最新刊期
      卷 40 ， 期 7 ， 2017
      • Shuting LIU,Tao SU,Peng ZHANG,Hongtao LIU
        Vol. 40, Issue 7, Article number: 070604(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.070604
        摘要：BackgroundMolten fluoride salts which havegood heat transfer and neutron characteristic, were used as the primary and secondary coolants in the loops of thorium molten salt reactor (TMSR) that is a candidate of the generation IV reactor. Structure of molten salt plays an important role in the design, construction and safe operation of molten salt reactor. Infrared absorption spectroscopy (IR)is one of the powerful tools to study the structure of molten salt. However, the commercial standard instrument cannot realize high temperature measurement. PurposeThis study aims to obtain the infrared absorption spectra of molten fluoride salt at the temperature upto 600 ℃ by developing an instrument constructed from commercially available components. MethodsThe main component of instrument is a Fourier transformation infrared (FTIR) spectrometer with wavenumber range of 14700-400 cm-1.Adetachable bottom board in sample compartment was built to allow a furnace to be put in it. The furnace was designed to be two-half pattern for the cuvette to be placed into and out of freely. It can be operated from room temperature to about 600℃. The cuvette, the most important component in the instrument, is made by Hastelloy C/N as the main body with a reverse'T'contour and diamond or crystalline SiC as the window plates. An optical translation stage was installed under the furnace to connect the furnace with the bottom board, which can make sure that the focus of light beam is overlapped with the center of cuvette. ResultsPerformances of the instrument are demonstrated and verified with spectral studies of water at room temperature and molten salt nitrite at high temperature. ConclusionUsing this instrument, the spectra of the molten fluoride salt (FLiBe)have been obtained.  
        关键词：TMSR;Molten fluoride salts;High-temperature IR;Structure investigation   
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        发布时间：2021-05-19
      • Yankai QIAO,Yun CAO,Maosong CHENG,Zhimin DAI
        Vol. 40, Issue 7, Article number: 070605(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.070605
        摘要：BackgroundThe passive shutdown system is an important safety guarantee for the nuclear energy system in case of accidents. PurposeThis study aims to analyze the feasibility of the passive shutdown device with high temperature shearing trigger absorber ball to ensure and enhance the safety of thorium-based molten salt reactor (TMSR) nuclear energy system. MethodsBased on the mechanical properties steep drop from 650 ℃ to 700 ℃ of inconel 625 alloy, a thin-wall baffle made of this alloy is designed as the high temperature shearing trigger structure. The steady state and transient fault fracture simulation of the two dimensional structure are carried out by Abaqus software at different temperatures under accident conditions. ResultsThe simulation results show that the thin-wall baffle cracks within 4-10 s when the preset temperature exceeds 650 ℃ and continues rising. While it will not fracture under the non-accident condition when the temperature rises to 670 ℃ and then reduces immediately. ConclusionThe high temperature shearing trigger structure can reliably fracture to trigger the passive shutdown system under the emergency condition, and further enhance the safety of thorium-based molten salt reactor.  
        关键词：Passive shutdown;High temperature shearing;Inconel 625 alloy;Abaqus;Fracture simulation   
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        发布时间：2021-05-19
      • Heng AN,Shengsheng YANG,Yujun MIAO,Yuxiong XUE,Zhou CAO,Jun WANG,Chenguang ZHANG
        Vol. 40, Issue 7, Article number: 070502(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.070502
        摘要：BackgroundComplementary metal oxide semiconductor active pixel sensor (CMOS APS) with less energy consumption, small volume and less weight is already a major development direction of imaging for remote sensing satellites. During the satellites flying on orbit, electron devices are exposed in space radiation, and degraded by space charged particles. Along with the improvement of semiconductor technology, sensibility of single event effect is more obvious, and is a key factor of reliability. PurposeThis study aims to obtain the characteristics of CMOS APS subjected to charged particles. MethodsBased on analysis of structure and characteristic of silicon on insulator metal-oxide-semiconductor field-effect transistor (SOI MOSFET), radiation damage of CMOS APS irradiated by heavy ions is discussed using the method of theoretical analysis and numerical simulation. And charge collect mechanism of the transistor and photodiode is also analyzed. ResultsThe procedure of charge collecting is simulated by technology computer aided design (TCAD), and obtained the relationship between the leakage current and linear energy transition (LET), incidence position of heavy ion, offset voltage. ConclusionThe result could be used for CMOS APS's single event effect and also provide theoretical guide for the design of radiation hardening.  
        关键词：CMOS APS;Single event effects;Charge collection;TCAD simulation   
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        发布时间：2021-05-19
      • Xiong YANG,Guangli ZENG,Chenguang GU,Yang ZHONG,Dong DING
        Vol. 40, Issue 7, Article number: 070601(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.070601
        摘要：BackgroundNuclear graphite has served as neutron moderator, reflector and structural material in the liquid molten salt reactor (MSR) due to its excellent irradiation performance and mechanical properties at high temperature. During the life time of reactors, the properties of nuclear graphite will be changed due to the irradiation damage. PurposeThe aim is to study the effect of V-shape notch on stress analysis of nuclear graphite component for liquid MSR. MethodsA user-defined material model (UMAT) was used to model the irradiation behavior of nuclear graphite component. The finite element method was used to develop numerical models for the stress analysis of nuclear graphite component. Results and ConclusionThe stress of nuclear graphite component increases as the irradiation gradient. What's more, the stress results of nuclear graphite component without crack and with V-shape crack are different. In the absence of a V-shape crack, the fracture position of the square-shaped graphite component may occur at the center of the structure. In the case of having a V-shape crack, the crack propagation may occur near the crack tip of the nuclear graphite component, which may cause fracture failure of the component.  
        关键词：Nuclear graphite;UMAT;Liquid MSR;Neutron irradiation;V-shape crack   
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        发布时间：2021-05-19
      • Dejun WANG,Miao HE,Zhi QIN,Qing HUANG,Shiyu DU
        Vol. 40, Issue 7, Article number: 070606(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.070606
        摘要：BackgroundUranium carbide has attracted extensive attention as a potential candidate for the fourth generation nuclear fuel, and it is crucial to understand its structures, bulk properties and defect formation to learn the impact of fission products on the performance of the fuels as the fission reaction proceeds for the purpose of proper and safety operation. PurposeThis study aims to help clarify the serving behaviors of uranium carbide as well as provide valuable clues for fuel designers. MethodsIrradiation in experiments and first-principles in theory are mostly used in the literature to analyze the point defect structures of uranium carbide nuclear fuels. ResultsThe theoretical and experimental studies for uranium carbides (UC, UC2 and U2C3) are reviewed, chemical and mechanical properties of defective structures are analyzed emphatically and recommendations for further studies are provided. ConclusionAll these provide new insight into the properties of carbide nuclear fuels.  
        关键词：Uranium carbide;Nuclear fuel;Point defects;Review   
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        发布时间：2021-05-19
      • Qiwei FAN,Haihua ZHU,Yushuang CHEN,Naxiu WANG,Zhiyuan ZHU
        Vol. 40, Issue 7, Article number: 070602(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.070602
        摘要：BackgroundHigh-temperature molten salt has been considered as medium for heat transfer in molten salt reactors and energy storage in solar powerdue to its excellent thermal physical properties. PurposeThis study aims at the heat transfer characteristics of molten saltand the enhanced heat transfer effect in finned tube. MethodsBased on the convective heat transfer experimental apparatus of KNO3-NaNO2-NaNO3 (53%-40%-7%) molten salt and heat transfer oil, the heat transfer characteristics of turbulent region in finned tube was studied.The convective heat transfer characteristics of molten salt in finned tube were analyzed on the basis of experimental data, and a new correlation was proposed by the least squares fitting method. Furthermore, the effect of enhanced heat transfer of finned tube was discussed based on above analysis. Results andConclusionThe error between the experimental data and the fitting formularis in the range of -7.1% and 7.5%. The Dittus-Boelter convective heat transfer correlation is used to evaluate the effect of heat transfer, and it shows that the enhanced convective heat transfer effect of the finned tube is 2.32-3.63 times of that of smooth tube.  
        关键词：Heat transfer;Turbulent region;Finned tube   
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        发布时间：2021-05-19
      • Yanzhi E,Yang ZOU,Wei GUO,Yu PENG,Hongjie XU
        Vol. 40, Issue 7, Article number: 070603(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.070603
        摘要：BackgroundPebble bed fluoride-salt cooled high temperature reactor (PB-FHR) is a kind of Generation IV reactor. Three-dimensional thermal hydraulic code of reactor core is expected to simulate cases with complex spatial effect for PB-FHR but takes very heavy time-consuming. Graphics processing unit (GPU) contains numerous computing cores, thus can be used to efficiently accelerate numerical calculation if applied properly. PurposeThis study aims to develop a GPU-accelerated thermal-hydraulic code (GATH) for PB-FHR core. MethodsThermal non-equilibrium porous media theory is adopted to build the reactor core physical model. Efficient iterative algorithms are researched and implemented on GPU. A PB-FHR core model is built for thermal hydraulic analysis with GATH. Simulation results are compared with ANSYS CFX software to verify GATH code and the GPU acceleration performance is analyzed. ResultsThe results between GATH and CFX are in good agreement. The speedup ratio of GATH can reach 8.39 times. Conclusion The physical model and calculation method adopted in GATH code are right. The GPU accelerating methods proposed in this paper can efficiently accelerate thermal hydraulic simulation.  
        关键词：PB-FHR;GPU-accelerated;Thermal hydraulic;Thermal non-equilibrium porous media   
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        发布时间：2021-05-19

        NUCLEAR PHYSICS, INTERDISCIPLINARY RESEARCH

      • Beidi MENG,Zhen CAO,Cuiyan SHI,Haiping CUI
        Vol. 40, Issue 7, Article number: 070501(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.070501
        摘要：BackgroundThe 125I brachytherapy source has become a popular treatment option in the treatment various tumors, in order to reduce the risk of surrounding normal tissue, it is important to know the dosimetric characteristics of seed source. PurposeThe aim is to develop a reliable and saving time method for calculating the dosimetric parameters of seed source. MethodsDosimetric parameters (dose rate constant, radial dose function and anisotropy function) of the model number 6711 125I seed source are calculated with point-kernel method following American association of physicists in medicine (AAPM) TG-43U1 recommendations. ResultsThe result was compared with the relative data recommended by AAPM TG-43U1 and Monte-Carlo (M-C) method. Dose rate constant with AAPM was in agreement with 6.76%, and that with M-C is 6.19%; radial dose function (except 0.1 cm, 0.15 cm and 0.25 cm) with AAPM is within 0.02%-2.27%, and that with M-C is within 0.06%-6.65%. ConclusionThe point-kernel method can be applicable to calculate the dosimetric characteristics of seed sources.  
        关键词：Point-kernel integration method;Dosimetric parameters;125I seed source   
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        发布时间：2021-05-19

        NUCLEAR ELECTRONICS AND INSTRUMENTATION

      • Yabing ZHANG,Zhimin LIU,Caichao JIANG,Sheng LIU,Shiyong CHEN,Junjun PAN,Chundong HU
        Vol. 40, Issue 7, Article number: 070402(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.070402
        摘要：BackgroundNeutral beam injector (NBI) is one of the important parts of experimental advanced superconducting tokamak (EAST) for auxiliary heating. Four grids structure, including accelerator grid, gradient grid, suppressor grid and ground grid, is adopted in extraction system of NBI ion source. The suppressor grid power supply is high voltage DC power supply to offer negative potential to suppressor grid. To meet the requirements of output characteristics of suppressor grid power supply, series-connected insulated gate bipolar transistor (IGBT) is used as modulation switch in output port. PurposeThis work aims to research the influence of the technology of series-connected IGBTs to voltage balancing effect and output characteristics of suppressor grid power supply. MethodsIn this paper, IGBT switch is modeled and simulated at different parameters with PSpice software. ResultsThe simulation results show that, under certain conditions, the value of capacitance in resistance capacitance diode (RCD) snubber circuit has a crucial influence on the effect of dynamic voltage balancing and the turn-off characteristics of power supply, and the value of resistance determines the discharge time and the peak discharge current of capacitance. Finally, the corresponding test result is presented. ConclusionThis research can identify the quantitative relationship between parameters of snubber circuit and effect of voltage balancing, as well as output characteristics of suppressor grid power supply. So that, it can guide the optimization of suppressor grid power supply with simulation data, which is meaningful for the security and stability of NBI ion source operation.  
        关键词：Suppressor grid power supply;Series connected IGBTs;Pspice;RCD;Voltage balancing   
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        发布时间：2021-05-19
      • Bin LIU,Huasi HU,Huanwen LYU,Lan LI
        Vol. 40, Issue 7, Article number: 070401(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.070401
        摘要：BackgroundGamma reaction history (GRH) is becoming important for inertial confinement fusion (ICF) diagnostic. The traditional design for GRH is by optical-ray-tracing method which is based on geometrical optics. However, the detector performances, such as detection efficiency and time response, are hard to improve as a result of lacking precise considerations of energy and angular distributions of secondary electrons. The optimization method genetic algorithm (GA) combining with GEANT4 can be used to enhance the detector performances during the design process. However, the computational time consumption of GEANT4 is great. PurposeIn order to accelerate the GEANT4 program, two continuation calculation methods, function fitting method and file read method, have been established. MethodsFor the function fitting method, distributions of positions, directions, time and wavelengths of Cherenkov photons are fitted as functions, and then the fitted functions are sampled in GEANT4 program. For the file read method, positions, directions, time, and energy of Cherenkov photons are stored as a matrix, and then the matrix is read in GEANT4 program as the continuation source. ResultsThe difference between the acceleration efficiencies of the two methods is small. The file read method is more accurate than the function fitting method. Time spectrum of Cherenkov photons with the file read continuation source agrees well with time spectra calculated with 16.7-MeV gamma source. Deviations of the efficiency and full width half maximum (FWHM) are 1.4% and 2.1%. ConclusionThe computational time of GEANT4 can be reduced by more than 50%. Moreover, the continuation calculation method can be applied to other GEANT4 simulation problems with convergence difficulty by direct simulation.  
        关键词：GEANT4 simulation;Continuation calculation;DT fusion;Gas Cherenkov detection system   
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        发布时间：2021-05-19

        SYNCHROTRON RADIATION TECHNOLOGY AND APPLICATIONS

      • Jianjun WANG,Wei ZHANG,Qiaogen ZHOU
        Vol. 40, Issue 7, Article number: 070102(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.070102
        摘要：Background As one of the most important equipment in free-electron lasers (FEL), undulator system is as long as tens meters or even hundreds meters. Due to the industrial technical constraints of the undulator manufacture, undulator system has to be segmented by 5-m length. In order to ensure that the phase of the radiation field between two adjacent undulators is matched with each other, conventionally, phase shifter components are inserted between the adjacent undulators. Purpose This study aims to minimize the integral field error of the phase shifter for undulator linkage. Methods Based on the factor that the nonlinearity of pure permanent magnet can be ignored, the first order integral term of magnet field is derivated. By shimming the height and tilt angle of vertically magnetization block in the phase shifter, its integral error can be reduced. Finally, a two-dimensional high-precision Hall probe is used in the experiment to measure the integral error of the phase shifter in different magnetic gaps. Results After field correction, the integral error of the phase shifter is less than 20 Gs·cm both in the center line for all gaps and horizontal position x less than 2 mm at the minimum gap. Conclusion This method has been applied for all the 6 phase shifters that satisfy engineering design requirements in Shanghai soft X-ray free electron laser (SXFEL).  
        关键词：Phase shifter;Magnetic moment;Field integral   
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        发布时间：2021-05-19
      • Lijun LIU,Shuhua WANG,Jian WANG,Ming LI,Yiyong LIU,Li WANG
        Vol. 40, Issue 7, Article number: 070101(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.070101
        摘要：BackgroundThe cryogenic permanent magnet undulator (CPMU) is one of the development trends of the insertion technology. The CPMU, made of NdFeB or PrFeB materials, has a better magnetic field performance at low temperature than that at room temperature. The operating temperature of the CPMU is in the range of 50-150 K up to the magnetic material to be adopted. The CPMU cooling system mainly consists of the CPMU sub-cooled liquid nitrogen cooling system and the CPMU magnet array cooling loop. PurposeThis study aims to develop the CPMU sub-cooled liquid nitrogen (SLN2) cooling system. MethodsAccording to the design scheme and design parameters of the first CPMU SLN2 cooling system for the Shanghai synchrotron radiation facility (SSRF), the heat loads of the system were calculated. The sub-cooled heat exchanger, one of the key components of the SLN2 system was designed. The flow resistance of the sub-cooled liquid nitrogen going through the whole CPMU cooling system was calculated, which provides the design base for liquid nitrogen recirculation pump. Results & ConclusionThe first CPMU, made of NdFeB material, and its SLN2 cooling system were installed at SSRF since August, 2016. Online test results showed that the SLN2 system met the CPMU cooling requirements and run stably.  
        关键词：CPMU;Sub-cooled liquid nitrogen cooling system;Sub-cooled heat exchanger;Flow resistance   
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        发布时间：2021-05-19

        LOW ENERGY ACCELERATOR, RAY AND APPLICATIONS

      • Qi SUN,Xiaobing LUO,Wanqiong LI,Chao WANG,Ziyue LI
        Vol. 40, Issue 7, Article number: 070201(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.070201
        摘要：Background The precise measurement of fission product yields is significant to many aspects of fission, because it's an important parameter in fission procedure. Purpose The aim is to measure fission product yields of 238U induced by neutrons accurately. Methods The T(d, n) 4He reaction on the PD-300 accelerator of China Academy of Engineering Physics was used to produce 14.8-MeV neutrons. The neutron flux was monitored by Au(Si) surface barrier semiconductor detector during the irradiation. The average neutron flux in the whole process of irradiation was calculated by Al. After the irradiation, the sample was placed in front of a high purity germanium detector to measure the characteristic gamma rays of the fission products. Then cumulative yields were calculated through the counts. The Monte Carlo program MCNPX was used to estimate the effects of multiple scattering and self-shielding of neutrons. The corrections of self-absorption and the neutron flux fluctuation were also calculated. Results The fission product yields for some long half-life radionuclide, i.e., 95Zr, 127Sb, 140Ba, 147Nd, 131I, 103Ru were determined. Conclusion The results were compared with previous literature values, and they are helpful to the analysis and evaluation of238U yield.  
        关键词：238U;Fission yields;DT accelerator neutron source;Activation method;Monte Carlo   
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        发布时间：2021-05-19

        NUCLEAR CHEMISTRY, RADIOCHEMISTRY, RADIOPHARMACEUTICALS AND NUCLEAR MEDICINE

      • Yuan WANG,Guobing YU,Xianbao GU,Huayan TAN,Deyun WEN,Jinlong WANG,Zhi CHEN,Xie XU
        Vol. 40, Issue 7, Article number: 070301(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.070301
        摘要：BackgroundDue to direct deposition on leaves or root uptake, the tobacco leaves may contain 210Po in significant concentration. There have been many surveys on the 210Po activity concentration in cigarettes, yet few researches on the distribution of 210Po during smoking. PurposeThe study aims to research the distribution of 210Po during smoking. Methods 209Po was used for chemical recovery calculation and 210Po was measured by α spectrometry using a passivated implanted planar silicon (PIPS) detector after chemical leaching and spontaneous on silver disk. The 210Po of fresh tobacco, filter, post-smoking filter and cigarette ash were measured. The 210Po activity concentration in smoke was determined on the basis of above data. ResultsThe 210Po activity concentration of the 7 types of cigarettes ranged from (28.13±1.75) mBq·g-1 to (47.78±2.83) mBq·g-1, and the average is 36.60mBq·g-1. On average, about 13.24% of total 210Po was retained in the cigarette ash, about 14.39% of total 210Po was retained in the filter. ConclusionAbout 72.37% of 210Po was transferred in the cigarette smoke, which may be deposited in the lung tissues.  
        关键词：α spectrometry;Distribution of 210Po   
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