Ⅲ-3. Radiochemistry & Nuclear Chemistry
RIKEN
Accel. Prog. Rep. 56 (2023)

RIKEN Accel. Prog. Rep. 56 (2023)

Activation cross sections of deuteron-induced reactions on naturalgadolinium up to 24 MeV†
D. Ichinkhorloo,∗1,∗2 M. Aikawa,∗1,∗3,∗4 Ts. Zolbadral,∗2,∗3,∗4 Y. Komori,∗3 and H. Haba∗3
Terbium (Tb) and gadolinium (Gd) radionuclides canbe used for medical applications. For example, 161 Tb(T1/2 = 6.89 d) can be used for targeted β − radionuclide
therapy.1) The production cross sections of the radionuclide are important nuclear data in terms of practical use.
The radionuclide can be produced via charged-particleinduced reactions on nat Gd, of which can yield the compositions as follows: 152 Gd (0.2%), 154 Gd (2.2%), 155 Gd(14.8%), 156 Gd (20.5%), 157 Gd (15.7%), 158 Gd (24.8%),
and 160 Gd (21.8%). In this study, we focused on thedeuteron-induced reactions on nat Gd. In the literature
survey, only two experimental studies of the cross sections were found.2,3) However, the experimental data
show a discrepancy between them. Therefore, we performed to measure cross sections of the deuteron-induced
reaction on nat Gd. The result was compared with the literature data2,3) and the TENDL-2021 values.4)
The experiment to determine the activation cross sections was conducted at the RIKEN AVF cyclotron. The
stacked-foil activation technique and the high-resolution
γ-ray spectrometry were adopted. The stacked target
comprised foils cut from nat Gd (0.025 × 50 × 100 mm,99.9% purity, Nilaco Corp., Japan) and nat Ti foils(0.005×50×100 mm, 99.6% purity, Nilaco Corp., Japan).
The thicknesses of the nat Gd and nat Ti foils were derived
from the measured size and weight and found to be 25.3
and 2.34 mg/cm2 , respectively. nat Ti foils were used forthe nat Ti(d, x)48 V monitor reaction to assess the beam
parameters and target thicknesses. The foils were cut
into a size of 8 × 8 mm and stacked into a target holderthat served as a Faraday cup.
The stacked target was irradiated with a deuteronbeam for 60 min. The average beam intensity measured by the Faraday cup was 98.1 nA. The beam energy
measured by the time-of-ﬂight method5) was 24.1 MeV.
Further, the energy degradation in the stacked target
was calculated using the target thicknesses and stopping
powers derived from the SRIM code.6)
The γ rays emitted from each irradiated foil were
measured using a high-resolution HPGe detector (ORTEC GMX30P4-70) and the dedicated software (SEIKOEG&G Gamma Studio). The spectra of each foil were
measured four times with diﬀerent cooling time and distance. The associated dead time was less than 6.3%.
Comparisons indicated that the beam intensity was corrected by +6.5% within its uncertainty (7%).
†∗1
∗2
∗3
∗4

Condensed from the article in Nucl. Instrum. Methods Phys.
Res. B 536, 30 (2023)
Faculty of Science, Hokkaido University
Nuclear Research Center, National University of Mongolia
RIKEN Nishina Center
Graduate School of Biomedical Science and Engineering,
Hokkaido University

The cross sections of the nat Ti(d, x)48 V monitor reaction, beam energy and measured foil thicknesses wereadopted without any correction. The cross sections using the corrected parameters were consistent with therecommended values.
The cross sections of the nat Gd(d, x)161 Tb reaction
were derived using the γ line at 74.57 keV (Iγ = 10.2%).
The self-absorption of the low-energy γ line in each nat Gd
foil was estimated as 9.5%. The measurements were performed following a cooling time of 39–42 d. The coproduced parent 161 Gd (T1/2 = 3.66 min) decayed during the cooling time.
The cumulative cross sections are shown in Fig. 1 withthe literature data2,3) and the TENDL-2021 values.5)
Both experimental data were consistent our data below
12 MeV with deviations observed above 12 MeV. The
TENDL-2021 values were smaller than the experimentaldata.

Fig. 1. Excitation function of the nat Gd(d, x)161 Tb reaction
with the previous data2,3) and the TENDL-2021 data.4)

In addition to 161 Tb, we also determined the production cross sections of 153, 154m1, 154m2, 155, 156, 160 Tb and153, 159
Gd. The cross sections are almost consistent withthe experimental data studied earlier. The results are expected to contribute to development of theoretical model
calculation and nuclear medicine.
References1) C. Müller et al., J. Nucl. Med. 53, 1951 (2012).
2) F. Szelecsényi et al., J. Radioanal. Nucl. Chem. 307, 1877(2016).
3) F. Tárkányi et al., Appl. Radiat. Isot. 83, 25 (2014).
4) A. J. Koning et al., Nucl. Data Sheets 155, 1 (2019).
5) T. Watanabe et al., Proc. 5th Int. Part. Accel. Conf.
(IPAC 2014) (2014), p. 3566.
6) J. F. Ziegler et al., SRIM: the Stopping and Range of Ionsin Matter, http://www.srim.org .
7) A. Hermanne et al., Nucl. Data Sheets. 148, 338 (2018).

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