最新刊期
      卷 40 ， 期 10 ， 2017

        SYNCHROTRON RADIATION TECHNOLOGY AND APPLICATIONS

      • Xu WEI,Bingbing ZHANG,Darui SUN,Ye TAO,Can YU,Hao WANG
        Vol. 40, Issue 10, Article number: 100101(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.100101
        摘要：Background Time-resolved experiments could provide a dynamical insight into the structure of materials. The ultrafast X-ray diffraction (UXRD) technique is a common way in time-resolved experiment with the laser pump and the X-ray probe method. Purpose This study aims to perform the UXRD experiments with the high repetition rate pump laser. Methods A picosecond resolution UXRD setup on high repetition rate laser pump at Beijing Synchrotron Radiation Facility (BSRF) was built and a test with the sample SrRuO3 (SRO) grown on the substrate SrTiO3 (STO) was performed at the repetition rate of 310 kHz. Some exploratory experiments on the static heating problem accompanied by high repetition rate photoexcitation were discussed briefly. Results Compared with the previous 1-kHz repetition rate measurement, the signal to noise ratio (SNR) of those at 310 kHz was improved dramatically. And a cooling system was necessary for the overheating problem. Conclusion Those UXRD experiments at BSRF were performed at high repetition rate, which laid a foundation for the future work.  
        关键词：UXRD;High repetition rates;SRO/STO;Structural dynamics   
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        发布时间：2021-05-19
      • Wei QI,Huihao XIA,Can ZHANG,Jinliang SONG,Ping HUAI,Xingtai ZHOU
        Vol. 40, Issue 10, Article number: 100103(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.100103
        摘要：Background The distribution of nanoscale pore is of great significance to irradiation damage behavior of nuclear graphite under intense radiation. Small angle X-ray scattering (SAXS) is an important method used to study the number distribution and its fractal characteristics of pore in nanoscale. Purpose This study aims at the changes in number distribution and its fractal characteristics of nanoscale pore in nuclear graphite. Methods Two typical nuclear graphite, i.e., IG-110 and NBG-18 were sampled and tested at synchrotron radiation SAXS beamline station at temperatures of 25℃, 100℃, 200℃, 300℃ and 400℃, respectively. Results The results showed that there was a non-uniform area in the microstructure of nuclear graphite, and the solid-gas structure of the nuclear graphite pore had a sharp interface, but the change of solid-gas interface does not show obvious regularity with the increase of temperature. In addition, the number of nanoscale pore in IG-110 nuclear graphite increases with the temperature, and is more obvious than that of NBG-18. The fractal dimension of the solid-gas interface decreases with the temperature increasing, indicating that the fractal structure of the graphite become smoother with the increasing of temperature. And the change of IG-110 is more obvious than that of NBG-18. Conclusion The temperature has a significant impact on the pore number distribution and its fractal characteristics.  
        关键词：Graphite;Microporous structure;SAXS   
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        发布时间：2021-05-19
      • Songqi GU,Peiquan DUAN,Shuo ZHANG,Zheng JIANG,Yuying HUANG,Jiong LI
        Vol. 40, Issue 10, Article number: 100102(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.100102
        摘要：Background High energy resolution spectrometer can perform high energy resolution fluorescence detected X-ray absorption spectroscopy (HERFD-XAS), X-ray emission spectroscopy (XES), resonant X-ray emission spectroscopy (RXES), and other experiments. The energy resolution could be sub-eV level and the system can get more fine electronic structure information compared with the conventional spectral experimental methods. Purpose This study aims to develop a data acquisition system of high energy resolution spectrometer based on LabVIEW at BL14W1 X-ray absorption fine structure (XAFS) station in Shanghai synchrotron radiation facility (SSRF). Methods The hardware system includes two parts:VME motion control system for multi-dimension adjusting and silicon drift detector (SDD) fluorescence detector. The software architecture of the spectrometer consists of two parts, the experimental and physics industrial control system (EPICS) for motor control system and LabVIEW for data acquisition system (DAQ). LabVIEW's data logging and supervisory control (DSC) module is used for data exchange between the motion control system and the DAQ. Results The energy resolution of this spectrometer is 0.5 eV, which can distinguish different compounds in the mixture. Conclusion It is proved by experiment that the energy resolution and counting rate of this high energy resolution spectrometer has reached the level of the same kind of devices in the world.  
        关键词：Synchrotron radiation;High energy resolution spectrometer;LabVIEW;Motion control;Data acquisition   
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        发布时间：2021-05-19

        NUCLEAR CHEMISTRY, RADIOCHEMISTRY, RADIOPHARMACEUTICALS AND NUCLEAR MEDICINE

      • Chang CAI,Qi CHEN,Jing MIAO,Yonghui CHEN,Zhibin JIANG,Dan MO,Jie LIU
        Vol. 40, Issue 10, Article number: 100301(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.100301
        摘要：Background Polycarbonate (PC) and polyethylene terephthalate (PET) films were widely used as the materials for nuclear track membranes because both of them could be etched effectively with alkaline solutions. Purpose This paper aims to research the characteristics of polycarbonate and polyester nuclear track membranes. Methods The PC and PET foils were irradiated with Au ions (11.4 MeV·u-1) and Kr ions (20 MeV·u-1) respectively. Then the irradiated foils were etched with the NaOH aqueous solution. The pore sizes of PC and PET nuclear track membranes were in the range of 20 nm to 400 nm and 100 nm to 700 nm, respectively. Results The pore sizes and their distributions of these membranes were characterized with scanning electron microscopy (SEM) and the method of gas-liquid displacement, respectively. It suggested that the irradiation fluence determined the membrane pore density; the longer the etching time, the larger the membrane pore size, and the evener the distribution of membrane pore sizes. The surfaces of the irradiated PET membranes were more hydrophilic than those of the irradiated PC membranes. Conclusion The experimental results suggest that bovine serum albumin (BSA) in aqueous solution could be rejected effectively by PET nuclear track membranes with different membrane pore sizes at 0.15 MPa and ambient temperature. The smaller the membrane pore size, the higher the rejection to BSA, and the higher the operating pressure required, resulting in more serious membrane fouling.  
        关键词：Nuclear track membrane;Pore size;Bovine serum albumin;Rejection performance   
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        发布时间：2021-05-19

        NUCLEAR ENERGY SCIENCE AND ENGINEERING

      • Xianbao YUAN,Liangzhi CAO,Hongchun WU
        Vol. 40, Issue 10, Article number: 100603(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.100603
        摘要：Background The small modular reactor is considered by International Atomic Energy Agency (IAEA) to be one of the most promising nuclear reactors in the future, which could not only improve the safety and economy of nuclear energy, but also prevent the nuclear proliferation. Purpose This paper puts forward a small modular Pb-Bi cooled reactor with nitride nuclear fuel (SMPBN) which is designed to meet the requirements for nuclear energy improvement. Methods The physical characteristics and security features of the SMPBN were analyzed by PIJ and CITATION, including the reactive coefficient and its change with burnup, discharge burnup, power peak factor, fuel conversion ratio and shut-down allowance, etc. Results The SMPBN is expected to possess a good fuel conversion capability during the life-time of 20 a, with a small reactive fluctuation and a negative reactivity coefficient, which means that the SMPBN has inherent safety. Conclusion It is considered to be satisfying the requirements of the G-IV, which provides a valuable reference for development of small modular fast neutron reactor in future.  
        关键词：SMPBN;Lead-bismuth coolant;Nitride fuel;Physical characteristics   
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        发布时间：2021-05-19
      • Ruimin JI,Rui YAN,Xiaoxiao LI,Ye DAI,Guimin LIU,Yang ZOU
        Vol. 40, Issue 10, Article number: 100604(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.100604
        摘要：Background Packing fraction of tristructural-isotropic (TRISO) particles in pebble fuel is lower than 10% in general, which leads to great randomness in distribution, resulting in various challenges in neutronics modeling, such as double heterogeneity effect, preserving exact number of particles, and their random distributions in pebble. Purpose This study aims to verify the calculations, the infinite pebble fuel with refectory boundary conditions based on the thorium-based molten salt reactor with solid fuel (TMSR-SF1) pebble design using Monte-Carlo code MCNP6 ver1.0 and ENDF/B Ⅶ.0. Methods Four types of models of TRISO particles have been performed based on MATLAB, the equivalently filled regular model, the disturbed regular model, the randomly filled regular model, and the fully random model. Results The neutronic effect of various modeling approaches was quantitatively evaluated. Conclusion The results show that the four kinds of modeling methods form different randomness. The clustering of the coated particles enhances the Dancof effect which raises the neutron absorption probability in the fuel. As a result, the infinite multiplication factor is increased while the fuel temperature coefficient is decreased.  
        关键词：Coated particle fuel;Infinite multiplication factor;Temperature coefficient   
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        发布时间：2021-05-19
      • Quan WEI,Wei GUO,Hailing WANG,Jingen CHEN,Xiangzhou CAI
        Vol. 40, Issue 10, Article number: 100605(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.100605
        摘要：Background As one of the six candidates for the Generation IV reactor types, molten salt reactor (MSR) is characterized by its use of the fluid-fuel. Compared with solid-fuel reactors, there are some differences in physics for liquid fuel reactor. The fluid-fuel not only serves as the fuel, but also serves as both the coolant and the moderator, hence a must for the neutron physics coupling with the thermal-hydraulic. Due to fuel flow in MSR, the delayed neutron precursors (DNP) partly flow out and decay outside of the reactor core, resulting in reactivity losses in the core. Purpose This study aims to develop and verify coupling program of neutron physics and thermal-hydraulic for MSR. Methods Distribution of DNP and temperature is different from solid-fuel reactor, it is necessary to study the change of relevant physical parameters in MSR under different operating conditions. Considering the flow of DNP impacting on MSR, a new space-time neutron dynamics program was developed to couple with the thermal-hydraulics program on the basis of two-dimensional RZ cylindrical geometry. The unprotected pump driven transient and inlet fuel temperature overcooling/overheating transient was simulated to analyze the intrinsic safety of MSR. Results The related experimental data in molten salt reactor experiment (MSRE) were verified by coupling calculation of neutron dynamics and thermal hydraulics, and the results showed that simulated data was in good agreement with the experiment results. Conclusion The program is available in simulating related experimental data in MSRE, and MSR has intrinsic safety.  
        关键词：MSR;Delayed neutron precursors;Reactivity;Intrinsic safety   
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        发布时间：2021-05-19
      • Dafu LIN,Fengrui LIU,Xingwei CHEN,Rui YAN,Mudan MEI,Jie ZHANG,Yang ZOU
        Vol. 40, Issue 10, Article number: 100606(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.100606
        摘要：Background Thorium-based molten salt reactor with solid fuel (TMSR-SF) is one type of the fourth nuclear power plant which combines high-temperature graphite-matrix coated-particle pebble fuel for hightemperature gas-cooled reactors and liquid salts developed for the molten salt reactors.The design of TMSR-SF requires detailed understanding of the packing structure of the pebble bed in reactor core.Purpose:This article is aimed to explore the effectiveness of refractive index matched scanning technique (RIMS) in the 3D-reconstruction of reactor core. Methods The cross sections of the pebble bed are imaged by a charge-coupled device (CCD), then the threshold transformation, filter transformation and Hough transformation are used to process the images, and the coordinates of points on the spheres'edge are extracted.Then an algorithm is used to acquire the relative center coordinates of each sphere. Results The result shows that excluding irrelevant distractors can improve the accuracy of the 3D-reconstruction, and creating region of interest (ROI) to make threshold transformation is a good method to enhance circles'edges, and when the circles in the images distort, minimum bounding rectangle (MBR) functions is more effective than Hough circle transformation. Conclusion Our scheme of reconstruction can reconstruct the 3D packing structure of the pebble bed with the mean distance-overlapped which is 1.43 mm, and this precision needs to be improved later.  
        关键词：RIMS;Image processing;Visual liquid-pebble bed;3D-reconstrution;Regularly arranged pebble bed   
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        发布时间：2021-05-19
      • Bo XU,Yang ZOU,Qiang SUN,Xiaohan YU
        Vol. 40, Issue 10, Article number: 100601(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.100601
        摘要：Background Thorium fluoride salt reactor-solid fuel 2 (TMSR-SF2) is a small module reactor (SMR) based on the experimental prototype SF1. Its concept design combines many outstanding characteristics from fluoride high temperature reactor (FHR), and brings in or enhances many more attractive features inspired from the small module idea. Purpose This study aims to evaluate its operation performance and assess the safety limits during postulated transients. Methods A preliminary analysis of station blackout (SBO) in SF2 is presented by using RELAP5/MOD4.0 code, relative hydraulic components have been equivalently modeled. Results Modification result shows that an immediate safety shutdown can be obtained and guaranteed by strong thermal inertia while passive safety system based on natural circulation can maintain long term cooling of the reactor core and guarantee no server consequences and sufficient redundancy. Several postulated initiating events and sensitivity analyses covering several reactivity coefficients are also performed to reveal their influence degree and tendency on final results. Conclusion The conclusion is that the shutdown system is crucially responsible for short-term safety while a long-term reactor cooling has to depend on the direct reactor auxiliary cooling system (DRACS).  
        关键词：TMSR;Small module reactor;Station blackout;Accident analysis;RELAP5   
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        发布时间：2021-05-19
      • Pan ZHANG,Chao XU,Lijing WEN,Wenchao HU,Yusheng LIU,Congxin LI
        Vol. 40, Issue 10, Article number: 100602(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.100602
        摘要：Background The passive residual heat removal system (PRHR) is an important safety facility for passive nuclear power plants. In the station blackout accident, most of the core decay heat is transferred to the in-containment refueling water storage tank through PRHR heat exchanger to ensure the safety of nuclear reactors. The transfer process of PRHR heat exchanger is not steady, and the transfer mechanism is very complex. Purpose This study aims at the flow and heat transfer characteristics of the PRHR system by computational analysis. Methods The computational fluid dynamics (CFD) software was employed to establish the geometric model for PRHR in the passive reactor cooling system test facility, and the physical model (turbulence, thermal phase change) and boundary conditions were defined for numerical calculation. Results The temperature field, velocity field and heat transfer coefficient of the heat transfer tubes in in-containment refueling water storage tank (IRWST) were obtained, and their regularities were analyzed. Conclusions Obvious temperature stratification phenomenon was found along the vertical height, and the temperature distribution in the horizontal direction tends to be uniform. The flow in IRWST is mainly along the vertical section of the C-type heat transfer tubes, and the velocity increases gradually. In the two-phase stage, the flow of the upper tank is obviously enhanced. The heat transfer coefficient of the upper horizontal segment and the upper vertical segment of the C-type heat transfer tube is obviously higher than that of the other area, and the heat transfer coefficient of the joint of upper horizontal segment and the vertical segment is the largest. The heat transfer coefficient of the upper region in tank increases obviously in the two-phase stage.  
        关键词：PRHR;IRWST;Heat exchanger;Numerical simulation   
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        发布时间：2021-05-19

        NUCLEAR ELECTRONICS AND INSTRUMENTATION

      • Zhenchao ZHANG,Guoping ZUO,Junwen TAN,Yang ZHOU,Fan ZHANG
        Vol. 40, Issue 10, Article number: 100402(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.100402
        摘要：Background With the increase application of radioactive sources, the possibility of radiation accidents is raised as well in recent years. Purpose This study aims to fastly locate lost radioactive sources using a directional detector of γ rays. Methods Three different coupled scintillators, i.e., NaI, CsI, Bi4Ge3O12 (BGO), together with center lead cylinder were employed to build the γ ray directional detection system. Localizing spatial radioactive source and the influences of angular resolution caused by lead-crystal ratio, rays energy and source dose rate were simulated by using MCNP (Monte Carlo N particle transport code). Results The angle deviation is less than 0.99°, provided that the air absorbed dose rate of 137Cs source is not lower than 0.331 μGy·h-1. The average angle measurement deviation is 0.46° when the air absorbed dose rate of 60Co source is 0.586 μGy·h-1. The positioning deviation of 3.7×107 Bq 137Cs source at a distance of 7 m and height of 4 m is about 5%. Conclusion The three-coupled-crystals directional detector of γ rays can be used to identify the direction of incident γ rays and locate the spatial position of unknown radioactive source with reasonable radiant intensity.  
        关键词：γ rays;Three-coupled-crystals;MCNP5;Source locating   
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        发布时间：2021-05-19
      • Jun HE,Huizhou MA,Zhizhuo WANG,Qiang YE,Lingda YU,Yanfeng SUI,Junhui YUE,Jianshe CAO
        Vol. 40, Issue 10, Article number: 100401(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.100401
        摘要：Background Beam position monitor (BPM) is one of the most important and most commonly used beam instruments. There are more than 150 kinds of BPM components in Beijing electron positron collider Ⅱ (BEPCⅡ) including the button-and stripline-types. Purpose This study aims to analyze the signal generated by the beam's electromagnetic field and calculate the transfer impedance and sensitivity map. Methods Microwave-and particle-studios of the computer simulation technology (CST) software were used to study the quality of the BPM. The simulation results such as the amplitude of button signal, the sensitivity of horizontal and vertical direction, transfer impedance, coupling coefficient of electrodes etc, were compared with analytical formula. Further computation of signal for stripline BPM in time and frequency domain were also obtained. Results It showed that the calculation results accorded quite well with the experimental results. Conclusion CST is a useful tool to study the character of the BPMs and the simulation results can be used to optimize the geometry of the position monitor.  
        关键词：BPM;Button;Stripline;Transfer impedance;Particle studio   
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        发布时间：2021-05-19

        LOW ENERGY ACCELERATOR, RAY AND APPLICATIONS

      • Meng LI,Hongyu FAN,Hejing CUI,Hongyu FAN,Lishan WEI
        Vol. 40, Issue 10, Article number: 100201(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.100201
        摘要：Background Currently, tungsten has been selected as one of the best plasma-facing materials for international thermonuclear experimental reactor (ITER) due to its low hydrogen solubility, low sputtering yield, high melting point and high thermal conductivity. Purpose In this paper, the responses of polycrystalline tungsten to low-energy helium-ions irradiation were investigated. Methods Helium-ions irradiation was performed at 923 K with a He+ flux of 7×1021 m-2×s-1. A strong correlation between the surface morphology change and the grain orientation was confirmed from scanning electron microscope (SEM), conducive atomic force microscope (CAFM), X-ray diffraction (XRD) and electron backscattered diffraction (EBSD) analysis. Results SEM and CAFM measurement revel that nano-scale helium bubble formed on the surface of tungsten at earlier stage. The size and number of the formed helium bubbles increase with the increase of helium fluence until they break. Mass loss and sputtering yields analysis indicated that the surface spalling caused by the damage of helium bubble is the main format of tungsten damage. XRD and EBSD found that helium atom is shown to be not energetically favorable to dissolve, self-trap and cluster at (101) surface in comparison to (111) and (001) surface. Conclusion The results will provide a useful reference for optimization of the plasma facing materials.  
        关键词：Low energy helium ions;Tungsten;Morphology;He bubble   
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        发布时间：2021-05-19

        NUCLEAR PHYSICS, INTERDISCIPLINARY RESEARCH

      • Shi SU,Qin XIE,Zhenping CHEN,Jinsen XIE,Wenjie ZENG,Zijing LIU,Pengcheng ZHAO,Lihua HE,Tao YU
        Vol. 40, Issue 10, Article number: 100501(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.100501
        摘要：Background The open source Monte Carlo code (OpenMC) released by Massachusetts Institute of Technology (MIT) only provides source code rather than executable code. Purpose This study aims at the compatibility issues for different versions of the auxiliary programs in the compilation of OpenMC. Methods The various versions of OpenMPI, Mpich and HDF5 programs that support OpenMC were compiled and checked, and the complied OpenMC was validated using 96 representative routines recommended in the international criticality safety benchmark evaluation project (ICSBEP). The calculation results were compared with those of the ICSBEP experiments using general MC code. Results The calculated values by complied OpenMC are in line with the experimental values of the ICSBEP benchmarks, as well as calculations by other programs. Conclusion This study provides a reference for the correct compilation of the OpenMC with feasibility. It is useful in future applications and improvements of these programs.  
        关键词：OpenMC;OpenMPI;Mpich;HDF5;ICSBEP   
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