This article is devoted to obtaining the α-emitter
149
Tb for radioimmunotherapy. A method for producing
149
Tb based on the reaction
151
Eu(
3
He, 5n)
149
Tb is proposed. It is proposed that ...europium with native isotopic composition (
151
Eu – 47.81%,
153
Eu – 52.19%) or enriched
151
Eu be used as the target. The 29 MeV threshold of the indicated reaction makes it possible to use accelerators with the initial
3
He energy 40–70 MeV.
The results of the study of magnetization and dynamic magnetic susceptibility are correlated with changes in the microstructure of superconducting intermetallic Nb
3
Sn plates irradiated at the ...Kurchatov Institute cyclotron with fast protons with an energy of 12.8 MeV to a fluence of 1 · 10
18
cm
−2
. The dependence of the superconducting transition temperature on the total irradiation dose is determined. For one of the samples, the dynamic magnetic susceptibility exhibits several steps corresponding to superconducting transitions at different temperatures. It is assumed that a Nb-enriched phase is separated in the region of maximum radiation damages. A microstructural analysis shows the appearance of randomly oriented Nb-enriched regions from 0.1 to 0.5
μ
m in size.
The activation method was used to determine the cross sections of the nuclear reactions sup.82Kr(sup.3He, 3n)sup.82Sr, sup.83Kr(sup.3He, 4n)sup.82Sr, and sup.84Kr(sup.3He, 5n)sup.82Sr in the sup.3He ...energy range 20-75 MeV on targets with highly enriched krypton isotopes. The results were used to calculate the sup.82Sr yield in a yield-optimized cascade target with sup.82,83,84Kr and initial sup.3He energy 75 MeV. The computed sup.82Sr yield was equal to 2.9 MBqf(microA x h), which makes it possible to count on the practical application of the method of sup.82Sr production based on the reactions sup.82,83,84Kr(sup.3He, xn)sup.82Sr in a cascade target.
The concept of a solution target for obtaining the radioisotope sup.82Sr via the reaction Rb(p, xn) sup.82Sr is propounded. A computational estimate of the main technological parameters of a solution ...target is made. The sup.82Sr yield in a solution target is calculated for solutions of certain compounds of rubidium and initial proton energy 70 MeV. It is shown that the highest sup.82Sr yield 7.44 MBqf(muA x h) in a solution target can be obtained by using a saturated solution of RbF. The solution flow rate in the circulation loop of the target allowing the operation of a target without boiling-up in a 100 muA proton beam is obtained for a target solution with RbF. The mass/size parameters of the heat-exchanger allowing the solution to be cooled to the initial temperature in a single pass are calculated. The influence of radiolysis of the proton-irradiated solution on the operation of the target is determined. It is shown that on the whole radiolysis of the solution target is not large but does require definite efforts to utilize the hydrogen.
This work is devoted to the use of beams of radioactive nuclei for applied purposes--to study the wear-resistance of materials used in different industries. The crux of the method is that the ...radioactive nuclei obtained in the nuclear reactions sup.1H(sup.7Li, sup.7Be) and sup.1H(sup.10B, sup.7Be) are implanted in the experimental sample. After implantation of the nuclei, the sample undergoes wear tests. The gamma-radiation of the implanted nuclei is high-energy; the spectrum is comparatively simple and does not produce appreciable radiation damage in the test samples. The method has been successfully tested in determining the wear-resistance of machine parts and mechanisms.
Method for production of alpha emitter
Tb by irradiation of
Eu with 70 MeV
He nuclei is proposed. For the first time, the cross sections for the formation of isotopes
Tb were measured experimentally ...using a stack foil technique in the
He particles energy range 70 → 12 MeV. The thick target yield of
Tb is 39 MBq/μAh, or 230 MBq/μA
Tb at saturation. The optimal energy range from the point of view of radioisotopic purity is 70 → 40 MeV. At these conditions about 150 MBq/μA
Tb can be produced in 8 hours irradiation, which is sufficient for therapeutic applications. The main impurities are
Tb (~100% in activity) and
Tb (~30% in activity). The proposed method surpasses its counterparts by the high content of the target isotope in the natural mixture and the simplicity of the radiochemical separation of
Tb from the bulk target material.
New experimental approach is developed to explore plasma facing materials accounting for neutron induced radiation damage on erosion of these materials in plasma. The radiation damage has been ...produced in carbon materials by 5
MeV
12C
+ ions accelerated on cyclotron of Kurchatov Institute. A high level of radiation damage (1–10
dpa) has been obtained on these materials. The erosion of irradiated materials including CFC under plasma impact was studied on the LENTA linear plasma simulator. Surface modification was analyzed and the erosion rate was evaluated. Enhancement of the erosion process was detected for the radiation-damaged materials.
This paper presents a summary of scientific results obtained during the last few years in the National Research Centre "Kurchatov Institute" (NRC KI). The main aims of this research are the ...development of a new experimental method that can be applied for the investigation of the influence of a high level of radiation damage on the plasma erosion effects of irradiated materials (graphite materials and tungsten) at different temperatures and the investigation of hydrogen isotope accumulation in these materials relevant to fusion reactor conditions (in ITER).
A high level of radiation damage in these materials (0.1 to 10 displacements per atom) was achieved by irradiating them with fast charged particles at the NRC KI cyclotron, simulating fast neutron irradiation in a fusion reactor. The plasma erosion effects in irradiated and nonirradiated materials were compared using the linear plasma simulator LENTA at NRC KI.
The performed investigations have shown that the erosion factor of irradiated graphite materials is increased and the tungsten surface structure is changed due to the accumulation of radiation damage. No influence of irradiation on tungsten erosion rate was observed in these experimental tests. The accumulation of hydrogen isotopes and helium concentrations were measured in the irradiated tungsten.
The performed work and the obtained results suggest a new promising experimental method for the experimental investigation of plasma effects on fusion structural materials at different irradiation temperatures and different radiation damage levels.
Irradiation of
W targets by
He particles was carried out. For the first time the cross sections for the reactions of production of
Re,
Os,
W were measured by the stack foil technique in the
He energy ...range of 15-45 MeV. The results were compared to the data from the TENDL-2019 library. Using the experimental excitation functions, the thick target yields of medically relevant rhenium radioisotopes were calculated.
This work is devoted to the use of beams of radioactive nuclei for applied purposes – to study the wearresistance of materials used in different industries. The crux of the method is that the ...radioactive nuclei obtained in the nuclear reactions
1
H(
7
Li,
7
Be) and
1
H(
10
B,
7
Be) are implanted in the experimental sample. After implantation of the nuclei, the sample undergoes wear tests. The γ-radiation of the implanted nuclei is high-energy; the spectrum is comparatively simple and does not produce appreciable radiation damage in the test samples. The method has been successfully tested in determining the wear-resistance of machine parts and mechanisms.
