最新刊期
      卷 41 ， 期 1 ， 2018

        SYNCHROTRON RADIATION TECHNOLOGY AND APPLICATIONS

      • Liang WU,Guoliang XU,Yifu ZHOU,Chuanjia ZHANG,Shifeng MAO,Zhengping LUO,Yong GUO,Xuebing PENG,Minyou YE
        Vol. 41, Issue 1, Article number: 010602(2018) DOI: 10.11889/j.0253-3219.2018.hjs.41.010602
        摘要：BackgroundDue to unacceptable high erosion rate of low-Z material and the problem of tritium co-deposition, full-tungsten wall is excepted for future fusion reactor. However, the core tungsten concentration has to be limited to very low level of 10-5 due to its the high radiative cooling rate. China fusion engineering test reactor (CFETR) requires high-power steady-state operation, full tungsten wall is preferred. PurposeThis study aims to evaluate the core tungsten concentration for CFETR with full tungsten wall. MethodsEdge plasma simulation software scrape-off layer plasma simulation (SOLPS) is employed to simulate the edge plasma with different Ne seeding rates for the lower-single null configuration. With the simulated edge plasma as the background, Monte Carlo impurity transport code DIVertor and IMPurity (DIVIMP) is used to simulate the transportations of the impurity of tungsten. ResultsWhen the Ne seeding rate is low and the target temperature keeps high, the simulated core tungsten concentration is too high to be considered. The contribution of tungsten target becomes acceptable when the target temperature is lower to about 10 eV; however, when the main chamber tungsten wall is included, the core tungsten concentration is still at the level of 10-4. ConclusionThe tungsten source from main chamber wall is the main cause of high core tungsten concentration when seeding impurity rate is high. The influence of tungsten wall on the core tungsten impurity should be further focused in future work.  
        关键词：CFETR;DIVIMP;Plasma-wall interaction;Numerical simulation;Tungsten impurity transport   
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        发布时间：2021-05-19
      • Chao QIN,Song XUE,Nan WANG,Xiaopei SUN,Wanqian ZHU
        Vol. 41, Issue 1, Article number: 010101(2018) DOI: 10.11889/j.0253-3219.2018.hjs.41.010101
        摘要：BackgroundBent elliptically cylindrical mirror is required for some beam lines of the 2nd phase of Shanghai synchrotron radiation facility (SSRF). A double rod bending mechanism has been developed accordingly. PurposeThis paper aims to bend an elliptical cylindrical mirror we need by using this mechanism. MethodsTheoretical calculation and analysis combined with finite element analysis were carried out on this mechanism. ResultsIn horizontal focusing, when the displacements of the rod were 9.2 mm and 10.1 mm, the slope error was 0.35 μrad. In vertical focusing, if not using the gravity compensation mechanism, the slope error was 0.88 μrad when the displacements of the rod were 7.4 mm and 8.4 mm, so the gravity compensation mechanism is necessary, and now when the displacements of the rod were 9.1 mm and 10.1 mm, the slope error was 0.45 μrad. ConclusionThe results can meet our requirements, and this analysis result is useful for the engineering application.  
        关键词：Bending;Elliptically cylindrical;Finite element analysis;Surface-shape error   
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        发布时间：2021-05-19
      • Youshi ZENG,Shengwei WU,Yuan QIAN,Lin DU,Guanghua WANG,Yu HUANG,Wenguan LIU,Wei LIU
        Vol. 41, Issue 1, Article number: 010604(2018) DOI: 10.11889/j.0253-3219.2018.hjs.41.010604
        摘要：BackgroundMolten FLiNaK is a secondary heat-transfer fluid of a molten salt reactor or a FLiBe self-cooled nuclear fusion reactor, in which tritium would be produced at high rates and permeate the molten FLiNaK. PurposeThe aim is to provide more reliable reference for tritium behaviors in molten FLiNaK by further study of the permeation and diffusion behaviors of hydrogen as well as the isotope effect on hydrogen behaviors. MethodsExperiments on hydrogen charged at salt surface and metal surface in molten FLiNaK were conducted to study permeation and diffusion characteristics of hydrogen isotope in molten salt. And contrast experiments between hydrogen and deuterium charged at metal surface were carried out to study the isotope effect on hydrogen behaviors. ResultsThe results showed that hydrogen charged at salt surface had more advantages for reporting the permeation and diffusion characteristics of hydrogen. And the diffusion coefficients and solubility constants of hydrogen in molten salt FLiNaK could be correlated to DH2=1.62×10-5exp(-48.20×103/RgT) m2·s-1 and KH2=6.18×10-5 exp(-11.14×103/RgT) mol·m-3·Pa-1. The deuterium showed little isotope effect on the permeation and diffusion behaviors of hydrogen in molten FLiNaK. ConclusionThe permeation and diffusion characteristics of tritium are analogous to the hydrogen behaviors, indicating that hydrogen can be used forsubstituting tritium in the experimental researches in molten FLiNaK.  
        关键词：Molten FLiNaK;Hydrogen;Deuterium;Permeation;Diffusion   
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        发布时间：2021-05-19
      • Haiyan DU,Wanchang LAI,Xiyu SHI,Cheng CHEN,Yan HU,Rui ZHAO
        Vol. 41, Issue 1, Article number: 010202(2018) DOI: 10.11889/j.0253-3219.2018.hjs.41.010202
        摘要：BackgroundThe study of the detection limit of X-ray fluorescence instrument is of great significance, as it is widely used in the analysis of low content elements because of its excellent performance. PurposeTo reduce the detection limit and measuring low content of metal elements more accurately, we provided reference for the choice of background subtraction methods and measurement conditions, etc. MethodsThis paper studied the influence factors for the detection limit of the portable X-ray fluorescence instrument, such as background subtraction method, tube voltage and tube current. Blank sample-, linear-and Sterlinski-background subtraction methods were used to subtract the backgrounds and the suitable tube voltage and tube current range were tested. Certain corresponding relationship exists between detection limit and determination limit, so the determination limit was obtained using the detection limit, and the low content samples were analyzed. ResultsDetection limit varies with tube voltage and tube current due to different background subtraction methods. The suitable tube voltage range of blank sample background subtraction is 28-40 kV and tube current range is 18-24mA, while that of linear background subtraction and Sterlinski background subtraction is 24-26 kV, 28-40 kV and 12-14 mA, 18-40 mA correspondingly. ConclusionBlank sample background subtraction is the best, followed by Sterlinski background subtraction, while linear background subtraction is not suitable for the low content element analysis. Each background subtraction method has its suitable tube voltage and tube current range. When the content of elements is equal to the detection limit, the signal of the element detected is reliable, but it can not be used in quantitative analysis.  
        关键词：X-ray fluorescence instrument;Detection limit;Background subtraction;Tube voltage;Tube current   
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        发布时间：2021-05-19
      • Liuwei KUANG,Huarong LIU,Zhe CHEN
        Vol. 41, Issue 1, Article number: 010603(2018) DOI: 10.11889/j.0253-3219.2018.hjs.41.010603
        摘要：BackgroundFuel availability and economical efficiency are very important for nuclear reactor, measuring the relative burn-up of large-diameter fuel tubes is a challenge issue in nuclear engineering. PurposeThis study aims to design a γ scanning system of fuel tubes based on the fuel tubes' structure to exactly measure the relative burn-up and verify the operating correctness of fuel tubes. MethodsFirst of all, the reliability of the device and feasibility of the method was verified through a 10-mm standard 137Cs point source. Then the γ scanning was carried out for three different diameter fuel tubes of the same fuel assembly to measure the relative burn-up distribution of fuel tubes separately in the radial and axial directions. The positive and cathode faces of fuel tubes were confirmed according to the relative burn-up distribution in the radial direction. Finally, the relative burn-up of fuel tubes in different layers was determined by γ scanning the fuel tube in the axial direction at the positive face with maximum burn-up. ResultsThe measuring technique of relative burn-up of fuel tubes was realized with less than 4% relative error. ConclusionMeasuring technique of relative burn-up of fuel tubes was established by proposed approach, it provides a new way for the relative burn-up measurement of other fuel assembly.  
        关键词：Fuel tube;Nuclide choose;Relative burn-up   
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        发布时间：2021-05-19
      • Bingbing XU,Kun XU,Minyou YE,Shifeng MAO,Mingzhun LEI,Xuebing PENG
        Vol. 41, Issue 1, Article number: 010601(2018) DOI: 10.11889/j.0253-3219.2018.hjs.41.010601
        摘要：BackgroundThe China fusion engineering test reactor (CFETR) under development, mainly consists of a physical design platform and an engineering design platform, and the latter includes various modules. In the design of the modules, computational fluid dynamics (CFD) software is used for thermal-hydraulic analysis of the fusion in-vessel components of which the nuclear heating is a necessary source term generated from neutronics calculations of Monte Carlo N particle transport code (MCNP). PurposeThis study aims to transfer the 3D nuclear heating profiles from MCNP to CFD software and develop neutronics-thermal hydraulics coupling module for CFETR integration design platform. MethodsThe 3D nuclear heating profiles were processed by two different interpolation methods: element-to-element mapping method and point-to-point mapping method, and the 1D nuclear heating profiles were also processed for comparison. Thermal-hydraulic analysis based on breeder unit of the helium cooled ceramic breeder blanket (HCCB) for CFETR was performed on ANSYS CFX for verification. The total interpolated nuclear heating, heating distributions and temperature distributions were compared in detail according to the CFX simulation results. ResultsComparison results showed that all schemes satisfied the conservation of nuclear heating with appropriate mesh. Element-to-element mapping method and point-to-point mapping method differs in the heating peak value due to the different interpolation method. ConclusionThe neutronics-thermal hydraulics coupling module proposed in this paper possesses high reliability for CFETR integration design platform.  
        关键词：CFETR integration design platform;Neutronics-thermal hydraulics coupling module;MCNP;CFX;HCCB   
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        发布时间：2021-05-19
      • Nan LI,Ning QI,Zhiquan CHEN,Bo WANG
        Vol. 41, Issue 1, Article number: 010201(2018) DOI: 10.11889/j.0253-3219.2018.hjs.41.010201
        摘要：BackgroundThe precision of positron lifetime measured in the experiment is of great concern. PurposeSome typical materials were chosen to repeat the positron lifetime measurements over a long time to assure the precision. MethodsBy adjusting the working conditions of the spectrometer, we studied the factors affecting the precision of the measured positron lifetime, such as the time resolution, total count of the lifetime spectrum, number of lifetime components in the sample and also the interval between each lifetime components. ResultsIt was found that with stable working condition of the spectrometer and a total count of 1 million for each spectrum, the positron bulk lifetime in Si single crystal is about 218 ps, and the standard deviation is only 0.5 ps after several repeated measurements. In poly(methyl methacrylate) (PMMA), where positrons have three lifetime components, the standard deviation of the average lifetime is also only 1 ps, and the standard deviation of the longest lifetime τ3 (1.83 ns) is 0.016 ns. Our experiment also shows that the time resolution of the spectrometer has little effect on the measure of positron lifetime. ConclusionThe results indicate the positron lifetime measurement has high precision, and is a reliable tool to detect the change of the microstructure of materials.  
        关键词：Positron lifetime;Time resolution;Standard deviation;Precision   
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        发布时间：2021-05-19

        NUCLEAR PHYSICS, INTERDISCIPLINARY RESEARCH

      • Wenbiao LIU,Wei CHEN,Zining TIAN,Xuemei WANG,Chuanying SU,Tiancheng FENG
        Vol. 41, Issue 1, Article number: 010501(2018) DOI: 10.11889/j.0253-3219.2018.hjs.41.010501
        摘要：BackgroundThe phenomenon that right is higher than left in full-energy peak of the γ spectrum in the high active sample using HPGe gamma-ray spectrometry in laboratory, brings error into the gamma-radioactive nuclide analysis. PurposeThis paper aims to explain the phenomenon to realize accurate quantitative analysis. MethodsThe theoretical formula of the right-to-left ratios was developed, and experiment was designed to prove it. ResultsThe experiment indicates that the theoretical calculation is right. The research achievement shows that the phenomenon is caused by accidental coincidence. ConclusionThe right-to-left ratios increase first, then decrease with the higher dead time. When the dead time is lower than 1.0%, the right is approximate equal to the left in full energy peak. With the dead time is higher than 1.0% and lower than 4.0%, the ratios increases with the dead time. As the dead time is higher than 4.0% and lower than 56%, the ratios decreases with the dead time. Comparing the experiment with LabSOCS, it indicated that the phenomenon has no influence on analysis of the point source.  
        关键词：γ spectrometry;Full-energy peak;Accidental coincidence   
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        发布时间：2021-05-19
      • Lin ZHANG,Dan MO,Tiandong DING
        Vol. 41, Issue 1, Article number: 010502(2018) DOI: 10.11889/j.0253-3219.2018.hjs.41.010502
        摘要：BackgroundPeople keen on tasting tea are plagued by the presence of crushed impurities in the tea soup, such as particles of tea leaf and hairs of tea leaf. PurposeThe aim is to expand the use of nuclear track membranes (NTMs) for filtration of tea soup. MethodsFlat membrane filtration equipment with the NTM placed in is used to separate the tea soup. ResultsThe colority and turbidity of tea soup after the separation decrease with the intercept aperture. The total volume of residual particles in tea soup decreases with pore size; the peaks of size distribution of particles decrease with the pore size. The flux of NTM is good and decreases with the pore size. After cleaning, membrane flux of 15-μm NTM can be restored to more than 80% of the original. It is found that the membrane can extend the life time and improve economic efficiency by controlling the initial flow rate. ConclusionNTM can effectively intercept the particles larger than its pore size in the tea soup. The 15-μm NTM is the best to separate the tea soup with the excellent flux and retention effect during gravity, and 1-μm NTM is the best choice under pressure filtration.  
        关键词：Nuclear track membrane;Microfiltration membrane;Filtration of tea soup;Particle size;Life time;Initial flow rate   
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        发布时间：2021-05-19

        NUCLEAR ELECTRONICS AND INSTRUMENTATION

      • Qi LI,Shilian WANG,Yuanqing FAN,Yungang ZHAO,Xinjun ZHANG,Huaimao JIA,Shujiang LIU,Yinzhong CHANG
        Vol. 41, Issue 1, Article number: 010403(2018) DOI: 10.11889/j.0253-3219.2018.hjs.41.010403
        摘要：BackgroundDue to the chemical inertness, the noble gases escape more easily from underground nuclear explosions into atmosphere than the fission products in solid form. Among the noble gases, four of radioxenon isotopes, i.e. 131Xem, 133Xem, 133Xe and 135Xe, have high fission yields with half-lives of several hours to several days, which can be detected after long distances diffusion from where they were released. So these four radioxenon isotopes play a key role for underground nuclear test monitoring compliance with comprehensive nuclear-test-ban treaty (CTBT). Accurate measurement of radioxenon isotopes activities is a key technique to identify characteristic of nuclear test from the monitoring data. PurposeRadioxenon isotopes activities are usually determined using relative measurement methods-HPGe γ spectrometers or β-γ coincidence systems. The detection efficiency calibration of the relative measurement system by standard samples is the critical factor of these relative measurement methods. MethodsThis article describes the process and method of accurate measurement of activity concentration of 131Xem by internal gas proportional counting system which adopted length-compensated method. ResultsThe activity concentration of 131Xem is determined to be (1.75±0.01) Bq·mL–1 using internal gas proportional counters with corrections for dead time, background, discrimination, end effects and wall effects. ConclusionThe activity concentration of 131Xem sample was measured accurately, which can be used to calibrate detection efficiency of relative measurement system as a standard sample.  
        关键词：Radioxenon isotopes;Activity concentration;Internal gas proportional counter   
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        发布时间：2021-05-19
      • Minghui LI,Pingjuan NIU,Mingyi DONG,Hang ZHAO,Peng HU,Liyuan YU,Tao HU,Zhigang WANG
        Vol. 41, Issue 1, Article number: 010402(2018) DOI: 10.11889/j.0253-3219.2018.hjs.41.010402
        摘要：BackgroundIn the proposal of the circular electron positron collider (CEPC) scheme, readout unit consisting of a silicon photomultiplier (SiPM) and a plastic scintillator has become a research hotspot as one of the main options of electromagnetic calorimeter (ECAL). PurposeThis study aims to optimize the detector prototype by setup an automated testing system to test, analyze and improve the performance of each readout unit of CEPC ECAL. MethodsBased on the DT5751 waveform sampling plug-in module, SiPM drive circuit, stepper motor, low-voltage power supply (LVPS), relay, etc., the hardware of CEPC ECAL readout unit was built up whilst the software was developed with the LabVIEW. Repeated measurements were carried out to find the optimized parameters, and the SiPM calibration was performed. ResultsExperimental results show that proposed automated testing system satisfied basic requirements of CEPC ECAL readout unit. Setup of the testing platform of scintillator readout unit based on waveform sampling is option for CEPC ECAL and be used for SiPM calibration, scintillator uniformity of light output and reflective material study. ConclusionThe experiment rwsult shows that the plastic scintillator strip with the ESR has the highest light yeild and the light yeild of 25 μm coupled with SiPM 3 times than 10 μm.  
        关键词：SiPM;Plastic scintillator;Electromagnetic calorimeter;CEPC   
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        发布时间：2021-05-19
      • Shiyu YIN,Lishuang MA,Sen QIAN,Feng GAO,Yao ZHU,Zhigang WANG,Zhe NING,Zhile WANG,Pengyu CHEN,Binhuan YUAN
        Vol. 41, Issue 1, Article number: 010401(2018) DOI: 10.11889/j.0253-3219.2018.hjs.41.010401
        摘要：BackgroundThe spectral response range of the bi-alkali photocathode photomultiplier tube (PMT) is 300 nm to 700 nm. So infrared light is often used as a background light of PMTs during producing or testing. However, the PMT had a red storm, when use the infrared light emitting diode (LED) for its calibration. PurposeThis paper aims to prove that the PMT itself is really responsive to infrared light, rather than the presence of stray light in the LED. MethodsThe infrared light was used to interfere the single-photon state of bi-alkali photocathode PMTs. ResultsWhen the power of the infrared laser tube is up to mW, the single photon state of PMTs changed. ConclusionIt is proved that the bi-alkali photocathode PMTs does respond to the infrared light.  
        关键词：Bi-alkali photocathode;PMT;Single photon test;Infrared response   
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        发布时间：2021-05-19

        NUCLEAR ENERGY SCIENCE AND ENGINEERING

      • Shihe YU,Rui YAN,Ruimin JI,Bo ZHOU,Yafen LIU,Yang ZOU
        Vol. 41, Issue 1, Article number: 010605(2018) DOI: 10.11889/j.0253-3219.2018.hjs.41.010605
        摘要：BackgroundReactivity control design is a key part of reactor neutronics design. The control-rods made of B4C-absorber for reactivity control in pebble bed-fluoride-salt-cooled high-temperature reactor (PB-FHR) are located in the hole of side graphite. The space layout, geometric structure, absorber properties are the key influencing factors to the reactivity control. PurposeThis study aims at the influence of different factors of the control rod in graphite reflection layer on control rod worth, including radial position, effective stroke, absorber length, absorber density, etc. MethodsThe 10-MW thorium molten salt reactor-solid fuel (TMSR-SF1) model was taken as the reference reactor, and the calculation was completed based on SCALE6. All above mentioned factors such as radial position, effective stroke, absorber length and absorber density, were taken into account for parameters design. ResultsComputational results reveal that radial position of the control rod has obvious impact on control rod worth. The absorber length, the upper limit, lower limit and overflow lower limit of the control rod that lead to the change in worth, should be considered comprehensively. The influence of10B atomic density on control rod worth was negligible. ConclusionThis study provides basic theoretical reference for the design of PB-FHR reactivity control.  
        关键词：PB-FHR;Reactivity control;Control rod layout;Control rod worth   
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        发布时间：2021-05-19

        NUCLEAR CHEMISTRY, RADIOCHEMISTRY, RADIOPHARMACEUTICALS AND NUCLEAR MEDICINE

      • Qi LIU,Wenjun LI,Lina LU,Yuanyuan XIE,Mingchao WANG,Song QIN,Zhenning DU
        Vol. 41, Issue 1, Article number: 010302(2018) DOI: 10.11889/j.0253-3219.2018.hjs.41.010302
        摘要：BackgroundPhycocyanin (PC) is a pigment protein present in cyanobacteria, cryptophyta, etc. PurposeThis study aims at the protective effect of phycocyanin on oxidative damage induced by irradiation by establishing injury mouse model by X-ray irradiation. Methods72 C57 BL/6 male mice were randomly divided into normal control group, irradiation model group, PC pretreatment group and positive control group. The mice were continuously fed for 7 d. On the 8th day of intragastric administration, except for the normal control group, the rest of the mice were subjected to total body irradiation to a dose of 6 Gy for the preparation of radiation damage model. The plasma and tissues were collected at 1 d, 3 d and 7 d after irradiation, and the activities of antioxidant enzymes in plasma and liver were measured. The content of reactive oxygen species (ROS) in liver tissue was detected by dihydroethidium (DHE) staining. ResultsPhycocyanin increased the activities of superoxide dismutase (SOD) and glutathione peroxidase (GSH-PX) in the plasma of mice after irradiation, and increased the activity of SOD (p < 0.05), decreased malondialdehyde (MDA) content ( p < 0.05), and reduced liver tissue ROS content ( p < 0.05). ConclusionThe results show that phycocyanin can improve the antioxidant capacity of mice, reduce oxidative damage to the body caused by irradiation, and provide a better protective effect on irradiation injury of mice.  
        关键词：Phycocyanin;X-ray irradiation;Antioxidant system   
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        发布时间：2021-05-19
      • Shun HUANG,Yanjiang HAN,Kongzhen HU,Meng WANG,Penghui SUN,Hubing WU,Quanshi WANG,Suqing ZHAO,Xi ZHENG
        Vol. 41, Issue 1, Article number: 010301(2018) DOI: 10.11889/j.0253-3219.2018.hjs.41.010301
        摘要：BackgroundPET imaging of 11C-Erlotinib was used to distinguish responders from nonresponders in the targeted therapy for non-small cell lung cancer (NSCLC). However, the short half-life (20 min) of carbon-11 limits its widespread use as a tool for community-based diagnostic screening and therapeutic evaluation. We proposed that this shortcoming could be overcome by the development of a fluorine-18 (half-life is 109 min) labeled Erlotinib. PurposeWe automatically labelled Erlotinib with flurorine-18 through the "click chemistry" and explored its preliminary evaluation. Methods18F-FEA-Erlotinib was synthesized from 2-18F-fluorine azide ethane (18F-FEA), a radiochemical intermediate, through the "click chemistry" in the PET-MF-2V-IT-I synthesis module and purified by semi-preparative high performance liquid chromatography (HPLC). The stability of 18F-FEA-Erlotinib was performed in phosphate buffer saline (PBS) and fetal bovine serum (FBS). The octanol/water partition coefficient and routine quality control were tested. Results18F-FEA-Erlotinib was achieved within 70 min with (54±2)% radiochemical yield (decay corrected), an average specific activity over 200MBq·μmol-1, and over 99% radiochemical purity. The log P of 18F-FEA-Erlotinib was 2.36±0.01. The final injection was free of bacteria and pyrogen, and the K2.2.2 concentration was lower than 10 mg·L-1. Conclusion18F-FEA-Erlotinib was easy to be prepared by the "click chemistry" in an automatic synthesis system. 18F-FEA-Erlotinib has a similar lipophilicity to Erlotinib and a high metabolic stability in vitro.  
        关键词：18F-FEA-Erlotinib;Epidermal growth factor receptor;Fully automated synthesis;Click chemistry   
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