Measurement of neutron-induced fission cross sections of 232Th from 1 to 300 MeV at CSNS Back-n

232Th/233U fuel cycle is an alternate candidate for future nuclear energy. Neutron-induced fission cross section of 232Th is one of the important nuclear data if using thorium as the fuel in the future. 232Th(n, f) cross sections from 1 to 300 MeV were measured at China Spallation Neutron Source (CS...

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Published inPhysics letters. B Vol. 839; p. 137832
Main Authors Chen, Yonghao, Yang, Yiwei, Ren, Zhizhou, Jiang, Wei, Fan, Ruirui, Yi, Han, Liu, Rong, Tang, Jingyu, Jing, Hantao, Li, Yang, Li, Qiang, Tan, Zhixin, An, Qi, Bai, Jiangbo, Bao, Jie, Bao, Yu, Cao, Ping, Chen, Haolei, Chen, Qiping, Chen, Zhen, Cui, Zengqi, Feng, Changqing, Gao, Keqing, Gao, Xiaolong, Gu, Minhao, Han, Changcai, Han, Zijie, He, Guozhu, He, Yongcheng, Hong, Yang, Hu, Yiwei, Huang, Hanxiong, Huang, Xiru, Jiang, Haoyu, Jiang, Zhijie, Kang, Ling, Li, Bo, Li, Chao, Li, Jiawen, Li, Xiao, Liu, Jie, Liu, Shubin, Liu, Xingyan, Long, Ze, Luan, Guangyuan, Ning, Changjun, Niu, Mengchen, Qi, Binbin, Ren, Jie, Ruan, Xichao, Song, Zhaohui, Sun, Kang, Sun, Zhijia, Tang, Xinyi, Tian, Binbin, Wang, Lijiao, Wang, Pengcheng, Wang, Zhaohui, Wen, Zhongwei, Wu, Xiaoguang, Wu, Xuan, Xie, Likun, Yang, Xiaoyun, Yu, Li, Yu, Tao, Yu, Yongji, Zhang, Guohui, Zhang, Linhao, Zhang, Qiwei, Zhang, Xianpeng, Zhang, Yuliang, Zhang, Zhiyong, Zhou, Luping, Zhou, Zhihao, Zhu, Kejun
Format Journal Article
LanguageEnglish
Published Elsevier B.V 10.04.2023
Elsevier
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Summary:232Th/233U fuel cycle is an alternate candidate for future nuclear energy. Neutron-induced fission cross section of 232Th is one of the important nuclear data if using thorium as the fuel in the future. 232Th(n, f) cross sections from 1 to 300 MeV were measured at China Spallation Neutron Source (CSNS) Back-streaming neutron facility (Back-n) relative to 235U(n, f) and n-p scattering. A fast ionization chamber for fission cross section measurement (FIXM) and a proton recoil telescope (PRT) were used to perform the measurement. The neutron energy in this measurement reaches up to 300 MeV which is supposed to be the highest among the current Experimental Nuclear Reaction Data (EXFOR) library. It stands as the only experimental data in the region of 200-300 MeV in EXFOR as well. The experimental and evaluated data of 232Th(n, f) cross section above 60 MeV are scarce, the measurement data of this work will be valuable references for future evaluation in high energy. For the data below 60 MeV, most of our data are more consistent with ENDF/B-VIII.0, excepting in the region of 1-2 MeV where our data are more in favor of CENDL-3.2.
ISSN:0370-2693
1873-2445
DOI:10.1016/j.physletb.2023.137832