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 cross sections of the reactions
186
W(
4
He, p3n)
186
Re,
186
W(
4
He, pn)
188
Re, and
186
W(
4
He, p)
189
Re were measured by the activation method in the energy range of 4He nuclei 24–63 MeV. ...For all three reactions the cross sections in the TENDL-2019 nuclear data library differ from experiment by more than a factor of 2 in a wide energy range.
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.
The effect of deuterium plasma on tungsten with high levels of radiation damage was studied experimentally. Tungsten was examined as a candidate plasma-facing material for a fusion reactor. The ...effect of damage accumulation in a material irradiated with fusion neutrons was simulated using high-energy ions. Primary radiation defects of 1–100 dpa were produced in tungsten irradiated with He
2+
and C
3+
ions accelerated to 3–10 MeV in the cyclotron at the Kurchatov Institute with a fluence of 10
17
–10
19
ion/cm
2
. The irradiated material was exposed to deuterium plasma at the LENTA linear plasma facility operated in the continuous regime and providing a plasma flux of 10
21
–10
22
D/cm
2
. The erosion dynamics, the development of surface microstructure, and the accumulation of deuterium in tungsten were studied. Enhanced retention of deuterium was observed in the samples damaged both by helium and carbon ions at room temperature (ERDA). The effect of deuterium retention was suppressed in the damaged tungsten samples processed at a temperature of 500°C.
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.
The cross sections for nuclear reactions natEr(α,x) were measured in the energy range 60 → 10 MeV using the stacked-foil technique. The experiments were carried out in a wider energy range in ...comparison with previous works. The results are consistent with other studies and modeling using TENDL-2019. The 167Tm yield was 5.4 MBq/μAh in the range 60 → 30 MeV, and the main long-lived impurity is 168Tm (0.78% in terms of activity). The 165Tm yield is 4.6 MBq/μAh (60 → 40 MeV). 169Yb is formed with a yield of 1.0 MBq/μAh in the energy range 60 → 20 MeV.
•Activation cross-sections of alpha-particle induced reactions were measured on natural erbium target.•Stacked-foil technique, activation method and gamma-spectroscopy were used.•Cross section for ytterbium (167,169Yb and thulium (165Tm, 166Tm, 167cumTm, 168Tm) were determined.•Production routs of 169Yb, 167Tm and 165Er were discussed.
To study the effect of helium (He) on tensile properties and microstructure of oxide dispersion strengthened EUROFER-ODS steel, flat tensile specimens were homogeneously implanted with 30MeV ...α-particles at the NRC KI cyclotron up to 1000appm He at 573K and 773K. High-resolution and energy-filtered transmission electron microscopy showed that partly coherent Y2O3 particles are strong trapping centers for diffusing He atoms (at least up to 773K) in reduced activation ferritic/martensitic 9Cr–1WMnVTa–0.3Y2O3 steel. After 573K and 773K implantation the He bubbles or He filled voids have average diameters of 1.9 and 4.2nm with concentrations about 8×1022 and 7×1022m−3, respectively. Tensile testing after 573K implantation revealed a uniform elongation of more than 10%, despite an irradiation induced hardening of about 250MPa. The role that nanoscaled Y2O3 particles play in He distribution, tensile properties, and on the mitigation of He embrittlement are discussed.
The
230
U yield in the direct reactions
232
Th(
3
He, 5
n
)
230
U and
232
Th(
4
He, 6
n
)
230
U on thick ThO
2
targets irradiated by 65 and 55 MeV nuclei
3,4
He was measured and compared with ...calculations. The experimental yield of
230
U in the reaction
232
Th(
3
He, 5
n
)
230
U is approximately 10 times higher than the value computed using the constants from TENDL-2019. The experimental yield of
230
U in the reaction
232
Th(
4
He, 6
n
)
230
U the same, to within t5he limits of error, as the computed value. Comparing the experimental and computed yield in the reaction
232
Th(
4
He, 6
n
)
230
U with the cross section obtained by the ALICA program (USA) showed that the computed cross section is incorrect and the prognoses for
230
U production based on it are unsubstantiated. It is concluded that the reactions
232
Th(
3
He, 5
n
)
230
U and
232
Th(
4
He, 6
n
)
230
U are inefficient for
230
U production in the U-150 cyclotron at the NRC Kurchatov Institute in amounts required for clinical applications.
A method for improving the production of the radioisotope
123
I in proton cyclotrons, which makes it possible to increase its technological yield by 2–3 times, is reported. For this purpose, it is ...proposed to introduce hydrogen into a target with
124
Xe, which makes it possible to extract from it the
123
I formed over the irradiation time on decay of the accumulated
123
Xe.
