最新刊期
      卷 38 ， 期 4 ， 2015
      • CHEN Can,TONG Yajun,XU Zhaoqian,MAO Dingli,XIAO Tiqiao
        Vol. 38, Issue 4, Article number: 040101(2015) DOI: 10.11889/j.0253-3219.2015.hjs.38.040101
        摘要：Background and Purpose: The Laue bent crystal is one of the most effective optical elements for focusing, collimating and monochromating of high flux density high energy X-rays (above 30 keV), because of its excellent performance in reducing the high heat load effectively and reusing of transmission beam directly. The dispersion characteristics is very important for developing high performance and multipurpose Laue bent crystal monochromator. Methods: Self-developed X-ray trace program was employed to study the dispersion characteristics of Laue bent crystal in aspects of diffraction, focus, etc. Results: The distribution of diffraction energy with the beam spot was obtained and the focused beams with different energies created by single Laue bent crystal were got. The general formula of center energy and energy bandwidth of the double beam was also derived. Conclusion: This research provides a basis for the further application of Laue bent crystal. Abstract  
        关键词：X-ray optics;Laue bent crystal;Dispersion characteristics;Ray-tracing   
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        发布时间：2021-03-03
      • ZHENG Honglong,TUO Xianguo,SHI Rui,YANG Gang,DENG Chao,CAO Wen,LIU Yao
        Vol. 38, Issue 4, Article number: 040201(2015) DOI: 10.11889/j.0253-3219.2015.hjs.38.040201
        摘要：Background: Efficiency of HPGe detector directly effects accuracy of physical measurement result. On the condition of detector crystal remains unchanged, efficiency of detector to point source is mainly determined by energy, angle and detecting distance. Purpose: The aim is to study the effect of energy, angle and detecting distance to HPGe detector efficiency of point source. Methods: Spatial location of point source is determined in polar coordinates. Experimental spectra of 137Cs and 60Co on the condition of different angle and detecting distance are measured. Efficiency of point source is determined through the method of combination of Monte Carlo software-MCNP simulation with experimental measurement. Results: Relative deviation of point source efficiency of 137Cs and 60Co between the experimental and MCNP simulation results is less than 8% when the angle from 0 rad to 9π/24 rad. Conclusion: Efficiency function of HPGe detector to point source and its parameters are determined by using multivariate non-linear regression of efficiency simulation results of 137Cs and 60Co. Abstract  
        关键词：MCNP;HPGe detector;Point source;Detecting efficiency;Efficiency function   
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        发布时间：2021-03-03
      • WANG Qibiao,TUO Xianguo,HUANG Hong,MA Qiao,WANG Xu,DENG Li,YANG Jianbo
        Vol. 38, Issue 4, Article number: 040202(2015) DOI: 10.11889/j.0253-3219.2015.hjs.38.040202
        摘要：Background: The peaceful use of radioactive materials is a huge wealth for humans, but illegal transfer of radioactive materials brings a serious potential safety hazard to the public security. Purpose: This study aims to design a gantry system for ? radiation detection to avoid the illegal transfer of radioactive materials. Methods: MCNP code is used to simulate the system which measured two typical ? sources (137Cs and 60Co) using two plastic scintillator detectors (EJ200) in the size of 200 cm × 40 cm × 6 cm. Nuclides are identified by analyzing the spectrum, and locations are obtained according to the response of NaI(Tl) detector array. Results: Theoretical computation results showed that ?radiation detection limitation of this system was identified to be 370 Bq for both 137Cs and 60Co, characteristic peaks can be identified effectively, and locations of 137Cs are obtained rapidly and accurately. Conclusion: This system satisfies the use of crowd places well, and prevents ? radioactive sources from transferring illegally in the event of a nuclear accident. Abstract  
        关键词：r radiation;Gantry system;Nuclide identification;Positioning   
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        发布时间：2021-03-03
      • WU Wanying,YAO Guangchao,ZHANG Xiaowen,CHEN Zhumei,ZHANG Xiaofeng,CHEN Diyun
        Vol. 38, Issue 4, Article number: 040301(2015) DOI: 10.11889/j.0253-3219.2015.hjs.38.040301
        摘要：Background: Agricultural wastes are widely applied in heavy metal wastewater treatment, and became a hot point in this field. Purpose: The aim is to study modified rice straw with significant removal ability of thorium. Methods: The rice straw modified with butanedioic acid was used to remove Th4+ from aqueous solution. And its influence factors such as adsorbent dosage, pH, adsorption time and reaction temperature were investigated through dynamic tests. Results: The optimal conditions were found to be 0.50 g of modified rice straw, pH=3.5, 0.5 h of adsorption time and 10 mg?L?1 of initial thorium concentration at 65 oC. Under these conditions, the removal rates reach 96%. Fourier transform infrared spectroscopy (FTIR) analysis shows some new adsorption peaks such as carboxyl, ester and hydroxyl has added to modified rice straw. The adsorption behavior of Th4+ could be fitted well by the Freundlich adsorption isotherms and the quasi-second order kinetics equation. Conclusion: Its absorptive property enhancement might attribute to expose more internal porous structure of lignin and cellulose and add special functional groups by the modifying process.Cited  
        关键词：Thorium;Butanedioic acid;Modified rice straw;Adsorption   
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        发布时间：2021-03-03
      • LIU Shaohai,CHEN Yongzhong,HAN Lifeng
        Vol. 38, Issue 4, Article number: 040401(2015) DOI: 10.11889/j.0253-3219.2015.hjs.38.040401
        摘要：Background: Redundancy technology can be used as an effective solution to improve the reliability of Experimental Physics and Industrial Control System (EPICS) applied to nuclear reactor, and the most popular redundancy method is a standby mode with the switching time less than 1 s. Meanwhile, the Parallel Redundancy Protocol (PRP) released in standard IEC62439-3 is proposed as a possible solution to provide zero switching time in case of a single-point failure. Purpose: In order to further improve the reliability of EPICS to fulfill the high-reliability requirements of the redundancy control network in nuclear reactor, the "parallel" redundancy mode elaborated in PRP is applied to the nuclear reactor. Methods: The feasibility of EPICS achieving a high reliability based on PRP technology is analyzed, and a software implementation example of Channel Access (CA) protocol of EPICS has been developed over Linux based on PRP which implemented on the application layer. Results: Test results show that the high-reliability requirements of completely seamless switchover can be realized when a single-point failure occurs in the redundant network. Conclusion: With the proposed implementation plan, the redundant EPICS can be employed to achieve a high-reliability network for nuclear reactor. Abstract  
        关键词：Parallel Redundancy Protocol (PRP);Nuclear reactor;Experimental Physics and Industrial Control System (EPICS);Network redundancy;Reliability   
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        发布时间：2021-03-03
      • SUN Yuan,ZHOU Aiyu,XIAO Songwen,WU Yanyan,HAN Qingfu,ZHU Tao
        Vol. 38, Issue 4, Article number: 040402(2015) DOI: 10.11889/j.0253-3219.2015.hjs.38.040402
        摘要：Background: The Multi-purpose Reflectometer (MR) is one of the three spectrometers in the first-phase construction of the China Spallation Neutron Source (CSNS). The neutron beam line switch plays an important role in MR of the neutron beam. Purpose: This study aims to design high precision and high reliability switching control of the neutron beam line in MR that guarantees the security of operators and devices. Methods: A programmable logic controller (PLC) is employed as kernel processor, a step motor as driving component, and a high precision circular grating for position-feedback. Redundancy of the protective design and error handling is taken to ensure that the system is working steadily and safely. Results: Simulation test showed that the system can deal with error condition safely and maintain a stable running. A repeat positioning accuracy of 16.2″ is achieved during the no load test. Conclusion: The results of tests show that the design of our neutron beam line switch control system can satisfy the experiment requirements in MR. Abstract  
        关键词：Programmable logic controller (PLC);Neutron beam line switch;High precision   
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        发布时间：2021-03-03
      • JIAO Cangwen,DENG Ming,LU Shili,YUAN Ming,MA Yanfang
        Vol. 38, Issue 4, Article number: 040403(2015) DOI: 10.11889/j.0253-3219.2015.hjs.38.040403
        摘要：Background: γ spectrometry logging is one method for accurately computing uranium content in uranium-thorium mixed type deposit for slim borehole application. Purpose: The aim is to design slim borehole γ spectrometry logger N451 with ?30 mm×100 mm high detection efficiency Bi4Ge3O12 (BGO) scintillation detector, whose diameter and length are 45 mm and 1300 mm, respectively. Methods: By applying the configuration of dual-microprocessor plus dual port RAM to improving the data throughput rate, the aim of reducing dead time was achieved. As to auto-stabilization, by means of 4-window algorithm with 133Ba reference source, plus temperature-based coarse set while power on and fine tune Photomultiplier Tube (PMT) high voltage while logging, the auto-stabilization accuracy was considerably improved. Using Pb-Sn mask method, N451 overcomes the interference on auto-stabilization system from the high level uranium deposit low energy γ-ray. Results: After multiple saturated modules and 226Ra point source calibration and Fe as well as H2O coefficient correction, field logging was surveyed. Conclusion: The uranium content relative error was less than 10%. The slim borehole γ spectrometry logger is up to the specification. Abstract  
        关键词：Slim borehole;Bi3Ge4O12 (BGO) crystal;Automatic spectrum stabilization   
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        发布时间：2021-03-03
      • LIU Ye,LIU Zhenbao,HOU Jie
        Vol. 38, Issue 4, Article number: 040404(2015) DOI: 10.11889/j.0253-3219.2015.hjs.38.040404
        摘要：Background: Field Programmable Gate Array (FPGA) can be used to overcome the software common cause failures (CCF), thus is a more and more widely applied to design the Digital Reactor Protection System (DRPS). There are many companies such as State Nuclear Power Automation System Engineering Company (SNPAS, China), RPC Radiy (Ukraine), etc., are doing research on FPGA-based DRPS. Thorium Molten Salt Reactor (TMSR) project plans to do the same work now. Purpose: Digital signal process (analog to digital converter driven, digital filter, and quantitative comparison), logic process (two-out-of-four logic, 2oo4) and data communication are some key components in DRPS design. It is important to test whether FPGA is able to realize these key techniques or not. Methods: First of all, the flash-based FPGA made by Actel Company is selected to design for digital signal process and logic process, and coded by Verilog Hardware Description Language (Verilog HDL, Verilog) under Libero SoC program. Then the Icarus Verilog (iVerilog) program is employed for simulation, and finally the signal waveform is watched by GtkWave program. Hardware test is performed by using FPGA development board together with some necessary chips. Results: Experimental results showed that the digital signal process and logic process were realized in the dedicated FPGA and performed well. Analog to Digital Converter (ADC) driven module was stable and executed as fast as the ADC chip could. Digital filter module made the ADC data much more stable. Quantitative comparison module got expected results accurately. The 2oo4 logic module gave the result immediately when the inputs had 2 or more “1”. It is of most importance that all of these modules worked simultaneously. Conclusion: It is practicable to use flash-based FPGA in DRPS of TMSR project technically due to its non-software common cause failure, fast speed, simplification and parallelism. Abstract  
        关键词：Field Programmable Gate Array (FPGA);Digital Reactor Protection System (DRPS);Logical process;Analog to Digital Converter (ADC)   
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        发布时间：2021-03-03
      • MAI Xiyuan,ZHANG Feng,LIN Jun,WANG Peng,ZHU Zhiyong
        Vol. 38, Issue 4, Article number: 040501(2015) DOI: 10.11889/j.0253-3219.2015.hjs.38.040501
        摘要：Background: The coating of TRISO (Tristructural isotropic) type fuel particle is prepared by chemical vapor deposition in spouted bed. Gas and solid flow behaviors are considerably influenced by particle properties during coating process. Purpose: This study aims to investigate the influence of particle properties on gas and solid flow behavior in spouted bed. Methods: Based on the two-fluid model, the Fluent software was applied to conduct simulation of the property change of particle during the spouting process with emphasis on particle spatial distribution, volume fraction and gas temperature on centerline of spout zone. Experiments were set up to compare and verify simulated results. Results: It is found that fountain height and particle quantity in spout zone decreased with coating process. Gas heating rate in spout zone decreased with the increase of particle diameter and the decrease of particle volume fraction. Conclusions: Increase in particle diameter has a considerable effect on hydrodynamics of spouted bed during coating process. The inlet gas flow rate is suggested to adjust to maintain the steady gas-solid hydrodynamic state at the later stage of coating process. In the meanwhile, temperature of furnace wall and inlet gas should be appropriately increased to maintain a proper pyrolysis rate. Abstract  
        关键词：TRISO (Tristructural isotropic) particle;Nuclear fuel;Spouted bed   
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        发布时间：2021-03-03
      • WANG Feifei,WANG Hailing,YU Haiying
        Vol. 38, Issue 4, Article number: 040502(2015) DOI: 10.11889/j.0253-3219.2015.hjs.38.040502
        摘要：Background: With the development of the current nuclear reactor system, some characteristics such as complex structure, material variety and diverse spectrum of reactor cores need more and more computation consumption for reactor physics. Graphic Processing Unit (GPU) computing technology is widely used on the reactor calculation due to its rapid development. Purpose: This paper illustrates the GPU computing environment based on Compute Unified Device Architecture (CUDA) architecture, which is established on the design platform of Thorium Molten Salt Reactor (TMSR). And the neutron three-dimensional diffusion calculation module of the reactor would be transplanted into the GPU for testing and verification. Methods: First of all, center difference method was used to deduce the difference equations of three dimensional diffusion calculations, make it suitable for GPU. Then, the over relaxation iteration method was applied to solve these difference equations. Finally, the over relaxation iteration algorithm was studied in the parallel implementation of GPU processes. Results: The results show that the transplantation of GPU computing module section can be used to obtain correct output, and it can effectively improve the computing speed. Conclusion: The GPU computing environment on the TMSR design platform can work normally by carefully transplanting of several key methods for difference equations based on the CUDA of GPU. Abstract  
        关键词：Graphic Processing Unit (GPU);Compute Unified Device Architecture (CUDA);Design platform of Thorium Molten Salt Reactor (TMSR);3D diffusion calculation;Successive Over Relaxation Method (SOR)   
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        发布时间：2021-03-03
      • TANG Yanze,ZHENG Haiwei,CHEN Yushuang,FU Yuan,TANG Zhongfeng,ZHU Haihua,KONG Xiangbo,WANG Naxiu
        Vol. 38, Issue 4, Article number: 040601(2015) DOI: 10.11889/j.0253-3219.2015.hjs.38.040601
        摘要：Background: System code is important for the dynamic simulation and safety analysis of the molten salt cooling system. There is no professional system code for molten salt-cooled system yet. The HYSYS code is a process simulation environment designed to serve many processing industries. It has a potential ability for the global simulation of the molten salt cooling system as well as transient and accident safety analysis. Purpose: The aim is to validate the modified HYSYS code for molten salt cooling system application. Methods: Based on the KNO3-NaNO2-NaNO3 molten salt (HTS) experiment device, the thermal-dynamic and transport properties were implemented into the HYSYS code, and a precise and complete model was built for HYSYS code. The model was used to simulate the HTS loop under different conditions. The corresponding experiments were also executed, and then the simulated results were compared with the experimental data to validate the HYSYS code application. Results: The simulated temperature data are in good agreement with the experimental results. Conclusion: The modified HYSYS code is available in simulating molten salt-cooled loop system. Abstract  
        关键词：Molten salt system;HYSYS code;Transient simulation;Experimental validation   
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        发布时间：2021-03-03
      • WANG Kai,CAI Chuangxiong,HE Zhaozhong,CHEN Kun
        Vol. 38, Issue 4, Article number: 040602(2015) DOI: 10.11889/j.0253-3219.2015.hjs.38.040602
        摘要：Background: Nitrate salt natural circulation loop (NNCL) system is an important platform for studying molten salt natural circulation characteristic. And the foundation for the design and verification passive residual heat removal system in the fluoride slat-cooled high temperature reactor might be obtained in this platform. Purpose: This study aims to analyze characteristics of NNCL system under different heating power, air flow, etc. Methods: The RELAP5/MOD4.0 code was employed with modification of applicability for NNCL. Simulation was performed for the NNCL system under various running conditions. Results: The calculation results show that air flow has an important effect on NNCL mass flow rate and an inverse relationship with mass flow rate; the steady temperature and mass flow rate of NNCL will increase with the heating power and the steady mass flow rate of NNCL will decrease with the air inlet temperature; NNCL system needs a long time to get a steady state, about 8?27 h. In order to keep the nitrate salt in liquid and not deteriorate, power should be limited in 20?40 kW at the rated air mass flow rate. Conclusion: Heating power and air mass flow rate are the most important factors to effect of the NNCL steady state, which can influence the temperature and the mass flow rate of NNCL system.Cited  
        关键词：Natural circulation;RELAP5/MOD4.0;Passive residual heat removal system;Nitrate slat   
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        发布时间：2021-03-03
      • ZHANG Ning,WANG Quanquan,GUO Bing,SUN Xuejing,XU Haixia,CHEN Yongzhong
        Vol. 38, Issue 4, Article number: 040603(2015) DOI: 10.11889/j.0253-3219.2015.hjs.38.040603
        摘要：Background: Redundancy configuration is widely adopted in the digitalized instrumentation and control (I&C) system of third-generation reactors. For further availability improvement, state monitoring method of redundant configured Programmable Logic Controller (PLCs) and Input/Output Controller (IOC) components in Experimental Physics and Industrial Control System (EPICS) based I&C system prototype was studied for the Thorium Molten Salt Reactor (TMSR) project. Purpose: In order to avoid serious consequence or potential risks caused by switch-over or redundancy failure, the running states of redundant units composed high availability (HA) devices in reactor I&C system are expected to be accessed in real-time in this study. Methods: By means of adding the unit state reporting channels which could be transferred into Process Variables (PVs) for the acquisition of EPICS upper tier application, a novel method of monitoring redundant states of device units was developed. Source code of redundant monitor task (RMT) was modified by adding a routine to record state-related information for the IOC pairs whilst a new state-read program block for local and remote units was developed for PLCs. All state monitoring related variables was acquired and passed into EPICS records by IOC driver. In terminal layer, a CSS (Control System Studio)-based OPI (Operator Interface) Plug-In was implemented for on-line state monitoring. Results: Redundant state-related information of each unit pair were successfully acquired as PV values and showed in the designed OPI interface by proposed method. Test proved it could achieve real-time monitoring of redundant state variation. Conclusion: By developing and modifying program for HA units, and designing OPI interface, reactor I&C system could monitor redundant unit state for a long-term with few additional system resources. It could provide technological support for further improvement of availability of the reactor I&C system. Abstract  
        关键词：Redundancy;Distributed Control Systems (DCS);Experimental Physics and Industrial Control System (EPICS);High availability;State monitoring   
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        发布时间：2021-03-03
      • HE Jian,ZHU Zhiqiang,HUANG Qunying,WANG Hai,SHANG Hua
        Vol. 38, Issue 4, Article number: 040604(2015) DOI: 10.11889/j.0253-3219.2015.hjs.38.040604
        摘要：Background: Liquid lead-bismuth eutectic (PbBi) has been proposed as one of mainly coolant materials for Accelerator Driven Sub-critical Systems (ADS) reactors, and the valve is a key component for flow regulation in high temperature liquid PbBi experimental loop. The flow resistance has a direct impact on the structural design and safe operation of the loop. Purpose: This study aims to reduce the resistance loss of the valve in high temperature liquid PbBi experimental loop of the drive system, ensuring the safe and stable operation of the loop. Methods: Based on liquid PbBi fluid measurement experimental loop PREKY, the resistance characteristics experiment of Y-type globe valve in the typical conditions of liquid PbBi reactor was performed, and the pressure datum were achieved by using differential pressure transmitter and compared with the theoretical calculation results. Results: The results verified the rationality of experimental results and reasonability of measurement method. In addition, the flow resistance theoretical calculated index on Y-type globe valve was proved to be 2.4 in the flow rate range of 1.2–2.0 m?s?1 for the liquid PbBi loop. Conclusion: The experimental results could be directly applied to calculation and analysis of flow resistance in liquid PbBi experimental loop in future. Abstract  
        关键词：Liquid lead-bismuth;Y-type globe valve;PREKY;Flow resistance   
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        发布时间：2021-03-03
      • XU Rui,DONG Bing,FU Yaru,MEI Qiliang,WANG Dezhong
        Vol. 38, Issue 4, Article number: 040605(2015) DOI: 10.11889/j.0253-3219.2015.hjs.38.040605
        摘要：Background: A large quantity of fission products would be produced when the nuclear reactor runs. These fission products would be released to the pellet-rod gap and then to the primary circuit while the fuel rod is broken. The fission products in the primary circuit become the main source term of the reactor. Purpose: This study aims to analysis the source term accurately by calculating the release to birth ratio (RBR) of volatile fission products precisely. Methods: After researching American NRC ANSI/ANS-5.4 methods and French methods for calculating the RBR of volatile fission products, we calculated the RBR of volatile fission products of a fuel rod at different power and different burn-up by these methods, and made some comparison and analysis of these results. Results: Computation results showed that the RBR of volatile fission products would increase with the power and burn-up of the fuel rod. Compared with the ANSI/ANS-5.4-2011, the French method is more conservative whilst the ANSI/ANS-5.4-1982 is the most conservative among these methods. Conclusion: ANSI/ANS-5.4-2011 is the best method among these three methods and it can be used to calculate the release to birth ratio of volatile fission products with good results. Abstract  
        关键词：Fuel rod;Fission products;Release to birth ratio;ANSI/ANS-5.4;METEOR1.5   
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        发布时间：2021-03-03
      • XU Zhi,BAO Qi
        Vol. 38, Issue 4, Article number: 040606(2015) DOI: 10.11889/j.0253-3219.2015.hjs.38.040606
        摘要：Background: The over temperature/over power ΔT (OT/OP ΔT) is a key protection to Pressurized Water Reactor (PWR) and the response time testing of the protection is required in technical specifications of Preliminary Safety Analysis Report (PSAR). Purpose: To have credible response time testing of the protection, including the effects of dynamic compensation unit, analysis was conducted on the requirements of the rules and the application of the design. Methods: Firstly, the application of the protection algorithm is analyzed. Then the requirements of IEEE388 and the dynamic response of the typical dynamic compensation units upon step and impulse stimulations are studied. Results: Base on the analysis, corresponding to the nominal thermohydraulics and the instrumentation and control design, a recommend testing parameter configuration set for AP1000 OT/OP ΔT protection response time testing is developed. The non-negligible effect of dynamic compensation units is concluded as well. Conclusion: As a result, the requirement of having the dynamic compensations on line for the response time testing is strongly proposed. Abstract  
        关键词：AP1000;OT/OP ΔT protection;Response time testing;Dynamic compensation;Lead-lag   
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