最新刊期
      卷 43 ， 期 6 ， 2020

        SPECIAL SECTION ON THE 11TH NATIONAL CONFERENCE ON NEW AND RESEARCH REACTORS (PART II)

      • “在核反应堆堆芯计算领域，超级均匀化方法显著提升了Pin-by-pin计算精度，为堆芯设计提供新思路。”
        ZHANG Bin,LI Yunzhao,WU Hongchun
        Vol. 43, Issue 6, Article number: 060001(2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.060001
        摘要：BackgroundThe new generation of pin-by-pin calculation method has gradually become the state-of-the-art approaches along with the improvement of computer technology and the development of core design.The difference between the pin-by-pin calculation and the traditional two-step scheme leads to the homogenization technique difficult to implement.PurposeThis study aims to evaluate super homogenization techniques for pin-by-pin core calculationwith emphasis on equivalent homogenization constants.MethodsSuper homogenization method was used as one of the main homogenization techniques of pin-by-pin calculation. For fuel assembly, the traditional super homogenization method was employed to generate the group constants. For reflector assembly with neutron leakage, the super homogenization method related to space leakage was applied to the generation of equivalent homogenization constant including super homogenization factor.ResultsBased on the three-dimensional C5G7 benchmark, the application performance of the super homogenization method in pin-by-pin calculation is evaluated. The eigen-value relative error of pin-by-pin calculation is -0.001 6, assembly-power and pin-power relative errors are less than 5.5%.ConclusionsNumerical results showed that the pin-by-pin calculations have the higher accuracy than the assembly-homogenized results.  
        关键词：Pin-by-pin calculation;Super homogenization method;Group constants;C5G7 benchmark   
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      • “在深空探测领域，热管核反应堆电源因其非能动性、长寿命和高可靠性成为研究热点。本文重点调研了热管电源系统、火星探索反应堆、安全可负担裂变引擎方案和Kilopower，总结了其结构设计、燃料选择、热管排布和功率设计，为未来热管空间核反应堆电源设计提供思路和参考。”
        WANG Ao,SHEN Fengyang,HU Gu,GUO Jian AN Weijian
        Vol. 43, Issue 6, Article number: 060002(2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.060002
        摘要：BackgroundWith the in-depth exploration of space, the power supply requirements for energy supply are gradually increasing. Space nuclear reactor power supply stands out in the deep space exploration mission due to its advantages of passivity, long life and high reliability, hence heat pipe nuclear reactor has become the focus of research in the field of space nuclear reactor.PurposeThis study aims to evaluate the progress and technology of heat pipe space nuclear reactor used as power supply.MethodFirst of all, the conceptual design of heatpipe reactor in the early stage and its application in Kilopower was summarized. Then the details of heatpipe power system (HPS), the heatpipe-operated mars exploration reactor (HOMER), safe affordable fission engine (SAFE) and Kilopower were investigated with emphasis on the structure design, fuel selection, heatpipe arrangement and power design of each reactor.ResultsThis survey provides ideas and references for future research and design of heatpipe space nuclear reactor power system.ConclusionsThe design of heatpipe reactor is highly flexible and innovative. The use of different alkali metal heat pipes and thermoelectric conversion methods has a direct impact on the system power and the quality of the entire system. The combination of heat pipe and various thermoelectric conversion methods can be attempted.  
        关键词：Space nuclear reactor;Heatpipe;HPS;SAFE;Kilopower   
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        发布时间：2024-10-25
      • “在堆芯核设计领域，专家运用DRAGON程序建立燃耗实验模型，验证了多群常数库的准确性，为核反应堆设计提供解决方案。多数核素模拟结果与基准值符合良好，误差在10%以内。”
        WANG Tianxiong,ZHANG Tengfei,WU Haicheng,LIU Xiaojing,XIONG Jinbiao,CHAI Xiang
        Vol. 43, Issue 6, Article number: 060003(2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.060003
        摘要：BackgroundAssembly calculation plays an important role in reactor core design. The depletion calculation accuracy of the assembly calculation is of great significance to the power distribution, refueling life and reactivity control design of nuclear reactor core.PurposeThis study aims to evaluate the accuracy of the multi-group constant library in the neutron depletion calculation and establish a set of depletion experimental calculation model.MethodsThe depletion historical parameters and the final nuclide composition information were provided by the SFCOMPO-2.0 database. The information of the Takahama-3 reactor, H.B. Robinson-2 reactor and Beznau-1 reactor samples were modeled using the DRAGON code. Some simplified methods were applied to some unavailable data information. The numerical results were compared and analyzed with the benchmark results in the SFCOMPO-2.0 database. [Result &ConclusionsThe results show that most of the nuclide productions are in good agreement with the reference value, and the errors are within 10%. Nuclides with large differences between numerical results and benchmark results are discussed simultaneously, and computational results of three reactor samples were compared and analyzed.  
        关键词：Assembly calculation;SFCOMPO-2.0;Modeling and analysis of depletion experiment benchmark   
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        发布时间：2024-10-25
      • “直接循环二氧化碳冷却反应堆研究取得进展，初步提出安全设计所需始发事件和验收准则，为核动力系统安全设计奠定基础。”
        MAO Huihui,ZHANG Dan,GAO Chuntian,WU Pan,LIU Yu,BI Shumao,MI Zhengpeng
        Vol. 43, Issue 6, Article number: 060004(2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.060004
        摘要：BackgroundAs a new concept reactor, direct circulation CO2 cooled reactor has different system configurations and safety characteristics compared with direct cycle boiling water reactor, indirect cycle helium gas cooled reactor and pressurized water cooled reactor, hence the CO2 cooled reactor has different initial events and safety criteria. The selection of initial events is the foundation for the safety design of reactor whilst the safety criteria provides criterion for whether the safety analysis results meet the safety requirements.PurposeThis study aims at the initial events and acceptance criteria for the safety design of CO2 cooled reactor.MethodThe main logic diagram analysis method was employed to study the initial events of the direct circulation CO2 cooled reactor. Based on the existing engineering experience of pressurized water reactor, gas cooled reactor, the acceptance criteria for the direct circulation CO2 cooled reactor were proposed according to its own characteristics.Results & ConclusionsThe proposed initial events and acceptance criteria required for safety analysis are applicable to direct circulation reactor, providing a basis for the safety analysis of CO2 cooled nuclear power plant, and gives an important reference for the safety design of direct cycle circulation reactors.  
        关键词：CO2 cooled reactor;Direct circulation;Initial events;Safety criteria   
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        发布时间：2024-10-25
      • “在核电厂事故放射性源项分析领域，专家建立了事故后放射性核素迁移和扩散计算模型，为核电厂辐射防护提供解决方案。”
        FAN Yuxuan,ZHANG Jingyu,WANG Xiaodong,CHEN Yixue,GUO Qingyang,LIANG Qiuying,XIONG Wenwen
        Vol. 43, Issue 6, Article number: 060005(2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.060005
        摘要：BackgroundWhen an accident occurs in a pressurized water reactor (PWR), the radioactive nuclides are released into the environment and endanger the safety of the environment and the staff. Therefore, the analysis of the radioactive source term released into the environment after the accident is critical to the radiation protection of PWR.PurposeThis study aims to calculate and analyze the source term of the steam generation tube rupture (SGTR) accident in PWR power plant.MethodsAccording to the frequency of the accident and the severity of the consquences, the accident was divided into two conditions: pre-accident the iodine peek release and accident concurrent iodine peek release. Calculation models were established for radio-nuclide migration and diffusion after accident, and the parameters of advanced pressurized water reactor AP1000 were used for calculation and verification with emphasis on the radioactivity of inert gases and volatile nuclides iodine in the environment. [Results andConclusionsThe calculation results show that the radioactive source term calculated by proposed model in this paper is quite consistent with the design source term. The release activity of noble gas is in good agreement with the design source term under two accident conditions, but the release activity of iodine is quite different.  
        关键词：PWR;SGTR;Source term;Noble gas;Iodine   
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        发布时间：2024-10-25
      • “在核能系统领域，专家提出了铅铋合金冷却的铅冷快堆BLESS-D，通过计算主要部件的原子离位数评估辐照损伤程度，为提高反应堆安全性提供解决方案。”
        YEOH Eing Yee,LI Linsen,CHEN Xiaosong CHEN Yaodong
        Vol. 43, Issue 6, Article number: 060006(2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.060006
        摘要：BackgroundA lead-bismuth eutectic cooled fast reactor called breeding lead-based economical safe system – demonstration (BLESS-D） is proposed to meet the public demands of a safer, more economical and more environmental-friendly nuclear system. BLESS-D is a pool-type reactor with 300 MW thermal power. The materials undergo changes of their mechanical and physical properties under neutron irradiation. Some of the internal components in BLESS-D are not replaceable during the reactor life, which results in radiation damage to the material that affects the reactor life.PurposeThis study aims to evaluate the radiation damage of the structural materials through the computation of displacement-per-atom (DPA) for the main components of BLESS-D reactor.MethodsThe DPA calculation was implemented by using the SPECTER and MCNP computer code. DPAs of materials for fuel cladding, inner vessel, main pump casing, steam generator casing and reactor vessel were obtained and compared with the DPA limits of irradiation effect of these materials.ResultsThe maximum DPA of the fuel cladding, inner vessel, pump, #1 steam generator, #2 steam generator and reactor tank are 5.35 dpa·a-1, 2.38×10-1 dpa·a-1, 8.48×10-3 dpa·a-1, 7.25×10-2 dpa·a-1, 7.50×10-2 dpa·a-1 and 1.94×10-5 dpa·a-1, respectively. The accumulated DPA value is analyzed and compared to the imposed limit.ConclusionsConsidering that the reactor life of BLESS-D is 20 years, the maximum accumulated DPA value in the inner vessel segment is higher than the imposed limits, it is necessary to conduct detailed analysis and design optimizations to reduce the accumulated DPA.  
        关键词：Lead-cooled fast Reactor;Radiation damage;DPA;MCNP;SPECTER   
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        发布时间：2024-10-25
      • “在小型化特种动力反应堆领域，专家建立了控制鼓仿真模型，验证了其反应性控制功能，为反应堆稳定运行提供解决方案。”
        CHENG Ming,LYU Zheng,JIA Yuwen
        Vol. 43, Issue 6, Article number: 060007(2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.060007
        摘要：BackgroundReactor control is one of pivotal issues of the nuclear reactor science, and various reactivity control devices are developed as multiple reactor types.PurposeThis study aims to understand the operation and control characteristics of the control drums in miniaturized special power reactors by simulation modeling technique to analyze the principle and key parameters.MethodsBy object-oriented and modularized modeling in advanced simulation platform 3KEYMASTER, the model of reactor control drum was established, then it was coupled with reactor core system program and proportional integral differential (PID) controller. The reactivity disturbance simulation test was done on this coupled system under a stable nuclear power. Finally, the variation trend of nuclear power, control drum reactivity, control drum angle, were obtained together with core data such as disturbance eliminating time and power overshoot. [Results andConclusionsThe simulation results show that all functions and characteristics of control drum are realized in the established model. The reactivity value and driving mechanism of control drum are rational and controllable, the response speed of eliminating disturbance is fast, and the reactivity control function can be implemented effectively.  
        关键词：Reactor control;Control drum;Simulation modeling;3KEYMASTER   
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        发布时间：2024-10-25
      • “在快堆设计领域，专家提出积分形式的变分节块法，为六角形组件几何快堆高效、精确模拟提供解决方案。”
        YIN Han,ZHANG Bin,LIU Xiaojing,ZHANG Tengfei
        Vol. 43, Issue 6, Article number: 060008(2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.060008
        摘要：BackgroundAccurate and efficient neutron calculation method is a prerequisite for fast reactor conceptual design and scheme optimization.PurposeThe study aims to propose an integral form of variational nodal method to solve the three-dimensional multi-group neutron transport equation with hexagonal geometry.MethodsThe integral method was used to deal with the angular flux within hexagonal nodes while angular flux distributions on nodal interfaces are approximated by even-parity spherical harmonics. Besides, the quasi-reflected interface condition (QRIC) method was employed to reduce the number of interfacial angular terms to save computational costs. Finally, the TAKEDA-4 benchmark was taken for evaluation.ResultsThe calculation results of TAKEDA-4 benchmark show that, compared with low angular order approximations, the integral method exhibits superior accuracy than the standard variational node method based on spherical harmonic discretization, and reduces the errors by 2~5 times in eigenvalue. In addition, the joint performance of the integral method and the QRIC method yields a remarkable computational time gain of 33.0 with the P7 angular approximation.ConclusionsThe integral variational node method presented in this paper realizes accurate and efficient simulation of fast reactor in hexagonal geometry.  
        关键词：Variational nodal method;Hexagonal geometry;Integral method;Quasi-reflected interface condition   
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        发布时间：2024-10-25

        SYNCHROTRON RADIATION TECHNOLOGY AND APPLICATIONS

      • “上海软X射线自由电子激光光束线建设取得进展，模拟结果表明，通过控制面形误差，可满足生物成像实验站需求。”
        ZHANG Ximing,GUO Zhi,MENG Xiangyu,ZHANG Xiangzhi,JIN Zuanming,WANG Yong
        Vol. 43, Issue 6, Article number: 060101(2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.060101
        摘要：BackgroundThe self-amplified spontaneous emission (SASE) free-electron laser beamline, dedicated for live-cell imaging, is under construction in the Shanghai soft X-ray free-electron facility. The energy range of the beamline is from 100 eV to 1 000 eV and the beamline covers two branch lines, including frontend, attenuator, plane mirror PM1, variable-line-spacing grating PM2, monochromator, bendable mirror, Kirkpatrick-Baez (KB) mirrors and ellipsoidal mirror etc. The Kirkpatrick-Baez mirrors of the north branch line consisting of a plane mirror and two elliptical cylinder mirrors are used for biological-cell imaging. The surface of mirrors should be highly reliable and precise in the system of the free-electron laser beamline. Slope error of optical elements during the production processing is an important criterion for measuring the surface quality of optical elements. The slope error of mirror is associated with the height error, and affects the coherent and wavefront of the beam, and further affects the final light spot.PurposeThis study aims to explore the variation of the slope error on X-ray coherent and wavefront after propagating in the beamline, and choose appropriate mirror whose slope error has little influence on the beam.MethodsThe software SHADOW and SRW were employed for the simulation to trace the X-ray propagation in the KB mirror and the whole beamline.ResultsWhen the slope error of plane mirrors is controlled between 0.1 μrad and 0.2 μrad, the slope error of elliptical cylinder mirrors is less than 0.4 μrad, and the height error is approximately 3 nm, the high-quality image with spot size less than 4 μm is obtained, satisfying the imaging needs of biological imaging experimental station.ConclusionsResults of this study provide comprehensive detailed data for the optimal design of soft X-ray free-electron laser beamline.  
        关键词：Soft X-ray;Free-electron laser;Kirkpatrick-Baez mirror;Slope error   
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        ACCELERATOR, RAY TECHNOLOGY AND APPLICATIONS

      • “金属氘化物电极真空弧离子源研究取得新进展，为中子发生器等领域提供新选择。”
        LYU Huiyi,WANG Tao,YANG Zhen,DONG Chenyang,XU Haobo,DONG Pan
        Vol. 43, Issue 6, Article number: 060201(2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.060201
        摘要：BackgroundThe vacuum arc ion source with metal deuteride electrodes can generate high current deuterium ion beam, hence can be widely used in neutron generators, high-intensity accelerators and other fields.PurposeThis study aims to introduce a novel alloy deuteride electrode (Zr0.45Ti0.5Cu0.05Dx).MethodsThe novel alloy material was made by vacuum levitation melting with Ti, Zr, and Cu. The deuteride electrode (Zr0.45Ti0.5Cu0.05Dx) was made in a high temperature deuteration apparatus. The material properties of the electrode and the discharge of the vacuum arc ion source were analyzed. In addition, composition of deuterium alloy cathode produced by vacuum arc discharge was analyzed by the magnetic analysis technology. The stability of the deuterium composition was compared with the traditional titanium deuteride electrode ion source.ResultsThe volume expansion of the novel alloy deuteride (MDx, x=1.6~1.7) is about 18%. Macroscopic crack on the surface of the alloy deuteride is found by naked eyes while some micro cracks can be seen by the scanning electron microscope (SEM). The size of the micro cracks is less than 100 nm.ConclusionsThe novel alloy deuteride electrode (Zr0.45Ti0.5Cu0.05Dx) is a good candidate for the vacuum arc ion source.  
        关键词：Vacuum arc ion source;Alloy deuteride electrode;Magnetic analysis;Deuteron composition   
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      • “在束流发射度要求高的120 MeV电子直线加速器领域，研究者采用基于在线束流准直方法，使用消色散校正法对加速器束流匹配传输段进行模拟计算，验证了其良好的应用效果。”
        SUN Bin,WANG Yu,HEI Dongwei,LI Binkang,TAN Xinjian,WENG Xiufeng,LIU Jun,ZHANG Xiaodong,FU Zhuming
        Vol. 43, Issue 6, Article number: 060202(2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.060202
        摘要：Background120 MeV electron linear accelerator has high requirement for beam emittance, and the traditional optical collimation cannot meet the requirement.PurposeThis study aims to use beam-based alignment (BBA) method to achieve higher precision collimation and obtain better beam quality.MethodsAccording to the configuration of 120 MeV electron linear accelerator, all of beam position monitor (BPM) measurement data of the corresponding position under different energy were collected, then, the dispersion-free steering (DFS) algorithm was used to simulate the correction of accelerator matching transmission section in different beam jitter conditions.ResultsThe simulation results indicate that the algorithm can minimize the transverse offset of quadrupole to 50 μm.ConclusionsThe DFS algorithm can reduce the trajectory distortion in the low beam jitter accelerator.  
        关键词：Beam-base alignment;Linear accelerator;Dispersion-free steering algorithm;Beam jitter;Orbit correction   
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        NUCLEAR ELECTRONICS AND INSTRUMENTATION

      • “航空γ能谱测量中，本底扣除是关键任务。改进的SNIP算法提高了本底扣除的准确度和效率。”
        YANG Jin,LI Fei,GE Liangquan,ZHANG Qingxian,XIONG Maolin,SUN Kun,GU Yi
        Vol. 43, Issue 6, Article number: 060401(2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.060401
        摘要：BackgroundThe background count in airborne gamma-ray spectrum measurement is mainly caused by Compton scattering effects, small angle scattering of gamma rays in the sensitive volume of the detector and interference caused by electronic noise in the energy range of the energy spectrum. Background subtraction is one of the important tasks of instrument spectral resolution in airborne gamma-ray measurement.PurposeThis study aims to propose an improved background subtraction method to achieve accurate and efficient spectral analysis of airborne gamma-ray instrument spectrum.MethodsAs one of the best background subtraction algorithms, the statistics-sensitive nonlinear iterative peak-clipping (SNIP) algorithm with simple mathematical structure and reliable background subtraction effect, was easily affected by the parameters of peak width, and lead to longer running time due to slow convergence speed of iterative process. Motivated by the idea of the Simpson formula with higher algebraic precision, the second step of the SNIP iteration in the original algorithm was improved by using three points of interval bisection for integral interpolation. Comparison of SNIP algorithm before and after the improvement was performed for background subtraction of airborne gamma-ray spectrum with different iteration times and appropriate width of transformation.ResultsThe comparison results show that the accuracy and the overall operating efficiency of the improved algorithm are improved by 41.8% and 2.53%, respectively, compared with the original SNIP algorithm.ConclusionsThe improved Simpson-SNIP algorithm achieves fast convergence speed and better accuracy of calculation results while preserves the advantages of simplicity and efficiency of the original, hence better background deduction effect.  
        关键词：Airborne gamma-ray;SNIP algorithm;Simpson;Background subtraction   
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      • “在光电转换器件领域，研究人员开发了一款新型SiPM高压电源模块，通过电压补偿有效稳定了SiPM增益，拓宽了其应用范围。”
        HOU Huiliang,HUANG Yuefeng,CHENG Maosong,DAI Zhimin
        Vol. 43, Issue 6, Article number: 060402(2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.060402
        摘要：BackgroundAs a new solid-state photosensor, silicon photomultiplier (SiPM) has high gain (106), low power consumption (supply current is several μA), small size (several square milimeters), low operating voltage (less than 100 V) and other advantages. Compared with traditional photomultiplier tube, SiPM does not affected by magnetic fields. However, there is a disadvantage that the gain of SiPM is greatly affected by temperature, the gain will decrease by about 5×105 for every 10 °C rise in temperature, which will have a greater impact on energy spectrum measurement and radiation imaging applications.PurposeThis study aims to design and develop a small programmable SiPM power supply for temperature independent gain.MethodsFirst of all, a high-voltage power supply module was designed for SiPM, making use of the gain regulation by voltage. Temperature sensor, DC-DC power chip, etc., were integrated into an ARM-based micro control unit (MCU) module for automatic SiPM power supply. Then the effect of voltage compensation to gain in the temperature range of 5 ℃ to 40 ℃ was verified by using digital multi-channel analyzer with comparison of the channels of full energy peak on the energy spectrum of 241Am source.ResultsThe channel of full energy peak which indicates the gain of the SiPM is stable by using the voltage compensation (gain drift correction), and the maximum drift of the SiPM gain from 5 ℃ to 40 ℃ decreases from 87.3% before compensation to 2.76%.ConclusionsGain drift correction achieved by a small intelligent programmable SiPM power supply broadens the scope of SiPM application.  
        关键词：Silicon photomultiplier;Gain drift correction;γ spectrometry   
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        NUCLEAR PHYSICS, INTERDISCIPLINARY RESEARCH

      • “山东泰山抽水蓄能电站上水库渗漏特征研究取得新进展，为水库渗漏诊断与控制提供重要指导。”
        ZHANG Li,ZHENG Xiaohe,LI Guangkai,YANG Zhangyang,RAO Wenbo,MAO Changping
        Vol. 43, Issue 6, Article number: 060501(2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.060501
        摘要：BackgroundReservoir leakage is typically a potential risk to reservoir operation in the world. However, due to the difference of climate, hydrology and geology conditions, the patterns and causes of water leakage in different reservoirs are quite different. In recent years, H-O isotope tracing has become an important tool used for reservoir leakage detection because it can effectively determine water recharge sources and water discharge.PurposeThis study aims to analyze the H-O isotope characteristics of various water bodies and their hydraulic relations in detail.MethodsThe Taishan pumped storage power station reservoir in Shandong Province was taken as an example. The hydrogen and oxygen isotope compositions of different waters in the reservoir region were investigated to discuss the hydraulic relations among various water bodies.ResultsThe results show that the δ18O, δ17O and δ2H values in the reservoir water collected in July are significantly more positive than those in September and October, and similar variations exist in other water bodies. The isotopic difference between September and October was not significant. The characteristics of reservoir water leakage are different in different parts and months: in October, well water and leakage water in the right bank gallery and bottom gallery drainage hole do not come from the reservoir, while other water bodies are closely related to the leakage of reservoir water; in September, well water in the left bank does not originate from reservoir water leakage, while water in the measuring weir behind dam and the right bank gallery drainage hole are closely related to the reservoir water. In July, leakage water in the right bank gallery drainage hole and reservoir water have a close relationship.ConclusionsOur findings are expected to be helpful for guiding the treatment and control of reservoir water leakage.  
        关键词：Environmental isotopes;Leakage water;Hydraulic connection;Power station reservoir   
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        NUCLEAR ENERGY SCIENCE AND ENGINEERING

      • “在聚变研究领域，科学家利用TRANSP和ORBIT程序，结合诊断数据，研究了EAST托卡马克中性束注入加热时快离子输运行为。实验和模拟结果表明，提高等离子体电流和纵场强度，有利于快离子约束，提高加热效率，增加聚变中子产额和等离子体储能。”
        XIAO Min,WU Bin,ZHONG Guoqiang,HU Liqun,WANG Jinfang,HAO Baolong,HUANG Juan,ZHOU Ruijie,LI Kai
        Vol. 43, Issue 6, Article number: 060601(2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.060601
        摘要：BackgroundIn order to realize a magnetically confined plasma self-sustaining fusion reaction, fast ions need to be confined in the magnetic field for a long time for them to collide sufficiently, heat the main plasma, and drive the plasma current.PurposeThis study aims to explore the fast ions transport behavior of experimental advanced superconducting Tokamak (EAST) neutral beam injection (NBI) heating under different plasma currents and toroidal magnetic field.MethodsThe plasma transport analysis code TRANSP and particle-guided center orbit simulation code ORBIT were combined with fusion neutron and plasma stored energy diagnostic data to study the transport behavior of fast ions. Experimental data under different plasma current and toroidal magnetic field intensity were compared with the simulation results.ResultsExperimental and simulation results show that the prompt loss power of fast ions from the neutral beam injection (NBI) counter-beam is higher than that from the NBI co-beam. Under the effect of the clockwise plasma current and the counterclockwise toroidal magnetic field, the loss areas of fast ions prompt loss from the four beam lines of NBI are mainly concentrated in the first wall below midplane and divertor area of the device. Within the current operating parameters of EAST, increasing the plasma current and toroidal magnetic field can reduce the drift orbit width and the larmor radius of fast ions in the plasma, which is much better for the confinement of the fast ions.ConclusionsIncreasing the plasma current and toroidal magnetic field can improve the heating efficiency of the NBI, especially for the counter-beam, which can increase the fusion neutron yield and stored energy of plasma.  
        关键词：Fast ion behavior;Fusion neutron;Prompt loss;Neutral beam injection;EAST   
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      • “阿尔及利亚比林核研究中心重水反应堆完成数字化升级改造，首次临界启动成功，为极低光激中子水平下临界启动提供解决方案。”
        DING li,XU Pengcheng,HUA Xiao,ZHEN Jianxiao,GE Yanyan
        Vol. 43, Issue 6, Article number: 060602(2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.060602
        摘要：BackgroundThe Multi-purposes heavy water research reactor (MHWRR) at the Birine Nuclear Research Center in Algeria had been upgraded. Its instrumentation, control and electrical system had been upgraded and fission molybdenum radiation apparatus were installed in the reactor core. First critical startup at very low photoneutron level after MHWRR upgrade is of great significance to the reactor modernization, marking the completion of the upgrading project.PurposeThis study aims to fulfill successful critical startup of the reactor without additional neutron source, solve the problem of nuclear measurement blind area, and ensure the startup safety of the MHWRR after long period shutdown.MethodsBased on the theoretical calculation and analysis of the residual photoneutron source intensity, the nuclear measurement blind area and the critical control rod height, a critical startup experiment scheme was put forward. The experiment was carried out in full accordance with the expectation of theoretical design in the absence of reference data, and nuclear power parameters were effectively monitored.ResultsThe measuring data range of startup monitoring devices are well connected with the original monitoring ionization chambers outside the reactor core, and the error between theoretical value of critical control rods position and experimental value is less than 0.84%.ConclusionsSuccessful critical startup and the agreement between the experimental results and the theoretical results show that the experiment technique for critical startup of MHWRR is reasonable and feasible.  
        关键词：MHWRR;Photoneutron;Criticality startup   
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      • “在先进核反应堆燃料元件领域，专家建立了环形燃料芯块一维稳态温度场计算模型，开发了PTFA程序，为热工水力计算分析提供解决方案。”
        MA Huiqiang,YU Tao,CHEN Zhenping,ZHAO Pengcheng,XIE Jinsen,LIU Zijing,LIU Jianxing,LEI Zhouyang,HE Qingling
        Vol. 43, Issue 6, Article number: 060603(2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.060603
        摘要：BackgroundThe annular fuel pellet has a lower operating temperature, which can achieve higher power density, and has become one of the development directions of the advanced nuclear reactor fuel elements. The method of temperature field solution of rod fuel pellets can not solve the temperature field of annular fuel pellets due to the flow distribution and heat distribution problems in the double-sided cooling annular fuel elements.PurposeThis study aims to calculate one-dimensional steady temperature field of the annular fuel core block.MethodsBased on the thermal conductivity differential equation and Fourier law, a one-dimensional steady-state temperature field calculation model of annular fuel core block was established. Computational program of temperature field of annular fuel pellets (PTFA) was developed to calculate the position of the adiabatic surfaces, the maximum temperature of the adiabatic surfaces and the temperature field of the annular core block by using the equivalence of the boundary conditions. Results of the insulation surface position, maximum temperature and temperature field distribution of annular fuel pellets under different pellets thickness and different power densities were obtained. Finally, the finite element program COMSOL5.4 was employed to verify these results.ResultsThe verification results show that the results calculated by the one-dimensional steady-state temperature field calculation model are in good agreement with those of the finite element method, and the relative deviation is less than 0.2%.ConclusionsThe model can be used for thermal-hydraulic calculation and analysis of annular fuel elements.  
        关键词：Annular fuel pellets;Temperature field;Steady heat conduction   
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