https://doi.org/10.1140/epja/s10050-021-00513-9
Regular Article – Experimental Physics
Measurement of the neutron total cross sections of aluminum at the back-n white neutron source of CSNS
1
Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, 621900, Mianyang, China
2
Institute of High Energy Physics, Chinese Academy of Sciences (CAS), 100049, Beijing, China
3
Spallation Neutron Source Science Center, 523803, Dongguan, China
4
Key Laboratory of Nuclear Data, China Institute of Atomic Energy, 102413, Beijing, China
5
State Key Laboratory of Particle Detection and Electronics, 100049, Beijing, China
6
Department of Modern Physics, University of Science and Technology of China, 230026, Hefei, China
7
State Key Laboratory of Nuclear Physics and Technology, School of Physics, Peking University, 100871, Beijing, China
8
University of South China, 421001, Hengyang, China
9
Northwest Institute of Nuclear Technology, 710024, Xi’an, China
10
Department of Engineering and Applied Physics, University of Science and Technology of China, 230026, Hefei, China
11
School of Physics, Beihang University, 100083, Beijing, China
12
Xi’an Jiaotong University, 710049, Xi’an, China
Received:
11
September
2020
Accepted:
18
May
2021
Published online:
13
July
2021
Aluminum and its alloys are widely used in the nuclear industry. Therefore, it is essential to precisely measure and accurately know the neutron total cross section of aluminum in the wider energy region. The measurement is performed by using the transmission method at the Back-n White Neutron Source of CSNS. Two aluminum samples 70 mm in diameter and thicknesses of 40 and 60 mm, respectively, were positioned at 55 m from the neutron source. The transmission detector consisted of a multi-layer fast fission chamber loaded with 
U and 
U, and it was located at the 76-m measurement station. By applying the time-of-flight technique, it was possible to extract the n+
Al total cross section in a wide energy region, from 1 eV to 20 MeV, after the correction for the double-bunch mode of the CSNS accelerator. The total cross sections obtained with the two Al samples are consistent and the results obtained with the U fission cells are in good agreement with that with U in the energy range of 1–20 MeV. The uncertainty of neutron total cross section measured with U for 40 mm and 60 mm thick aluminum is 0.7–22.3% and 0.6–12.4% in the energy range of 10 keV–20 MeV. Results are in fair agreement with respect to previous data and evaluations.
© The Author(s), under exclusive licence to Società Italiana di Fisica and Springer-Verlag GmbH Germany, part of Springer Nature 2021. corrected publication 2021
