摘要:Lepton scattering is an established ideal tool for studying inner structure of microscopic particles such as nucleons as well as nuclei. As a future high energy nuclear physics project, an Electron-ion collider in China (EicC) has been proposed. It will be constructed based on an upgraded heavy-ion accelerator, High intensity heavy-ion accelerator facility (HIAF) which is currently under construction, together with an additional electron ring. The proposed collider will provide highly polarized electrons (with the polarization ~80%), protons and Helium-3 (both with the polarization ~70%), as well as unpolarized ion beams from carbon to uranium with viable center of mass energy from 15 GeV to 20 GeV and the luminosity of (2~4)×1033 cm-2∙s-1. The main foci of the EicC will be the precision measurements of proton structure in the sea quark region, including 3D tomography of nucleon; the partonic structure of nuclei and the parton interaction with the nuclear environment, in particular, the short range correlation of nucleons and the cold nuclear matter effects; the exotic hadronic states, especially those with heavy flavor quark contents. In addition, issues fundamental to understanding the origin of mass could be addressed by measurements of heavy quarkonia near-threshold production at the EicC. In order to achieve the above-mentioned physics goals, a hermetical detector system will be constructed with the cutting-edge technology. During preparation of the document, we have received valuable inputs and help from experts across the globe. The EicC physics program complements the ongoing scientific programs at the Jefferson Laboratory and the future EIC project in the United States. The success of this project will also advance both nuclear and hadron physics as well as accelerator and detector technology in China.
关键词:Electron ion collider;Nucleon structure;Nucleon mass;Exotic hadronic states;Quantum chromodynamics;Helicity;Transverse momentum dependent parton distribution;Generalized Parton Distribution;Deeply virtual compton scattering;Deeply virtual meson production;Energy recovery linac;Polarization;Spin rotator;3D-tomography
摘要:BackgroundAluminizing is often used as a protective coating for aero-engine turbine blades, but the current nondestructive testing equipment can not achieve accurate measurement of the coating thickness. The uniformity of aluminizing thickness has a great impact on the performance of turbine blades and the safety and stability of engine.PurposeThis study aims to develope a nondestructive measurement method for the thickness of diffusion aluminized layer based on X-ray fluorescence absorption.MethodsFirst of all, according to the theoretical calculation formula of X-ray fluorescence absorption, the linear relationship between the logarithm of the fluorescence intensity ratio (lnR) and the thickness of the fluorescence penetrating material (x) was obtained. Then a unitary linear regression model related to the main elements of K403 alloy and a multiple regression model based on the forward selection variable method were established. Finally, the comparative study of the prediction results of the two models was carried out.ResultsThe experimental results show that the multi regression calculation model is relatively stable in comparison with the unitary regression calculation model, and the average relative error of measurement results under different thicknesses is only 3.2%.ConclusionsThe proposed method provides a convenient and feasible guiding idea for solving the problem of measuring the thickness of diffusion permeable layer.
摘要:BackgroundDuring the uranium enrichment process, the generated wastewater containing fluoride and uranyl ions, has potential threat to aquatic ecosystem and human health. Thus, the uranium concentration in the wastewater and its secondary sources must be reduced to an acceptable value before being discharged into the environment.PurposeThis study aims to graft acrylonitrile (AN) and methacrylic acid (MAA) onto ultra-high molecular weight polyethylene (UHMWPE) fiber to synthesize amidoxime (AO)-based sorbent for removing uranium (U(VI)) from simulated wastewater containing fluoride ions.MethodsThe AO-based sorbent was prepared by radiation grafting of AN and MAA onto UHMWPE fiber, followed by amidoximation. The chemical structures and surface morphologies of the pristine and modified UHMWPE fiber were characterized by Fourier transformed infrared spectroscopy (FTIR), scanning electron microscopy (SEM) and X-ray photoelectron spectroscopy (XPS), respectively. The uranium adsorption performance of the sorbent was investigated by batch adsorption in simulated wastewater. Results and Conclusions1) The uranium sorption kinetics and isotherm of AO-based UHMWPE fiber were in congruence with the pseudo-second-order model and the Langmuir model, respectively. 2) The maximum U(VI) adsorption capacity in simulated wastewater (U(VI): 40 mg∙L-1; sodium fluoride (NaF): 10 g∙L-1; sorbent dosage: 0.2 g∙L-1; time: 21 d) was 151.98 mg∙g-1, which is basically consistent with the theoretical saturated adsorption capacity (153.85 mg∙g-1). 3) The removal ratio of U(VI) in simulated wastewater reached 99.93% by increasing sorbent dosage (1.5 g∙L-1), and the residual uranium (28 μg∙L-1) can meet the national discharge standard (< 50 μg∙L-1).
摘要:BackgroundNuclear database is the basis of neutron transport calculation. It provides necessary nuclear data for lattice program. At present, the nuclear data of MCNP program are developed based on ENDF/B-VII.0 library or evaluation library of previous version. The latest version of ENDF/B series libraries was released in 2011. The incident neutron library contains 423 nuclides, 32 new nuclides and 2 natural nuclides are reduced. A total of 234 materials have been updated on the basis of ENDF/B-VII.0.PurposeThis study aims to produce Advanced hybrid database (AHD) 1.0 for MCNP program.MethodsBased on the ENDF/B-VII.1 evaluation library, the NJOY was used to produce the AHD1.0 for MCNP. The highly enriched uranium, the medium enriched uranium and low enriched uranium with fast spectra, intermediate spectra and thermal spectra benchmarks were selected from the International Handbook of Evaluated Criticality Safety Benchmark Experiments (ICSBEP) to validate the this library. The results of MCNP were compared with the experiments.ResultsThe calculation results coincide well with the experimental values, but when elements such as W, Fe, Gd are contained, the uncertainty range of the benchmark is excedded due to unavailable data in the library or the source of the evaluation library for the nuclide.ConclusionsThe results show that the AHD1.0 is reliable, can be used in nuclear design.
摘要:BackgroundAt present, most of the physical protection systems of nuclear facilities at home and abroad use the path analysis method to evaluate the effectiveness. The performance of the system is evaluated by calculating the cut off probability, hence the evaluation index is single and cannot reflect factors such as the system reliability, the command strategy, the information security design and other factors.PurposeThis study aims to analyze the comprehensive effectiveness of the physical protection system by using neural network method.MethodsThe comprehensive effectiveness evaluation index system of the physical protection system was established by using the analytic hierarchy process (AHP), and the comprehensive effectiveness evaluation model of the physical protection system for nuclear facilities was established by using the composite ability of the nonlinearity of the BP (back propagation) neural network. The comprehensive effectiveness of the physical protection system for the marine nuclear power platform was evaluated.Results & ConclusionsThe evaluation results show that the BP neural network evaluation model converges fast, avoids the shortcomings of the majority of sample concentration effects in the AHP evaluation process, and has better adaptability and stability. It provides a kind of field for physical protection effectiveness evaluation.
摘要:BackgroundComputational time and calculation accuracy are key features of the application of neutron transfer method.PurposeThis paper aims to reduce the computational time on the premise of ensuring the accuracy of calculation.MethodsBased on a neutron transport calculation program for hexagonal nodal, a fast solution method was proposed to solve the 1/6 core is solved with 60° periodic symmetric boundary conditions, and calculated in parallel. The natural decoupling between the response matrices corresponding to different energy groups and nodes, and the parallelism between non-overlapping spatial regions was taken into account to solve the response matrix equation. Based on message passing interface (MPI), parallel program of the response matrix construction was developed to solve the matrix equation. Calibration calculation for the TAKEDA4 benchmark was carried out by parallel computing.ResultsThe computational results show that the 60° periodic symmetric boundary condition and the parallel computing function can greatly improve the computational efficiency while ensuring the same calculation accuracy, and verify the correctness of the fast solution strategy. Compared with the full core serial calculation, the total calculation time overhead of the 1/6 core under 9 processors can be reduced by 26, 25, and 22 times under P1, P3, and P5, respectively.ConclusionsA quick solution for hexagonal nodes is initially achieved.