A lead-shielded HPGe detector and offlineγ-ray spectra of the residual product were used to measure the cross section(CS)and ratios of isomeric CS(σm/σg)in^(134)Xe(n,2n)^(133m),gXe reactions at different energies(1...A lead-shielded HPGe detector and offlineγ-ray spectra of the residual product were used to measure the cross section(CS)and ratios of isomeric CS(σm/σg)in^(134)Xe(n,2n)^(133m),gXe reactions at different energies(13.5 MeV,13.8 MeV,14.1 MeV,14.4 MeV,14.8 MeV)relative to the^(93)Nb(n,2n)^(92)mNb reaction CS.The target was high-purity natural Xe gas under high pressure.The T(d,n)4He reaction produces neutrons.TALYS code(version 1.95)for nuclear reactions was used for calculations,with default parameters and nuclear level density models.The uncertainties in the measured CS data were thoroughly analyzed using the covariance analysis method.The results were compared with theoretical values,evaluation data,and previous experimental findings.CS data of the 134Xe(n,2n)133mXe and 134Xe(n,2n)133gXe reactions and the corresponding isomeric CS ratios at 13.5 MeV,13.8 MeV,and 14.1 MeV neutron energies are reported for the first time.This research advances our knowledge of pre-equilibrium emission in the(n,2n)reaction channel by resolving inconsistencies in the Xe data.展开更多
Experimentally measured neutron activation cross sections are presented for the ^(65)Cu(n,0)^(62m)Cu,^(41) K(n,a)^(38C)l,and ^(65)Cu(n.2n)^(64)Cu reactions with detailed uncertainty propagation.The neutron cross secio...Experimentally measured neutron activation cross sections are presented for the ^(65)Cu(n,0)^(62m)Cu,^(41) K(n,a)^(38C)l,and ^(65)Cu(n.2n)^(64)Cu reactions with detailed uncertainty propagation.The neutron cross secions were measured at an incident energy of 14.92±0.02 MeV,and the neutrons were based on the(d,n)a fusion reaction.The ^(27) Al(n,a)^(24)Na reaction was used as a reference reaction for the normalization of the neutron flux.The pre-calib-rated lead-shielded HPGe detector was used to detect the residues'γ-ray spetra.The data from the measured cross sections are compared to the previously measured cross sections from the EXFOR database,theoretically calculated cross sections using the TALYS and EMPIRE codes,and evaluated nuclear data.展开更多
In order to check the conceptual design of the subcritical blanket in a fusion-fission hybrid reactor, a depleted uranium/polyethylene simulation device with alternate shells has been established. The measurement of t...In order to check the conceptual design of the subcritical blanket in a fusion-fission hybrid reactor, a depleted uranium/polyethylene simulation device with alternate shells has been established. The measurement of the 23SU（n, 2n） reaction rate was carried out using an activation technique, by measuring the 208 keV T rays emitted from 237U. The self-absorption of depleted uranium foils with different thicknesses was experimentally corrected. The distribution of the 23SU（n, 2n） reaction rate at 90° to the incident D＋ beam was obtained, with uncertainty between 5.3% and 6.0%. The experiment was analyzed using MCNP5 code with the ENDF/BVI library, and the calculated results are all about 5% higher than the measured results.展开更多
Experimentally measured neutron activation cross sections are presented for the^(65)Cu(n,α)^(62m)Cu,^(41)K(n,α)^(38)Cl,and^(65)Cu(n,2n)^(64)Cu reactions with detailed uncertainty propagation.The neutron cross sectio...Experimentally measured neutron activation cross sections are presented for the^(65)Cu(n,α)^(62m)Cu,^(41)K(n,α)^(38)Cl,and^(65)Cu(n,2n)^(64)Cu reactions with detailed uncertainty propagation.The neutron cross sections were measured at an incident energy of 14.92±0.02 MeV,and the neutrons were based on the t(d,n)αfusion reaction.The^(27)Al(n,α)^(24)Na reaction was used as a reference reaction for the normalization of the neutron flux.The pre-calibrated lead-shielded HPGe detector was used to detect the residues'γ-ray spectra.The data from the measured cross sections are compared to the previously measured cross sections from the EXFOR database,theoretically calculated cross sections using the TALYS and EMPIRE codes,and evaluated nuclear data.展开更多
^(232)Th(n,2n)数据对于钍基反应堆研究十分重要,有必要针对其开展中子积分实验,因此,建立了聚乙烯球基准宏观装置,利用活化法在DT中子源下开展了测量^(232)Th(n,2n)反应率的中子积分实验。实验中分别采用了钍粉末以及钍片两种样品形态...^(232)Th(n,2n)数据对于钍基反应堆研究十分重要,有必要针对其开展中子积分实验,因此,建立了聚乙烯球基准宏观装置,利用活化法在DT中子源下开展了测量^(232)Th(n,2n)反应率的中子积分实验。实验中分别采用了钍粉末以及钍片两种样品形态,以消除实验样品状态对实验结果的影响,将样品置于与D离子入射方向成0°的位置进行辐照,利用金硅面α探测器进行中子产额监测以及中子注量波动监测。辐照结束后,利用高纯锗谱仪离线测量反应产物231Th发射的能量为84.2 ke V的γ射线,得到^(232)Th(n,2n)反应率值。同时使用MCNP(Monte Carlo N Particle Transport Code)在数据库ENDF/B-Ⅶ.1、ENDF/B-Ⅶ.0、JENDL4.0下对实验进行了精确模拟,数据库JENDL4.0下的反应率计算结果与实验符合较好。展开更多
The cross-section for the 93Nb（n, 2n）92gNb reaction has been measured at the neutron energy of 14.6 MeV using neutron activation and accelerator mass spectrometry （AMS） determination of the long-lived product nucl...The cross-section for the 93Nb（n, 2n）92gNb reaction has been measured at the neutron energy of 14.6 MeV using neutron activation and accelerator mass spectrometry （AMS） determination of the long-lived product nuclide 92gNb. The neutron energy was generated from the D＋T neutron source at the China Institute of Atomic Energy （CIAE）. The neutron flux was monitored by measuring the activity of 92mNb produced in the competing reaction channel of 93Nb（n, 2n）92mNb. At the neutron energy of 14.6 MeV, the 93Nb（n, 2n）92gNb reaction cross-section of （736±220） mb was obtained for the first time.展开更多
The cross-section data of the 85Rb(n,2 n)84Rb reaction have been measured with the neutron energies of 12 MeV to 19.8 MeV using the activation technique and the relative method.The 85Rb samples were irradiated on the ...The cross-section data of the 85Rb(n,2 n)84Rb reaction have been measured with the neutron energies of 12 MeV to 19.8 MeV using the activation technique and the relative method.The 85Rb samples were irradiated on the surface of a two-ring orientation assembly with neutrons produced from the 3H(d,n)4He reaction at the 5SDH-21.7-MV Tandem accelerator in China.Theoretical model calculations were performed with the TALYS-1.9 code.The present data were compared with previously obtained experimental data and the available evaluated data.展开更多
基金supported by the National Natural science Foundation of China(Nos.11875016,12165006).
文摘A lead-shielded HPGe detector and offlineγ-ray spectra of the residual product were used to measure the cross section(CS)and ratios of isomeric CS(σm/σg)in^(134)Xe(n,2n)^(133m),gXe reactions at different energies(13.5 MeV,13.8 MeV,14.1 MeV,14.4 MeV,14.8 MeV)relative to the^(93)Nb(n,2n)^(92)mNb reaction CS.The target was high-purity natural Xe gas under high pressure.The T(d,n)4He reaction produces neutrons.TALYS code(version 1.95)for nuclear reactions was used for calculations,with default parameters and nuclear level density models.The uncertainties in the measured CS data were thoroughly analyzed using the covariance analysis method.The results were compared with theoretical values,evaluation data,and previous experimental findings.CS data of the 134Xe(n,2n)133mXe and 134Xe(n,2n)133gXe reactions and the corresponding isomeric CS ratios at 13.5 MeV,13.8 MeV,and 14.1 MeV neutron energies are reported for the first time.This research advances our knowledge of pre-equilibrium emission in the(n,2n)reaction channel by resolving inconsistencies in the Xe data.
基金the UGC-DAE Consortium for scientific research(UGC-DAE-CSR-KC/CRS/19/NP03/0913)SERB-DST+1 种基金Government of India(CRG/2019/000360)Institutions of Eminence(IoE)BHU(Grant No.6031)。
文摘Experimentally measured neutron activation cross sections are presented for the ^(65)Cu(n,0)^(62m)Cu,^(41) K(n,a)^(38C)l,and ^(65)Cu(n.2n)^(64)Cu reactions with detailed uncertainty propagation.The neutron cross secions were measured at an incident energy of 14.92±0.02 MeV,and the neutrons were based on the(d,n)a fusion reaction.The ^(27) Al(n,a)^(24)Na reaction was used as a reference reaction for the normalization of the neutron flux.The pre-calib-rated lead-shielded HPGe detector was used to detect the residues'γ-ray spetra.The data from the measured cross sections are compared to the previously measured cross sections from the EXFOR database,theoretically calculated cross sections using the TALYS and EMPIRE codes,and evaluated nuclear data.
基金Supported by Chinese Special Project for ITER (2010GB111002)
文摘In order to check the conceptual design of the subcritical blanket in a fusion-fission hybrid reactor, a depleted uranium/polyethylene simulation device with alternate shells has been established. The measurement of the 23SU（n, 2n） reaction rate was carried out using an activation technique, by measuring the 208 keV T rays emitted from 237U. The self-absorption of depleted uranium foils with different thicknesses was experimentally corrected. The distribution of the 23SU（n, 2n） reaction rate at 90° to the incident D＋ beam was obtained, with uncertainty between 5.3% and 6.0%. The experiment was analyzed using MCNP5 code with the ENDF/BVI library, and the calculated results are all about 5% higher than the measured results.
基金UGC-DAE Consortium for scientific research (UGC-DAE-CSR-KC/CRS/19/NP03/0913)SERB-DST, Government of India (CRG/2019/000360)Institutions of Eminence (IoE) BHU (Grant No. 6031)
文摘Experimentally measured neutron activation cross sections are presented for the^(65)Cu(n,α)^(62m)Cu,^(41)K(n,α)^(38)Cl,and^(65)Cu(n,2n)^(64)Cu reactions with detailed uncertainty propagation.The neutron cross sections were measured at an incident energy of 14.92±0.02 MeV,and the neutrons were based on the t(d,n)αfusion reaction.The^(27)Al(n,α)^(24)Na reaction was used as a reference reaction for the normalization of the neutron flux.The pre-calibrated lead-shielded HPGe detector was used to detect the residues'γ-ray spectra.The data from the measured cross sections are compared to the previously measured cross sections from the EXFOR database,theoretically calculated cross sections using the TALYS and EMPIRE codes,and evaluated nuclear data.
文摘^(232)Th(n,2n)数据对于钍基反应堆研究十分重要,有必要针对其开展中子积分实验,因此,建立了聚乙烯球基准宏观装置,利用活化法在DT中子源下开展了测量^(232)Th(n,2n)反应率的中子积分实验。实验中分别采用了钍粉末以及钍片两种样品形态,以消除实验样品状态对实验结果的影响,将样品置于与D离子入射方向成0°的位置进行辐照,利用金硅面α探测器进行中子产额监测以及中子注量波动监测。辐照结束后,利用高纯锗谱仪离线测量反应产物231Th发射的能量为84.2 ke V的γ射线,得到^(232)Th(n,2n)反应率值。同时使用MCNP(Monte Carlo N Particle Transport Code)在数据库ENDF/B-Ⅶ.1、ENDF/B-Ⅶ.0、JENDL4.0下对实验进行了精确模拟,数据库JENDL4.0下的反应率计算结果与实验符合较好。
基金Supported by National Natural Science Foundation of China(10975195)
文摘The cross-section for the 93Nb（n, 2n）92gNb reaction has been measured at the neutron energy of 14.6 MeV using neutron activation and accelerator mass spectrometry （AMS） determination of the long-lived product nuclide 92gNb. The neutron energy was generated from the D＋T neutron source at the China Institute of Atomic Energy （CIAE）. The neutron flux was monitored by measuring the activity of 92mNb produced in the competing reaction channel of 93Nb（n, 2n）92mNb. At the neutron energy of 14.6 MeV, the 93Nb（n, 2n）92gNb reaction cross-section of （736±220） mb was obtained for the first time.
基金Supported by National Natural Science Foundation of China(11575163)
文摘The cross-section data of the 85Rb(n,2 n)84Rb reaction have been measured with the neutron energies of 12 MeV to 19.8 MeV using the activation technique and the relative method.The 85Rb samples were irradiated on the surface of a two-ring orientation assembly with neutrons produced from the 3H(d,n)4He reaction at the 5SDH-21.7-MV Tandem accelerator in China.Theoretical model calculations were performed with the TALYS-1.9 code.The present data were compared with previously obtained experimental data and the available evaluated data.
