New measurement of 165Ho neutron capture cross-sections

DATA ARTICLE

New measurement of ¹⁶⁵Ho neutron capture cross-sections

Su-Ya-La-Tu Zhang ，

Yong-Shun Huang，

Wei Jiang，

Jie Ren，

Rui-Rui Fan，

De-Xin Wang，

Chun-Lei Zhang，

Guo- Li，

Dan-Dan Niu，

Mei-Rong Huang

Nuclear Science and Techniques

Vol.36, No.9

Article number 168

Published in print Sep 2025

Available online 29 Jun 2025

DOI：10.1007/s41365-025-01763-8

CSTR：32136.14.NST.2025.09168

11000

The neutron capture cross-section for ¹⁶⁵Ho was measured at the backstreaming white neutron beam line (Back-n) of the China Spallation Neutron Source (CSNS) using total-energy detection systems, composed of a set of four C₆D₆ scintillator detectors coupled with pulse-height weighting techniques. The resonance parameters were extracted using the multilevel multichannel R-matrix code SAMMY to fit the measured capture yields of the ¹⁶⁵Ho(n,γ) reaction in the neutron energy range below 100 eV. Subsequently, the resonance region’s capture cross-sections were reconstructed based on the obtained parameters. Furthermore, the unresolved resonance average cross-section of the ¹⁶⁵Ho(n,γ) reaction was determined relative to that of the standard sample ¹⁹⁷Au within the neutron energy range of 2 keV to 1 MeV. The experimental data were compared with the recommended nuclear data from the ENDF/B-VIII.0 library, as well as with results of calculations performed using the TALYS-1.9 code. The comparison revealed agreement between the measured ¹⁶⁵Ho(n,γ) cross-sections and these data. The present results are crucial for evaluating the ¹⁶⁵Ho neutron capture cross-section and thus enhance the quality of evaluated nuclear data libraries. They provide valuable guidance for nuclear theoretical models and nuclear astrophysical studies.

HolmiumNeutron capture reactionCross-sectionTotal-energy detection principleC6D6 scintillator detectorChina Spallation Neutron Source

Introduction

Nuclear data are used to describe the physical properties of atomic nuclei and their interactions, thus playing a key role in fundamental nuclear physics research and the development of nuclear energy and nuclear technology [1, 2]. Neutron capture cross-section data are critical for stellar nucleosynthesis of heavy elements, medical applications, radiation dosimetry, transmutation of nuclear waste, and advanced nuclear energy systems [3-5].

Numerous laboratories worldwide, including CERN n_TOF [6], Los Alamos National Laboratory DANCE [7], Karlsruhe [8], and GELINA [9] have developed two types of detection systems for online measurement of neutron capture cross-sections. These systems include γ-ray total-energy and total-absorption detectors. Total-energy detection systems generally use a low-efficiency C₆D₆ scintillator detector, which is suitable for measuring stable nuclei exhibiting large cross-sections and requiring the use of large samples. Total-absorption detection systems often use a BaF₂ crystal detector array with high energy resolution, good time resolution, low neutron sensitivity, and high efficiency to perform neutron capture measurements for small-sized samples, small cross-sections, and unstable radio nuclides. The China Spallation Neutron Source (CSNS) [10] produces neutrons by bombarding a high-intensity 1.6-GeV proton beam on a tungsten target. The backstreaming neutron beam line (Back-n) is positioned in the reverse direction of the proton beam at the CSNS, with a flight pass length of approximately 76 m. Figure 1 illustrates a schematic view of the experimental setup of the CSNS Back-n. Currently, five types of spectrometers are being constructed at the Back-n facility for nuclear data measurements. These instruments include a set of four C₆D₆ detectors [11-13] and a 4π BaF₂ detector array, referred to as the Gamma Total Absorption Facility II (GTAF-II) [14], which will be utilized for neutron capture measurements. In addition, a multilayer fast ionization chamber (FIXM) is employed for fission reaction measurements [15], and a neutron total cross-section detector (NTOX) has been specifically designed for total cross-section measurements [16]. Furthermore, light-charged particle detectors are used to measure light-charged particle emissions [17]. A detailed description of the spectrometers is provided in Refs. [18].

Fig. 1

(Color online) Schematic view of the experimental setup of the CSNS Back-n [18]

Holmium (composed entirely of the isotope ¹⁶⁵Ho with 100% natural abundance) has been proposed as the standard for neutron capture cross-section measurements owing to its favorable radioactive half-life and large capture cross-section observed at the first resonance peak, which is essential for “saturation resonance” calibration [19-21]. Previous studies on ¹⁶⁵Ho(n,γ) have revealed notable discrepancies. Poenitz et al. [22, 23] have reported divergent keV–MeV cross-sections determined using time-of-flight (TOF) and statistical models, and Voignier et al. [24] have identified data scarcity for holmium. Recently reported Oslo-method analyses [25] reduce MACS uncertainties; however, they highlight unresolved impacts of low-energy isomers on s-process abundances. Therefore, extensive neutron capture measurements of ¹⁶⁵Ho are required to test the accuracy of the evaluated nuclear data and available experimental data. This paper presents a new dataset of the ¹⁶⁵Ho(n, γ)¹⁶⁶Ho reaction in the neutron energy range from 1 eV to 1 MeV, measured using the C₆D₆ detection system at the CSNS Back-n white neutron source. In the following sections, we outline the methods employed in the experiment and data analysis, discuss the reliability of the results, and provide detailed information on the CERN ROOT code [26] relevant to this study.

Methods

2.1

Measurements

In May 2022, the ¹⁶⁵Ho(n, γ)¹⁶⁶Ho reaction was measured in the CSNS Back-n experimental area (#ES2), which has a flight path length of approximately 76 m. The neutron beam, with ϕ30 mm beam spots, was delivered at ES2 with approximately 6.92×10⁵cm^-2s^-1 neutrons per nominal pulse of 1.6×10¹³ protons in the energy range from 0.3 eV to 200 MeV. The neutron energy spectrum was determined using two different detectors, viz. a Li–Si detector and a calibrated fission chamber, with working principles based on the ⁶Li(n, t) and ²³⁵U(n, f) reactions, respectively [27, 28]. The neutron flux in the experiment was monitored using a silicon flux monitor (SiMon) comprising a thin ⁶LiF conversion layer and eight silicon detectors; the SiMon was installed approximately 20 m upstream from the sample location. The γ-rays from the ¹⁶⁵Ho capture reaction were detected using a set of four C₆D₆ scintillators. These detectors were positioned approximately 17 cm away from the target at an angle of 125 relative to the neutron beam (Fig. 2). The characteristics of the samples used in this experiment were provided by the China Institute of Atomic Energy (Table 1). A natural metallic holmium sample was used to determine the neutron capture cross-section of ¹⁶⁵Ho, whereas a gold sample was used to measure the neutron flux and normalize the neutron capture data. Background signals due to scattered neutrons and in-beam γ-rays were measured using a lead sample. Additionally, an empty-sample run was performed to evaluate the sample-independent background. The detector signals were recorded using the CSNS Back-n General Purpose Data Acquisition System [29], which was operated at a sampling rate of 1 GS/s with 12-bit full-waveform digitizers. Data acquisition was triggered by a pickup signal from the proton beam. Dead-time corrections were disregarded owing to the lower event statistics observed in this experiment. The total beam measurement time was 100 h, and the offline analysis was performed using the CERN ROOT code.

Fig. 2

(Color online) Setup of the four C₆D₆ detectors in the measurement. The detectors were positioned approximately 17 cm away from the target at an angle of 125 relative to the neutron beam

Characteristic parameters of samples

Sample	Thickness (mm)	Diameter (mm)	Mass (mg)	Area density (atom·b^-1)
¹⁶⁵Ho	0.20	30	1243.32	6.42×10^-4
¹⁹⁷Au	0.10	30	1357.17	5.87×10^-4
^natPb	0.53	30	4249.75	1.75×10^-3
Empty holder

2.2

Data analysis

The ^natPb sample data were parameterized using Eq. (1) to evaluate the in-beam γ-ray and scattered neutron background contributions. The ¹⁶⁵Ho sample, with ¹⁸¹Ta and ⁵⁹Co neutron filters, was used to determine the normalization factors f_n and fγ for the B_n and $B_{γ}$ components by matching the dips of the filtered spectra. The influence of the filters on the in-beam γ-rays and neutrons was carefully assessed by analyzing the neutron flux and energy distribution of the in-beam γ-rays [30]. The energy spectra of the neutrons and γ-rays produced at the spallation target were randomly sampled to analyze the incident particle energy spectra using the GEANT4 Monte Carlo code [31]; this step allowed simulations both with and without filters. The counts of the scattered neutrons and γ-rays were recorded at the detector position. The reduced attenuation factors for neutrons and γ-rays are found to be 0.92 and 0.68 [12], respectively, which are applied as corrections to f_n and fγ. Further information on the evaluation method used in this study is reported elsewhere [12]. $B (E_{n}) = f_{γ} B_{γ} (E_{n}) + f_{n} B_{n} (E_{n})$ (1) where $B_{γ}$ and B_n denote the background contributions of the in-beam γ-rays and scattered neutrons, respectively, and can be formulated using Eqs. (2–3). $B_{γ} (E_{n}) = b \times e^{- c / \sqrt{E_{n}}} + d \times e^{- e \times \sqrt{E_{n}}} + f$ (2) $B_{n} (E_{n}) = \frac{a}{\sqrt{E_{n}}}$ (3) The experimental neutron capture yield can be calculated as a function of neutron energy using Eq. (4). $Y_{exp} (E_{n}) = \frac{1}{f_{n}} \frac{S (E_{n}) - B (E_{n})}{ϵ_{c} \times Φ (E_{n})}$ (4) where E_n is the incident neutron energy converted from the neutron TOF spectra by using a relativistic relationship; $S (E_{n})$ is the ¹⁶⁵Ho sample count; B(E_n) is the evaluated background; and Φ(E_n) is the neutron flux. The normalization factor f_n, determined by self-normalizing the measured capture yield of the 4.9-eV resonance of ¹⁹⁷Au, accounts for the absolute incident neutron flux. $ϵ_{c}$ is the detection efficiency for a captured event. The total-energy detection principle was utilized by combining the aforementioned C₆D₆ detection system with the pulse height weighting technique (PHWT) [32, 33] to achieve proportionality between ϵc and the total γ-ray energy (E_c) released in the capture event. Therefore, we can express $ϵ_{c} = k E_{c} = k (S_{n} + E_{cm})$ , where S_n is the neutron separation energy (6.24 MeV) of the compound nucleus, E_cm is the center of mass energy of the incident neutron, and the proportionality factor k is set as 1 MeV^-1. In the analysis of the ¹⁶⁵Ho(n,γ)¹⁶⁶Ho measurements, the established thresholds were $E_{dep}^{min} = 250$ keV and $E_{dep}^{max} = 7$ MeV, corresponding to the Compton edges for γ-ray energies of 124 keV and 6.75 MeV, respectively. The weighted function (WF), as a 5^th order polynomial function, was fitted using the Geant4 Monte Carlo code to simulate the C₆D₆ detector’s response for 27 different monoenergetic γ-rays from 0.1 MeV to 10 MeV. This WF was then applied to all the $S (E_{n})$ and B(E_n) spectra for data analysis.

The resonance shape analysis code SAMMY [34] was used to fit the measured neutron capture yield with Eqs.(4). In the SAMMY code, the reaction cross-section is described by a multilevel multichannel Reich–Moore formalism, which only depends on the properties of the nuclear excitation state. This code considers all experimental conditions, such as multiple interacting events, sample characteristics, self-shielding, broadening of resonances due to thermal motion, and the experimental resolution of the CSNS Back-n facility [35]. During the fitting process, the initial resonance parameters were obtained from the evaluated nuclear data library ENDF/B-VIII.0 [36] and iteratively refined until convergence. The resonance parameters, including the resonance energy and capture kernels, were determined by SAMMY fitting within the resonance region up to 100 eV, where individual neutron resonances were fitted with high precision. Based on these resonance parameters, the resonance cross-sections for the ¹⁶⁵Ho(n, γ)¹⁶⁶Ho reaction were reconstructed. However, the resonance structures could not be adequately resolved beyond approximately 100 eV because of deterioration in the experimental resolution and reduced event statistics with increasing neutron energy. Consequently, an average neutron capture cross-section was directly derived from the measured neutron capture yield in the unresolved resonance range using 5 (where N_s represents the areal density of the sample). In this case, the measured capture yield was corrected for multiple scattering and self-shielding effects using the Geant4 code, which accounted for sample composition, geometry, and both neutron scattering and capture cross-sections. Subsequently, the ¹⁶⁵Ho neutron capture cross-section was determined relative to that of the standard ¹⁹⁷Au sample [37] within the neutron energy range from 2 keV to 1 MeV. $σ_{γ} = \frac{Y_{exp} (E_{n})}{N_{s}}$ (5) The uncertainties in the experimental data were attributed to both statistical and systematic errors. The systematic errors were evaluated based on the contributions from various sources, including the energy-dependent neutron flux shape (4.5% below 150 keV and 8.0% above this threshold), normalization (1%), background subtraction using filters (approximately 8.6%), sample impurities (0.01%), and the calculation of PHWT (3%). The sum of these components yielded an overall systematic uncertainty of 10.2%(12.2%) for the capture cross-section.

Data records

For each neutron pulse, the data from three different types of detectors were recorded and stored simultaneously. The first type is a proton beam counter, which is monitored by the pickup detector of the Proton Synchrotron accelerator. The second type was a neutron flux counter composed of eight SiMon detectors. These two data types were utilized for cross-validation and normalization of various measurements. The third type includes event information for the radiative neutron capture recorded by four C₆D₆ scintillator detectors. All the aforementioned data were acquired using the fully digital data acquisition system of the CSNS Back-n [29], with event-by-event connectivity based on the CERN ROOT code. For each neutron capture event, the deposited energy, represented as the pulse height spectrum in the C₆D₆ detector, and TOF information of the incident neutrons were recorded. Table 2 summarizes the event information for all the samples used in the measurements. The data records are organized in a Tree format according to the CERN ROOT version 5.34 and consist of two branch datasets: “NeuDataTree” and “SiDataTree.” “NeuDataTree” recorded data from four C₆D₆ detectors, including nine leaves: GPSsec (triggering time in seconds), GPSnsec (triggering time in nanoseconds), T0id (trigger T0 identification number), BCid (detector identification number), Energy (neutron energy spectrum), Tof (time-of-flight spectrum), Ph (pulse height spectrum), PeakValue (pulse amplitude), and PeakPoint (pulse timing information). “SiDataTree,” on the other hand, contained data from eight SiMon detectors, organized into six leaves: GPSsec (triggering time in seconds), GPSnsec (triggering time in nanoseconds), T0id (trigger T0 identification number), BCid(detector identification number), SiTof (time-of-flight spectrum), and SiPeakValue (pulse amplitude). This structured organization of data enables efficient storage and facilitates detailed analysis of the time, energy, and spectral characteristics captured by the detectors.

Summary of the event information for all the samples

Sample	Measurement time	Document number	Number of files
¹⁶⁵Ho	52 h 56 m	15935,15955	1085
¹⁹⁷Au	5 h16 m	15927,15946	102
^natPb	9 h 41 m	15931,15950	182
Empty holder	12 h 48 m	15944,15956	190

All the raw data described in this paper have been uploaded to the Science Data Bank. A direct link to the dataset is available at (https://doi.org/10.57760/sciencedb.21041https://doi.org/10.57760/sciencedb.21041).

Technical validation

Figure 3 compares the SAMMY fitting results (red lines) with the measured capture yields (black circles), for the ¹⁶⁵Ho(n, γ)¹⁶⁶Ho reaction, across neutron energy ranges below 100 eV. Good agreement is observed between the measured and SAMMY fitting results, both in terms of resonance energy and spectral shape. The resonance energies E_R, radiative width Γ_γ, neutron width Γ_n, and capture kernels k ( $k = g Γ_{n} Γ_{γ} / (Γ_{n} + Γ_{γ})$ , g is a statistical factor) obtained in this study are compared with the data from the ENDF/B-VIII.0 library [36], as detailed in Table 3. The experimental capture resonance parameters are in good agreement with the ENDF/B-VIII.0 values in the energy range below 100 eV. However, disparities are observed in the energy range between 100 eV and 2 keV due to the degradation of the experimental resolution function encountered at the CSNS Back-n facility during this measurement.

Fig. 3

(Color online) SAMMY fitting (red lines) to the measured capture yields (black circles) of ¹⁶⁵Ho(n, γ)¹⁶⁶Ho reaction

Resonance parameters up to a neutron energy of 100 eV for the ¹⁶⁵Ho (n, γ) cross-sections

J	This work				ENDF/B-VIII.0
	E_R (eV)	Γ_n (meV)	Γ_γ (meV)	k	E_R (eV)	Γ_n (meV)	Γ_γ (meV)	k
4	3.91 ± 0.01	1.28 ± 0.01	129.10 ± 0.13	0.71 ± 0.01	3.91	2.13	85.70	1.17
3	8.17 ± 0.02	0.20 ± 0.01	98.66 ± 0.06	0.09 ± 0.01	8.17	0.19	90.30	0.08
4	12.68 ± 0.07	11.73 ± 0.15	122.82 ± 0.17	6.02 ± 0.04	12.69	10.31	84.00	5.17
3	18.24 ± 0.02	1.56 ± 0.18	159.76 ± 0.45	0.67 ± 0.06	18.25	0.95	78.10	0.41
4	21.16 ± 0.04	0.58 ± 0.02	167.16 ± 0.13	0.32 ± 0.01	21.19	0.52	68.00	0.29
3	28.38 ± 0.10	0.01 ± 0.01	16.50 ± 0.26	0.00 ± 0.00	24.79	0.02	84.00	0.01
3	35.58 ± 0.02	7.01 ± 0.08	184.08 ± 0.50	2.95 ± 0.03	35.33	8.69	73.60	3.40
4	37.41 ± 0.08	0.52 ± 0.02	162.36 ± 0.28	0.29 ± 0.01	37.36	0.50	83.00	0.28
4	39.76 ± 0.02	17.98 ± 0.02	193.14 ± 0.36	9.25 ± 0.01	39.67	16.80	88.00	7.94
3	47.82 ± 0.03	16.56 ± 0.16	329.52 ± 0.64	6.90 ± 0.06	47.80	28.23	92.00	9.45
3	51.57 ± 0.02	129.27 ± 0.12	95.13 ± 0.13	23.98± 0.03	51.55	56.57	85.00	14.86
4	54.50 ± 0.04	3.55 ± 0.53	241.76 ± 0.94	1.97 ± 0.19	54.42	2.40	84.00	1.31
4	65.23 ± 0.03	17.11 ± 0.15	360.22 ± 0.65	9.19 ± 0.07	65.15	18.67	77.00	8.45
4	69.01 ± 0.12	1.14 ± 0.06	269.18 ± 0.37	0.64 ± 0.03	68.91	1.10	89.00	0.61
4	72.12 ± 0.03	20.31 ± 0.03	218.50 ± 0.67	10.45± 0.02	71.93	20.44	74.00	9.01
3	-	-	-	-	75.08	0.09	84.00	0.04
4	80.30 ± 0.04	3.69 ± 0.08	1.80 ± 0.24	0.68 ± 0.03	80.10	1.55	82.00	0.85
4	-	-	-	-	83.80	13.51	67.00	6.32
3	84.15 ± 0.07	20.08 ± 0.05	397.93 ± 0.20	10.75± 0.02	84.73	5.60	84.00	2.30
3	85.96 ± 0.32	46.34 ± 0.68	293.48 ± 0.89	24.08± 0.17	85.80	37.37	84.00	11.32
4	93.80 ± 0.03	45.31 ± 0.33	515.19 ± 0.72	23.43± 0.13	93.63	73.78	79.00	21.46

Figure 4 compares the ¹⁶⁵Ho(n,γ)¹⁶⁶Ho cross-sections calculated using TALYS-1.9 [38] with the results reconstructed based on the SAMMY resonance fitting for neutron energies below 100 eV. In Fig. 5, the measured neutron capture cross-sections in the energy range of 2 keV to 1 MeV are displayed with the results calculated using TALYS-1.9 and the data derived from the ENDF/B-VIII.0 library [36]. These comparison results demonstrate that the cross-sections determined in this study were accurately reproduced by both the TALYS-1.9 calculations and evaluated data across the investigated full neutron energy range. These results confirm that the experimental apparatus and data analysis methodologies are reliable and effective.

Fig. 4

(Color online) Comparison of ¹⁶⁵Ho(n, γ)¹⁶⁶Ho cross-sections, reconstructed from SAMMY resonance fitting, up to a neutron energy of 100 eV, with the calculations from TALYS code version 1.9 [38]

Fig. 5

(Color online) Comparisons of the neutron capture cross-section of ¹⁶⁵Ho, measured in this study, with the TALYS-1.9 calculations [38] and ENDF/B-VIII.0 evaluated data [36] from 2 keV to 1 MeV

Usage notes

The obtained dataset presents newly measured cross-sections for the ¹⁶⁵Ho(n, γ)¹⁶⁶Ho reaction studied at the CSNS Back-n facility. Our objective is to comprehensively document the data analysis procedures and make the neutron capture data accessible to both the nuclear physics community and researchers working in related fields for future studies. This dataset has numerous applications in nuclear physics, particularly in the following areas:

(1) The spectroscopic information of heavy nuclei is challenging to obtain experimentally because of the rapid increase in the nuclear level density (NLD) with increasing excitation energies. To address this, statistical models provide a framework for understanding the internal structure of these nuclei at higher energies, relying on key parameters such as the NLD and γ-ray strength function (γSF). These parameters are essential for a wide array of calculations in nuclear reactions, particularly for determining the neutron capture reaction cross-sections. The accuracy of these calculations is vital for evaluating the reliability of the nuclear models. In this context, ¹⁶⁶Ho, which is an odd–odd deformed nucleus, plays a significant role. The ¹⁶⁵Ho(n, γ)¹⁶⁶Ho neutron-capture reaction is a crucial tool for validating theoretical descriptions of the NLD and γSF. By examining this reaction, researchers can test and refine the predictive power of nuclear models, thereby enhancing our understanding of the underlying nuclear structures and reaction dynamics.

(2) The nucleosynthesis of elements heavier than iron is considered one of the "11 Biggest Unsolved Mysteries in Physics" that require urgent attention in this century. Nuclear astrophysicists generally agree that slow neutron capture (s-process) and rapid neutron capture (r-process) are the primary mechanisms governing the production of these heavier elements. Holmium, an important rare-earth element, is primarily produced through explosive r-process nucleosynthesis, with approximately 9% of its abundance synthesized in the main s-process during the evolution of intermediate-mass stars. The isotope ¹⁶⁶Ho is a significant branching nucleus, characterized by a ground-state half-life of 26.9 h and an isomeric state (7^-) with a half-life of 1200 years, primarily formed by the neutron capture of ¹⁶⁵Ho. Consequently, the ¹⁶⁵Ho(n, γ)¹⁶⁶Ho reaction not only depletes the abundance of ¹⁶⁵Ho but also influences the abundance of ¹⁶⁶Ho and the subsequent s-process nucleosynthesis products. Therefore, this reaction cross-section is critically important for the study of nucleosynthesis in nuclear astrophysics.

(3) Holmium has extensive applications in nuclear medicine, particularly the $β^{-}$ and γ-emitting isotope ¹⁶⁶Ho[ $T_{1 / 2} = 26.9$ h, $E_{β} = 1.77$ MeV (48%) and 1.85 (51%) MeV, $E_{γ} = 81$ keV (6.7%)], which has been developed for radionuclide therapy and single photon emission computed tomography (SPECT) imaging due to its favourable decay properties. The isotope ¹⁶⁵Ho is the only naturally stable isotope of Ho (^natHo) and is used to produce ¹⁶⁶Ho through the (n, γ) reaction. Accurate data on the neutron capture cross-section and resonance integral for the ¹⁶⁵Ho(n, γ)¹⁶⁶Ho reaction are essential for evaluating the neutron irradiation time, activity, and yield of ¹⁶⁶Ho produced in nuclear reactors.

Code availability

Publication of the dataset is accompanied by a software package based on CERN ROOT version 5.34/34 [26], which includes examples for reading the data, generating pulse-height spectra of neutrons, performing background subtraction, analyzing neutron resonances, and deriving neutron capture cross-sections.

In the dataset, the neutron energy range from 0.2 eV to 2 MeV was logarithmically divided into 3500 bins. The bin intervals and quantities can be reallocated according to a user’s range of interest. Two classes, C₆D₆ Data and LiSi Data, are defined to read the corresponding data from the ROOT file. The TChain function was used to read all the ROOT files under the same experimental conditions. For the C₆D₆ data, the neutron energy thresholds were set to $E_{dep}^{min} = 250$ keV and $E_{dep}^{max} = 7$ MeV, with the following detector parameters:

C₆D₆:1 C₆D₆Data₁.BCid=1, Min:bin=2822, Max:bin=78865;

C₆D₆:2 C₆D₆Data₁.BCid=2, Min:bin=2822, Max:bin=78865;

C₆D₆:3 C₆D₆Data₁.BCid=3, Min:bin=2807, Max:bin=78342;

C₆D₆:4 C₆D₆Data₁.BCid=4, Min:bin=2890, Max:bin=80629.

For the LiSi data, the signals from eight LiSi detectors were divided into two paths for storage with the following parameters:

LiSi:1 LiSiData₁.BCid=5

LiSi:1 LiSiData₁.BCid=6

During the in-beam experiment, there was an issue with the second signal from the LiSi detector (LiSiData₁.BCid=6). Thus, the first signal(LiSiData₁.BCid=5) was selected for data processing. The reaction between neutrons and ⁶Li primarily generates helium (α) and tritium nuclei (T), resulting in a bimodal structure in the energy spectrum. Owing to the high-energy peak (2.73 MeV) of T, saturation may have occurred during the experiment, leading to a poor statistical performance. Therefore, the α peak was selected as the effective neutron count for the LiSi detector to determine neutron flux. More detailed information related to the data analysis code can be accessed as a notebook in the Science Data Bank, where the complete dataset for this study has been uploaded. A direct link to the dataset is available at: (https://doi.org/10.57760/sciencedb.21041https://doi.org/10.57760/sciencedb.21041).

References

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