最新刊期
      卷 40 ， 期 3 ， 2017

        SYNCHROTRON RADIATION TECHNOLOGY AND APPLICATIONS

      • Limin JIN,Zhongmin XU,Hongliang QIN,Li SONG
        Vol. 40, Issue 3, Article number: 030101(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.030101
        摘要：BackgroundThe double crystal monochromator is one of the key equipments on the beamline of synchrotron radiation light source. It obtains the required single wavelength light using the first crystal and the second crystal, thus the assembly and installation of the crystals directly affect the quality of synchrotron radiation. PurposeThe aim is to introduce the proposed method of finite element analysis (FEA), as well as providing useful guidance and reference for the high-precision installation of crystal with high surface quality. MethodsThe simplified finite element model of the first crystal assembly subjected to a certain bolt fastening force is established. By validating the effectiveness of the model, as well as analyzing the slope error of crystal, the stress distribution of the installation parts and the deformation of the "O" ring, to study the mechanical response and mechanism of crystal and its mounting assembly during installation process. ResultsIt is found that the experimental result shows good agreement with FEA result, which proves the accuracy of the presented finite element model. For the phenomenon of stress concentration of various parts and deformation of "O" ring, all of which locate in the allowable range. ConclusionThe installation indicators of first crystal assembly meet the engineering requirements. And the proposed effective FEA technique is expected to be used for the mechanical properties analysis of synchrotron radiation facilities.  
        关键词：Synchrotron radiation;Monochromator;The first crystal;FEA   
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        发布时间：2021-05-19

        LOW ENERGY ACCELERATOR, RAY AND APPLICATIONS

      • Xiong DING,Xinli SUN,Zhen LI,Yuanjiang ZHU,Wurui HUANG
        Vol. 40, Issue 3, Article number: 030201(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.030201
        摘要：BackgroundNeutron reflectivity has a great impact on the transformation of nuclear energy, so the neutron reflection performance should be considered in the neutron shielding material. PurposeThe aim is to analyze the neutron reflection and shielding properties of several materials. MethodsThe Monte Carlo particle transportation program named SuperMC is used for calculating neutron reflecting and shielding properties of various materials with thickness of 1-5 cm. These materials include metal materials (Be, Pb, Cu, boron steel and 238U) and non-metal materials (Polyethylene (PE), LiH and concrete). Results & ConclusionThe neutron reflecting and shielding properties will increase as the thickness of the materials increases, but the increasing amplitude gradually decreases. The reflecting and shielding properties of Be and PE are superior to the other six materials. Besides, the reflecting and shielding properties of Pb are the worst of eight materials, though Pb is often used as the gamma-ray shielding material. In addition, only in the condition that the material thickness is relatively small and 238U have an outstanding performance. However, with the increase in the thickness of the material, its performance will be far worse than most other materials. Considering the mechanical properties of materials, the comprehensive properties of Be are relatively better in eight materials.  
        关键词：Monte Carlo;SuperMC;Neutron reflecting;Shielding property   
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        发布时间：2021-05-19
      • Honglong ZHENG,Xianguo TUO,Rui SHI,Qibiao WANG,Guiyu ZHANG,Qiang HAN
        Vol. 40, Issue 3, Article number: 030202(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.030202
        摘要：BackgroundWith low and intermediate level density sample, linear attenuation coefficient is mainly determined by gamma ray energy and material density. PurposeThe aim is to determine the relationships and effect of gamma ray energy and material density to linear attenuation coefficient. MethodsThis work has constructed different samples with different densities from 0.3 g·cm-3 to 3.0 g·cm-3 by using Monte Carlo N Particle Transport Code (MCNP). Linear attenuation coefficients are obtained for gamma ray energies from 100 keV to 1 500 keV. Relationships and effect of gamma ray energy and material density to linear attenuation coefficient are determined by using a function model. Through experimental measurement of 137Cs and 60Co, linear attenuation coefficients are obtained for gamma ray energies 661.661 keV, 1 173.238 keV, 1 332.513 keV in different samples with densities from 1.0 g·cm-3 to 2.7 g·cm-3. ResultsRelative deviations of linear attenuation coefficients between experimental and MCNP simulation results are less than 7%. ConclusionSimulation results are in good agreement with experimental measurement data. Linear attenuation coefficient function accurately reveals relationships and effect of gamma ray energy and material density to linear attenuation coefficient.  
        关键词：Nuclear waste;Monte Carlo;Gamma ray;Linear attenuation coefficient;Function   
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        发布时间：2021-05-19
      • Tingxing YAN,Yitao YANG,Tongda MA,Chonghong ZHANG,Jiaqi FAN,Zhaonan DING,Yin SONG
        Vol. 40, Issue 3, Article number: 030203(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.030203
        摘要：BackgroundVanadium alloy (V-Cr-Ti) is an important fusion reactor candidate material due to its low activation characteristics, desirable high-temperature strength and good resistance to radiation damage. However, studies at lower temperature have shown a substantially reduced radiation resistance, manifested in a loss of ductility and enhanced hardening. PurposeThis work aims to investigate the irradiation hardening behavior of vanadium alloys under He-ion implantation and displacement damage, and provide an experimental evidence for optimizing the radiation resistance of vanadium alloys. MethodsIn this study, irradiation of V-4Cr-4Ti alloy and V-5Cr-5Ti alloy samples were carried out with He-ions and swift-heavy-ions. A thick layer with a uniform damage distribution in samples was produced by varying energy of He ions, or by using an energy degrade wheel for swift-heavy-ion irradiation. The nanoindentation technique was used to measure the irradiation hardening. Cross-sectional transmission electron microscopy (TEM) sample fabricated from the irradiated samples were investigated with TEM. ResultsThe results show that the hardening saturation occurs when the dose of He-ion implantation is more than 4 200 (Atomic parts per million, APPM)/0.2 (Displacement per atom, DPA). The irradiation hardening by He-ions is far larger than that by the swift-heavy-ions at the same displacement damage level. ConclusionThe phenomenon of the enhanced hardening by He-ions can be attributed to the accelerated formation of defect clusters due to the combination of He-atoms and vacancies.  
        关键词：V-4Cr-4Ti;V-5Cr-5Ti;Irradiation damage;Irradiation hardening   
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        发布时间：2021-05-19

        NUCLEAR ELECTRONICS AND INSTRUMENTATION

      • Guoqiang ZENG,Xiaoping OUYANG,Mingfu YU,Qiang LI,Shilong WEI,Chuanhao HU,Jian YANG,Liangquan GE
        Vol. 40, Issue 3, Article number: 030401(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.030401
        摘要：BackgroundRising time discrimination of current pulse signal by using Cs2LiYC16:CE (CLYC), boron plastic scintillator and other neutron gamma detector, analog multi-channel and common digital multi-channel analyzer can not meet the requirements. PurposeThis study aims to develop a high-speed digital multi-channel analyzer. MethodsIn this paper, by using the direct coupling way, a special high-speed analog front end circuit is designed. The high-speed analog-to-digital converter (ADC) is connected with field-programmable gate array (FPGA) could realize digital design well, then the system will finish data filtering, pulse amplitude extraction, baseline restorer, spectrum storage, transmission function and so on in the FPGA chip. The universal serial bus (USB) peripheral hangs on the embedded PowerPC kernel, the system can not only simplify the complex timing function of the external controller, but also realize high-speed data transmission with personal computer software. In this work, low noise and high current switching power supply is also designed, finally implemented a hand-held offline independent operation of the high speed digital multi-channel single plate. ResultsAfter the experimental tests, we can see that the digital multi-channel analog front end circuit designed in this paper used in NaI (Tl), boron plastic scintillator, LaBr3(Ce) and other scintillation detector can reach to 110 MHz of large signal bandwidth and climb to 200 MHz of small signal bandwidth. Furthermore, it also has real-time sampling rate of 500 MHz, pulse counting rate by more than 107 s-1, and the linearity is up to 0.999 8. ConclusionThe ultimate measured scintillation spectrum in this paper can satisfy the actual requirement.  
        关键词：Digital multi-channel analyzer;500-MHz high speed sampling;Neutron gamma detector;High counting rate spectrum;Current pulse signal   
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        发布时间：2021-05-19
      • Min YUE,Chao YUAN,Shizhe GOU,Wei ZHANG,Yongping WANG,Jianjun CHANG
        Vol. 40, Issue 3, Article number: 030402(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.030402
        摘要：BackgroundData archiving system is an important part of SECRAL-Ⅱ (Superconducting Electron Cyclotron Resonance ion source with Advanced design in Lanzhou-Ⅱ, SECRAL-Ⅱ) control system which is based on the Experimental Physics and Industrial Control System (EPICS). The SECRAL-Ⅱ researchers have special request for data archiving system, but the Channel Archiver of EPICS cannot satisfy their requirements. PurposeThis study aims to develop a novel data archive system to meet user's special requirements. MethodsEpicsSharp, a software library for the NET platform, is employed to implement the channel access protocol of EPICS. Based on C# language and Oracle database, EPICS Client library combined with Microsoft.Excel 14.0 object library are used to implement a novel data archive system which can read EPICS process variable (PV) values and save them into files in Excel format. Corresponding file management system based on hypertext preprocessor (PHP) is developed for user convenience and the safety of the file system. ResultsThe data system is stable and reliable and has been running in practice for half a year. Through the web browser, user can login into the file manager system and select any file to download to the local computer. Then the data file can be viewed or imported into another analysis system. ConclusionThe archive system is reliable and suitable for SECRAL-Ⅱ control system. This scheme is applicable to the similar requirements of other control system.  
        关键词：SECRAL-Ⅱ;EPICS;Oracle;PHP;Data archive   
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        发布时间：2021-05-19

        NUCLEAR PHYSICS, INTERDISCIPLINARY RESEARCH

      • Liang DU,Ping WANG,Shicheng LI,Xiaolong LI,Zhaoya HUANG,Zhaoyi TAN,Ning LIU
        Vol. 40, Issue 3, Article number: 030501(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.030501
        摘要：BackgroundVery low level waste (VLLW) landfill antiseepage layer is a key engineering measure to prevent the radioactive nuclides from entry into the surrounding environment. PurposeThis study aims to give an example of quickly evaluating the retardation capability of a VLLW antiseepage. MethodsThe landfill soil's distribution coefficient (Kd), saturated permeability coefficient (Ks) and dispersion coefficient (D) were got by batch test and column migration test, and the concentration of nuclides through antiseepage layer was calculated with the advection dispersion equation. ResultsThe results showed that the Kd of Co and Ni were 140.92 mL·g-1 and 380.43 mL·g-1, respectively, and retardation factors (Rd) of Co and Ni were 859 and 2 317, respectively, which means this soil has a very strong retardation capacity for Co and Ni. In addition, the breakthrough concentrations of Co and Ni by calculation under the normal circumstance were very low. ConclusionSo the antiseepage layer using this site soil can effectively ensure the environment safety.  
        关键词：VLLW landfill;Antiseepage layer;Retardation capability;Co;Ni   
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        发布时间：2021-05-19
      • Yan WANG,Zhimin LIU,Jingyang YAN,Lizhen LIANG,Chundong HU
        Vol. 40, Issue 3, Article number: 030502(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.030502
        摘要：BackgroundNeutral beam injection (NBI) has been widely used in thermal nuclear fusion experiments for auxiliary heating. The high proton ratio can improve the efficiency of plasma heating and current drive, so it is essential to know the variations of the neutral beam proton ratio with discharge parameters. In the experiment, the macro operation parameters of high current ion source, such as filament voltage, arc voltage and gas flow rate, determine the level of neutral beam proton ratio. PurposeThis study aims to study the effect of the filament voltage and the arc voltage on the neutral beam proton ratio. MethodsBased on the beam extraction experiments applied on Experimental Advanced Superconducting Tokamak (EAST) NBI test bed, the multiple linear regressive model is used to analyze extraction neutral beam proton ratio. ResultsThe filament voltage and the arc voltage are positively correlated with the neutral beam proton ratio, and to establish the prediction equation which can give the value and the trends of the neutral beam proton ratio and the correctness of the model is proved. ConclusionThe neutral beam proton ratio can be analyzed by the multiple linear regressive model with the dependent variables of filament voltage and arc voltage. Between the two parameters, the filament voltage plays a major role in influencing proton ratio, and arc voltage is less important.  
        关键词：NBI;Proton ratio;Multiple linear regressive model   
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        发布时间：2021-05-19

        NUCLEAR ENERGY SCIENCE AND ENGINEERING

      • Yanfei MA,Junlian YIN,Yalan QIAN,Dezhong WANG
        Vol. 40, Issue 3, Article number: 030601(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.030601
        摘要：BackgroundOne advantage of the liquid fueled Thorium Molten Salt Reactor (TMSR) is that the fuel can be burned up deeply with the neutron poisonous gas removal system that can be achieved by bubbling degassing approach. In order to quantify the separation efficiency for the separator and provide useful guidelines to determine the dimensions for the separator, the separation trajectories of bubbles with different sizes in the swirl flow inside the separator are needed. PurposeThis study aims to develop an alternative method to predict the bubble's motion which can avoid the troubleshooting induced by the two-phase simulation. MethodsThe Lagrangian approach is modified to obtain the continuous phase velocity by a single phase simulation, and curve fitting is applied to further approximation of this velocity. Combing the known velocity distribution with explicit mathematical expression and the interaction model for the gas-liquid interface, a mathematical model to calculate the bubble motion is well posed. ResultsA comparison between the numerical results and the experimental data indicates that the result agrees well with each other. As for the separation length concerned, the maximal error is less than 20%. ConclusionIt has theoretical guidance meaning for research on the movement of bubbles in cyclone separator. And it can be used to guide the determination of swirl chamber space.  
        关键词：Bubble separator;Force analysis;Separation length   
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        发布时间：2021-05-19
      • Qifeng ZENG,Libing ZHU,Gaihuan YUAN,Lian WANG,Jiazheng LIU,Bo GAO
        Vol. 40, Issue 3, Article number: 030602(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.030602
        摘要：BackgroundZirconium alloys are widely used as cladding tube and structural materials in pressurized water reactors because of their low thermal neutron cross section, good mechanical properties and corrosion resistance. At present, the main problem in the development of domestic zirconium alloys is the development of new zirconium alloys with independent intellectual property rights, and improving the corrosion resistance and hydrogen pick-up behaviors of zirconium alloys, making them significantly better than Zr-4 alloy, at the same time, keeping comparable mechanical properties, radiation growth and creep resistance with Zr-4 alloy. PurposeTherefore, a series of various model zirconium alloys were prepared by vacuum arc smelting based on Zr-Sn-Nb alloy with minor alloying elements such as Ge and Si, in order to select the most promising candidate alloys to meet these requirements, via comparative studies on the corrosion resistance, hydrogen pick-up behaviors and mechanical properties. MethodsTransmission electron microscopy (TEM) was used to characterize the detail microstructure of base alloys. Corrosion resistance was examined by the weight gain in static autoclave with different water chemistry environments. Hydrogen pick-up behaviors were directly reflected by the hydrogen contents across the oxidation layers and underneath matrix measured by hydrogen determinator. The mechanical properties were evaluated by conventional tensile testing. ResultsIt was found that SZA-6 and SZA-4 alloys consisted of fully recrystallized grain structures with uniformly distributed fine second phase particles located within grain interior and at grain boundaries. Both SZA-4 and SZA-6 alloys exhibited excellent corrosion resistance in all three water chemistry conditions. The corrosion resistance of SZA-6 was better than the reference commercial alloys, and SZA-4 was slightly better than SZA-6. However, the SZA-6 alloy seemed to be less susceptible to hydrogen pick-up compared to SZA-4 alloy. In addition, the mechanical properties of two new zirconium alloys met the design criterion. ConclusionConsidering the outstanding corrosion resistance and low hydrogen pick-up in simulated water chemistry conditions and satisfied mechanical performances, the SZA-4 and SZA-6 alloys were suggested as promising alloys used for CAP1400 fuel assembly in the future.  
        关键词：New zirconium alloy;Alloy composition;Manufacturing process;Microstructure;Corrosion resistance   
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        发布时间：2021-05-19
      • Di JIANG,Yingying LI,Xianghui YIN,Jia FU,Ling ZHANG,Bo LYU,Guosheng XU,Xiang GAO
        Vol. 40, Issue 3, Article number: 030603(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.030603
        摘要：BackgroundCharge eXchange Recombination Spectroscopy (CXRS) is a routine diagnostic method for the measurement of plasma ion temperature and rotation velocity on nuclear fusion devices. The experimental spectrum can be obviously broadened by the instrument function (IF) convoluted, thus the deconvolution is needed for accurate data analysis. PurposeThis study aims to improve accuracy of data analysis by using the Bayesian deconvolution and impurity spectrum identification. MethodsThe deconvoluted method utilizes the Bayesian condition probability formula. Standardized neon lamp is applied to get spectrometric IF for deconvolution processing. Finally, the impurity spectra is identify fast-time-response extreme ultraviolet (EUV) to further improve the analysis accuracy. ResultsExperimental results on Experimental Advanced Superconducting Tokamak (EAST) confirmed the reliability of Bayesian deconvolution that was previously verified by simulation study. ConclusionBayesian deconvolution combined with fast-time-response EUV can be effectively applied to the edge CXRS analysis on tokamak.  
        关键词：Bayesian deconvolution;CXRS;IF;Impurity spectra identification   
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        发布时间：2021-05-19
      • Nanshun HUANG,Lifeng HAN,Fuchun ZHANG,Yongzhong CHEN,Ziwei LIANG,Guimin LIU
        Vol. 40, Issue 3, Article number: 030604(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.030604
        摘要：BackgroundHigh temperature flow meter has been widely applied in the molten salt reactor, solar power generation, high temperature hydrogen production, etc. With the limitation of the material characteristics, the flow meter can only be used in a temperature below 535℃. To be applied in high temperature more than 650℃ environment, the ultrasonic waveguide plate had been modified to raise the temperature resistance. However, there is no standard flow meter or calibration equipment for flow calibration. PurposeThis study aims to design a stable and controllable molten salt flow platform for flow calibration with temperature less than 800℃, pipe diameter about 50 mm, measuring range 1-5 m·s-1, and calibration error less than 5%. MethodsArgon gas was used to control the velocity of the molten salt in the pipe connecting two tanks. The proportion-integration-differentiation (PID) closed-loop control system was employed to control the gas mass flow rate to achieve stable differential pressure and get more than 40-s calibration time. MATLAB simulation was conducted to get the optimization parameters and determine the control scheme of the calibration platform. Some factors affecting the stability of the flow rate are analyzed. ResultsThe optimized scheme, by setting an initial liquid level difference, has been proven to be capable of reducing the total consumption of molten salt ( < 0.1 m 3) and driving gas, and reducing the requirements of the mass flow meter. After calculation, it can get 40-s stable molten salt flow, reached velocity of 4 m·s-1, and with a theoretical calibration error about 1.2%. Conclusions:The physical model of a high temperature molten salt flow meter calibration platform based on gas pressure control deduces a specific expression of the system flow rate. Optimized parameters provide reference for flow meter components selection.  
        关键词：Ultrasonic flowmeter;Flow calibration platform;MATLAB physical simulation;Molten salt loop   
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        发布时间：2021-05-19
      • Jie CHEN,Tao ZHOU,Liang LIU,Bangyang XIA
        Vol. 40, Issue 3, Article number: 030605(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.030605
        摘要：BackgroundReactor core of supercritical water-cooled reactor of China (CSR1000) is selected as research object. PurposeThe establishment of thermal-hydraulic calculation model is to calculate coolant outlet flow and the outlet pressure, which is on the condition of changing the core power, flow and temperature distribution, and the size of the core inlet structure. MethodsTaking the SCAC (Steady supercritical water-cooled reactor analysis code) safety analysis code as calculation method. ResultsThe calculated results show that adjusting moderately the flow distribution of initial inlet fuel assembly will distribute uniformly the flow distribution of respective sub-channel. Inside and outside of the fuel assembly channel outlet pressure drop show an "N" shaped variation. Increasing the inlet core power of internal fuel assembly will reduce the flow distribution within internal fuel assembly. ConclusionAdjusting moderately the flow distribution of initial inlet core will distribute uniformly the power distribution.  
        关键词：CSR1000;Inside and outside the fuel assembly;Mass flow distribution;Pressure drop   
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