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Effective extraction of photoneutron cross-section distribution using gamma activation and reaction yield ratio method
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作者 Zhi‑Cai li Yue Yang +6 位作者 Zong‑Wei Cao xin‑xiang li Yun Yuan Zong‑Qing Zhao Gong‑Tao Fan Hong‑Wei Wang Wen Luo 《Nuclear Science and Techniques》 SCIE EI CAS CSCD 2023年第11期103-111,共9页
Photoneutron cross-section(PNCS)data are important in various current and emerging applications.Although a few sophis-ticated methods have been developed,there is still an urgent need to study the PNCS data.In this st... Photoneutron cross-section(PNCS)data are important in various current and emerging applications.Although a few sophis-ticated methods have been developed,there is still an urgent need to study the PNCS data.In this study,we propose the extraction of PNCS distributions using a combination of gamma activation and reaction yield ratio methods.To verify the validity of the proposed extraction method,experiments for generating^(62,64)Cu and^(85m,87m)Sr isotopes via laser-induced pho-toneutron reactions were performed,and the reaction yields of these isotopes were obtained.Using the proposed extraction method,the PNCS distributions of^(63)Cu and^(86)Sr isotopes(leading to^(85m)Sr isotope production)were successfully extracted.These extracted PNCS distributions were benchmarked against available PNCS data or TALYS calculations,demonstrating the validity of the proposed extraction method.Potential applications for predicting the PNCS distributions of the 30 iso-topes are further introduced.We conclude that the proposed extraction method is an effective complement to the available sophisticated methods for measuring and evaluating PNCS data. 展开更多
关键词 Photonuclear data Photoneutron cross section Gamma activation Reaction yield TALYS calculation
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Measurement of Br(n,γ)cross sections up to stellar s-process temperatures at the CSNS Back‑n
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作者 Gao‑Le Yang Zhen‑Dong An +43 位作者 Wei Jiang Xian‑Kai li Wei‑Wei Qiu Zheng‑Fa liao Zi‑Yue Zhuang Xiao‑Ping Zhang Sheng‑li Chen Chen‑Chen Guo Er‑Xi Xiao Xiao Fang xin‑xiang li xin‑Rong Hu Bing Jiang Jin‑Cheng Wang Jie Ren Wen Luo Zhi‑Chao Zhu Hao‑Yang Lan Zong‑Wei Cao Xu Ma Ying‑Du liu Pu‑Sen Wang Yi Yang Ping Su Xian‑Gai Deng Wan‑Bing He Chun‑Wang Ma Yu‑Ting Wang Zhi‑Tao Dai Peng‑Qin He Ren‑Guang Tang Tao Zhou Jing Wang Han Yi Yue Zhang Yong‑Hao Chen Rui‑Rui Fan Ke‑Qing Gao Qiang li Kang Sun Zhi‑xin Tan Min‑Hao Gu Han‑Tao Jing Jing‑Yu Tang 《Nuclear Science and Techniques》 SCIE EI CAS CSCD 2023年第11期226-241,共16页
The neutron capture cross sections(n,γ)of bromine were obtained using the time-of-flight technique at the Back-n facility of the China Spallation Neutron Source.Promptγ-rays originating from neutron-induced capture ... The neutron capture cross sections(n,γ)of bromine were obtained using the time-of-flight technique at the Back-n facility of the China Spallation Neutron Source.Promptγ-rays originating from neutron-induced capture events were detected using four C_(6)D_(6) detectors.The pulse-height weighting technique and double-bunch unfolding method based on Bayesian theory were used in the data analysis.Background deductions,normalization,and corrections were carefully considered to obtain reliable measurement results.The multilevel R-matrix Bayesian code SAMMY was used to extract the resonance parameters in the resolved resonance region(RRR).The average cross sections in the unresolved resonance region(URR)were obtained from 10 to 400 keV.The experimental results were compared with data from several evaluated libraries and previous experi-ments in the RRR and URR.The TALYS code was used to describe the average cross sections in the URR.The astrophysical Maxwell average cross sections(MACSs)of ^(79,81)Br from kT=5 to 100 keV were calculated over a sufficiently wide range of neutron energies.At a thermal energy of kT=30 keV,the MACS value for ^(79)Br 682±68 mb was in good agreement with the KADoNiS v1.0 recommended value.By contrast,the value of 293±29 mb for ^(81)Br was substantially higher than that of the evaluated database and the KADoNiS v1.0 recommended value. 展开更多
关键词 Time-of-flight technique Neutron capture cross sections Maxwell average cross sections
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