A precise determination of the CKM angle γ from Bs0 oscillations in Bs0 → DsK± decays offers a critical test of the Standard Model and probes for new physics. We present a comprehensive study on the prospects o...
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A new value for the emission probability of 137.144 keV γ-rays from 186gRe decay is recommended to be (9.47±0.03)/%. Using this value the measured cross sections for 187Re(n,2n)186mRe and 187Re(n,2n)186gRe...
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A new value for the emission probability of 137.144 keV γ-rays from 186gRe decay is recommended to be (9.47±0.03)/%. Using this value the measured cross sections for 187Re(n,2n)186mRe and 187Re(n,2n)186gRe reactions around 14 MeV are analyzed, and the cross section for187Ke(n,2n)186m+gRe reaction at 14.g MeV is (2213=k116) mb. The UNF code was adopted to calculate the cross sections for the 187Re(n,2n)186m+gRe reaction below 20 MeV, fitting to the value (2213±116) mb at 14.8 MeV using a set of optimum neutron optical potential parameters which were obtained based on the relevant experimental data of rhenium. The isomeric cross section ratio for the 187Re(n,2n)186m,gRe reaction was analyzed using the V-H method based on nuclear statistical theory. Combining these calculated results, the excitation functions for the 187Re(n,2n)lS6mRe and 187Re(n,2n)186gRe reactions were obtained. The obtained results are in good agreement with the available experimental data.
Based on the multi-coincidence measurement, the time resolution of three liquid scintillation detectors (BC501A) were determined strictly by solving the coincidence equations, where the influence from electronics es...
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Based on the multi-coincidence measurement, the time resolution of three liquid scintillation detectors (BC501A) were determined strictly by solving the coincidence equations, where the influence from electronics estimated by self coincidence measurement as well as the background had been considered. The result of this work agreed well with the result that was deduced from the traditional method, and it will be helpful to analyze the energy resolution of neutron time of flight spectra measured by using such detectors at CIAE (China Institute of Atomic Energy).
A complete set of n+233U neutron reaction data from 10-6 eV-20 MeV is updated and revised based on the evaluated experimental data and the feedback information of various benchmark tests, The main revised quantities ...
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A complete set of n+233U neutron reaction data from 10-6 eV-20 MeV is updated and revised based on the evaluated experimental data and the feedback information of various benchmark tests, The main revised quantities are nubars, cross sections as well as angular distributions, etc. The benchmark tests indicate that the present evaluated data achieve very promising results.
A set of optimal proton optical potential parameters for pd-lS4w reactions are obtained at incident proton energy up to 250 MeV. Based on these parameters, the reaction cross-sections, elastic scattering angular distr...
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A set of optimal proton optical potential parameters for pd-lS4w reactions are obtained at incident proton energy up to 250 MeV. Based on these parameters, the reaction cross-sections, elastic scattering angular distributions, energy spectra and double differential cross sections of proton-induced reactions on lS4w are calculated and analyzed by using theoretical models which integrate the optical model, distorted Born wave approximation theory, intra- nuclear cascade model, exciton model, Hauser-Feshbach theory and evaporation model. The calculated results are compared with existing experimental data and good agreement is achieved.
Iron is commonly used as a structural and shielding material in nuclear devices. The accuracy of its nucleardata is critical for the design of nuclear devices. The evaluation data of ^(56)Fe isotopes in the latest ve...
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Iron is commonly used as a structural and shielding material in nuclear devices. The accuracy of its nucleardata is critical for the design of nuclear devices. The evaluation data of ^(56)Fe isotopes in the latest version of the CENDL-3.2 library from China was significantly updated. This new data must be tested before it can be used. To test the reliability of this data and assess the shielding effect, a shielding benchmark experiment was conducted with natural Fe spherical samples using a pulsed deuterium–tritium neutron source at the China Institute of Atomic Energy(CIAE). The leakage neutron spectra from the natural spherical iron samples with different thicknesses(4.5, 7.5, and 12 cm) were measured between 0.8 and 16 MeV after interacting with 14 MeV neutrons using the time-of-flight method. The simulation results were obtained by Monte Carlo simulations by employing the Fe data from the CENDL-3.2, ENDF/B-VIII.0, and JEDNL-5.0 libraries. The measured and simulated leakage neutron spectra and penetration rates were compared, demonstrating that the CENDL-3.2 library performs sufficiently overall. The simulation results of the other two libraries were underestimated for scattering at the continuum energy level.
Fast neutron radiography(FNR) is an effective non-destructive testing *** to the scattering effect and low detection efficiency,the detection limit of FNR under certain conditions cannot be *** order to obtain the min...
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Fast neutron radiography(FNR) is an effective non-destructive testing *** to the scattering effect and low detection efficiency,the detection limit of FNR under certain conditions cannot be *** order to obtain the minimum detectable thickness by FNR,we studied the contrast sensitivity of FNR lead samples,both theoretically and *** then clarified the relationship between pixel value and irradiation time,and sample materials and *** experiment,using a4-cm-thick lead sample,verified our theoretical expression of FNR contrast sensitivity.
The fission yield data in the 14 MeV energy neutron induced fission of^(238)U play an important role in decay heat calculations and generation-Ⅳ reactor *** order to accurately measure fission product yields(FPYs)of^...
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The fission yield data in the 14 MeV energy neutron induced fission of^(238)U play an important role in decay heat calculations and generation-Ⅳ reactor *** order to accurately measure fission product yields(FPYs)of^(238)U induced by 14 MeV neutrons,the cumulative yields of fission products ranging from^(92)Sr to^(147)Nd in the^(239)U(n,f) reaction with a 14.7 MeV neutron were determined using an off-line γ-ray spectrometric ***14.7 MeV quasi-monoenergetic neutron beam was provided by the K-400 D-T neutron generator at China Academy of Engineering Physics(CAEP).Fission products were measured by a low background high purity germanium gamma *** neutron flux was obtained from the^(93)Nb(n.2n)^(92m)Nb reaction,and the mean neutron energy was calculated using the cross-section ratios for the^(90)Zr(n,2n)^(89)Zr and^(93)Nb(n,2n)^(92m)Nb *** a series of corrections,high precision cumulative yields of 20 fission products were *** FPYs for the^(238)U(n,f) reaction at 14.7 MeV were compared with the existing experimental nuclear reaction data and evaluated nucleardata,*** results will be helpful in the design of a generation-Ⅳ reactor and the construction of evaluated fission yield databases.
Ti-based two-dimensional transition-metal carbides (MXenes) have attracted attention due to their superior properties and are being explored across various applications1,2. Despite their versatile properties, supercon...
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New evaluations for several actinide nuclei of the third version of Chinese Evaluated nucleardata Library for Neutron Reaction data (CENDL-3.1) have been completed and released. The evaluation is for all neutron in...
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New evaluations for several actinide nuclei of the third version of Chinese Evaluated nucleardata Library for Neutron Reaction data (CENDL-3.1) have been completed and released. The evaluation is for all neutron induced reactions with uranium, neptunium, plutonium and americium in the mass range A-232-241, 236 239, 236-246 and 240-244, respectively, and cover the incident neutron energy up to 20 MeV. In the present evaluation, much more effort was devoted to improving the reliability of the evaluated nucleardata for available new measured data, especially scarce or absent experimental data. A general description for the evaluation of several actinides' data is presented.
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