期刊
CHINESE PHYSICS C
卷 46, 期 4, 页码 -出版社
IOP Publishing Ltd
DOI: 10.1088/1674-1137/ac3fa4
关键词
124,126,128,130,131,132Xe isotopes; 14 MeV neutrons; (n, 2n) and (n, p) reactions; Excitation function; TALYS-1.95 code
资金
- National Natural Science Foundation of China [11875016, 12165006]
The reaction cross-sections of several xenon isotopes under neutron irradiation at different energies were measured and compared with existing experimental data, database evaluation results, and theoretical models. This study provides first-time reported cross-section data for reactions in the 13-15 MeV energy range, contributing to the improvement of database quality.
The reaction cross-sections of Xe-124(n, 2n)Xe-123, Xe-126(n, 2n)Xe-125, Xe-128(n, 2n )Xe-127, Xe-130(n, 2n)Xe-129m, Xe-132(n, 2n)Xe-131m, Xe-130(n, p)I-130, Xe-131(n, p) I-131, and Xe-132(n, p)I-132 were measured at the 13.5, 13.8, 14.1, 14.4, and 14.8 MeV neutron energies. The monoenergetic neutrons were generated via the H-3(d,n)He-4 reaction at the China Academy of Engineering Physics using the K-400 Neutron Generator with a solid H-3-Ti target. A high-purity germanium detector was employed to measure the activities of the product. The reactions Nb-93(n, 2n)Nb-92m and Al-27(n, alpha)Na-24 were adopted for neutron flux calibration. The cross sections of the (n, 2n) and (n, p) reactions of the xenon isotopes were obtained within the 13-15 MeV neutron energy range. These cross-sections were then compared with the IAEA-exchange format (EXFOR) database-derived experimental data, together with the evaluation results of the CENDL-3, ENDF/B-VIII.0, JENDL-4.0, RUSFOND, and JEFF-3.3 data libraries, as well as the theoretical excitation function obtained using the TALYS-1.95 code. The cross-sections of the reactions (except for the Xe-124(n, 2n)Xe-123 and Xe-132(n, p)I-132) at 13.5, 13.8, and 14.1 MeV are reported for the first time in this study. The obtained results are beneficial in providing better cross-section constraints for the reactions in the 13-15 MeV region, thus improving the quality of the corresponding database. Meanwhile, these data can also be used for the verification of relevant nuclear reaction model parameters.
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