
