Measurement of the U-238/U-235 fission cross section ratio at CSNS – Back-n WNS

Wen, Jie; Yang, Yiwei; Wen, Zhengqi; Liu, Rong; Liu, Xingyan; Han, Zijie; Chen, Qiping; Ren, Zhongzhou; An, Qi; Bai, Huaiyong; Bao, Jie; Cao, Ping; Chen, Yonghao; Cheng, Pinjing; Cui, Zengqi; Fan, Ruirui; Feng, C. Q.; Gu, Min; Feng, Guo; Han, Changcai; He, Guo‐Zhong; He, Yongcheng; He, Yuefeng; Huang, Hanxiong; Huang, Weiling; Huang, Xiru; Ji, Xiaolu; Ji, Xiuling; Jiang, Haoyu; Jiang, Wei; Jing, Hantao; Kang, Lihua; Kang, Mingtao; Li, Bo; Li, Lun; Li, Qiang; Xiao, Li; Li, Yang; Liu, Shubin; Luan, Guangyuan; Ma, Y.; Ning, Congqin; Qi, Binbin; Ren, Jie; Ruan, Xichao; Zhang, Song; Sun, Hong-xiang; Sun, Xiaoyang; Sun, Zhi‐Wei; Tan, Zhixin; Tang, Hongqing; Tang, Jingyu; Wang, Pengcheng; Wang, Qi; Wang, Taofeng; Wang, Yanfeng; Wang, Zhaohui; Wang, Zheng; Wu, Qingbiao; Wu, X.; Wu, Xuan; Xie, Likun; Yu, Lei; Yu, Tao; Yu, Yongji; Zhang, Guohui; Zhang, Jing; Zhang, Linhao; Zhang, Liying; Zhang, Qingmin; Zhang, Qiwei; Zhang, Xianpeng; Zhang, Yuliang; Zhi-yong, Zhang; Zhao, Yingtan; Zhou, Liang; Zhou, Zuying; Zhu, Dan; Zhu, K.; Zhu, Ping

doi:10.1016/j.anucene.2019.107301

Cited by 10 publications

(3 citation statements)

References 12 publications

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“…The original data were decoded into ROOT file for data analysis. ENDF/B-VIII.0 evaluation [21,26], as shown in Fig. 9.…”

Section: B Experiments On Fission Cross-sectionsmentioning

confidence: 99%

“…The measured total cross-sections with 235 U cells are in good agreement with those with 238 U cells. For comparison, the evaluated data of carbon in ENDF/B-VIII.0 [26] are broadened using the Gaussian function according to the bunch modes. The measured and unfolded results are generally in agreement with the single-bunch broadening data of ENDF/B-VIII.0, and the positions of the resonance peak of 2.077 MeV are consistent [32], as shown in Fig.…”

Section: B Experiments On Total Cross-sectionsmentioning

confidence: 99%

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Initial years’ neutron-induced cross-section measurements at the CSNS Back-n white neutron source *

Tang¹,

Liu²,

Zhang³

et al. 2021

Chinese Phys. C

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The Back-n white neutron source (known as Back-n) is based on back-streaming neutrons from the spallation target at the China Spallation Neutron Source (CSNS). With its excellent beam properties, e.g., a neutron flux of approximately 1.8×107 n/cm2/s at 55 m from the spallation target, energy range spanning from 0.5 eV to 200 MeV, and time-of-flight resolution of a few per thousand, along with the equipped physical spectrometers, Back-n is considered to be among the best facilities in the world for carrying out nuclear data measurements. Since its completion and commencement of operation in May 2018, five types of cross-section measurements concerning neutron capture cross-sections, fission cross-sections, total cross-sections, light charged particle emissions, in-beam gamma spectra, and more than forty nuclides have been measured. This article presents an overview of the experimental setup and result analysis on the neutron-induced cross-section measurements and gamma spectroscopy at Back-n in the initial years.

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“…The original data were decoded into ROOT file for data analysis. ENDF/B-VIII.0 evaluation [21,26], as shown in Fig. 9.…”

Section: B Experiments On Fission Cross-sectionsmentioning

confidence: 99%

Section: B Experiments On Total Cross-sectionsmentioning

confidence: 99%

Initial years’ neutron-induced cross-section measurements at the CSNS Back-n white neutron source *

Tang¹,

Liu²,

Zhang³

et al. 2021

Chinese Phys. C

Self Cite

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“…. 238 U/ 235 U fission prior and posterior cross section ratios with the experimental cross section ratios used for evaluation [59,61,63,64,73,[98][99][100][101][102][103][104][105][106][107][108][109][110][111][112][113][114]. The prior cross section is taken from JENDL-4.0 (below 20 MeV) and JENDL-4.0/HE (above 20 MeV).…”

mentioning

confidence: 99%

EXFOR-based simultaneous evaluation of neutron-induced uranium and plutonium fission cross sections for JENDL-5

Otuka,

Iwamoto

2022

Preprint

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The neutron-induced fission cross sections were simultaneously evaluated for the JENDL-5 library for 233,235 U and 239,241 Pu from 10 keV to 200 MeV and for 238 U and 240 Pu from 100 keV to 200 MeV. Evaluation was performed by least-squares fitting of Schmittroth's roof function to the logarithms of the experimental cross sections and cross section ratios in the EXFOR library. A simultaneous evaluation code SOK was used with its extension to data in arbitrary unit. The outputs of the code were adopted as the evaluated cross sections without any further corrections. The newly obtained evaluated cross sections were compared with the evaluated cross sections in the JENDL-4.0 library and the IAEA Neutron Data Standards 2017. The evaluated cross sections were also validated against the californium-252 spontaneous fission neutron spectrum averaged cross sections, ΣΣ (coupled thermal/fast uranium and boron carbide spherical assembly) neutron spectrum averaged cross sections, and small-sized LANL fast system criticalities. The changes in the obtained evaluated cross sections from those in the JENDL-4.0 library are within 4% ( 241 Pu), 3% ( 233 U, 240 Pu), or 2% ( 235 U, 239 Pu). The newly evaluated 235 U, 238 U and 239 Pu cross sections agree with the IAEA Neutron Data Standards 2017 within 2% with some exceptions.(This is a preprint of N. Otuka and O. Iwamoto, J. Nucl. Sci. Technol., to be published online as an open access article.)

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Measurement of the 232Th(n,f) cross section in the 1–200 MeV range at the CSNS Back-n

et al. 2023

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Measurement of the U-238/U-235 fission cross section ratio at CSNS – Back-n WNS

Cited by 10 publications

References 12 publications

Initial years’ neutron-induced cross-section measurements at the CSNS Back-n white neutron source *

Initial years’ neutron-induced cross-section measurements at the CSNS Back-n white neutron source *

EXFOR-based simultaneous evaluation of neutron-induced uranium and plutonium fission cross sections for JENDL-5

Measurement of the 232Th(n,f) cross section in the 1–200 MeV range at the CSNS Back-n

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