دورية أكاديمية

Progress in measurements of fission cross sections and total cross sections at CSNS Back-n white neutron source.

التفاصيل البيبلوغرافية
العنوان: Progress in measurements of fission cross sections and total cross sections at CSNS Back-n white neutron source.
المؤلفون: Rong Liu, Yiwei Yang, Zhizhou Ren, Zhongwei Wen, Jie Wen, Xingyan Liu, Yonghao Chen, Han Yi, Zijie Han, Qiping Chen, Jie Bao, Qi An, Huaiyong Bai, Ping Cao, Pinjing Cheng, Zengqi Cui, Ruirui Fan, Changqing Feng, Minhao Gu, Fengqin Guo
المصدر: Nuclear Analysis; Jun2023, Vol. 2 Issue 2, p1-7, 7p
مصطلحات موضوعية: NEUTRON sources, FISSION counters, IONIZATION chambers, NUCLEAR energy, THRESHOLD energy, NUCLEAR reactors
مستخلص: The neutron-induced cross sections are of great significance for the design of nuclear devices and advanced reactors for the nuclear energy production. At CSNS Back-n white neutron source, new measurements of the fission cross sections and total cross sections are performed with two sets of Day-one spectrometers based on the multicell fast fission ionization chamber (FIC). The neutron-induced 236,238U fission cross sections relative to 235U from the fission threshold energy to 200 MeV were measured by using the TOF method and the Fast Ionization Chamber Spectrometer for Fission Cross Section Measurement (FIXM) in the single/double bunch mode of Back-n. The experimental uncertainties are analyzed in detail, and the results from the two modes are consistent. The measured 236,238U/235U fission cross section ratios are compared with previous experiments and evaluations. The 236,238U(n,f) cross sections are obtained based on the standard 235U fission cross section. The neutron total cross sections of carbon and aluminum in the energy region from 1 eV to 20 MeV have been measured by using the TOF method and transmission method based on the Neutron Total Cross Section Spectrometer (NTOX) in the double bunch mode. The total cross section results after unfolding are in good agreement with the previous measurements as well as the broadening of the ENDF/B-VIII.0 evaluation with Gaussian function within the experimental uncertainty. The present results provide the experimental data for further measurements, relevant evaluations and the design of nuclear system. [ABSTRACT FROM AUTHOR]
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قاعدة البيانات: Complementary Index
الوصف
تدمد:27731839
DOI:10.1016/j.nucana.2023.100073