Nuclear Science and Techniques

《核技术》(英文版) ISSN 1001-8042 CN 31-1559/TL     2019 Impact factor 1.556

Nuclear Science and Techniques ›› 2019, Vol. 30 ›› Issue (9): 139 doi: 10.1007/s41365-019-0660-9

• NUCLEAR ELECTRONICS AND INSTRUMENTATION • Previous Articles     Next Articles

Measurement of the neutron total cross section of carbon at the Back-n white neutron beam of CSNS

Xing-Yan Liu1, Yi-Wei Yang1, Rong Liu1, Jie Wen1, Zhong-Wei Wen1, Zi-Jie Han1, Zhi-Zhou Ren1, Qi An, et al.   

  1. 1Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang 621900, China
    2State Key Laboratory of Particle Detection and Electronics, Chinese Academy of Sciences (CAS), Beijing 100049, China
    3Department of Modern Physics, University of Science and Technology of China, Hefei 230026, China
    4State Key Laboratory of Nuclear Physics and Technology, School of Physics, Peking University, Beijing 100871, China
    5Key Laboratory of Nuclear Data, China Institute of Atomic Energy, Beijing 102413, China
    6Institute of High Energy Physics, Chinese Academy of Sciences (CAS), Beijing 100049, China
    7Dongguan Neutron Science Center, Dongguan 523803, China
    8University of South China, Hengyang 421001, China
    9Northwest Institute of Nuclear Technology, Xi’an 710024, China
    10Department of Engineering and Applied Physics, University of Science and Technology of China, Hefei 230026, China
    11Xi’an Jiaotong University, Xi’an 710049, China
    12Beihang University, Beijing 100083, China
  • Received:2019-02-12 Revised:2019-06-15 Accepted:2019-06-24
  • Contact: Rong Liu E-mail:liurongzy@163.com
  • Supported by:
    This work was supported by the National Key Research and Development Plan (2016YFA0401603), and the National Natural Science Foundation of China (11675155).
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Xing-Yan Liu, Yi-Wei Yang, Rong Liu, Jie Wen, Zhong-Wei Wen, Zi-Jie Han, Zhi-Zhou Ren, Qi An. Measurement of the neutron total cross section of carbon at the Back-n white neutron beam of CSNS.Nuclear Science and Techniques, 2019, 30(9): 139     doi: 10.1007/s41365-019-0660-9

Abstract: To verify the performance of the neutron total cross-sectional spectrometer, the neutron total cross section of carbon is initially measured in the energy range of 1 eV to 20 MeV using the time-of-flight method. The measurement is performed at the Back-n white neutron source with a 76-m time-of-flight path using the China Spallation Neutron Source. A multilayer fast fission chamber with 235U and 238U is employed as the neutron detector. The diameter and thickness of the natural graphite sample are 70 mm and 40 mm, respectively. Signal waveforms are collected using a data acquisition system. Off-line data processing was used to obtain the neutron time-of-flight spectra and transmissions. The uncertainty of the counting statistics is generally approximately 3% for each bin in the energy range of 1–20 MeV. It is determined that the results for the neutron total cross section of carbon obtained using 235U cells are in good agreement with the results obtained using 238U cells within limits of statistical uncertainty. Moreover, the measured total cross sections show good agreement with the broadening evaluated data.

Key words: CSNS, Back-n white neutron source, NTOX, Neutron total cross-section, Carbon, Multi-layer fast fission chamber