Measurement of the neutron total cross sections of aluminum at the back-n white neutron source of CSNS
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 Neut...
Ausführliche Beschreibung
Gespeichert in:
| Autor*in: |
Liu, Xingyan [verfasserIn] |
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| Format: |
Artikel |
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| Sprache: |
Englisch |
| Erschienen: |
2021 |
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| Anmerkung: |
© The Author(s), under exclusive licence to Società Italiana di Fisica and Springer-Verlag GmbH Germany, part of Springer Nature 2021. corrected publication 2021 |
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| Übergeordnetes Werk: |
Enthalten in: The European physical journal / A - Springer Berlin Heidelberg, 1998, 57(2021), 7 vom: Juli |
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| Übergeordnetes Werk: |
volume:57 ; year:2021 ; number:7 ; month:07 |
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| DOI / URN: |
10.1140/epja/s10050-021-00513-9 |
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| Katalog-ID: |
OLC2126609979 |
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| 245 | 1 | 0 | |a Measurement of the neutron total cross sections of aluminum at the back-n white neutron source of CSNS |
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| 500 | |a © The Author(s), under exclusive licence to Società Italiana di Fisica and Springer-Verlag GmbH Germany, part of Springer Nature 2021. corrected publication 2021 | ||
| 520 | |a 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. | ||
| 700 | 1 | |a Yang, Yiwei |4 aut | |
| 700 | 1 | |a Liu, Rong |4 aut | |
| 700 | 1 | |a Wen, Zhongwei |4 aut | |
| 700 | 1 | |a Wen, Jie |4 aut | |
| 700 | 1 | |a Han, Zijie |4 aut | |
| 700 | 1 | |a Chen, Yonghao |4 aut | |
| 700 | 1 | |a Jing, Hantao |4 aut | |
| 700 | 1 | |a Yi, Han |4 aut | |
| 700 | 1 | |a Bao, Jie |4 aut | |
| 700 | 1 | |a Ren, Zhizhou |4 aut | |
| 700 | 1 | |a An, Qi |4 aut | |
| 700 | 1 | |a Bai, Huaiyong |4 aut | |
| 700 | 1 | |a Cao, Ping |4 aut | |
| 700 | 1 | |a Chen, Qiping |4 aut | |
| 700 | 1 | |a Cheng, Pinjing |4 aut | |
| 700 | 1 | |a Cui, Zengqi |4 aut | |
| 700 | 1 | |a Fan, Ruirui |4 aut | |
| 700 | 1 | |a Feng, Changqing |4 aut | |
| 700 | 1 | |a Gu, Minhao |4 aut | |
| 700 | 1 | |a Guo, Fengqin |4 aut | |
| 700 | 1 | |a Han, Changcai |4 aut | |
| 700 | 1 | |a He, Guozhu |4 aut | |
| 700 | 1 | |a He, Yongcheng |4 aut | |
| 700 | 1 | |a He, Yuefeng |4 aut | |
| 700 | 1 | |a Huang, Hanxiong |4 aut | |
| 700 | 1 | |a Huang, Weiling |4 aut | |
| 700 | 1 | |a Huang, Xiru |4 aut | |
| 700 | 1 | |a Ji, Xiaolu |4 aut | |
| 700 | 1 | |a Ji, Xuyang |4 aut | |
| 700 | 1 | |a Jiang, Haoyu |4 aut | |
| 700 | 1 | |a Jiang, Wei |4 aut | |
| 700 | 1 | |a Kang, Ling |4 aut | |
| 700 | 1 | |a Kang, Mingtao |4 aut | |
| 700 | 1 | |a Li, Bo |4 aut | |
| 700 | 1 | |a Li, Lun |4 aut | |
| 700 | 1 | |a Li, Qiang |4 aut | |
| 700 | 1 | |a Li, Xiao |4 aut | |
| 700 | 1 | |a Li, Yang |4 aut | |
| 700 | 1 | |a Li, Yang |4 aut | |
| 700 | 1 | |a Liu, Shubin |4 aut | |
| 700 | 1 | |a Luan, Guangyuan |4 aut | |
| 700 | 1 | |a Ma, Yinglin |4 aut | |
| 700 | 1 | |a Ning, Changjun |4 aut | |
| 700 | 1 | |a Qi, Binbin |4 aut | |
| 700 | 1 | |a Ren, Jie |4 aut | |
| 700 | 1 | |a Ruan, Xichao |4 aut | |
| 700 | 1 | |a Song, Zhaohui |4 aut | |
| 700 | 1 | |a Sun, Hong |4 aut | |
| 700 | 1 | |a Sun, Xiaoyang |4 aut | |
| 700 | 1 | |a Sun, Zhijia |4 aut | |
| 700 | 1 | |a Tan, Zhixin |4 aut | |
| 700 | 1 | |a Tang, Hongqing |4 aut | |
| 700 | 1 | |a Tang, Jingyu |4 aut | |
| 700 | 1 | |a Wang, Pengcheng |4 aut | |
| 700 | 1 | |a Wang, Qi |4 aut | |
| 700 | 1 | |a Wang, Taofeng |4 aut | |
| 700 | 1 | |a Wang, Yanfeng |4 aut | |
| 700 | 1 | |a Wang, Zhaohui |4 aut | |
| 700 | 1 | |a Wang, Zheng |4 aut | |
| 700 | 1 | |a Wu, Qingbiao |4 aut | |
| 700 | 1 | |a Wu, Xiaoguang |4 aut | |
| 700 | 1 | |a Wu, Xuan |4 aut | |
| 700 | 1 | |a Xie, Likun |4 aut | |
| 700 | 1 | |a Yu, Li |4 aut | |
| 700 | 1 | |a Yu, Tao |4 aut | |
| 700 | 1 | |a Yu, Yongji |4 aut | |
| 700 | 1 | |a Zhang, Guohui |4 aut | |
| 700 | 1 | |a Zhang, Jing |4 aut | |
| 700 | 1 | |a Zhang, Linhao |4 aut | |
| 700 | 1 | |a Zhang, Liying |4 aut | |
| 700 | 1 | |a Zhang, Qingmin |4 aut | |
| 700 | 1 | |a Zhang, Qiwei |4 aut | |
| 700 | 1 | |a Zhang, Xianpeng |4 aut | |
| 700 | 1 | |a Zhang, Yuliang |4 aut | |
| 700 | 1 | |a Zhang, Zhiyong |4 aut | |
| 700 | 1 | |a Zhao, Yingtan |4 aut | |
| 700 | 1 | |a Zhou, Liang |4 aut | |
| 700 | 1 | |a Zhou, Zuying |4 aut | |
| 700 | 1 | |a Zhu, Danyang |4 aut | |
| 700 | 1 | |a Zhu, Kejun |4 aut | |
| 700 | 1 | |a Zhu, Peng |4 aut | |
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10.1140/epja/s10050-021-00513-9 doi (DE-627)OLC2126609979 (DE-He213)s10050-021-00513-9-p DE-627 ger DE-627 rakwb eng 530 VZ 530 VZ Liu, Xingyan verfasserin aut Measurement of the neutron total cross sections of aluminum at the back-n white neutron source of CSNS 2021 Text txt rdacontent ohne Hilfsmittel zu benutzen n rdamedia Band nc rdacarrier © The Author(s), under exclusive licence to Società Italiana di Fisica and Springer-Verlag GmbH Germany, part of Springer Nature 2021. corrected publication 2021 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. Yang, Yiwei aut Liu, Rong aut Wen, Zhongwei aut Wen, Jie aut Han, Zijie aut Chen, Yonghao aut Jing, Hantao aut Yi, Han aut Bao, Jie aut Ren, Zhizhou aut An, Qi aut Bai, Huaiyong aut Cao, Ping aut Chen, Qiping aut Cheng, Pinjing aut Cui, Zengqi aut Fan, Ruirui aut Feng, Changqing aut Gu, Minhao aut Guo, Fengqin aut Han, Changcai aut He, Guozhu aut He, Yongcheng aut He, Yuefeng aut Huang, Hanxiong aut Huang, Weiling aut Huang, Xiru aut Ji, Xiaolu aut Ji, Xuyang aut Jiang, Haoyu aut Jiang, Wei aut Kang, Ling aut Kang, Mingtao aut Li, Bo aut Li, Lun aut Li, Qiang aut Li, Xiao aut Li, Yang aut Li, Yang aut Liu, Shubin aut Luan, Guangyuan aut Ma, Yinglin aut Ning, Changjun aut Qi, Binbin aut Ren, Jie aut Ruan, Xichao aut Song, Zhaohui aut Sun, Hong aut Sun, Xiaoyang aut Sun, Zhijia aut Tan, Zhixin aut Tang, Hongqing aut Tang, Jingyu aut Wang, Pengcheng aut Wang, Qi aut Wang, Taofeng aut Wang, Yanfeng aut Wang, Zhaohui aut Wang, Zheng aut Wu, Qingbiao aut Wu, Xiaoguang aut Wu, Xuan aut Xie, Likun aut Yu, Li aut Yu, Tao aut Yu, Yongji aut Zhang, Guohui aut Zhang, Jing aut Zhang, Linhao aut Zhang, Liying aut Zhang, Qingmin aut Zhang, Qiwei aut Zhang, Xianpeng aut Zhang, Yuliang aut Zhang, Zhiyong aut Zhao, Yingtan aut Zhou, Liang aut Zhou, Zuying aut Zhu, Danyang aut Zhu, Kejun aut Zhu, Peng aut Enthalten in The European physical journal / A Springer Berlin Heidelberg, 1998 57(2021), 7 vom: Juli (DE-627)239430387 (DE-600)1413603-X (DE-576)064448398 1434-6001 nnns volume:57 year:2021 number:7 month:07 https://doi.org/10.1140/epja/s10050-021-00513-9 lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_OLC SSG-OLC-PHY AR 57 2021 7 07 |
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10.1140/epja/s10050-021-00513-9 doi (DE-627)OLC2126609979 (DE-He213)s10050-021-00513-9-p DE-627 ger DE-627 rakwb eng 530 VZ 530 VZ Liu, Xingyan verfasserin aut Measurement of the neutron total cross sections of aluminum at the back-n white neutron source of CSNS 2021 Text txt rdacontent ohne Hilfsmittel zu benutzen n rdamedia Band nc rdacarrier © The Author(s), under exclusive licence to Società Italiana di Fisica and Springer-Verlag GmbH Germany, part of Springer Nature 2021. corrected publication 2021 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. Yang, Yiwei aut Liu, Rong aut Wen, Zhongwei aut Wen, Jie aut Han, Zijie aut Chen, Yonghao aut Jing, Hantao aut Yi, Han aut Bao, Jie aut Ren, Zhizhou aut An, Qi aut Bai, Huaiyong aut Cao, Ping aut Chen, Qiping aut Cheng, Pinjing aut Cui, Zengqi aut Fan, Ruirui aut Feng, Changqing aut Gu, Minhao aut Guo, Fengqin aut Han, Changcai aut He, Guozhu aut He, Yongcheng aut He, Yuefeng aut Huang, Hanxiong aut Huang, Weiling aut Huang, Xiru aut Ji, Xiaolu aut Ji, Xuyang aut Jiang, Haoyu aut Jiang, Wei aut Kang, Ling aut Kang, Mingtao aut Li, Bo aut Li, Lun aut Li, Qiang aut Li, Xiao aut Li, Yang aut Li, Yang aut Liu, Shubin aut Luan, Guangyuan aut Ma, Yinglin aut Ning, Changjun aut Qi, Binbin aut Ren, Jie aut Ruan, Xichao aut Song, Zhaohui aut Sun, Hong aut Sun, Xiaoyang aut Sun, Zhijia aut Tan, Zhixin aut Tang, Hongqing aut Tang, Jingyu aut Wang, Pengcheng aut Wang, Qi aut Wang, Taofeng aut Wang, Yanfeng aut Wang, Zhaohui aut Wang, Zheng aut Wu, Qingbiao aut Wu, Xiaoguang aut Wu, Xuan aut Xie, Likun aut Yu, Li aut Yu, Tao aut Yu, Yongji aut Zhang, Guohui aut Zhang, Jing aut Zhang, Linhao aut Zhang, Liying aut Zhang, Qingmin aut Zhang, Qiwei aut Zhang, Xianpeng aut Zhang, Yuliang aut Zhang, Zhiyong aut Zhao, Yingtan aut Zhou, Liang aut Zhou, Zuying aut Zhu, Danyang aut Zhu, Kejun aut Zhu, Peng aut Enthalten in The European physical journal / A Springer Berlin Heidelberg, 1998 57(2021), 7 vom: Juli (DE-627)239430387 (DE-600)1413603-X (DE-576)064448398 1434-6001 nnns volume:57 year:2021 number:7 month:07 https://doi.org/10.1140/epja/s10050-021-00513-9 lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_OLC SSG-OLC-PHY AR 57 2021 7 07 |
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10.1140/epja/s10050-021-00513-9 doi (DE-627)OLC2126609979 (DE-He213)s10050-021-00513-9-p DE-627 ger DE-627 rakwb eng 530 VZ 530 VZ Liu, Xingyan verfasserin aut Measurement of the neutron total cross sections of aluminum at the back-n white neutron source of CSNS 2021 Text txt rdacontent ohne Hilfsmittel zu benutzen n rdamedia Band nc rdacarrier © The Author(s), under exclusive licence to Società Italiana di Fisica and Springer-Verlag GmbH Germany, part of Springer Nature 2021. corrected publication 2021 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. Yang, Yiwei aut Liu, Rong aut Wen, Zhongwei aut Wen, Jie aut Han, Zijie aut Chen, Yonghao aut Jing, Hantao aut Yi, Han aut Bao, Jie aut Ren, Zhizhou aut An, Qi aut Bai, Huaiyong aut Cao, Ping aut Chen, Qiping aut Cheng, Pinjing aut Cui, Zengqi aut Fan, Ruirui aut Feng, Changqing aut Gu, Minhao aut Guo, Fengqin aut Han, Changcai aut He, Guozhu aut He, Yongcheng aut He, Yuefeng aut Huang, Hanxiong aut Huang, Weiling aut Huang, Xiru aut Ji, Xiaolu aut Ji, Xuyang aut Jiang, Haoyu aut Jiang, Wei aut Kang, Ling aut Kang, Mingtao aut Li, Bo aut Li, Lun aut Li, Qiang aut Li, Xiao aut Li, Yang aut Li, Yang aut Liu, Shubin aut Luan, Guangyuan aut Ma, Yinglin aut Ning, Changjun aut Qi, Binbin aut Ren, Jie aut Ruan, Xichao aut Song, Zhaohui aut Sun, Hong aut Sun, Xiaoyang aut Sun, Zhijia aut Tan, Zhixin aut Tang, Hongqing aut Tang, Jingyu aut Wang, Pengcheng aut Wang, Qi aut Wang, Taofeng aut Wang, Yanfeng aut Wang, Zhaohui aut Wang, Zheng aut Wu, Qingbiao aut Wu, Xiaoguang aut Wu, Xuan aut Xie, Likun aut Yu, Li aut Yu, Tao aut Yu, Yongji aut Zhang, Guohui aut Zhang, Jing aut Zhang, Linhao aut Zhang, Liying aut Zhang, Qingmin aut Zhang, Qiwei aut Zhang, Xianpeng aut Zhang, Yuliang aut Zhang, Zhiyong aut Zhao, Yingtan aut Zhou, Liang aut Zhou, Zuying aut Zhu, Danyang aut Zhu, Kejun aut Zhu, Peng aut Enthalten in The European physical journal / A Springer Berlin Heidelberg, 1998 57(2021), 7 vom: Juli (DE-627)239430387 (DE-600)1413603-X (DE-576)064448398 1434-6001 nnns volume:57 year:2021 number:7 month:07 https://doi.org/10.1140/epja/s10050-021-00513-9 lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_OLC SSG-OLC-PHY AR 57 2021 7 07 |
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10.1140/epja/s10050-021-00513-9 doi (DE-627)OLC2126609979 (DE-He213)s10050-021-00513-9-p DE-627 ger DE-627 rakwb eng 530 VZ 530 VZ Liu, Xingyan verfasserin aut Measurement of the neutron total cross sections of aluminum at the back-n white neutron source of CSNS 2021 Text txt rdacontent ohne Hilfsmittel zu benutzen n rdamedia Band nc rdacarrier © The Author(s), under exclusive licence to Società Italiana di Fisica and Springer-Verlag GmbH Germany, part of Springer Nature 2021. corrected publication 2021 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. Yang, Yiwei aut Liu, Rong aut Wen, Zhongwei aut Wen, Jie aut Han, Zijie aut Chen, Yonghao aut Jing, Hantao aut Yi, Han aut Bao, Jie aut Ren, Zhizhou aut An, Qi aut Bai, Huaiyong aut Cao, Ping aut Chen, Qiping aut Cheng, Pinjing aut Cui, Zengqi aut Fan, Ruirui aut Feng, Changqing aut Gu, Minhao aut Guo, Fengqin aut Han, Changcai aut He, Guozhu aut He, Yongcheng aut He, Yuefeng aut Huang, Hanxiong aut Huang, Weiling aut Huang, Xiru aut Ji, Xiaolu aut Ji, Xuyang aut Jiang, Haoyu aut Jiang, Wei aut Kang, Ling aut Kang, Mingtao aut Li, Bo aut Li, Lun aut Li, Qiang aut Li, Xiao aut Li, Yang aut Li, Yang aut Liu, Shubin aut Luan, Guangyuan aut Ma, Yinglin aut Ning, Changjun aut Qi, Binbin aut Ren, Jie aut Ruan, Xichao aut Song, Zhaohui aut Sun, Hong aut Sun, Xiaoyang aut Sun, Zhijia aut Tan, Zhixin aut Tang, Hongqing aut Tang, Jingyu aut Wang, Pengcheng aut Wang, Qi aut Wang, Taofeng aut Wang, Yanfeng aut Wang, Zhaohui aut Wang, Zheng aut Wu, Qingbiao aut Wu, Xiaoguang aut Wu, Xuan aut Xie, Likun aut Yu, Li aut Yu, Tao aut Yu, Yongji aut Zhang, Guohui aut Zhang, Jing aut Zhang, Linhao aut Zhang, Liying aut Zhang, Qingmin aut Zhang, Qiwei aut Zhang, Xianpeng aut Zhang, Yuliang aut Zhang, Zhiyong aut Zhao, Yingtan aut Zhou, Liang aut Zhou, Zuying aut Zhu, Danyang aut Zhu, Kejun aut Zhu, Peng aut Enthalten in The European physical journal / A Springer Berlin Heidelberg, 1998 57(2021), 7 vom: Juli (DE-627)239430387 (DE-600)1413603-X (DE-576)064448398 1434-6001 nnns volume:57 year:2021 number:7 month:07 https://doi.org/10.1140/epja/s10050-021-00513-9 lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_OLC SSG-OLC-PHY AR 57 2021 7 07 |
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10.1140/epja/s10050-021-00513-9 doi (DE-627)OLC2126609979 (DE-He213)s10050-021-00513-9-p DE-627 ger DE-627 rakwb eng 530 VZ 530 VZ Liu, Xingyan verfasserin aut Measurement of the neutron total cross sections of aluminum at the back-n white neutron source of CSNS 2021 Text txt rdacontent ohne Hilfsmittel zu benutzen n rdamedia Band nc rdacarrier © The Author(s), under exclusive licence to Società Italiana di Fisica and Springer-Verlag GmbH Germany, part of Springer Nature 2021. corrected publication 2021 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. Yang, Yiwei aut Liu, Rong aut Wen, Zhongwei aut Wen, Jie aut Han, Zijie aut Chen, Yonghao aut Jing, Hantao aut Yi, Han aut Bao, Jie aut Ren, Zhizhou aut An, Qi aut Bai, Huaiyong aut Cao, Ping aut Chen, Qiping aut Cheng, Pinjing aut Cui, Zengqi aut Fan, Ruirui aut Feng, Changqing aut Gu, Minhao aut Guo, Fengqin aut Han, Changcai aut He, Guozhu aut He, Yongcheng aut He, Yuefeng aut Huang, Hanxiong aut Huang, Weiling aut Huang, Xiru aut Ji, Xiaolu aut Ji, Xuyang aut Jiang, Haoyu aut Jiang, Wei aut Kang, Ling aut Kang, Mingtao aut Li, Bo aut Li, Lun aut Li, Qiang aut Li, Xiao aut Li, Yang aut Li, Yang aut Liu, Shubin aut Luan, Guangyuan aut Ma, Yinglin aut Ning, Changjun aut Qi, Binbin aut Ren, Jie aut Ruan, Xichao aut Song, Zhaohui aut Sun, Hong aut Sun, Xiaoyang aut Sun, Zhijia aut Tan, Zhixin aut Tang, Hongqing aut Tang, Jingyu aut Wang, Pengcheng aut Wang, Qi aut Wang, Taofeng aut Wang, Yanfeng aut Wang, Zhaohui aut Wang, Zheng aut Wu, Qingbiao aut Wu, Xiaoguang aut Wu, Xuan aut Xie, Likun aut Yu, Li aut Yu, Tao aut Yu, Yongji aut Zhang, Guohui aut Zhang, Jing aut Zhang, Linhao aut Zhang, Liying aut Zhang, Qingmin aut Zhang, Qiwei aut Zhang, Xianpeng aut Zhang, Yuliang aut Zhang, Zhiyong aut Zhao, Yingtan aut Zhou, Liang aut Zhou, Zuying aut Zhu, Danyang aut Zhu, Kejun aut Zhu, Peng aut Enthalten in The European physical journal / A Springer Berlin Heidelberg, 1998 57(2021), 7 vom: Juli (DE-627)239430387 (DE-600)1413603-X (DE-576)064448398 1434-6001 nnns volume:57 year:2021 number:7 month:07 https://doi.org/10.1140/epja/s10050-021-00513-9 lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_OLC SSG-OLC-PHY AR 57 2021 7 07 |
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Liu, Xingyan Yang, Yiwei Liu, Rong Wen, Zhongwei Wen, Jie Han, Zijie Chen, Yonghao Jing, Hantao Yi, Han Bao, Jie Ren, Zhizhou An, Qi Bai, Huaiyong Cao, Ping Chen, Qiping Cheng, Pinjing Cui, Zengqi Fan, Ruirui Feng, Changqing Gu, Minhao Guo, Fengqin Han, Changcai He, Guozhu He, Yongcheng He, Yuefeng Huang, Hanxiong Huang, Weiling Huang, Xiru Ji, Xiaolu Ji, Xuyang Jiang, Haoyu Jiang, Wei Kang, Ling Kang, Mingtao Li, Bo Li, Lun Li, Qiang Li, Xiao Li, Yang Liu, Shubin Luan, Guangyuan Ma, Yinglin Ning, Changjun Qi, Binbin Ren, Jie Ruan, Xichao Song, Zhaohui Sun, Hong Sun, Xiaoyang Sun, Zhijia Tan, Zhixin Tang, Hongqing Tang, Jingyu Wang, Pengcheng Wang, Qi Wang, Taofeng Wang, Yanfeng Wang, Zhaohui Wang, Zheng Wu, Qingbiao Wu, Xiaoguang Wu, Xuan Xie, Likun Yu, Li Yu, Tao Yu, Yongji Zhang, Guohui Zhang, Jing Zhang, Linhao Zhang, Liying Zhang, Qingmin Zhang, Qiwei Zhang, Xianpeng Zhang, Yuliang Zhang, Zhiyong Zhao, Yingtan Zhou, Liang Zhou, Zuying Zhu, Danyang Zhu, Kejun Zhu, Peng |
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measurement of the neutron total cross sections of aluminum at the back-n white neutron source of csns |
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Measurement of the neutron total cross sections of aluminum at the back-n white neutron source of CSNS |
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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. © The Author(s), under exclusive licence to Società Italiana di Fisica and Springer-Verlag GmbH Germany, part of Springer Nature 2021. corrected publication 2021 |
| abstractGer |
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. © The Author(s), under exclusive licence to Società Italiana di Fisica and Springer-Verlag GmbH Germany, part of Springer Nature 2021. corrected publication 2021 |
| abstract_unstemmed |
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. © The Author(s), under exclusive licence to Società Italiana di Fisica and Springer-Verlag GmbH Germany, part of Springer Nature 2021. corrected publication 2021 |
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Measurement of the neutron total cross sections of aluminum at the back-n white neutron source of CSNS |
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Yang, Yiwei Liu, Rong Wen, Zhongwei Wen, Jie Han, Zijie Chen, Yonghao Jing, Hantao Yi, Han Bao, Jie Ren, Zhizhou An, Qi Bai, Huaiyong Cao, Ping Chen, Qiping Cheng, Pinjing Cui, Zengqi Fan, Ruirui Feng, Changqing Gu, Minhao Guo, Fengqin Han, Changcai He, Guozhu He, Yongcheng He, Yuefeng Huang, Hanxiong Huang, Weiling Huang, Xiru Ji, Xiaolu Ji, Xuyang Jiang, Haoyu Jiang, Wei Kang, Ling Kang, Mingtao Li, Bo Li, Lun Li, Qiang Li, Xiao Li, Yang Liu, Shubin Luan, Guangyuan Ma, Yinglin Ning, Changjun Qi, Binbin Ren, Jie Ruan, Xichao Song, Zhaohui Sun, Hong Sun, Xiaoyang Sun, Zhijia Tan, Zhixin Tang, Hongqing Tang, Jingyu Wang, Pengcheng Wang, Qi Wang, Taofeng Wang, Yanfeng Wang, Zhaohui Wang, Zheng Wu, Qingbiao Wu, Xiaoguang Wu, Xuan Xie, Likun Yu, Li Yu, Tao Yu, Yongji Zhang, Guohui Zhang, Jing Zhang, Linhao Zhang, Liying Zhang, Qingmin Zhang, Qiwei Zhang, Xianpeng Zhang, Yuliang Zhang, Zhiyong Zhao, Yingtan Zhou, Liang Zhou, Zuying Zhu, Danyang Zhu, Kejun Zhu, Peng |
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Yang, Yiwei Liu, Rong Wen, Zhongwei Wen, Jie Han, Zijie Chen, Yonghao Jing, Hantao Yi, Han Bao, Jie Ren, Zhizhou An, Qi Bai, Huaiyong Cao, Ping Chen, Qiping Cheng, Pinjing Cui, Zengqi Fan, Ruirui Feng, Changqing Gu, Minhao Guo, Fengqin Han, Changcai He, Guozhu He, Yongcheng He, Yuefeng Huang, Hanxiong Huang, Weiling Huang, Xiru Ji, Xiaolu Ji, Xuyang Jiang, Haoyu Jiang, Wei Kang, Ling Kang, Mingtao Li, Bo Li, Lun Li, Qiang Li, Xiao Li, Yang Liu, Shubin Luan, Guangyuan Ma, Yinglin Ning, Changjun Qi, Binbin Ren, Jie Ruan, Xichao Song, Zhaohui Sun, Hong Sun, Xiaoyang Sun, Zhijia Tan, Zhixin Tang, Hongqing Tang, Jingyu Wang, Pengcheng Wang, Qi Wang, Taofeng Wang, Yanfeng Wang, Zhaohui Wang, Zheng Wu, Qingbiao Wu, Xiaoguang Wu, Xuan Xie, Likun Yu, Li Yu, Tao Yu, Yongji Zhang, Guohui Zhang, Jing Zhang, Linhao Zhang, Liying Zhang, Qingmin Zhang, Qiwei Zhang, Xianpeng Zhang, Yuliang Zhang, Zhiyong Zhao, Yingtan Zhou, Liang Zhou, Zuying Zhu, Danyang Zhu, Kejun Zhu, Peng |
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