Measurement of the neutron energy spectrum of Back-n #ES1 at CSNS

Chen, Yonghao; Luan, Guangyuan; Bao, Jie; Jing, Hantao; An, Qi; Bai, Huaiyong; Cao, Ping; Chen, Qiping; Cheng, Pinjing; Cui, Zengqi; Fan, Ruirui; Feng, C. Q.; Gu, Min; Feng, Guo; Han, Changcai; Han, Zijie; He, Guo‐Zhong; He, Yongcheng; He, Yuefeng; Huang, Hanxiong; Huang, Weiling; Huang, Xiru; Ji, Xiaolu; Ji, Xiuling; Jiang, Haoyu; Jiang, Wei; Kang, Lihua; Kang, Mingtao; Li, Bo; Li, Lun; Li, Qiang; Xiao, Li; Li, Yang; Liu, Rong; Liu, Shubin; Liu, Xingyan; Ma, Y.; Ning, Congqin; Qi, Binbin; Ren, Jie; Ruan, Xichao; Zhang, Song; Sun, Hong-xiang; Sun, Xiaoyang; Sun, Zhi‐Wei; Tan, Zhixin; Tang, Hongqing; Tang, Jingyu; Wang, Pengcheng; Wang, Qi; Wang, Taofeng; Wang, Yanfeng; Wang, Zhaohui; Wang, Zheng; Wen, Jie; Wen, Zhengqi; Wu, Qingbiao; Wu, X.; Wu, Xuan; Xie, Likun; Yang, Yiwei; Yu, Lei; Yu, Tao; Yu, Yongji; Zhang, Guohui; Zhang, Jing; Zhang, Linhao; Zhang, Liying; Zhang, Qingming; Zhang, Qiwei; Zhang, Xianpeng; Zhang, Yuliang; Zhang, Zhiyong; Zhao, Yongqiang; Zhou, Liang; Zhou, Zuying; Zhu, Dan; Zhu, K.; Zhu, Ping

doi:10.1051/epjconf/202023917018

Cited by 6 publications

(7 citation statements)

References 12 publications

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“…The neutron energy spectrum of CSNS Back-n #ES1 was measured by Y.H. Chen [17,18] using a multi-layer fission chamber, with an energy range from 0.1 eV to 30 MeV, as shown in figure 1. However, as the accelerator operates mostly in double-bunch mode, the energy spectrum was only measured at ES#2 in single-bunch mode.…”

Section: Energy Spectrum Of the Back-nmentioning

confidence: 99%

Measurement of the neutron energy response curve of 4H-SiC detector based fission target detection system at the CSNS Back-n white neutron source

Zhang,

Song,

Zhang

et al. 2023

J. Inst.

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The fission target detection system, which is based on U-235(or U-238)fission target and large area 4H-SiC detector, has been developed for pulsed neutron detection. However, calibration of its neutron energy response curve is challenging due to its very low detection efficiency to fast neutrons. In the past, the calibration of the neutron sensitivity for the fission target detection system was limited to using ∼ 14 MeV neutrons generated by the Cockcroft-Walton accelerator. To obtain the response function for the complete range of neutron energies, extrapolation based on neutron fission cross sections was required. In this paper, we present the calibration of its energy response at the China Spallation Neutron Source (CSNS) Back-n beam line using the time of flight method, both with double-bunch and single-bunch mode in end-station 1(with a flight path of ∼ 55 m). The SiC detector with a thin sensitive thickness of 30 μm has lower scattering background than the traditional Si-PIN detector . As a result, the energy response curve of the fission target detection system above 0.26 MeV has been successfully acquired. The spectrum of the double-bunch mode was unfolded using the Bayesian algorithm, and the results indicate that, under conditions of sufficient counts, this method can yield results similar to those obtained from the single-bunch mode. The issue of pulse height defect of SiC detector to fission fragments is discussed. This experiment confirms that our detection system of SiC+fission target has a strong signal-to-noise ratio and anti-interference capability. At the same time, it demonstrates that this device has its own advantages in measuring the energy response of low sensitivity detectors.

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Section: Energy Spectrum Of the Back-nmentioning

confidence: 99%

Measurement of the neutron energy response curve of 4H-SiC detector based fission target detection system at the CSNS Back-n white neutron source

Zhang,

Song,

Zhang

et al. 2023

J. Inst.

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“…The measured neutron energy spectra are shown in Fig. 2 [9][10], and the neutron fluxes at different flight distances and with different spot sizes are listed in Table 1. Figure 3 shows the time resolutions with different accelerator operation modes [2].…”

Section: Back-n White Neutron Beammentioning

confidence: 99%

“…The improved FIC with an aluminum shell has a good performance with faster rise time (less than 30 ns), less electromagnetic noise, and lighter weight. The improved FIXM as the second version was applied to the measurements of the fission cross-sections of 232 Th and the total cross-sections of 9 Be and nat Li, as shown in Fig. 8.…”

Section: A Spectrometer Fixm Fixm Was Established As a Day-one Spectr...mentioning

confidence: 99%

“…The present experiments are performed using the transmission method and the Neutron Total Cross Section Spectrometer (NTOX) at Back-n. In the past three years, the total cross-sections of 12 C, 27 Al, 9 Be, and nat Li were measured. Back-n.…”

Section: Total Cross-section Measurementsmentioning

confidence: 99%

“…The experiments on the total cross-sections of 9 Be and nat Li were performed by NTOX with the double bunch mode and the beam power of 100 kW. The data analysis is being processed.…”

Section: B Experiments On Total Cross-sectionsmentioning

confidence: 99%

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Initial years’ neutron-induced cross-section measurements at the CSNS Back-n white neutron source *

Tang¹,

Liu²,

Zhang³

et al. 2021

Chinese Phys. C

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The Back-n white neutron source (known as Back-n) is based on back-streaming neutrons from the spallation target at the China Spallation Neutron Source (CSNS). With its excellent beam properties, e.g., a neutron flux of approximately 1.8×107 n/cm2/s at 55 m from the spallation target, energy range spanning from 0.5 eV to 200 MeV, and time-of-flight resolution of a few per thousand, along with the equipped physical spectrometers, Back-n is considered to be among the best facilities in the world for carrying out nuclear data measurements. Since its completion and commencement of operation in May 2018, five types of cross-section measurements concerning neutron capture cross-sections, fission cross-sections, total cross-sections, light charged particle emissions, in-beam gamma spectra, and more than forty nuclides have been measured. This article presents an overview of the experimental setup and result analysis on the neutron-induced cross-section measurements and gamma spectroscopy at Back-n in the initial years.

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Nondestructive technique for identifying nuclides using neutron resonance transmission analysis at CSNS Back-n

Tang,

Chen,

Tang

et al. 2024

NUCL SCI TECH

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Measurement of the neutron energy spectrum of Back-n #ES1 at CSNS

Cited by 6 publications

References 12 publications

Measurement of the neutron energy response curve of 4H-SiC detector based fission target detection system at the CSNS Back-n white neutron source

Measurement of the neutron energy response curve of 4H-SiC detector based fission target detection system at the CSNS Back-n white neutron source

Initial years’ neutron-induced cross-section measurements at the CSNS Back-n white neutron source *

Nondestructive technique for identifying nuclides using neutron resonance transmission analysis at CSNS Back-n

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