Measurements of the ¹⁹⁷Au(n, γ) cross section up to 100 keV at the CSNS Back-n facility Enhanced Publication

Measurements of the 197 Au(n, γ ) cross section up to 100 keV at the CSNS Back-n facility 1 2 first-author 3 4 5 6 3 corresp Long-Xiang Liu liulongxiang@zjlab.org.cn Long-Xiang Liu liulongxiang@zjlab.org.cn liulongxiang@zjlab.org.cn 2 3 corresp Hong-Wei Wang wanghongwei@zjlab.org.cn Hong-Wei Wang wanghongwei@zjlab.org.cn wanghongwei@zjlab.org.cn 7 1 2 4 5 1 2 1 2 1 1 1 2 8 8 9 10 10 11 11 11 Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China University of Chinese Academy of Sciences, Beijing 100049, China University of Chinese Academy of Sciences, Beijing 100049, China Shanghai Advanced Research Institute, Chinese Academy of Sciences, Shanghai 201210, China Shanghai Advanced Research Institute, Chinese Academy of Sciences, Shanghai 201210, China Institute of High Energy Physics, Chinese Academy of Sciences, Beijing 100049, China Institute of High Energy Physics, Chinese Academy of Sciences, Beijing 100049, China Spallation Neutron Source Science Center, Dongguan 523803, China Spallation Neutron Source Science Center, Dongguan 523803, China Key Laboratory of Nuclear Data, China Institute of Atomic Energy, Beijing 102413, China Key Laboratory of Nuclear Data, China Institute of Atomic Energy, Beijing 102413, China Xiangtan University, Xiangtan 411105, China Xiangtan University, Xiangtan 411105, China Institute of Nuclear Physics, Inner Mongolia University for the Nationalities, Tongliao 028000, China Institute of Nuclear Physics, Inner Mongolia University for the Nationalities, Tongliao 028000, China Sun Yat-sen University, Zhuhai 510275, China Sun Yat-sen University, Zhuhai 510275, China Henan Normal University, Xinxiang 453007, China Henan Normal University, Xinxiang 453007, China Beijing Normal University, Beijing 100875, China Beijing Normal University, Beijing 100875, China The neutron capture cross section of 197 Au was measured using the time-of-flight (TOF) technique at the Back-n facility of the China Spallation Neutron Source (CSNS) in the 1 eV to 100 keV range. Prompt γ -rays originating from neutron-induced capture events were detected by four C 6 D 6 liquid scintillator detectors. Pulse height weighting technology (PHWT) was used to analyze the data. The results are in good agreement with ENDF/B-VIII.0, CENDL-3.1, and other evaluated libraries in the resonance region, and in agreement with both n_TOF and GELINA experimental data in the 5-100 keV range. Finally, the resonance peaks in the energy range from 1 eV to 1 keV were fitted by the SAMMY R-matrix code. Cross section 197 Au( n , γ ) Back-n C 6 D 6 Pulse height weighting technology 1 Introduction 1 Neutron-induced reactions play an essential role in the synthesis of the heavy elements of the universe, and approximately half of the chemical elements heavier than iron are produced by the slow neutron capture process (s process) in stars [ 1 1 - 4 4 1-4 ]. Most neutron capture cross-sections are measured relative to the cross-section standards and normalized to absolute values. To date, the cross section of the 197 Au(n, γ ) reaction with thermal neutron energy up to 2.5 MeV is the only capture criterion, while most neutron capture cross-section measurements refer to one or both energy regions [ 5 5 ]. Using the standard neutron capture cross-section data from the ENDF/B-VIII.0 database [ 6 6 ], we can check the feasibility of our experimental setup and method. We use the C 6 D 6 detector system to measure the decay of gamma rays emitted from the compound nucleus owing to its low sensitivity to neutrons and short response time [ 7 7 ]. The 197 Au(n, γ ) cross section was measured from 1 eV to 100 keV owing to the influence of the gamma flash from a white neutron source at high neutron energy regions. We then analyzed the experimental data using the pulse height weighting technique (PHWT), and compared our experimental data with the evaluation data of the evaluated nuclear data file (ENDF). Finally, we used SAMMY code [ 37 37 ] to fit the experimental data in the resonance energy range from 1 eV to 1 keV and extracted the corresponding resonance parameters. The remainder of this paper is organized as follows: A detailed introduction of the C 6 D 6 detector system at Back-n is given in Sect. 2. The raw data analysis using the PHWT method for neutron capture cross-sections is presented in Sect. 3. Finally, conclusions and uncertainty analysis are presented in Sect. 4. 2 Measurements 1 The China Spallation Neutron Source (CSNS) [ 9 9 , 10 10 ] is the first spallation neutron source facility that provides a pulsed neutron beam with energy from thermal energy to 400 MeV in China [ 11 11 , 12 12 ]. The neutron beam is produced through the pulses of protons with an energy of 1.6 GeV and a pulse frequency of 25 Hz, bombarding a tungsten (W) target. The Back-n white neutron beamline is constructed 180 to the proton beam direction, and the neutron flux can reach up to 10 7 n/cm 2 /s at the experimental station (ES). There are two experimental stations on the Back-n beamline, as shown in Fig. 1 Fig. 1 ; ES#1 is approximately 55 m from the spallation target, which mainly studies the ( n , lcp (light charge particle)) reaction cross section, and ES#2 is approximately 76 m, which is mainly for the measurements of (n, γ ), (n, tot ), and (n, f ) reactions cross sections [ 13 13 - 16 16 13-16 ]. 2.1 The C 6 D 6 detector system in Back-n neutron beamline 2 The Back-n C 6 D 6 detector system consists of four C 6 D 6 liquid scintillation detectors, one aluminum detector’s brackets, and one aluminum sample holder, as shown in Fig. 2 Fig. 2 . The C 6 D 6 detectors are placed upstream of the neutron beam sample target to decrease the elastic scattering neutron background, and the detector axis is at an angle of 110 °from the neutron beam. The distance between the C 6 D 6 detectors front center to the sample target center was 150 mm and 80 mm from the neutron beam axis. The C 6 D 6 detector is a liquid scintillator EJ315 [ 17 17 ] produced by the ELJEN Technology Corporation. The shell of the scintillator shell is made of aluminum owing to its low capture rate, with a diameter and length of 130 mm and 76.2 mm, respectively. The structure of the detector system used in the Geant4 simulation is shown in Fig. 3 Fig. 3 . In the neutron capture cross-section measurements, the amplitude of the anode signals of the C 6 D 6 detectors is from 0.01 to 3 V. Signals from the C 6 D 6 detectors are delivered to the readout electronics, which can digitize the analog signals into a full waveform with a 1 GS/s sampling rate and 12 bits resolution [ 18 18 ]. The neutron start time T 0 signals are picked up by the pulsed proton beam, while the stop time T s of the neutrons that have reacted in the sample is picked up by the C 6 D 6 detectors; further, the electronics record these signals so that the incident neutron energy can be determined using the time-of-flight (TOF) technique. The energy of the incident neutron ( E n ) is given by Eq. (1), and the neutron energy resolution is calculated using Eq. (2) [ 19 19 ], <math display="block" id="M1"><mrow><msub><mi>E</mi><mtext>n</mtext></msub><mo>=</mo><mfrac><mn>1</mn><mn>2</mn></mfrac><msub><mi>m</mi><mtext>n</mtext></msub><msup><mi>v</mi><mn>2</mn></msup><mo>=</mo><msup><mrow><mrow><mo>(</mo><mrow><mfrac><mrow><mn>72.2977</mn><mi>L</mi></mrow><mrow><mi>t</mi><mi>o</mi><mi>f</mi></mrow></mfrac></mrow><mo>)</mo></mrow></mrow><mn>2</mn></msup><mn>,</mn></mrow></math> <math display="block" id="M2"><mrow><mfrac><mrow><mi>Δ</mi><msub><mi>E</mi><mtext>n</mtext></msub></mrow><mrow><msub><mi>E</mi><mtext>n</mtext></msub></mrow></mfrac><mo>=</mo><mn>2</mn><msqrt><mrow><msup><mrow><mrow><mo>(</mo><mrow><mfrac><mrow><mi>Δ</mi><mi>L</mi></mrow><mi>L</mi></mfrac></mrow><mo>)</mo></mrow></mrow><mn>2</mn></msup><mo>+</mo><msup><mrow><mrow><mo>(</mo><mrow><mfrac><mrow><mi>Δ</mi><mi>t</mi><mi>o</mi><mi>f</mi></mrow><mrow><mi>t</mi><mi>o</mi><mi>f</mi></mrow></mfrac></mrow><mo>)</mo></mrow></mrow><mn>2</mn></msup></mrow></msqrt><mn>,</mn></mrow></math> where the flight length L = L 0 +Δ L ( E n ), L 0 is the geometric distance from the spallation target to the sample, and Δ L ( E n ) is the equivalent change in moderation length associated with the incident neutron energy. E n , L , and tof = T s - T 0 are in units of MeV, m, and ns, respectively. In addition, the setup of the capture measurements is complemented by a silicon flux monitor (SiMon); the SiMon consists of a thin 6 LiF conversion layer and eight silicon detectors outside the neutron beam (Li-Si Monitor) to count the number of neutrons by detecting alpha particles and 3 H through the reaction 6 Li(n, α ) 3 H [ 20 20 ]. 2.2 Samples 2 The gold sample(Au) with Φ 50舁mm × 1舁mm, natural C sample with Φ 50舁mm × 1舁mm, and natural Pb sample (an additional experiment with a proton power of 80 kW) with Φ 30舁mm × 0.53舁mm are shown in Table 1 Table 1 . The nat C and empty samples were used for background subtraction in our experiment because of sample scattered neutrons and γ rays from the surroundings, and the nat Pb sample was used for subtracting the in-beam γ -ray background. 1 1 Sample 1 1 Diameter(mm) 1 1 Thickness(mm) 1 1 Weight(g) 1 1 Area(cm 2 ) 1 1 Area density Atoms/Barn 1 1 197 Au 1 1 50 1 1 1 1 1 37.93 1 1 19.63 1 1 5.907×10 -3 1 1 nat C 1 1 50 1 1 1 1 1 4.42 1 1 19.63 1 1 1.128×10 -2 1 1 nat Pb 1 1 30 1 1 0.53 1 1 4.24 1 1 7.07 1 1 1.748×10 -3 1 1 Empty target 1 1 - 1 1 - 1 1 - 1 1 - 1 1 - 3 Analysis of the C 6 D 6 data 1 The C 6 D 6 detector system is one of the total energy detection systems primarily used for neutron capture cross-section measurements [ 19 19 ]. Because of the low detection efficiency of γ rays and the detection efficiency being directly proportional to the γ ray energy, the pulse height weighting technique (PHWT) was used in the data analysis. 3.1 From measured count rate to capture yield 2 The experimental yield Y exp is obtained as a function of the neutron energy E n from the weighed rate N W through the PHWT [ 21 21 , 22 22 ] <math display="block" id="M3"><mrow><msub><mi>Y</mi><mrow><mtext>exp</mtext></mrow></msub><mo>=</mo><msub><mi>f</mi><mtext>N</mtext></msub><mfrac><mrow><msub><mi>N</mi><mtext>W</mtext></msub></mrow><mrow><mi>I</mi><msub><mi>E</mi><mtext>c</mtext></msub></mrow></mfrac><mn>,</mn></mrow></math> where Y exp , N W , and the neutron intensity I depend on the TOF or neutron energy; the weighted count rate N W is described in the following sections. The neutron intensity I ( E n ) is proportional to the total number of neutrons interacting with the sample with energy E n , as shown in Fig. 4 Fig. 4 . The fixed fraction f N is the yield normalization factor for flux calibration, which was normalized to one at 4.9 eV owing to the saturated resonance of the thick gold sample. E c represents the total capture energy, which for the kinetic energy E n of the center-of-mass frame is given by E c = E n + S n , where S n =6.512 MeV is the neutron separation energy of the compound nuclei 198 Au. 3.2 Pulse height weighting technique 2 In 1963, Moxon and Rae [ 24 24 ] first proposed the principle of the PHWT and constructed a simple gamma detector consisting of a carbon disk and a thin plastic scintillator. Macklin and Gibbons [ 25 25 ] first applied a pair of C 6 F 6 detectors to neutron capture cross-section studies in 1967. Using this technique, the detection efficiency is proportional to the gamma energy; thus, ϵ γ = c·E γ . Because <math id="M4"><mrow><msub><mi>ϵ</mi><mi>γ</mi></msub><mo>≪</mo><mn>1</mn></mrow></math> and E c = E n + S n , the capture efficiency ϵ c can be written as [ 7 7 ] To validate the equation, we introduced the weighting function (WF) W ( E i ) as follows: <math display="block" id="M6"><mrow><mi>W</mi><mo stretchy="false">(</mo><msub><mi>E</mi><mi>i</mi></msub><mo stretchy="false">)</mo><mo>=</mo><mstyle displaystyle="true"><munderover><mo>∑</mo><mrow><mi>k</mi><mo>=</mo><mn>0</mn></mrow><mn>4</mn></munderover></mstyle><msub><mi>a</mi><mi>k</mi></msub><msub><mi>E</mi><mi>i</mi></msub><msup><mrow/><mi>k</mi></msup><mn>.</mn></mrow></math> The WFs used for the present measurements were obtained from the response functions of mono-energetic γ -rays, which were calculated using Monte Carlo simulations of the experimental setup with Geant4.10.06 [ 26 26 - 28 28 26-28 ]. The simulated γ -rays with energies ranging from 0.15 to 7 MeV were produced from the volume (surface) of the gold sample, and then emitted homogeneously; further, part of the gamma ray was deposited energy in the C 6 D 6 detectors. The simulated γ -ray energy deposition spectrum or pulse height (PH) spectrum is shown in Fig. 5 Fig. 5 ; the energy threshold was 100 keV. Moreover, the original detection efficiency of the primary C 6 D 6 setup is approximately 2%, the weighted efficiency has a fixed linear relationship with γ -ray energy, and the ratios of each energy point are very close to those shown in Fig. 6a Fig. 6a . We compared the γ -rays emitted from the volume of the gold sample and from the surface of the sample, and there was little difference between the two modes of emissions. The χ 2 method is applied to ensure that the WF parameters a k use gamma-ray energy ranging from 0.15 to 7 MeV, as shown in Eq. (5) or Eq. (6) <math display="block" id="M7"><mrow><msup><mi>χ</mi><mn>2</mn></msup><mo>=</mo><mstyle displaystyle="true"><munder><mo>∑</mo><mi>i</mi></munder></mstyle><msup><mrow><mrow><mo>[</mo><mrow><mi>c</mi><msub><mi>E</mi><mrow><mi>γ</mi><mi>j</mi></mrow></msub><mo>−</mo><mstyle displaystyle="true"><mrow><msubsup><mo>∫</mo><mrow><msub><mi>E</mi><mi>L</mi></msub></mrow><mi>∞</mi></msubsup></mrow></mstyle><mi>R</mi><mrow><mo>(</mo><mrow><msub><mi>E</mi><mtext>d</mtext></msub><mn>,</mn><msub><mi>E</mi><mrow><mi>γ</mi><mi>j</mi></mrow></msub></mrow><mo>)</mo></mrow><mi>W</mi><mrow><mo>(</mo><mrow><msub><mi>E</mi><mtext>d</mtext></msub></mrow><mo>)</mo></mrow><mtext>d</mtext><msub><mi>E</mi><mtext>d</mtext></msub></mrow><mo>]</mo></mrow></mrow><mn>2</mn></msup><mn>,</mn></mrow></math> <math display="block" id="M8"><mrow><msup><mi>χ</mi><mn>2</mn></msup><mo>=</mo><mstyle displaystyle="true"><munderover><mo>∑</mo><mrow><mi>j</mi><mo>=</mo><mn>1</mn></mrow><mrow><mn>16</mn></mrow></munderover></mstyle><msup><mrow><mrow><mo>[</mo><mrow><mstyle displaystyle="true"><munderover><mo>∑</mo><mrow><mi>i</mi><mo>=</mo><mn>0</mn></mrow><mrow><mn>700</mn></mrow></munderover></mstyle><mstyle displaystyle="true"><munderover><mo>∑</mo><mrow><mi>k</mi><mo>=</mo><mn>0</mn></mrow><mn>4</mn></munderover></mstyle><msub><mi>a</mi><mi>k</mi></msub><msup><mrow><mo stretchy="false">(</mo><mo stretchy="false">(</mo><mi>i</mi><mo>−</mo><mn>0.5</mn><mo stretchy="false">)</mo><mi>Δ</mi><mi>E</mi><mo stretchy="false">)</mo></mrow><mi>k</mi></msup><msubsup><mi>R</mi><mi>i</mi><mi>j</mi></msubsup><mo>−</mo><msub><mi>E</mi><mrow><mi>γ</mi><mi>j</mi></mrow></msub></mrow><mo>]</mo></mrow></mrow><mn>2</mn></msup><mn>.</mn></mrow></math> Usually, the constant factor c is set to one, and <math id="M9"><mrow><mi>R</mi><mo stretchy="false">(</mo><msub><mi>E</mi><mtext>d</mtext></msub><mn>,</mn><msub><mi>E</mi><mrow><mi>γ</mi><mi>j</mi></mrow></msub><mo stretchy="false">)</mo></mrow></math> or <math id="M10"><mrow><msubsup><mi>R</mi><mi>i</mi><mi>j</mi></msubsup></mrow></math> is the response function of the detectors of the j th γ -rays with an energy of E γ j from the Geant4 simulation, E d is the deposion gamma energy, and Δ E denotes the γ energy bin width of 10 keV. The weight function is solved by the ROOT Minuit method shown in Fig. 6b Fig. 6b . 3.3 From capture yield to cross section 2 In the experiment, we measured data from the gold sample, carbon sample to subtract the elastic scattering contribution, empty sample (beamOn) to subtract the ambient background, and lead sample to subtract the in-beam γ background. The raw counts from the experiment shown in Fig. 7a Fig. 7a were normalized to the SiMon rate. The experimental capture yield, as shown in Fig. 7b Fig. 7b , was normalized to a single neutron using the counts of the SiMon detectors. The weighted counts NW of the gold sample were deduced from the ambient background through the empty sample (beam on), neutron elastic scattering background through the carbon sample, and in-beam c-ray background through the natural lead sample, as expressed by Eq. (7), where N net , N Bkg , N C , and N Pb are the sample counts after subtracting the background, empty sample counts, natural carbon sample counts, and natural Pb sample counts, respectively. W is the weighting function of the detector system, and η is directly proportional to the product of the number of target nuclei per unit area and the elastic scattering cross section of the sample. In theory, the multiple scattering and self-shield-corrected capture yield [ 5 5 , 21 21 ] is related to the capture cross section rc, total cross section σ t (from ENDF’s evaluated database), density of the sample n, thickness of the sample t, and fixed factor f c of the sample thickness, which is related to the capture cross sections, as shown in Eq. (8). The experimental capture yield, as shown in Fig. 7b Fig. 7b , was normalized to a single neutron using the counts of the SiMon detectors. The weighted counts N W of the gold sample were deduced from the ambient background through the empty sample (beam on), neutron elastic scattering background through the carbon sample, and in-beam γ -ray background through the natural lead sample, as expressed by Eq. (7), where N net , N Bkg , N C , and N Pb are the sample counts after subtracting the background, empty sample counts, natural carbon sample counts, and natural Pb sample counts, respectively. W is the weighting function of the detector system, and η is directly proportional to the product of the number of target nuclei per unit area and the elastic scattering cross-section of the sample. In theory, the multiple scattering and self-shield-corrected capture yield [ 5 5 , 19 19 ] is related to the capture cross section σ c , total cross section σ t (from ENDF’s evaluated database), density of the sample n , thickness of the sample t , and fixed factor f c of the sample thickness, which is related to the capture cross sections, as shown in Eq. (8). <math display="block" id="M11"><mrow><msub><mi>N</mi><mtext>W</mtext></msub><mo>=</mo><msub><mi>N</mi><mrow><mtext>net</mtext></mrow></msub><mo>⋅</mo><mi>W</mi><mo>=</mo><mo stretchy="false">[</mo><msub><mi>N</mi><mrow><mtext>sample</mtext></mrow></msub><mo>−</mo><msub><mi>N</mi><mrow><mtext>Bkg</mtext></mrow></msub><mo>−</mo><mi>η</mi><mo stretchy="false">(</mo><msub><mi>N</mi><mtext>C</mtext></msub><mo>−</mo><msub><mi>N</mi><mrow><mtext>Bkg</mtext></mrow></msub><mo stretchy="false">)</mo><mo>−</mo><msub><mi>N</mi><mrow><mtext>Pb</mtext></mrow></msub><mo stretchy="false">]</mo><mo>⋅</mo><mi>W</mi></mrow></math> <math display="block" id="M12"><mrow><msub><mi>Y</mi><mrow><mtext>th</mtext></mrow></msub><mo stretchy="false">(</mo><msub><mi>E</mi><mtext>n</mtext></msub><mo stretchy="false">)</mo><mo>=</mo><mo stretchy="false">(</mo><mn>1</mn><mo>−</mo><msup><mi>e</mi><mrow><mo>−</mo><mi>n</mi><mi>t</mi><msub><mi>σ</mi><mi>t</mi></msub><mo stretchy="false">(</mo><msub><mi>E</mi><mtext>n</mtext></msub><mo stretchy="false">)</mo><msub><mi>f</mi><mtext>c</mtext></msub></mrow></msup><mo stretchy="false">)</mo><mfrac><mrow><msub><mi>σ</mi><mtext>c</mtext></msub><mo stretchy="false">(</mo><msub><mi>E</mi><mtext>n</mtext></msub><mo stretchy="false">)</mo></mrow><mrow><msub><mi>σ</mi><mtext>t</mtext></msub><mo stretchy="false">(</mo><msub><mi>E</mi><mtext>n</mtext></msub><mo stretchy="false">)</mo></mrow></mfrac></mrow></math> Then, combined with the experimental capture yield Y exp ( E n ), the present experimental capture cross-section formula is as follows: <math display="block" id="M13"><mrow><msub><mi>σ</mi><mtext>c</mtext></msub><mo stretchy="false">(</mo><msub><mi>E</mi><mtext>n</mtext></msub><mo stretchy="false">)</mo><mo>=</mo><mfrac><mrow><msub><mi>σ</mi><mtext>t</mtext></msub><mo stretchy="false">(</mo><msub><mi>E</mi><mtext>n</mtext></msub><mo stretchy="false">)</mo></mrow><mrow><mn>1</mn><mo>−</mo><msup><mi>e</mi><mrow><mo>−</mo><mi>n</mi><mi>t</mi><msub><mi>σ</mi><mtext>t</mtext></msub><mo stretchy="false">(</mo><msub><mi>E</mi><mtext>n</mtext></msub><mo stretchy="false">)</mo><msub><mi>f</mi><mtext>c</mtext></msub></mrow></msup></mrow></mfrac><msub><mi>Y</mi><mrow><mtext>exp</mtext></mrow></msub><mo stretchy="false">(</mo><msub><mi>E</mi><mtext>n</mtext></msub><mo stretchy="false">)</mo><mn>.</mn></mrow></math> Considering the multi-elastic scattering of neutrons in the thick sample, we introduced the factor f c , which is related to the sample’s absorption cross-section and the thickness of the sample. The factor f c is defined in Eq. (10). It is the ratio of the mean neutron transmission length <math id="M14"><mover accent="true"><mi>L</mi><mo>¯</mo></mover></math> (the addition of all step lengths extracted from the Geant4 simulation) to the target thickness t . <math display="block" id="M15"><mrow><msub><mi>f</mi><mtext>c</mtext></msub><mo>=</mo><mover accent="true"><mi>L</mi><mo>¯</mo></mover><mo>/</mo><mi>t</mi></mrow></math> Fig. 8 Fig. 8 shows the Geant4 simulated results of gold targets with thicknesses of 0.1 mm and 1 mm and neutrons with energy in the range from 0.1 eV to 100 keV. The negative peaks show strong resonance absorption, such as 4.9 eV (the first resonance peak in 197 Au target). The regions of the positive peaks indicate that neutrons multi-scattered in those elastic scattering energy regions. Thus, the sufficient thickness of the sample ( <math id="M16"><mover accent="true"><mi>L</mi><mo>¯</mo></mover></math> ) is larger than the thickness of the target when the factor f c larger than one. 4 conclusions and uncertainty analysis 1 The 197 Au(n, γ ) reaction cross section was experimentally measured with neutrons with energy from 1 eV to 100 keV, and the results were in good agreement with the latest 197 Au standard evaluated capture cross sections ENDF/B-VIII.0 [ 29 29 ], CENDL-3.1 [ 30 30 ], and JENDL-4.0 [ 31 31 ] in the entire tested energy region, as shown in Fig. 9 Fig. 9 . More detailed results in the resolved resonance region(RRR) are shown in Fig. 10a and Fig. 10b Fig. 10a and Fig. 10b , which indicates that this work has a good energy resolution. Among the peak values of the energy points, the present results are larger than those of the ENDFs owing to the background in the experiment, which cannot be deducted completely [ 32 32 - 35 35 32-35 ]. Fig. 10c Fig. 10c indicates that there are many resonances in the region of 2-5 keV in the experimental data, as well as in the CENDL-3.1 data, while the average cross-section data is still used in the ENDF/B-VIII.0 database for this region. In addition, the present data in the unresolved resonance region (URR) from 10 keV to 100 keV are generally in agreement with those of the evaluated databases, Lederer’s data [ 36 36 ] in 2011 and Massimi’s data [ 37 37 ] in 2014 shown in Fig. 10d Fig. 10d . Finally, the R-matrix code SAMMY(R6) [ 8 8 ] in the Reich-Moore multi-level approximation was used to analyze the resonance shape of the capture cross section in the energy region from 1 eV to 1 keV. The analysis included self-shielding and multiple corrections, and Doppler broadening with an effective temperature of 300 K using the free gas model (FGM). The R-matrix fitting results were in agreement with the experimental data shown in Fig. 11 Fig. 11 ). The fitting resonance parameters of the resonance energy ( E R ), gamma width (Γ γ ), and neutron width (Γ n ) are listed in Table 2 Table 2 . 1 2 E R (eV) 1 2 l 1 2 J π 3 1 Γ γ (meV) 3 1 Γ n (meV) 1 1 This work 1 1 ENDF/B-VIII.0 1 1 n_TOF 1 1 This work 1 1 ENDF/B-VIII.0 1 1 n_TOF 1 1 4.904 1 1 0 1 1 2 + 1 1 119.0 1 1 121.4 1 1 124.0 1 1 16.01 1 1 14.96 1 1 15.2 1 1 .70 1 1 0 1 1 1 + 1 1 132.0 1 1 127.0 1 1 128.0 1 1 0.190 1 1 0.220 1 1 0.223 1 1 .08 1 1 0 1 1 1 + 1 1 111.7 1 1 113.0 1 1 112.0 1 1 4.55 1 1 4.31 1 1 4.34 1 1 .31 1 1 0 1 1 2 + 1 1 113.5 1 1 118.0 1 1 110.0 1 1 88.80 1 1 70.66 1 1 73.9 1 1 .53 1 1 0 1 1 1 + 1 1 118.5 1 1 124.0 1 1 120.0 1 1 25.59 1 1 17.00 1 1 17.79 1 1 .04 1 1 0 1 1 2 + 1 1 110.2 1 1 123.0 1 1 110.0 1 1 10.31 1 1 7.83 1 1 8.29 1 1 .25 1 1 0 1 1 2 + 1 1 128.0 1 1 121.0 1 1 128.0 1 1 0.730 1 1 0.900 1 1 0.86 1 1 .46 1 1 0 1 1 1 + 1 1 121.0 1 1 121.0 1 1 120.0 1 1 3.90 1 1 9.07 1 1 9.35 1 1 .42 1 1 0 1 1 2 + 1 1 150.0 1 1 121.0 1 1 150.0 1 1 36.15 1 1 22.26 1 1 21.6 1 1 .13 1 1 0 1 1 1 + 1 1 197.0 1 1 129.0 1 1 197.0 1 1 67.88 1 1 55.16 1 1 42.5 1 1 .25 1 1 0 1 1 2 + 1 1 109.0 1 1 121.0 1 1 109.0 1 1 7.17 1 1 9.98 1 1 8.67 1 1 .04 1 1 0 1 1 1 + 1 1 132.0 1 1 121.0 1 1 130.0 1 1 58.98 1 1 49.08 1 1 49.8 1 1 .21 1 1 0 1 1 1 + 1 1 178.0 1 1 121.0 1 1 180.0 1 1 0.473 1 1 0.860 1 1 0.860 1 1 .65 1 1 0 1 1 2 + 1 1 99.6 1 1 121.0 1 1 99.6 1 1 74.17 1 1 74.16 1 1 86.6 1 1 .82 1 1 0 1 1 1 + 1 1 124.0 1 1 124.0 1 1 130.0 1 1 0.204 1 1 0.561 1 1 0.500 1 1 .26 1 1 0 1 1 1 + 1 1 129.0 1 1 129.0 1 1 124.0 1 1 325.6 1 1 144.0 1 1 152.0 1 1 .95 1 1 0 1 1 2 + 1 1 121.0 1 1 121.0 1 1 110.0 1 1 1.58 1 1 4.83 1 1 4.41 1 1 .56 1 1 0 1 1 2 + 1 1 135.7 1 1 126.0 1 1 123.6 1 1 587.2 1 1 364.0 1 1 348.0 1 1 .39 1 1 0 1 1 2 + 1 1 137.0 1 1 137.0 1 1 137.0 1 1 31.56 1 1 46.0 1 1 41.5 1 1 .92 1 1 0 1 1 1 + 1 1 130.0 1 1 130.0 1 1 130.0 1 1 45.19 1 1 62.18 1 1 56.2 1 1 .25 1 1 0 1 1 2 + 1 1 125.0 1 1 125.0 1 1 125.0 1 1 24.46 1 1 40.00 1 1 37.6 1 1 .36 1 1 0 1 1 2 + 1 1 121.0 1 1 121.0 1 1 99.0 1 1 289.7 1 1 85.88 1 1 109.0 1 1 .20 1 1 0 1 1 1 + 1 1 121.0 1 1 121.0 1 1 125.0 1 1 4.77 1 1 13.92 1 1 12.3 1 1 .13 1 1 0 1 1 2 + 1 1 98.0 1 1 121.0 1 1 97.0 1 1 45.15 1 1 63.11 1 1 73.9 1 1 .27 1 1 0 1 1 2 + 1 1 128.0 1 1 128.0 1 1 128.0 1 1 6.83 1 1 6.83 1 1 6.08 1 1 .68 1 1 0 1 1 1 + 1 1 140.0 1 1 140.0 1 1 140.0 1 1 19.35 1 1 26.96 1 1 25.8 1 1 .45 1 1 0 1 1 1 + 1 1 150.0 1 1 150.0 1 1 149.0 1 1 650.5 1 1 297.3 1 1 281.4 1 1 .15 1 1 0 1 1 2 + 1 1 111.0 1 1 128.6 1 1 110.0 1 1 28.14 1 1 63.50 1 1 63.7 1 1 .60 1 1 0 1 1 2 + 1 1 124.0 1 1 137.1 1 1 124.9 1 1 927.0 1 1 317.0 1 1 296.1 1 1 .90 1 1 0 1 1 1 + 1 1 138.0 1 1 138.0 1 1 138.0 1 1 17.68 1 1 60.83 1 1 62.2 1 1 .98 1 1 0 1 1 2 + 1 1 110.0 1 1 121.0 1 1 111.0 1 1 10.36 1 1 28.16 1 1 28.5 1 1 .13 1 1 0 1 1 2 + 1 1 130.0 1 1 130.0 1 1 130.0 1 1 9.01 1 1 66.01 1 1 31.8 1 1 .58 1 1 0 1 1 1 + 1 1 128.0 1 1 121.0 1 1 127.0 1 1 19.45 1 1 62.14 1 1 58.6 1 1 .68 1 1 0 1 1 2 + 1 1 128.0 1 1 128.0 1 1 128.0 1 1 3.36 1 1 2.95 1 1 2.44 1 1 .26 1 1 0 1 1 2 + 1 1 126.6 1 1 155.6 1 1 126.0 1 1 647.2 1 1 358.7 1 1 288.4 1 1 .16 1 1 0 1 1 1 + 1 1 123.0 1 1 114.7 1 1 122.0 1 1 306.8 1 1 146.2 1 1 306.8 1 1 .84 1 1 0 1 1 2 + 1 1 134.0 1 1 134.0 1 1 134.0 1 1 22.86 1 1 23.86 1 1 22.4 1 1 .99 1 1 0 1 1 2 + 1 1 112.5 1 1 119.5 1 1 113.0 1 1 42.70 1 1 227.4 1 1 223.9 1 1 .37 1 1 0 1 1 1 + 1 1 313.6 1 1 127.5 1 1 135.0 1 1 128.3 1 1 128.3 1 1 111.0 1 1 .72 1 1 0 1 1 1 + 1 1 121.0 1 1 121.0 1 1 121.0 1 1 20.8 1 1 30.86 1 1 53.4 1 1 .23 1 1 0 1 1 2 + 1 1 138.0 1 1 121.0 1 1 138.0 1 1 11.55 1 1 50.15 1 1 24.7 1 1 .96 1 1 0 1 1 2 + 1 1 120.0 1 1 132.1 1 1 118.5 1 1 510.7 1 1 510.6 1 1 464.0 1 1 .16 1 1 0 1 1 2 + 1 1 97.0 1 1 97.0 1 1 97.0 1 1 1.04 1 1 4.84 1 1 4.20 1 1 .27 1 1 0 1 1 1 + 1 1 128.0 1 1 128.0 1 1 128.0 1 1 6.64 1 1 19.89 1 1 16.8 1 1 .04 1 1 0 1 1 1 + 1 1 142.5 1 1 159.1 1 1 139.0 1 1 699.8 1 1 716.4 1 1 666.7 1 1 .44 1 1 0 1 1 2 + 1 1 244.2 1 1 111.3 1 1 110.0 1 1 800.0 1 1 699.8 1 1 736.1 1 1 .88 1 1 0 1 1 2 + 1 1 112.0 1 1 121.0 1 1 112.0 1 1 17.96 1 1 114.4 1 1 110.0 1 1 .72 1 1 0 1 1 1 + 1 1 120.0 1 1 120.0 1 1 120.0 1 1 1.76 1 1 12.08 1 1 10.6 1 1 .16 1 1 0 1 1 1 + 1 1 113.0 1 1 119.0 1 1 110.0 1 1 34.97 1 1 411.6 1 1 426.7 1 1 .04 1 1 0 1 1 1 + 1 1 127.0 1 1 136.0 1 1 125.0 1 1 480.9 1 1 431.9 1 1 474.6 1 1 .62 1 1 0 1 1 2 + 1 1 140.0 1 1 140.0 1 1 140.0 1 1 20.74 1 1 110.3 1 1 14.0 1 1 .40 1 1 0 1 1 2 + 1 1 124.0 1 1 142.0 1 1 123.0 1 1 178.0 1 1 157.8 1 1 177.6 1 1 .81 1 1 0 1 1 1 + 1 1 128.0 1 1 128.0 1 1 128.0 1 1 15.46 1 1 24.11 1 1 22.1 1 1 .78 1 1 0 1 1 2 + 1 1 128.0 1 1 128.0 1 1 128.0 1 1 240.0 1 1 253.9 1 1 232.0 1 1 .56 1 1 0 1 1 2 + 1 1 155.3 1 1 134.8 1 1 117.0 1 1 560.0 1 1 523.1 1 1 426.4 1 1 .10 1 1 0 1 1 2 + 1 1 121.0 1 1 121.0 1 1 107.0 1 1 4.90 1 1 20.94 1 1 18.4 1 1 .18 1 1 0 1 1 2 + 1 1 66.0 1 1 121.0 1 1 66.0 1 1 6.43 1 1 30.92 1 1 35.2 1 1 .61 1 1 0 1 1 2 + 1 1 126.0 1 1 134.7 1 1 124.0 1 1 754.2 1 1 429.8 1 1 340.0 1 1 .27 1 1 0 1 1 2 + 1 1 128.0 1 1 121.0 1 1 128.0 1 1 2.40 1 1 6.18 1 1 6.30 1 1 .51 1 1 0 1 1 2 + 1 1 150.0 1 1 157.3 1 1 150.0 1 1 9.01 1 1 49.2 1 1 49.2 1 1 .85 1 1 0 1 1 2 + 1 1 125.5 1 1 116.3 1 1 94.0 1 1 586.0 1 1 327.8 1 1 250.0 1 1 .89 1 1 0 1 1 2 + 1 1 160.0 1 1 121.0 1 1 160.0 1 1 34.28 1 1 125.2 1 1 94.0 1 1 .81 1 1 0 1 1 2 + 1 1 131.0 1 1 121.0 1 1 130.0 1 1 505.1 1 1 505.0 1 1 350.0 The 197 Au(n, γ ) neutron capture cross section was measured at the Back-n neutron beamline of the CSNS, which is aimed at verifying the rationality of the new C 6 D 6 setup for neutron capture cross-section measurements. 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Mu , H.T. Jing et al. , A possible scheme for the surface muon beamline at CSNS . Nucl. Sci. Tech. 30 , 169 ( 2019 ). doi: 10.1007/s41365-019-0648-1 http://doi.org/10.1007/s41365-019-0648-1 A possible scheme for the surface muon beamline at CSNS All authors contributed to the study conception and design. Material preparation, data collection, and analysis were preformed by Hong-Wei Wang, Xin-Rong Hu, Long-Xiang Liu, and Gong-Tao Fan. The first draft of the manuscript was written by Xin-Rong Hu and all authors commented on previous of the manuscript. All authors read and approved the final manuscript. The authors would like to thank colleagues from the Back-n facility as well as Prof. Gui-Lin Zhang for his advice on data analysis. 10.1007/s41365-021-00931-w National Natural Science Foundation of China (Nos.11875311, 11905274, 11705156, and 11605097) and the Strategic Priority Research Program of the Chinese Academy of Sciences (No. XDB34030000). 2021-02-01 2021-06-17 2021-06-20 2021-09-13 2021-09-01 2022-10-11 © China Science Publishing & Media Ltd. (Science Press), Shanghai Institute of Applied Physics, the Chinese Academy of Sciences, ChineseNuclear Society and Springer Nature Singapore Pte Ltd. 2021 This is a post-peer-review, pre-copyedit version of an article published in Nuclear Science and Techniques. The final authenticated version is available online at: http://dx.doi.org/10.1007/s41365-021-00931-w http://dx.doi.org/10.1007/s41365-021-00931-w . 2021 Nuclear Science and Techniques 09 32