最新刊期
卷 45 ， 期 9 ， 2022
- “在上海光源BL14W1线站，基于PILATUS探测器搭建的von Hamos构型XES谱仪，能量分辨率达到eV量级，可满足高能量分辨实验需求。”摘要：BackgroundHigh energy resolution X-ray emission spectroscopy (XES) has higher energy resolution than conventional X-ray absorption fine structure spectroscopy (XAFS), hence a powerful tool to explore the fine electronic structure of matter. The PILATUS detector is a single photon counting detector without dark current and readout noise.PurposeThis study aims to build a von Hamos geometry high energy resolution XES and the data acquisition system (DAQ) at Shanghai Synchrotron Radiation Facility (SSRF) that can be used to combine multiple spectral methods and carry out the deep resolution of elements and the fine resolution of chemical forms.MethodsThe PILATUS detector was applied as a position sensitive detector and KOHZU stages were used to provide high-precision adjustment of six dimensions of cylindrical curved crystal, an X-ray emission spectrometer based on von Hamos geometry was developed at BL14W1 beamline of SSRF. The data acquisition system of XES was developed based on a PILATUS detector, KOHZU stages, a monochromator and an ion chamber. The software of the spectrometer was developed on the LabVIEW platform and CAlab module. Resonant inelastic X-ray scattering (RIXS) and high energy resolution fluorescence detected X-ray absorption spectroscopy (HERFD-XAS) experiments were conducted to verify the performance of this XES.ResultsResults of energy resolution test and X-ray emission spectrum experiment of sample show that a resolution of 1.67 eV full-width at half maximum (FWHM) for elastic scattering peak of sample at 8 046 eV is achieved, which is close to the world advanced level.ConclusionsThe von Hamos geometry X-ray emission spectrometer based on PILATUS detector meets the need of high energy resolution experiment at SSRF.关键词：PILATUS;X-ray emission spectroscopy;von Hamos;Data acquisition
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发布时间：2024-10-25
SYNCHROTRON RADIATION TECHNOLOGY AND APPLICATIONS
- “在材料科学领域，研究人员开发了核孔膜表面重孔分布分析程序，通过计算机模拟计算关键产品参数，为优化工艺参数提供辅助工具。”摘要：BackgroundThe porosity and hole overlap rate of nuclear track-etched membrane are important parameters to characterize its filtration performance.PurposeThis paper aims to develop an analysis platform for hole distribution on the nuclear track-etched membrane surface by computer simulation, which can predict some key product parameters and help optimize process parameters in actual production.MethodsBased on the Monte Carlo method, the platform was developed using the data analysis framework ROOT. The incident ions were under the hypothesis of two-dimensional (2D) uniform distribution and holes were under the hypothesis of the same size. The 2D coordinates of holes were generated by gRandom function in ROOT, and holes on the surface were drawn in 2D pixelated binary canvas. The hole area was calculated simply by counting the number of fired pixels, and porosity was equal to the effective hole area divided by canvas area. The probability distribution of single, double, and multiple holes on the surface under different porosities was calculated according to each specific image, so was the probability distribution of the area of multiple holes. Finally, the reliability of analysis platform was verified by comparing the calculation results with the theoretical deduction results and the scanning electron microscope observation results.ResultsThe results shows that hole overlap rate and porosity satisfy a certain functional relationship, and cannot be independently controlled in production. With the increase of porosity, the probability of single hole decreases monotonously, while the probability of multiple holes continues to increase. When the porosity is 10%, the hole overlap rate is close to 35%; as the porosity increases to 30%, the hole overlap rate reaches 80%.ConclusionsIt can be concluded that this analysis platform can analyze and calculate key product parameters such as porosity and overlap rate, therefore can be used as an auxiliary tool for optimizing process parameters in the production of nuclear track-etched membranes.关键词：Nuclear track-etched membrane;Monte Carlo simulation;Porosity;Hole overlap
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发布时间：2024-10-25 - “在核探测领域，专家利用MCNP5模拟计算点源探测效率，为探测器效率刻度提供参考。”摘要：BackgroundWhen the relative position of the point source and the detector changes, the detection efficiency will also change. Determining the functional relationship of the detection efficiency with the alteration of the detection distance and angle is beneficial to quickly obtain the detection efficiency of the point source at any position.PurposeThis study aims to determine the spatial point source efficiency function for a LaBr3(Ce) of a specific size.MethodsThe detection efficiency of 152Eu, 137Cs, and 60Co point sources at specific positions were simulated and calculated by MCNP5, and the efficiency of the 3.81-cm (diameter and length) LaBr3(Ce) detector was calibrated by simulation. The detection efficiency of the point source at different positions in the 2π space range of the front of the LaBr3(Ce) detector was calculated. The functional relationship between detection efficiency and angle and distance was obtained by data fitting.ResultsCompared with the experimental results, the maximum relative difference of detection efficiency of point sources calculated by MCNP5 is less than 6%. The maximum detection efficiency of LaBr3(Ce) detector appears at an angle of 90° with the detector axis. With the increase of detection distance and energy, the influence of angle on the detection efficiency of point source gradually decreases. The effect of the spatial position on the detection efficiency is actually the spatial solid angle efficiency of the point source relative to the detector.ConclusionThe detection efficiency of a point source at any position in space can be calculated based on the efficiency function, which has a good reference value and guiding significance for the solution of the LaBr3(Ce) detector efficiency matrix and the efficiency calibration.关键词：LaBr3(Ce) detector;Efficiency calibration;Point source efficiency function
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发布时间：2024-10-25 - “在增材制造材料领域，研究了316L不锈钢在不同辐照温度下的硬化行为，发现辐照硬化随温度升高而降低，氦泡和位错环是主要微观缺陷。”摘要：BackgroundThe additive manufacturing (AM) technology is expected to apply to the field of advanced nuclear energy because of its unrivalled design freedom and short lead times. However, the irradiation resistance of the AM materials needs to be studied. One of the key scientific problems is the irradiation hardening behavior of the AM materials under irradiation environment. As a candidate nuclear material, 316L stainless steel (SS) produced by selective laser melting (SLM, a very important AM technology of metals) is selected as the study object.PurposeThis study aims to investigate the irradiation hardening behavior and the irradiation defects evolution of the SLM 316L SS as function of temperature.MethodsThe SLM 316L SS was irradiated by 500 keV helium ions at different irradiation temperatures (from 350 °C to 800 °C) to explore the temperature effect of hardening behavior. The irradiation dose of each sample was 1.5×1016 ions·cm-2. The irradiation hardening and irradiation defects were characterized by nanoindentation and transmission electron microscopy (TEM) respectively. The contribution of helium bubbles and dislocation loops to irradiation hardening was calculated using the dispersed barrier hardening (DBH) model.ResultsThe results of the nanoindentation test show that the irradiation hardening degree of SLM 316L SS decreases from 71.65% at 350 °C to 23.62% at the highest temperature, suggesting an obvious irradiation hardening recovery with the temperatures increasing. The observation of TEM indicates that helium bubbles and dislocation loops are the main micro defects caused by the ion irradiation. The evolution trend of the two types of irradiation defects with temperature is the same whilst the helium bubble's contribution to the irradiation hardening is slightly higher than that of dislocation loops except at the highest temperature. With the increase of temperature, the average number density of the two defects decreases steadily with the increase of diameter, but the helium bubbles have the higher temperature sensitivity. The calculated values by the DBH model are in agreement with the experimental values obtained by nanoindentation testing.ConclusionsThe irradiation hardening of SLM 316L SS decreases with increasing temperature, and helium bubbles and dislocation loops are closely related to the irradiation hardening behavior. The higher temperature sensitivity of helium bubbles may be a very important reason for the high temperature recovery of irradiation hardening. With the increase of temperature, the decrease of irradiation defects induced by the enhancement of defects' diffusion ability is the main mechanism of the recovery of the hardening behavior of SLM 316L SS at high temperature.关键词：Additive manufacturing;316L stainless steel;Irradiation hardening;Helium bubbles;Dislocation loops
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发布时间：2024-10-25
ACCELERATOR, RAY TECHNOLOGY AND APPLICATIONS
- “在核电厂气态流出物14C测量领域，专家分析了影响准确度的因素，为提高测量准确度提供解决方案。”摘要：BackgroundThere is no national standard specifically for the analysis of gaseous effluents 14C from nuclear power plants in China, only one group standard available for reference. The group standard is technical specification for 14C analysis of gaseous effluents for nuclear power plants (TBSRS 005―2019). Most nuclear power plants in China refer to this group standard and use direct measurement method to analyze 14C in gaseous effluent.PurposeThis study aims to investigate the accuracy of 14C in gaseous effluent of nuclear power plant by the direct measurement method.MethodsA series of experiments were carried out, including optimal ratio of sample and scintillation cocktail, quenching effect, entrainment of tritium and influent factors of tritium on the analysis of 14C. The optimal ratio of sample and scintillation cocktail was selected after measuring different volume ratios of sample and scintillation liquid. The experiment of quenching effect was to measure the samples with different quenching degrees and to observe the influence of different quenching degrees on the measurement efficiency. Entrainment of tritium and the influence level experiment of tritium was to determine the existence of entrainment of tritium through the comparison of samples spectrogram, and to determine the influence level of tritium on the counting of 14C by added different proportions of tritium to 14C sample. Finally, direct measurement results of sixty-seven 14C samples of gaseous effluent from a nuclear power plant were statistically analyzed.ResultsThe experimental results show that tritium is entrained in the gaseous effluent 14C sample when the HAGUE 7000 14C sampler is used, and 1%~2% of the entrainment of tritium is contributed to the count of 14C. The optimal ratio of sample and scintillation cocktail is 6 mL vs. 14 mL. The difference of sample quenching causes the deviation of detection efficiency. The direct measurement results of sixty-seven 14C samples show that the maximum efficiency difference of 4.6% is introduced for different quenching degrees of samples.ConclusionThe main factors affecting the accuracy of the direct measurement method are the ratio of sample and scintillation cocktail, entrainment of tritium and accuracy of detection efficiency. The influence of entrainment of tritium can be reduced by resolving spectral channel, using suspension analysis method or changing sampling method.关键词：Nuclear power plant;14C in gaseous effluent;Entrainment of tritium;Direct measurement method
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发布时间：2024-10-25
NUCLEAR CHEMISTRY, RADIOCHEMISTRY, RADIOPHARMACEUTICALS AND NUCLEAR MEDICINE
- “在散裂中子源微小角中子散射谱仪领域，专家设计了双导轨导向、齿轮齿条传动的驱动结构，通过高精度伺服电机控制，实现了探测器移动小车的高精度定位控制。测试结果显示，其定位精度满足200微米要求。”摘要：BackgroundThe Very Small Angle Neutron Scattering (VSANS) instrument of China Spallation Neutron Source (CSNS) is a world-class SANS instrument with several detectors. It is necessary that the three 3He detectors move accurately and smoothly forward and backward in the vacuum scattering tank.PurposeThis study aims to create high-precision detector trolleys with a positioning accuracy of ≤200 μm in the traveling range of 5 m.MethodsThree detector trolleys supported by double guide rails with rack-pinion mechanism were designed, fabricated and aligned. They were motorized by three servo motors meshing with the rack-pinion system fixed on one side of the guide rail at the bottom of the detector tank. The rotation of the motors to maintain the smoothness of the action was realized by planetary gear reducer. The parallelism of the left and right sides of the guide rails was controlled within 50 μm during the 12 m stroke, and the reverse clearance of the rack and pinion was controlled within 100 μm to provide high motion accuracy of the detector trolleys.ResultsThe results of five round-trip repeat positioning tests of the detector trolleys demonstrate that the bidirectional repeated positioning accuracy of the detector trolleys is within 140 μm, and their positioning accuracy is within 167 μm.ConclusionsThree detector trolleys supported by double guide rails and powered by a rack-pinion mechanism are constructed for the CSNS-VSANS instrument. The positioning accuracy is better than 200 μm which meets the precision requirements of SANS experiments.关键词：Very small angle neutron scattering instrument;Rack-pinion mechanism;Accuracy test
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发布时间：2024-10-25 - “在造岩元素中子γ测井仪器领域，专家建立了蒙特卡罗模型，优化了仪器结构参数，为提高探测精度提供解决方案。”摘要：BackgroundThe rock-forming element neutron gamma logging tool is mainly composed of a deuterium-tritium neutron source, a shield, and a lanthanum bromide (LaBr3) scintillator detector. Among them, the instrument shell material, boron sleeve structure length, shield structure, and the distance (source distance) from the bromide crystal detector to the neutron source are main factors that affect the count and energy spectrum of the gamma detector. These factors have a crucial impact on the identification and determination of lithology, and it is necessary to optimize the parameters of the tool.PurposeThis study aims to obtain better counts and energy spectrum of the rock-forming element neutron gamma logging tool and effectively reduce the interference signal.MethodsBy establishing a Monte Carlo model of rock-forming element neutron gamma logging tool, the performances with different shell materials, boron sleeve structure lengths, shielding body structures, and source distances were simulated. And the relationships between the changes of the shell material, boron sheath structure length, shield structure, source distance and the response of the tool were systematically studied. Finally, the optimized structure parameters of the logging tool were obtained.ResultsThe results show that the optimum shell material is TC11 titanium steel, the optimum length of the boron sleeve is set to be 29 cm and the boron sleeve is embedded on the TC11 titanium steel instrument shell, the shielding body is made of tungsten nickel iron with a diameter of 11.8 cm, and the optimum source distance is 37.6 cm.ConclusionsThrough the simulation test of the instrument performance, it is determined that the optimized neutron gamma logging tool of rock-forming elements has a detection depth of 38.9 cm and a vertical resolution of 40 cm, and can obtain more accurate dry weight of elements in the borehole size of 7~40 cm. This study provides a theoretical reference for the design of rock-forming element neutron gamma tool and the logging interpretation.关键词：Monte Carlo simulation;Shell material;Length of boron sleeve structure;Shield structure;Source distance
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发布时间：2024-10-25
NUCLEAR ELECTRONICS AND INSTRUMENTATION
- “在航空γ能谱数据处理领域，研究者采用小波包软阈值降噪法，显著提升了探测精度和测量准确度。”摘要：BackgroundWith the continuous development of nuclear technology, radioactive material exploration requires higher and higher detection accuracy of aerial gamma energy spectrometer, meanwhile, the wavelet packet soft threshold noise reduction method has the advantages of good noise reduction effect and high signal-to-noise resolution.PurposeThis study aims to find the optimal wavelet packet soft threshold noise reduction scheme for the aerial gamma energy spectrum.MethodsFirst of all, the aerial gamma energy spectrum obtained by CeBr3 detector was taken for noise reduction study using various wavelet packet soft threshold noise reduction scheme schemes. Then three noise reduction schemes were selected on the base of the peak signal-to-noise ratio (SNR) and applied to the accuracy measurements. Based on the improvement effect of the three noise reduction schemes on the accuracy, the best noise reduction scheme was finally found.ResultsThe best noise reduction scheme is a wavelet packet soft threshold noise reduction method using db14 for 7-layer decomposition. This noise reduction scheme can improve the peak signal-to-noise ratio of the aviation gamma energy spectrum from 23.22 dB to 39.50 dB and improve the measurement accuracy of the aviation gamma energy spectrometer by 3.19%.ConclusionsThe wavelet packet soft threshold noise reduction method has good noise reduction effect, less distortion, and can also improve the accuracy of the measurement, which is suitable for application in the data processing of aviation gamma energy spectrum.关键词：Gamma energy spectrum;Noise reduction;Small wave bag;Soft Threshold
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发布时间：2024-10-25
NUCLEAR PHYSICS, INTERDISCIPLINARY RESEARCH
- “据最新研究，自适应径向基神经网络在预测反应堆堆芯热工参数方面表现出色，为核电厂安全运行提供有力保障。”摘要：BackgroundAlterations in thermal parameters directly affect the safety of reactors. Accurately predicting the trends of key thermal parameters under various working conditions can greatly improve reactor safety, thereby effectively preventing the occurrence of nuclear power plant accidents. The thermal and hydraulic characteristic parameters in the reactor are affected by many factors.PurposeThis study aims to explore the prediction method of core thermal-hydraulic parameters of fast reactor and determine the feasibility of neural network prediction.MethodsThe China experimental fast reactor (CEFR) was selected as the research object, and the maximum temperature of the fuel cladding surface and mass flow rate were used as predictor variables. After data samples were generated through the Subchannel code (named Subchanflow), two widely used adaptive neural networks were employed to perform the thermal parameter forecast analysis of CEFR fuel assembly under steady-state conditions, and CEFR 1/2 core was taken as subject to carry out single-step and continuous predictive analysis of thermal parameters under transient conditions.ResultsThe results show that, compared with adaptive BP neural network, the adaptive RBF neural network exhibits a better fitting ability and higher forecasting accuracy, and its maximum error under steady-state conditions is 0.5%. Under transient conditions, some local points have poor forecasting accuracy, however, the adaptive RBF neural network is generally excellent at predicting temperature and mass flow. The average relative error of temperature does not exceed 1%, and the average relative error of flow does not exceed 6%.ConclusionsThe adaptive RBF neural network model can provide real-time forecasting in a short time under unstable flow conditions, and its forecasting results have certain reference value.关键词：RBF neural network algorithm;Adaptive gradient descent method;Fast reactor;Thermal-hydraulic parameters prediction method
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发布时间：2024-10-25 - “在核反应堆严重事故中，自然对流、传热和湍流现象对安全壳内气体流动和分布至关重要。研究者采用计算流体力学方法，通过数值模拟分析了安全壳内气体流动和换热现象，为反应堆事故时安全壳内气体流动及分布提供参考。”摘要：BackgroundNatural convection, heat transfer and turbulence phenomena play important roles in the gas flow and distribution in containment during a severe accident in a nuclear reactor.PurposeThis study aims to explore the gas flow and heat transfer phenomena inside the containment during the accident, and to analyze the temperature distribution under natural convection.MethodsNumerical simulation study was conducted using the computational fluid dynamics (CFD) method. Firstly, the applicability of CFD method to analyze natural convective heat transfer phenomena in a closed space was verified by using experimental data of differential thermal cavity, and then, the geometric model corresponding to the Thermal-hydraulics, Hydrogen, Aerosols and Iodine (THAI)-TH21 experimental device was established to analyze the pressure change in the containment during the experiments and the flow heat transfer characteristics in the device after reaching the steady state.ResultsThe results show that the calculation method used in this paper has good applicability for analyzing the gas flow heat transfer in the containment. The simulated quasi-static pressure is 1.61% higher than the experimental pressure, and the temperature distribution near the cold wall is in good agreement with the experimental data, and the temperature distribution error near the hot wall surface is within 2%.ConclusionsThe study contributes to the validation and development of relevant numerical methods and models, and can provide some reference for the gas flow and distribution in the containment during the reactor accident.关键词：CFD;Containment;Buoyancy-driven flow;Natural convection;Thermal radiation
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发布时间：2024-10-25 - “国际热核聚变实验堆ITER将进入热核聚变运行实验阶段，产生各类含氚放射性废物。ITER设计了一整套放射性废物管理和存储体系，将废物分类为极低放废物、低放固体和液体废物、中放和含长寿命核素的废物和纯氚废物，针对各类废物特点设计不同管理方案，送往法国相应处置厂处置。了解ITER放射性废物管理现状，对促进中国聚变工程实验堆CFETR放射性废物安全管理，掌握含氚废物处理技术，获得社会公众理解和支持，具有重要参考意义。通过梳理和分析ITER放射性废物管理体系，提出了CFETR放射性废物管理研究建议。”摘要：International thermonuclear experimental reactor (ITER) will enter the experimental stage of thermonuclear fusion operation in a few years, and will produce various kinds of tritium-containing radioactive wastes (tritiated wastes). ITER has designed a complete radioactive waste management and storage system, for the management of different types of wastes. ITER classifies these wastes as very low level waste (Très Faible Activité, TFA), low and intermediate level short-lived waste (Type A), intermediate level long-lived waste (Type B) and purely tritiated waste (PT). For the sake of sending these wastes to the disposal sites of France, ITER has designed different management schemes for each kind of wastes. Studying and understanding the current status of ITER radioactive waste management, is of great importance to promote the safety management of radioactive waste in Chinese fusion engineering test reactor (CFETR), to master the tritium-containing waste treatment technology and win wide recognition in the society. By sorting out and analyzing ITER radioactive wastes management system, several research subjects and suggestions related with CFETR waste management are put forward. Much work needs to be done for CFETR waste management system. It is recommended to carry out systematic research and evaluation in terms of waste acceptance criteria, tritium release limits, and waste treatment processes.关键词：ITER;Radioactive waste;Management status;CFETR
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发布时间：2024-10-25 - “注锌可改变压水堆锆合金表面CRUD成分，提高燃料包壳换热能力。”摘要：BackgroundThe corrosion products deposited on the surface of pressurized water reactor (PWR) zirconium alloy will form chalk rivers unidentified deposit (CRUD), which will reduce the heat transfer capacity of fuel cladding and affect the primary radioactivity level. The main component of CRUD is ferronickel spinel whilst the zinc, as a more active metal than ferronickel, may change the composition of CRUD through displacement reaction, or precipitate in a higher heat flux environment and form a new metal complex with ferronickel. Hence zinc injection, as a hydrochemical regulating method, is being more and more widely used in nuclear power plants.PurposeThis study aims to investigate the effect of zinc injection on CRUD of zirconium allay surface.MethodsExperiments were conducted in artificial CRUD facility under similar PWR operation environment. Scanning electric microscope (SEM) and X-ray photoelectric spectroscopy (XPS) were employed to analyze the morphology, element and oxidized particles porosity of CRUD before and after zinc injection.ResultsThe experimental results show that zinc mainly precipitates inside CRUD in heating region; after zinc injection, the nickel-iron ration of CRUD elevates from 0.58 to 0.65, while oxidized particles porosity of CRUD decreases from 30.15% to 10.08%. Compared with the non-zinc environment, the cracking of CRUD becomes more obvious, and the micro size of CRUD changes from loose porous shape to dense shape.ConclusionsThese results provide a reference for evaluating the influence of zinc injection on fuel performance of in-service PWRs.关键词：Zinc injection;PWR;Zirconium alloy;CRUD
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发布时间：2024-10-25 - “在核反应堆领域，研究人员基于ThorLAT程序，验证了多种共振计算方法，为熔盐堆设计提供高精度解决方案。”摘要：BackgroundWith the improvement of the computer computing power, it has become a feasible scheme to generate few-group constants by two-dimensional full-core transport calculations for molten salt reactors (MSRs).PurposeThis study aims to implement resonance calculation approaches which are suitable for MSRs with complex fuel assignments or temperature distributions due to the fuel fluidity.MethodsThe general slowing-down equations of a single resonant nuclide for the subgroup, the embedded self-shielding method (ESSM), Tone's and Tone-N methods were summarized, and an integrated calculation process was designed and implemented in the ThorLAT code. The Tone-N method without uniform cross-section assumption in the Tone's method was specially proposed, and it took the influence of other fuel regions into consideration by introducing two additional fixed source equations. With the use of the SHEM361 energy group structure, the virtual environment for reactor applications (VERA) benchmark problems were used for verification and the fuel lattice of a channel-type MSR was calculated and analyzed.ResultsThe keff and pin power distributions for VERA benchmark problems are in good agreement with the reference solutions, and the maximum keff error of 2.23×10-3 is from the VERA-4B-2D case, which shows the correctness of the implementation. The results obtained with the ESSM and Tone's method, which are based on the interpolation of resonance integral tables for uniform materials, are acceptable for the MSR fuel lattice with uniform temperature or radial temperature distributions. The keff errors calculated by the ESSM and Tone's method for the MSR fuel lattice are less than 1.50×10-3, and the maximum errors of U-238 homogenized absorption cross sections in the fuel region are less than 3.1%.ConclusionsThe ESSM and Tone's method are more accurate and has a significant efficiency advantage than the subgroup method with uncorrelated model or full correlation model for the case with radial temperature distribution. The results of the Tone-N method are basically the same as those of the Tone's method, which shows that the uniform cross-section assumption in the Tone's method is reasonable. Compared with the results calculated with the XMAS172 group structure, the results obtained with the SHEM361 group structure can provide more fine spectrum structure for resolved resonances at low energy region, which can effectively improve accuracy.关键词：Molten salt reactors;Resonance calculation;ESSM;Tone;Subgroup
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发布时间：2024-10-25
NUCLEAR ENERGY SCIENCE AND ENGINEERING
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