最新刊期
      卷 42 ， 期 9 ， 2019

        SYNCHROTRON RADIATION TECHNOLOGY AND APPLICATIONS

      • JIA Dandan,ZHANG Min,LI Yongjun,WU Shuai,JIN Limin,XUE Song
        Vol. 42, Issue 9, Article number: 090101(2019) DOI: 10.11889/j.0253-3219.2019.hjs.42.090101
        摘要：BackgroundThe current beam lines structure design cannot satisfy the requirement of the first combined beamline station with soft and hard X-rays in Shanghai synchrotron radiation facility (SSRF).PurposeThis study aims to design the super-small angle Canted front-end at SSRF to support a wide-energy-range experimental platform with multiple methods for energy material research.MethodsTwo undulators, elliptical polarization undulator (EPU) and in vacuum undulator (IVU), were employed in the wide-range energy material beamline (E-Line) that contains soft and hard X-rays located in the straight line with a Canted angle of 2 mrad. The separated plane mirror, SM1, was designed to be located at the front-end. After SM1, the soft line was deflected 2.4°, allowing two dedicated beam lines to be set.ResultsThe two beam lines share the front-end components, and can independently operate the components of the front-end. The front-end of E-Line adopt a new structure and layout different from the standard ones that can handle the heat load up to 7.81 kW. Compared with the key equipment of other common insert device front-end with only one through-light aperture, the one of this front-end was designed with two through-light apertures.ConclusionThe installation of E-Line front-end has been accomplished, and the structure and layout fully satisfy the technical requirements of the beamline.  
        关键词：SSRF;Canted front-end;Layout;Structure design   
        315
        |
        21
        |
        0
        <HTML>
        <L-PDF><Meta-XML>
        <引用本文> <批量引用> 1531661 false
        发布时间：2024-10-25

        ACCELERATOR, RAY TECHNOLOGY AND APPLICATIONS

      • ZHANG Yu,SONG Yingming,YU Xiaohang,SHI Jian,XU Zhonghang,WANG Yan,FU Mengting
        Vol. 42, Issue 9, Article number: 090201(2019) DOI: 10.11889/j.0253-3219.2019.hjs.42.090201
        摘要：BackgroundThe simulation calculation of shielding performance of radiation protection materials at home and abroad is usually limited to one simulation of the Monte Carlo method, while the fine-grained calculation of gamma ray shielding of secondary products is less.PurposeThis study aims to analyze shielding performance and activation products of boron-containing stainless steel materials.MethodsMonte Carlo particle transport program combined with fuel consumption calculation and analysis program (MCNP5/ORIGEN2.1) was employed to calculate and analyze the shielding properties and activation products of stainless steel materials for radiation protection. Combined with the specific requirements of radiation shielding design, evaluation method of neutron/gamma integrated shielding performance was proposed. Based on the simplified model of three-layer shielding structure of single-layer external irradiation of nuclear reactor, the shielding effect of neutron in the neutron/γ mixed radiation field, photon, (n, γ) reaction photons and secondary activation product photons inside the material were simulated by boron stainless steel and ordinary stainless steel, and the overall shielding performance of the protective material was evaluated.Results & ConclusionsThe actual average photon transmittance of boron stainless steel is slightly lower than that of ordinary stainless steel, both of them have the same gamma-ray shielding performance, but boron stainless steel has advantages over ordinary stainless steel in weight reduction.  
        关键词：Boron-containing stainless steel material;Shielding performance calculation;Activation product calculation   
        335
        |
        32
        |
        0
        <HTML>
        <L-PDF><Meta-XML>
        <引用本文> <批量引用> 1531962 false
        发布时间：2024-10-25
      • LIU Longpeng,LIU Fuyan,PEI Shilun,KUANG Peng,WANG Baoyi,ZHANG Peng,ZHANG Huaiqiang,CAO Xingzhong
        Vol. 42, Issue 9, Article number: 090202(2019) DOI: 10.11889/j.0253-3219.2019.hjs.42.090202
        摘要：BackgroundSlow positron annihilation lifetime spectrum measurement is an important analytical method for high sensitivity and non-destructive detection of material micro-defects. Pulsed positron system is the core component of this technology.PurposeThis study aims to obtain periodic positron pulses with high time resolution for lifetime measurement and to provide a signal marking the time of positron generation.MethodsIn this paper, the Parmela program was applied to simulate and calculate the effect of different beam parameters on positrons bunching based on the “Prebuncher-Chopper” pulsed system. Effect of different beam parameters on 150 ps (half-width) bunching was simulated and compared with calculation results of “Prebuncher-Chopper” bunching system.ResultsThe results show that increasing beam energy, reducing beam energy spread and reducing beam spot size are beneficial to improve pulse efficiency. Moreover, when the positron beam energy is greater than 500 eV, the energy spread is less than 5 eV and the beam spot is less than 12 mm, the positron utilization ratio is more than 20% and the bunching efficiency is more than 85% using “Prebuncher-Chopper” pulsed system.ConclusionIn contrast to the “Chopper-Prebuncher” system, “Prebuncher-Chopper” pulsed system can provide a higher positron utilization rate under the same beam parameters. Meanwhile, the time resolution (≤150 ps) and the bunching efficiency (≤85%) meet the measurement requirement.  
        关键词：Slow positron beam;Pulsed system;Positron utilization ratio;Bunching efficiency;Parmela   
        321
        |
        24
        |
        0
        <HTML>
        <L-PDF><Meta-XML>
        <引用本文> <批量引用> 1531827 false
        发布时间：2024-10-25

        NUCLEAR CHEMISTRY, RADIOCHEMISTRY, RADIOPHARMACEUTICALS AND NUCLEAR MEDICINE

      • CHEN Chao,ZHU Jun,ZHANG Aiming
        Vol. 42, Issue 9, Article number: 090301(2019) DOI: 10.11889/j.0253-3219.2019.hjs.42.090301
        摘要：BackgroundThe migration of radionuclides carried by water flow in aquifer porous media is a complex physical and chemical process.PurposeThis study aims to accurately and truly reflect the nuclide transportation in the groundwater by physical experiments and numerical simulation techniques.MethodsFirst of all, the sand medium in arid area was taken as the research object, and a soil column device for saturated sandy soil dispersion and permeability test was developed for experimental test. Then, the U and 238Pu were arranged in the form of liquid point source in the form of liquid point source in the intake section of the soil column, respectively, and the concentration distribution of nuclides in the space of the soil column was measured after the test cycle. Finally, Hydrus-3D was used to establish a three-dimensional numerical model of nuclide migration and to fit the relevant experimental parameters.ResultsThe experimental results showed that U migrated downward 24.3 cm along the water flow direction in soil column after 14 days, the distribution coefficient was 35 mL‧g-1, the longitudinal dispersion was 22 cm, and the transverse dispersion was 25 cm. 238Pu migrated downward 2.1 cm along the water flow direction in soil column after 140 days, the peak concentration was 0.47 ng‧cm-3, the distribution coefficient was 6 500 mL‧g-1, the longitudinal dispersion was 2 cm, and the transverse dispersion was 25 cm. The different migration curves of U and 238Pu in heterogeneous test soil columns are mainly related to the adsorption and retention of sand media and solutes.ConclusionsThe proposed experimental method for nuclide migration in aquifer porous media can provide support for the study of the migration and transformation in soil media.  
        关键词：Radionuclide;Migration;Numerical simulation;U;238Pu   
        364
        |
        22
        |
        0
        <HTML>
        <L-PDF><Meta-XML>
        <引用本文> <批量引用> 1531723 false
        发布时间：2024-10-25

        NUCLEAR ELECTRONICS AND INSTRUMENTATION

      • PAN Junjun,LIU Zhimin,JIANG Caichao,LIU Sheng
        Vol. 42, Issue 9, Article number: 090401(2019) DOI: 10.11889/j.0253-3219.2019.hjs.42.090401
        摘要：BackgroundThe suppressor power supply is one of the power supplies of the experimental advanced superconducting Tokomak (EAST) neutral beam injection (NBI) acceleration system. The switch of the power uses a gate bipolar transistor (IGBT) with multiple tubes in series. The performance of IGBT is not only related to the reliability of the power supply, but also to the optical characteristics of the ion beam when beam extractions.PurposeThis paper aims to match the rising and falling edges of high voltage power supply and suppressor power supply, a scheme of controlling the switching speed of IGBT by capacitive feedback circuit is proposed.MethodsThe scheme of controlling the switching speed of IGBT with capacitive feedback circuit was adopted. The capacitive feedback of IGBT was modeled by Pspice software, and simulation was carried out under different parameters. Finally, an experimental platform was built to test the scheme.ResultsThe simulation results show that the feedback resistance and the feedback capacitance have opposite effects on the feedback circuit. When the gate resistance and the feedback resistance are large and the feedback capacitance is small, the turn-on speed of IGBT can be adjusted in a larger range and the turn-off speed can be reduced by charging the feedback resistance.ConclusionsThe optimization scheme can achieve the expected performance of suppressing the power supply IGBT switch with high reliability.  
        关键词：Suppressor power supply;IGBT;Pspice;Capacitor feedback;Switch speed   
        305
        |
        19
        |
        0
        <HTML>
        <L-PDF><Meta-XML>
        <引用本文> <批量引用> 1531930 false
        发布时间：2024-10-25
      • RONG Yi,ZENG Guoqiang,GE Liangquan,HU Chuanhao,HE Li,HOU Yang,LI Xinchi
        Vol. 42, Issue 9, Article number: 090402(2019) DOI: 10.11889/j.0253-3219.2019.hjs.42.090402
        摘要：BackgroundTraditional charge-sensitive preamplifiers use high-resistance resistors as low-frequency feedback circuit. The thermal noise introduced by high-resistance resistors is the main source of preamplifier noise.PurposeThis study aims to design and develop a novel charge-sensitive preamplifier by using N-channel junction field effect transistor and RC (Resistor-Capacitance) low-pass network instead of traditional high resistance feedback resistor.MethodsA junction field-effect transistor and an integrated operational amplifier were used to form an amplifying circuit with advantages of high input impedance and large open-loop gain. A high-pass loop was formed by a small capacitance capacitor to provide a high-frequency feedback loop for the circuit and integrates nuclear pulse current at the same time. The RC low-pass network constituted a DC (direct current) feedback loop to provide a stable DC operating point for the circuit, and a voltage divider for the N-channel junction field effect transistor operating in a forward bias state to realize a feedback capacitor for continuous discharge of its charge.ResultsThe charge-sensitive preamplifier was connected with BPX66 Si-PIN detector and the 241Am source was measured at room temperature. The energy resolution of 3.03%@59.5 keV was achieved.ConclusionsCompared with the traditional resistive capacitance feedback charge-sensitive amplifier, this circuit can effectively over-come the noise introduced by the large-resistance feedback resistor, especially for semiconductor detectors such as Si-PIN.  
        关键词：Charge-sensitive preamplifier;Semiconductor detector;Junction field effect transistor;Forward bias;RC low-pass network   
        335
        |
        19
        |
        0
        <HTML>
        <L-PDF><Meta-XML>
        <引用本文> <批量引用> 1531692 false
        发布时间：2024-10-25
      • YIN Shiyu,CHEN Pengyu,MA Lishuang,QIAN Sen,ZHU Yao,GAO Feng,WANG Yang,WANG Zhigang,NING Zhe
        Vol. 42, Issue 9, Article number: 090403(2019) DOI: 10.11889/j.0253-3219.2019.hjs.42.090403
        摘要：BackgroundSilicon photomultiplier (SiPM) also named multi-pixel photon counter (MPPC) has excellent performance, but it is difficult to carry out large scale testing due to the limitations of the power supply board.PurposeThis study aims to test the performance of the self-developed voltage-adjustable, batch-programmable SiPM low-voltage power supply module.MethodsThe performance of the new type of SiPM power driver board developed by our laboratory was tested and analyzed by the method of comparative test with commercial power supply.Results & ConclusionThe performances of proposed power module are comparable to that of the commercial module, and satisfy the reqiurments of SiPM batch test.  
        关键词：SiPM;Temperature effect;Multiphoton spectrum measurement   
        427
        |
        32
        |
        0
        <HTML>
        <L-PDF><Meta-XML>
        <引用本文> <批量引用> 1531867 false
        发布时间：2024-10-25

        NUCLEAR PHYSICS, INTERDISCIPLINARY RESEARCH

      • YAN Peng,HUO Gengyang,CHU Xinxing,ZHANG Gongjun,LI Bin,ZHOU Xingfei
        Vol. 42, Issue 9, Article number: 090501(2019) DOI: 10.11889/j.0253-3219.2019.hjs.42.090501
        摘要：BackgroundThe formation of amyloid fibers is closely related to the neurodegenerative diseases. Inhibiting the formation of mature amyloid fibers has become an important approach to prevent related diseases.PurposeThis work aims to prepare an efficient and rapid material to remove and degrade mature insulin fibers for the treatment of type II diabetes mellitus.MethodsIn this study, the effect of graphene oxide nanosheets (GOs) with an average thickness of 1 nm on mature insulin fibers was prepared by Hummer method. Both the ThT fluorescence and Micro Fourier Transform Infrared Spectroscopy (Micro-FTIR) were employed to measure the outputs.ResultsGOs can effectively dissociate mature insulin fibers into short fibers and remove them. The dissociation effect is significantly enhanced with the increase of GOs concentration.ConclusionsCombining the results of ThT fluorescence and Micro-FTIR, speculate that GOs changes the second structures of the mature insulin fibers by extracting the protein molecules, transforming it from the original beta fold to an alpha spiral structure.  
        关键词：Graphene oxide nanosheets;Insulin fibers;Degradation   
        319
        |
        21
        |
        0
        <HTML>
        <L-PDF><Meta-XML>
        <引用本文> <批量引用> 1531787 false
        发布时间：2024-10-25
      • GAN Quan,CAO Pei,HAO Lijuan,SONG Jing,LONG Pengcheng,YU Shengpeng
        Vol. 42, Issue 9, Article number: 090502(2019) DOI: 10.11889/j.0253-3219.2019.hjs.42.090502
        摘要：BackgroundThe self-powered detectors (SPD) are widely used in commercial reactor for the real-time measurement of neutron flux distribution, but neutron spectrum cannot be obtained by SPD. Meanwhile, due to the extreme condition of advanced reactor systems, the existing in-core measurement systems cannot meet the requirement of real-time measurement of neutron field in the core of advanced reactor.PurposeThis study aim to develop an inversion method of in-core neutron field based on ex-core neutron spectrum measurement.MethodsFirst of all, Monte Carlo calculation method was employed to obtain the spectrum response matrix between adjacent truncated planes in the core by forward neutron transport calculation. Then, the in-core neutron field could be inversed. Finally, two simplified reactor models were used for method verification and validation.ResultsFor the neutron field in the pressure vessel, the average relative deviation between the inversion result and the Monte Carlo transport computation result was about 14%, and for the neutron field in the external fuel region, the average relative deviation was about 11%.ConclusionThe inversion method of in-core neutron field proposed in this paper preliminarily demonstrated the feasibility of the method for neutron spectrum monitoring in the reactor core.  
        关键词：Neutron flux distribution;Ex-core neutron spectrum;Spectrum response matrix;Inversion;Advanced reactor system   
        324
        |
        23
        |
        0
        <HTML>
        <L-PDF><Meta-XML>
        <引用本文> <批量引用> 1531759 false
        发布时间：2024-10-25
      • GUO Guangshui,ZHANG Long,MENG Xianfang,CAO Ke,QIN Peizhong
        Vol. 42, Issue 9, Article number: 090503(2019) DOI: 10.11889/j.0253-3219.2019.hjs.42.090503
        摘要：BackgroundShielding materials has been widely used in nuclear field, but no uniform standards have been established so far for the neutron shielding performance test of shielding materials.PurposeThis study aims to analyze the factors affecting the reliability and stability of neutron response in neutron shielding test system.MethodThe SuperMC program was employed to simulate the neutron shielding test system modeling, and the influence factors such as the distance of test sample to the detector, the axis deviation of test sample to the detector, the axis deviation of the radiation source to the detector and the size of test sample. Simulation data of neutron flux, neutron mean energy and neutron energy spectrum were compared and analyzed with the neutron response curve of neutron detection instrument.ResultsAnalysis results show that the detector and radiator adjusted to the center line position of the collimation area achieve stable and reliable performance. The distance between the detector and the radiator in the range of 130~180 cm, and sample size greater than 30 cm are recommended.ConclusionThis paper provides reasonable and reliable test parameters for the neutron shielding test system, and theoretical basis for reducing the test error of the test system and improving reliability of test data.  
        关键词：Shielding materials;Monte Carlo;Neutron response;Neutron shielding test;SuperMC   
        317
        |
        26
        |
        0
        <HTML>
        <L-PDF><Meta-XML>
        <引用本文> <批量引用> 1531632 false
        发布时间：2024-10-25

        NUCLEAR ENERGY SCIENCE AND ENGINEERING

      • LIU Qiaofeng,HAN Jingru,ZHAO Chuanqi,CHEN Haiying,WU Yongle
        Vol. 42, Issue 9, Article number: 090601(2019) DOI: 10.11889/j.0253-3219.2019.hjs.42.090601
        摘要：BackgroundLeader factor of surveillance capsule is an important indicator in the reactor pressure vessel material supervision process, and is one of the key parameters for predicting of the lifetime of reactor pressure vessel.PurposeThis study aims at independent verification calculation of the leader factor of reactor surveillance capsule so as to evaluate the accuracy of the reactor design, and improve the independence, scientificality, and effectiveness of the nuclear safety review.MethodsMonte Carlo calculation program was employed to calculate the main factors of a three-generation pressurized water reactor (PWR) reactor monitoring cabin. Both the maximum fast neutron fluence at the inner surface of pressure vessel and fast neutron fluxes at samples in irradiation supervisory tubes were verified and calculated.ResultsThe results showed that the relative deviations between the calculated results and the design values were less than 5%, and the leader factors could comply with the requirement of the nuclear safety review.ConclusionThis work provides a reference for nuclear safety review and design departments of nuclear power plants. The calculation results provide effective technical support for nuclear safety review of the third-generation PWR nuclear power plant.  
        关键词：Leader factor;Monte Carlo;Independent verification calculation   
        311
        |
        21
        |
        0
        <HTML>
        <L-PDF><Meta-XML>
        <引用本文> <批量引用> 1531527 false
        发布时间：2024-10-25
      • WU Qigang,LIU Sumei,LEI Mingzhun,XU Kun,HUANG Wei
        Vol. 42, Issue 9, Article number: 090602(2019) DOI: 10.11889/j.0253-3219.2019.hjs.42.090602
        摘要：BackgroundBlanket is an important component of China fusion engineering test reactor (CFETR). A large amount of heat inside the blanket needs to bring coolant to the outside of the Tokamak device.PurposeThis study aims to design the channel of inboard (IB) and outboard (OB) back supporting structure (BSS) to suitable for multiple operating conditions.MethodsThe thermal analyses for BSS under four working conditions were performed by FLUENT, a computational fluid dynamics (CFD) software, which conducted by fluid-solid coupling finite element. The temperature distribution and the heat exchange of IB, OB BSS under 200 MW, 500 MW, 1 GW and 1.5 GW conditions were analyzed.ResultsThe temperature distribution of the BSS, the heat exchange of the internal fluid and the average temperature change of the fluid were obtained under four working conditions.ConclusionThe maximum temperature of the IB BSS and the OB BSS is less than the allowable temperature of the structural material; the average temperature change of the coolant on the IB and OB channels is consistent with the blanket outlet and inlet.  
        关键词：Blanket back supporting structure;Channel;Thermal analysis   
        311
        |
        21
        |
        0
        <HTML>
        <L-PDF><Meta-XML>
        <引用本文> <批量引用> 1531584 false
        发布时间：2024-10-25
      • SUN Guangzhi,REN Cai,MAO Congji,ZHANG Mi,LI Shucheng,LIU Wenzhen,ZENG Le,QIU Shunli,CHENG Hui,FENG Hongyi,XU Ling,WANG Yiyuan
        Vol. 42, Issue 9, Article number: 090603(2019) DOI: 10.11889/j.0253-3219.2019.hjs.42.090603
        摘要：BackgroundThe uniformity of uranium film thickness in fission chamber used in nuclear instrumentation system (NIS) has a great influence on its measurement accuracy.PurposeThis study aims to explore appropriate plating process and test method.MethodsBased on the study of the distribution of uranium foil in the fission chamber of the NIS system, an instrument which can measure the thickness of uranium film on the inner surface of cylinder electrode of the chamber was set up. Two fission chamber samples, one was coated with a vertical electrodepositing techniques and the other was coated with a horizontal electrodepositing techniques, were measured by the instrument. The difference between them was analyzed and the mechanism of uranium film formation and causes of distribution differences were investigated.ResultsThe results of the experiment are coincident with theoretical analysis.ConclusionThis study can be used to guide the production process control of fission chamber.  
        关键词：Fission chamber;Electrodeposition;Uranium film;PIPS detector   
        311
        |
        25
        |
        0
        <HTML>
        <L-PDF><Meta-XML>
        <引用本文> <批量引用> 1531600 false
        发布时间：2024-10-25
      • FAN Huiqing,LIN Liangcheng,CAI Maoyuan,HUANG Chaochao,ZHANG Xiaochun,FU Yuan
        Vol. 42, Issue 9, Article number: 090604(2019) DOI: 10.11889/j.0253-3219.2019.hjs.42.090604
        摘要：BackgroundHigh temperature molten salt pump, the design temperature can go up to 700 °C, is one of the key equipment in the primary loop in the simulator of Thorium-based Molten Salt Reactor with Solid Fuel (TMSR-SF0). The structural integrity of the pump is crucial to the safe operation of the reactor.PurposeThis study aims to reduce the load-controlled stress level of the molten salt pump tank of TMSR-SF0 to meet the evaluation requirements of American Society of Mechanical Engineers (ASME) BPV code.MethodsThree different schemes of the reinforcing rib for the bottom flat head including triangular shape, #-shape, and dual-#-shape were proposed and analyzed to optimize the initial tank design. The influence of the reinforcing rib spacing on the stress of pump tank in the dual-# scheme had been studied, and the optimal combination of parameters was found. According to the results of above analyses, the final tank design scheme was obtained, and then evaluated in accordance with ASME BPV code section III, Division 5.ResultsThe results show that all of the three schemes can significantly reduce the stress level of the pump tank, dual-#-shape scheme was the best, and then followed by the #-shape scheme and triangular shape scheme.ConclusionsThe final reinforcing rib design scheme for the bottom flat head of the pump tank is a dual-# scheme, which can reduce its stress from 413.4 MPa to 65.4 MPa, with a drop of 84.2%, and meet the stress assessment limit of ASME standard.  
        关键词：TMSR-SF0;High temperature molten salt pump;Structure optimization;ASME-HCB;Integrity assessment   
        313
        |
        22
        |
        0
        <HTML>
        <L-PDF><Meta-XML>
        <引用本文> <批量引用> 1531899 false
        发布时间：2024-10-25
      0