Measurement of the neutron total cross sections of aluminum at the back-n white neutron source of CSNS,The European Physical Journal A

当前位置： X-MOL 学术 › Eur. Phys. J. A › 论文详情

Our official English website, www.x-mol.net, welcomes your feedback! (Note: you will need to create a separate account there.)

Measurement of the neutron total cross sections of aluminum at the back-n white neutron source of CSNS
The European Physical Journal A ( IF 2.6 ) Pub Date : 2021-07-13 , DOI: 10.1140/epja/s10050-021-00513-9
Xingyan Liu ₁ , Yiwei Yang ₁ , Rong Liu ₁ , Zhongwei Wen ₁ , Jie Wen ₁ , Zijie Han ₁ , Zhizhou Ren ₁ , Qiping Chen ₁ , Yonghao Chen _{2,

3} , Hantao Jing _{2,

3} , Han Yi _{2,

3} , Ruirui Fan _{2,

3,

4} , Minhao Gu _{2,

4} , Fengqin Guo _{2,

3} , Yongcheng He _{2,

3} , Weiling Huang _{2,

3} , Xiaolu Ji _{2,

4} , Wei Jiang _{2,

3} , Ling Kang _{2,

3} , Mingtao Kang _{2,

3} , Bo Li _{2,

3} , Lun Li _{2,

3} , Qiang Li _{2,

3} , Xiao Li _{2,

3} , Yang Li _{2,

2,

3,

4} , Yinglin Ma _{2,

3} , Changjun Ning _{2,

3} , Hong Sun _{2,

3} , Xiaoyang Sun _{2,

3} , Zhijia Sun _{2,

3,

4} , Zhixin Tan _{2,

3} , Jingyu Tang _{2,

3} , Pengcheng Wang _{2,

3} , Yanfeng Wang _{2,

3} , Zheng Wang _{2,

3} , Qingbiao Wu _{2,

3} , Xuan Wu _{2,

3} , Li Yu _{2,

3} , Yongji Yu _{2,

3} , Jing Zhang _{2,

3} , Linhao Zhang _{2,

3} , Liying Zhang _{2,

3,

4} , Yuliang Zhang _{2,

3} , Liang Zhou _{2,

3} , Kejun Zhu _{2,

5} , Peng Zhu _{2,

3} , Jie Bao ₅ , Guozhu He ₅ , Hanxiong Huang ₅ , Jie Ren ₅ , Xichao Ruan ₅ , Hongqing Tang ₅ , Qi Wang ₅ , Zhaohui Wang ₅ , Xiaoguang Wu ₅ , Qiwei Zhang ₅ , Zuying Zhou ₅ , Qi An _{4,

6} , Ping Cao _{4,

6} , Changqing Feng _{4,

6} , Xiru Huang _{4,

6} , Xuyang Ji _{4,

7} , Shubin Liu _{4,

6} , Binbin Qi _{4,

6} , Likun Xie _{4,

7} , Tao Yu _{4,

6} , Zhiyong Zhang _{4,

6} , Danyang Zhu _{4,

6} , Huaiyong Bai ₈ , Zengqi Cui ₈ , Haoyu Jiang ₈ , Guangyuan Luan ₈ , Guohui Zhang ₈ , Pinjing Cheng ₉ , Yuefeng He ₉ , Changcai Han ₁₀ , Zhaohui Song ₁₀ , Xianpeng Zhang ₁₀ , Taofeng Wang ₁₁ , Qingmin Zhang ₁₂ , Yingtan Zhao ₁₂

Affiliation

Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang, 621900, China
Institute of High Energy Physics, Chinese Academy of Sciences (CAS), Beijing, 100049, China
Spallation Neutron Source Science Center, Dongguan, 523803, China
State Key Laboratory of Particle Detection and Electronics, Beijing, 100049, China
Key Laboratory of Nuclear Data, China Institute of Atomic Energy, Beijing, 102413, China
Department of Modern Physics, University of Science and Technology of China, Hefei, 230026, China
Department of Engineering and Applied Physics, University of Science and Technology of China, Hefei, 230026, China
State Key Laboratory of Nuclear Physics and Technology, School of Physics, Peking University, Beijing, 100871, China
University of South China, Hengyang, 421001, China
Northwest Institute of Nuclear Technology, Xi’an, 710024, China
School of Physics, Beihang University, Beijing, 100083, China
Xi’an Jiaotong University, Xi’an, 710049, China

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.

中文翻译：

CSNS背n白中子源铝中子总截面的测量

铝及其合金广泛用于核工业。因此，在更宽的能量范围内精确测量和准确了解铝的中子总截面至关重要。测量采用 CSNS 的 Back-n 白中子源处的透射法进行。两个直径为 70 毫米、厚度分别为 40 和 60 毫米的铝样品放置在距中子源 55 m 处。透射探测器由装有\(^{235}\) U和\(^{238}\) U的多层快裂变室组成，位于76米测量站。通过应用飞行时间技术，可以提取 n+ \(^{27}\)在对 CSNS 加速器的双束模式进行校正后，从 1 eV 到 20 MeV 的宽能量范围内的铝总截面。用两个铝样品获得的总截面是一致的，用\(^{235}\) U 裂变电池获得的结果与用\(^{238}\) U 在能量范围内获得的结果非常吻合1–20 MeV。对于 40 mm 和 60 mm 厚的铝，用\(^{235}\) U测量的中子总截面的不确定度在 10 keV-20 MeV 的能量范围内分别为 0.7-22.3% 和 0.6-12.4%。结果与之前的数据和评估相当一致。

更新日期：2021-07-13

点击分享查看原文

点击收藏

阅读更多本刊最新论文