Abstract
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 \(^{235}\)U and \(^{238}\)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+\(^{27}\)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 \(^{235}\)U fission cells are in good agreement with that with \(^{238}\)U in the energy range of 1–20 MeV. The uncertainty of neutron total cross section measured with \(^{235}\)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.
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Data Availability Statement
This manuscript has no associated data or the data will not be deposited. [Authors’ comment: All data generated or analysed during this study are included in this published article.]
Change history
10 August 2021
An Erratum to this paper has been published: https://doi.org/10.1140/epja/s10050-021-00556-y
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Acknowledgements
This work is supported by the National Key Research and Development Plan (2016YFA0401603), the National Natural Science Foundation of China (11675155 and 11790321), and the Foundation of President of China Academy of Engineering Physics (YZJJLX2016003). The authors thank the CSNS Back-n Collaboration for their support. The comments and suggestions of reviewer are gratefully acknowledged.
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Communicated by Robert Janssens.
The original online version of this article was revised: The name of the second author was corrected from Yiwei Zhang to Yiwei Yang.
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Liu, X., Yang, Y., Liu, R. et al. Measurement of the neutron total cross sections of aluminum at the back-n white neutron source of CSNS. Eur. Phys. J. A 57, 232 (2021). https://doi.org/10.1140/epja/s10050-021-00513-9
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DOI: https://doi.org/10.1140/epja/s10050-021-00513-9