最新刊期
      卷 47 ， 期 5 ， 2024

        Special Issue of Controlled Nuclear Fusion Power Engineering Technology

      • “在托卡马克装置辅助加热领域，中国环流三号拟安装6 MW ICRF加热系统。研究显示，ICRF频率和功率对聚变中子产额有显著影响，30 MHz的ICRF对中子产额增加最显著。中子相机能有效测量ICRF加热导致的中子产额变化，为优化中子相机诊断系统设计提供参考。”
        YANG Guanming,HAO Guangzhou,LU Lingfeng,DONG Guanqi,HAO Baolong,WANG Shuo
        Vol. 47, Issue 5, Article number: 050001(2024) DOI: 10.11889/j.0253-3219.2024.hjs.47.050001
        摘要：BackgroundIon cyclotron range of frequencies (ICRF) heating is one of the most widely used auxiliary heating methods in tokamaks. The HL-3 tokamak plans to equip a 6 MW ICRF heating system to conduct discharge experiments of high-performance plasma.PurposeThis study optimizes the parameters of ICRF using numerical simulations with the purpose of supporting the reactor-level plasma in HL-3 in future.MethodsOn the basis of NBI heating in the HL-3 device, ICRF heating was considered, and the TRANSP code was employed to explore the influence of ICRF frequency and power in HL-3 on the neutron emission rate, as well as the distribution of fast ions. The ICRF frequency range was between 25 MHz and 40 MHz, and the ICRF power range was between 1 MW and 6 MW. The neutron signals based on the concept of neutron camera diagnosis were also simulated.ResultsThe simulation results show that the ICRF frequency and power significantly influence the neutron emission rate. The neutron emission rate is directly proportional to the ICRF heating power at a fixed ICRF frequency whilst the increase in the neutron emission rate significantly depends on the ICRF frequency when the ICRF heating power is fixed. Among the investigated parameters, the ICRF with a frequency of 30 MHz yields the maximum increase in the neutron emission rate. The simulation results of fast ions demonstrate that the synergetic heating of neutral beam injection and ICRF can heat fast ions up to 1 MeV after considering ICRF heating, which effectively increases the neutron emission rate. The simulation results of neutron camera indicate that neutron camera can effectively measure the changes in neutron emission rate and distribution profile caused by ICRF heating.ConclusionsThe simulation results demonstrate that the appropriate selection of the ICRF frequency and power can effectively increase the neutron emission rate in HL-3 experiments, the optimal combination of ICRF frequency/power is 30 MHz/6 MW for the scenario analyzed in this study. The simulation of neutron camera for HL-3 provides a reference for designing future neutron camera systems and measuring neutron spatial distributions.  
        关键词：Ion cyclotron range of frequencies;Fusion neutrons;Fast ions;HL-3 tokamak   
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        发布时间：2024-12-06
      • “在磁约束聚变领域，我国HL-2M托卡马克装置实现1MA高参数运行，采用GTC程序研究其内部输运垒湍流输运，发现ITB湍流输运呈现两次连续饱和过程，为聚变等离子体约束提供新见解。”
        XIAO Zhengyao,LI Xinxia,WANG Sen
        Vol. 47, Issue 5, Article number: 050002(2024) DOI: 10.11889/j.0253-3219.2024.hjs.47.050002
        摘要：BackgroundHL-2M tokamak is a new-generation magnetic confinement fusion plasma device in China, which has realized the high parameter operation mode with 1 MA plasma current.PurposeThis study aims to investigate the turbulent transport associated with the internal transport barrier (ITB) using gyrokinetic calculations.MethodsNumerical simulation was performed based on the gyrokinetic theory. The turbulent transport relevant to ITB was studied using the gyrokinetic toroidal code (GTC) combined with the equilibrium of HL-2M tokamak. A filtering zonal flow was considered in analyzing the influence of zonal flow on turbulent saturation level. A time evolution analysis of turbulent poloidal spectrum was conducted to investigate the effect of different wavelength modes on turbulent transport.ResultsThe results show that the turbulent transport at ITB saturates twice in succession, and the calculated average ion heat transport diffusivity is approximately twice that of the first saturation level. Moreover, the short-wave mode kθρi~2.15 dominates the first turbulent transport saturation, whereas the long-wave mode kθρi~0.49 dominates the second turbulent transport saturation. Specifically, an "M" shape distribution of the radial heat transport diffusivities is obtained at the transport barrier position during the turbulent saturation period. Finally, the minimum radial heat transport diffusivity during the turbulent saturation period occurs near the ITB where a maximum plasma temperature and density gradient occurs.ConclusionsThe turbulent transport at ITB may be dominated by two types of microinstabilities at different stages of turbulence development. Turbulent energy of the system is inversely cascaded from the modes with short wavelengths to those with long-wavelengths. The results are in good agreement with the theoretical prediction of the ITB.  
        关键词：Tokamak;HL-2M device;Turbulence simulation of GTC;Microinstabilities   
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        发布时间：2024-12-06
      • “在托卡马克中，快电子损失行为研究取得进展，模拟揭示了闪烁体探头发光特性，为理解EAST实验中快电子损失信号提供基础。”
        WANG Kewen,HUANG Juan,CHANG Jiafeng,ZHOU Ruijie
        Vol. 47, Issue 5, Article number: 050003(2024) DOI: 10.11889/j.0253-3219.2024.hjs.47.050003
        摘要：BackgroundIn a tokamak, when fast electrons are deconfined by the tokamak magnetic field constraint and lost to the vacuum wall or limiter, the device may become damaged and the discharge may be affected.PurposeThis study aims to explore the loss behavior of fast electrons during discharge using a diagnostic system based on a ZnS(Ag) scintillator probe for detecting the loss of fast electrons on the Experimental Advanced Superconducting Tokamak (EAST).MethodsThe Geant4 simulation program was employed to simulate the interaction between electrons in different initial states and the scintillator probe of the diagnostic system. Firstly, the probe model and the filling material model of stainless steel and ZnS(Ag) coating were established in Geant4. Then, the interaction between electron beam and scintillator probe under different incident conditions (incident energy, angle, scintillator thickness, magnetic field size, etc.) were simulated, and the physical processes were recorded. Finally, the recorded data were accessed by MATLAB programming for analysis.ResultsThe results show that the contribution of secondary electrons and initial electrons to the luminescence intensity of scintillators occupies different dominant energy ranges. The luminescence intensity first increases and then decreases with the increase of incident electron energy, with a peak value around 12 MeV, and the number of emitted photons at oblique incidence is greater than that at vertical incidence. When the electron energy is lower than 4.3 MeV, secondary particles dominate the scintillation, and when the electron energy is higher than 4.3 MeV, primary particles dominate. The thickness of the scintillator has no significant effect on the peak position. After, the luminous intensity is considerably affected by the magnetic field angle and electron pitch angle after adding a magnetic field.ConclusionsThe results of this study contribute to the understanding of the fast electron loss signal detected by the scintillator probe in the EAST experiments, providing a basis for further study of fast electron loss.  
        关键词：Tokamak;Scintillator;GEANT4;Fast electron   
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        发布时间：2024-12-06
      • “在射频波驱动负离子源领域，专家设计了基于光电二极管的等离子体发光监测系统，实现了对等离子体放电状态的实时监测和参数定量分析，为未来中性束注入系统提供技术支撑。”
        LI Yufan,YANG Puqiong,WEI Jianglong,LIU Bo,PENG Xufeng,YANG Yuwen,LI Yuqian,XIE Yuanlai
        Vol. 47, Issue 5, Article number: 050004(2024) DOI: 10.11889/j.0253-3219.2024.hjs.47.050004
        摘要：BackgroundNegative ion sources driven by radio frequency (RF) waves have become the preferred solution for future neutral beam injection systems.PurposeThis study aims to monitor the plasma discharge state of each exciter of a high power RF negative ion source by developing a plasma luminescence monitoring system based on a photodiode is designed and constructed.MethodsThe intensity of plasma emission was closely related to the number of specific collisions, collision particle density, and collision particle energy. Therefore, the intensity of plasma emission was applied to monitoring plasma parameters qualitatively, and a photodiode-based multichannel plasma luminescence monitoring system was designed and implemented to monitor the plasma discharge state of each exciter of a high power RF negative ion source. Based on a reasonable collision radiation model, plasma parameters were quantitatively obtained by analyzing the intensity of plasma characteristic spectral lines, and the influence of the filtering magnetic field generated by plasma current on plasma emission signals as experimental tested.ResultsExperimental results this monitoring system demonstrate that the real-time intensity information of plasma emission from different positions is successfully collected, and subsequently presented and saved in the form of voltage signals for real-time monitoring and post-data processing by the host computer. The intensity of plasma emission has a good linearity with RF discharge power.ConclusionsThe plasma light monitoring system of this study can accurately and real-time measure the excitation, maintenance, and extinction processes of plasma in the RF exciter.  
        关键词：Negative ion source;Neutral beam injection;Plasma spectral diagnosis;Photodiode   
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        发布时间：2024-12-06
      • “聚变堆气态氚排放对环境影响研究，计算了聚变堆1g氚短期释放对公众辐射剂量，为聚变堆环境辐射效应研究提供解决方案。”
        ZUO Qingning,HUANG Jingyun,ZHANG Junnan,WANG Xiaoliang,BAI Xiaoping,WEI Qiming
        Vol. 47, Issue 5, Article number: 050005(2024) DOI: 10.11889/j.0253-3219.2024.hjs.47.050005
        摘要：BackgroundThe amount of gaseous tritium stored and released in fusion reactor is higher than that in current fission reactors, so that tritium is an important source of potential radioactivity in fusion reactor.PurposeThis study aims to investigate the environmental impact of gas tritium emission from fusion reactor for achieving the safety and environmental friendliness of fusion reactor in the future.MethodsTypical factory sites along the eastern coast of China with the highest frequency east wind direction was selected as the research object, and the Gauss model was employed to predict the atmospheric dispersion of gaseous tritium release and the dry deposition of tritium gas (HT), soil oxidation and re-evaporation of HTO. The radiation dose of 1 g HT in the case of short-term released from fusion reactor to the public in the surrounding environment was calculated.ResultsCalculation results show that the effective dose of inhalation internal irradiation of HT released at 10 m height for adults at 500~3 000 m west of the release point ranges from 0.38 mSv to 0.1 mSv. The dose caused by the re-evaporation effect of HTO at different distances is the main source of the dose of gaseous tritium. The proportion of the HT deposited to soil being oxidized to HTO and the atmosphere condition are the key parameter determining the effective dose of the tritium gas.ConclusionsThe study shows that the effective dose of HT released from fusion reactor to public is higher than which released from fission reactor, hence further attention to the environmental impact of the tritium is needed in the research on the fusion reactor subsequently.  
        关键词：Fusion reactor;tritium gas;atmosphere dispersion;revaporization;Effective dose   
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      • “在国际热核聚变实验堆安全运行领域，专家基于HL-2A托卡马克实验，使用MARS-F/K程序计算等离子体对共振磁扰动的漂移动理学响应，为控制边缘局域模提供解决方案。”
        LIU Yihuizi,ZHANG Neng,LIU Yueqiang,GONG Xueyu,WANG Shuo,LI Chunyu,WANG Lian,HAO Guangzhou
        Vol. 47, Issue 5, Article number: 050006(2024) DOI: 10.11889/j.0253-3219.2024.hjs.47.050006
        摘要：BackgroundThe control of edge localized modes (ELMs) is a key issue for the safety operation of ITER and future magnetic confinement fusion reactors. In recent years, extensive theoretical simulations and experimental studies have demonstrated that resonant magnetic perturbation (RMP) is a promising method for controlling edge localized modes (ELMs) in H-mode plasmas.PurposeThis study aims to investigate drift kinetic resonant effects of thermal particles on the plasma response to the applied RMP and compare with that of the fluid model for better understanding of ELMs control in HL-2A.MethodsBased on experimental plasma and RMP coil configurations in HL-2A, the MARS-F/K codes were employed to compute the drift dynamic response of plasma to RMP under high constraint mode and compared it with the results of fluid model. Further sensitivity studies were conducted on key parameters including the plasma equilibrium pressure, toroidal flow as well as the thermal particle collision effects.ResultsThe fluid response model predicts an initially relatively weak enhancement of the plasma response amplitude with the equilibrium pressure parameter βN, followed by a strong variation as βN approaches the Troyon no-wall beta limit. The latter is unphysical and is eliminated by the kinetic response model. Including kinetic response and considering particle collision, the non-adiabatic resonant contribution of trapped thermal ions is found to be significant. Neglecting the particle collision, however, the trapped thermal electron contribution becomes more pronounced.ConclusionsThe importance of considering kinetic effects for high-beta plasma response is emphasized by this study. It is important to include the non-adiabatic resonant contribution of trapped particles to the kinetic response while taking into account the particle collision effect.  
        关键词：Resonant magnetic perturbation;Edge localized modes;Plasma response;Kinetic effects   
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      • “在聚变反应堆领域，专家基于cosRMC程序开发了内耦合输运-活化计算功能，为屏蔽设计和辐射安全分析提供解决方案。”
        WANG Shengzhe,LIU Shichang,CHEN Yixue
        Vol. 47, Issue 5, Article number: 050007(2024) DOI: 10.11889/j.0253-3219.2024.hjs.47.050007
        摘要：BackgroundWhen fusion nuclear reactor is in operation, neutron activation causes a large number of radioisotopes. Activation calculation is a very important step in both of reactor shielding calculation and radiation safety analysis.PurposeThis study aims to develop the capability of transport-activation coupling calculation for fusion reactor based on the Monte Carlo code cosRMC.MethodsFirstly, the built-in burnup solver "Depth" of cosRMC was employed to develop transport-activation internal coupling calculation function under fixed source mode with embedded calculation of activation related nuclide single group reaction cross-sections in neutron transport process without the transmission of neutron spectra to external activation programs. Then, the developed code was applied to the activation calculations of the first wall (FW) material steel and plasma facing component (PFC) material tungsten of the Chinese Fusion Engineering Testing Reactor (CFETR) using continuous energy cross-sections and multi group cross-sections, respectively, and calculated results were compared and verified with that of the activation program ALARA.ResultsThe comparison results of activation calculation of FW steel and PFC tungsten in CFETR show the consistency between cosRMC-based internal coupling method and ALARA program, which preliminarily verifies the correctness of the transport activation internal coupling calculation function of the developed cosRMC program.ConclusionThe developed cosRMC-based internal coupling method can dynamically update neutron spectra and material information, and use continuous energy cross-sections for reaction rate calculation, obtaining reaction cross-sections related to the geometry and energy spectra of actual problems, thus accurately considering the influence of resonance zone nuclear cross-sections.  
        关键词：Activation calculation;Fusion reactor;Fixed source mode;ALARA;cosRMC   
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      • “在聚变堆屏蔽计算领域，专家通过模拟实验验证了cosRMC程序的准确性，为聚变堆屏蔽计算提供解决方案。”
        CHE Rui,LIU Shichang,TIAN Zhuo,CHEN Yixue
        Vol. 47, Issue 5, Article number: 050008(2024) DOI: 10.11889/j.0253-3219.2024.hjs.47.050008
        摘要：BackgroundFusion reactors have the characteristics of high neutron energy, large spatial scales, complex geometric structures, and large radiation attenuation gradients, which make nuclear design and analysis more challenging.PurposeThis study aims to verify the accuracy of the calculation of Monte Carlo code cosRMC on the material shielding effect in fusion reactor applications.MethodsTwo deep penetration benchmarks, i.e., FNS-Duct (Fusion Neutron Source Dogleg Duct Streaming) and FNS-W (FNS Clean Experiment on Tungsten Cylindrical Assembly) from the Shielding Integral Benchmark Archive Database (SINBAD), were taken for simulation study of the penetration behaviors of neutrons in models under different geometric shapes and materials. First of all, detailed cosRMC models was established based on benchmark experimental models, neutron flux spectra of detectors at different penetration depths in benchmark experiments were calculated using cosRMC. Then, the variance reduction technique of cell importance was applied to improving the accuracy of cosRMC in calculating deep penetration problems. Finally, neutron flux spectra calculated by cosRMC were compared with those calculated by MCNP5, as well as the experimental results of the benchmarks.ResultsThe comparison results show that the calculations of cosRMC conform to that of MCNP5 with relative deviations of less than three times the standard errors. Both calculation results match well with the experimental values.ConclusionsThe study verifies that cosRMC can be applied to shielding calculations of fusion reactors.  
        关键词：Fusion benchmark;Shielding calculation;SINBAD;cosRMC   
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      • “在航天推进系统领域，专家基于磁流体力学方程，探究了阳极半径对磁等离子体动力推进器效率的影响，为提升推进器效率提供有效手段。”
        TANG Zhuoyao,ZHENG Jinxing,LIU Haiyang,LU Yudong,DU Yifan,KE Maolin,WANG Luoqi,WU Meiqi,WU Tao,SHI Jiaming
        Vol. 47, Issue 5, Article number: 050009(2024) DOI: 10.11889/j.0253-3219.2024.hjs.47.050009
        摘要：BackgroundWith the development of human aerospace industry, it is necessary to develop propulsion systems suitable for different space mission scenarios. MegnetoPlasmaDynamic thruster (MPDT), which is similar to the principle of magnetic confinement fusion, is a typical representative of electromagnetic thruster, which stands out among many electric thrusters because of its superior performance in thrust power ratio and specific impulse. Anode power deposition is the result of the interaction between plasma and wall during MPDT operation. It is one of the main mechanisms of power loss of this type of thruster, accounting for 40%~90% of the total power, which seriously reduces the efficiency of thruster.PurposeThis study aims to solve the problem of low efficiency of thruster by investigating the influence of anode radius on the efficiency of thruster from the perspective of anode power deposition.MethodsFirst of all, based on MagnetoHydroDynamic (MHD) equations, numerical models for radial discharge parameters and physical model for anode power deposition were established. Then, the influences of anode radius on discharge parameters, anode power deposition and anode power deposition fraction were studied on the basis of these models by numerical calculation method. Finally, a water-cooled structure anode was designed, and the effectiveness of its heat dissipation structure was verified by thermal simulation.ResultsThe results show that with the increase of anode radius, the electron density and ion velocity are increased, the anode power deposition fraction is decreased whilst the anode power deposition is increased. The thruster efficiency is improved by increasing the anode radius. The thermal simulation results show that when the input power deposition of the water-cooled structure anode is about 3 kW, the corresponding temperature difference of the anode cooling water is 5 K.ConclusionsThis study verifies the reliability of the physical model of anode power deposition, indicating that increasing the anode radius is an effective means to improve the efficiency of the thruster.  
        关键词：MegnetoPlasmaDynamic thruster;Anode power deposition;Numerical calculation;Thermal simulation;MagnetoHydroDynamic   
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      • “在空间任务领域，高功率霍尔效应电推进器推力测量难题获突破，为航天器控制精度提供保障。”
        WANG Luoqi,ZHENG Jinxing,LIU Haiyang,LI Fei,MENG Dongdong,LU Yudong,DU Yifan,TANG Zhuoyao,WU Tao,SHI Jiaming
        Vol. 47, Issue 5, Article number: 050010(2024) DOI: 10.11889/j.0253-3219.2024.hjs.47.050010
        摘要：BackgroundElectric propulsion systems, compared to traditional chemical propulsion, offer longer operational lifespans and lower fuel consumption in space missions, garnering significant attention in recent years. However, for high-power Hall effect electric thrusters developed based on controlled fusion concepts, measuring thrust proves challenging due to the high-temperature environments required for ionizing propellants in electric thruster, resulting in the generation of hot plasma plumes during operation. As a result, traditional thrust measurement methods are unable to accurately measure the thrust.PurposeThis study aims to accurately measure thrust during ground testing of electric thrusters for precise control of the spacecraft's attitude and orbit maintenance.MethodsFirstly, a thrust measurement platform based on flexible beam structure was designed and implemented with capability of measuring the thrust generated by electric thrusters in high-temperature. Simultaneously, a calibration system was built to verify the stability and repeatability of the thrust measurement results. Then, simulation analysis was conducted on the structural mechanics and thermal coupling field of the thrust measurement system under different operating conditions. Finally, the variable specific impulse magnetoplasma rocket (VASIMR) was taken for experimental thrust measurement of its electric propulsion system.ResultsThe experimental results of VASIMR indicate the thrust is 266.5 mN measured in real time at the central magnetic field intensity of 0.2 T with a mass flow rate of 20 mg∙s-1.ConclusionsThe thrust measurement platform based on the bending beam structure can meet the measurement requirements of VASIMR, providing valuable references for subsequent experiments.  
        关键词：Electric thrusters;Controlled nuclear fusion;Plasma;Flexible beam;Thrust measurement   
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      • “在磁约束聚变实验中，中国环流三号托卡马克计划建造3条中性束注入加热系统，总功率达20 MW。7 MW中性束注入器设计完成，优化了束传输效率。”
        YANG Xianfu,WEI Huiling,WAN Yinxiang,ZHOU Bowen,YU Peixuan,LUO Huaiyu,ZHOU Hongxia,TANG Peiqin,GENG Shaofei
        Vol. 47, Issue 5, Article number: 050011(2024) DOI: 10.11889/j.0253-3219.2024.hjs.47.050011
        摘要：BackgroundNeutral beam injection heating is a very effective auxiliary heating method in magnetic confinement fusion experiment. The built 5 MW neutral beam injection plays an important role in the H-mode operation with 1 MA plasma current of HL-3 tokamak. In order to achieve the H-mode operation with 2.5 MA, three neutral beam injection heating systems will be constructed with a total heating power of 20 MW.PurposeThis study aims to investigate the transmission efficiency of 7 MW neutral beam injector designed for HL-3 tokamak.MethodsThe beam transmission efficiency was studied from two aspects of neutralization efficiency and power deposition. The initial target thickness of the neutralizer under two beam parameters was analyzed based on Monte Carlo method. The optimal neutralization efficiency was achieved by adding neutralizer gas supply, and the target thickness required for the optimal neutralization efficiency was given. Finally, power deposition method was employed to analyze the transmission performance of the two neutral beams with different parameters at different beam divergence angles.ResultsThe results show that the optimal neutralizer efficiency is achieved when the neutralizer gas supply is 0.6 Pa∙m3∙s-1 and 1.1 Pa∙m3∙s-1, respectively. The neutral beam power obtained under two beam parameters with a divergence angle of 1.2° is 7.2 MW and 6.8 MW, respectively, and the corresponding transmission efficiency is 0.4 and 0.35, respectively.ConclusionsThe new neutral beam injector of HL-3 tokamak will be built according to the design of this study, with optimized parameter of 100 kV/45 A, while still retaining the ability to deliver a 120 keV deuterium beam.  
        关键词：Neutral beam injection;Transmission efficiency;Neutralization efficiency;Divergence angle;Power density   
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      • “在托克马克装置中性束注入器中，量热靶承担接收和测量束功率任务，利用内置热电偶阵列实时监测靶板温升，获得引出离子束或中性束的功率密度分布。HL-3装置二号中性束注入束线上，设计了一种量热靶，利用直线推杆机构实现升降，并采用“W”字型靶板结构实现中性束能量吸收。通过Ansys Workbench流体计算模块模拟计算，量热靶设计满足满功率运行要求，为工程设计提供参考。”
        ZHOU Bowen,TANG Peiqin,WAN Yinxiang,YU Peixuan,LUO Huaiyu,WEI Huiling,GENG Shaofei
        Vol. 47, Issue 5, Article number: 050012(2024) DOI: 10.11889/j.0253-3219.2024.hjs.47.050012
        摘要：BackgroundIn neutral beam injectors (NBIs) of Tokamak device, the calorimetric target is one of the most important water-cooled components, responsible for receiving and measuring beam power. In addition, by using a built-in thermocouple array, the temperature rise at different positions of the target plate can be monitored in real-time, thereby obtaining the power density distribution of the extracted ion beam or neutral beam.PurposeThis study aims to develop a calorimetric target for the neutral beam injector in the HL-3 device, which can meet the requirements of target plate lifting and thermal load absorption.MethodsA linear push rod mechanism was applied to the design of the calorimetry target to achieve lifting and lowering, and a "W" - shaped target plate structure was adopted to achieve absorption of neutral beam energy. According to the design parameters, the fluid calculation module of Ansys Workbench was employed to simulate the temperature distribution of the calorimetry target under full power operation.ResultsCalculation results show that the maximum temperature rise of the calorimetry target is 526.4 ºC when the deflecting magnet is opened under full power operating conditions, and the temperature can be lowered to room temperature within 30 s, satisfying the requirements for the use of the beam line.ConclusionsThe successfully developed calorimetric target of this study meets application requirements on second neutral beam injection beamline of HL-3 device, providing references for further engineering design of calorimetric targets in other NBIs.  
        关键词：Neutral beam injectors;Calorimetric target;Finite element calculation   
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      • “新奥科技发展有限公司升级EXL-50U装置，设计高参数磁场电源，提升电源能力，制定保护策略，验证电源可靠性与可控性。”
        CHEN Junhong,WU Yi,WANG Yingqiao,LI Weibin,CHEN Yuhong,WANG Yali,ZHANG Xiaopeng,ZHENG Xue,ZHANG Chunguang,XUAN Weimin,YAO Lieying,TAN Hao,LUO Wenwu,ZHOU Peihai,SONG Xianming,LIU Shaoxuan,SUN Zequn,CONG Zijian,YANG Enwu,GE Xingxin,GAO Xiang
        Vol. 47, Issue 5, Article number: 050013(2024) DOI: 10.11889/j.0253-3219.2024.hjs.47.050013
        摘要：BackgroundENN Science and Technology Development Co., Ltd. (ENN Fusion Technology R&D Center) is upgrading its compact fusion research facility EXL-50 to EXL-50U. Both devices are the conventional conductor tokamak, on which the magnet power supply system is composed by 1 TF (Toroidal Field) power supply, 1 CS (Center Solenoid) power supply and 10 PF (Poloidal Field) power supplies PF1-10. All 12 sets of power supply system are powered by 2 AC pulse generators and output DC current through thyristor-based converters.PurposeThis study aims to design EXL-50U magnet power supply for satisfying high parameter requirements of EXL-50U.MethodsPower supply capacity was the first concern for upgrading and the corresponding protection strategies under high parameter conditions was taken into account as well. The configuration of AC pulse generator was introduced at the beginning. Then transformers and converters were listed and designed in scheme. Control system and protection process were implemented respectively, followed by detail power supply system illustration and commissioning waveforms display for each power supply.ResultsThe reliability and controllability of developed power supply system are verified by the waveforms that forms plasma current under the condition of CS breakdown.ConclusionIt is proved that this power supply system can work stably, and output waveforms can be repeated no matter it works alone or under complex condition of joint debugging.  
        关键词：EXL-50U;Spherical tokamak;Magnetic field coils power supply system;Motor generator;Thyristor converter   
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      • “据最新研究，中国聚变工程实验堆CFETR核聚变发电厂可利用储热技术解决热功率输出不稳定问题。研究对比了多种储热技术，发现熔融盐储热技术、相变储热技术、固相显热储热技术具有应用潜力。其中，相变储热成本最低，有望成为未来研究重点。”
        LUO Haodong,LIN Yan,LI Bin,XIANG Kui,ZHU Guangtao,ZENG Tao
        Vol. 47, Issue 5, Article number: 050014(2024) DOI: 10.11889/j.0253-3219.2024.hjs.47.050014
        摘要：BackgroundDue to its pollution-free nature and non consumption of fossil fuels, nuclear fusion is the most ideal future energy source. China is preparing to build a China Fusion Engineering Test Reactor (CFETR) with independent intellectual property rights, and plans to build a commercial thermonuclear fusion power plant that can generate electricity externally by the mid-20th century. However, there is contradiction between the instability of nuclear fusion heating power output and the smooth operation of steam turbine generators, hence thermal storage technology is used for peak shaving and valley smoothing of power output in nuclear fusion reactors.PurposeThis study aims to compare heat storage technologies applied to CFETR nuclear fusion power plants to reduce its the peak and valley power output.MethodsThe parameters of helium cooled ceramic breeder cladding in nuclear fusion reactors was selected as the boundary conditions for thermal storage technology. By evaluated the applicable temperature range of thermal storage technology, three potential thermal storage technologies, i.e., chemical heat storage, sensible heat storage technology and phase change heat storage, for CFETR nuclear fusion power plants were preliminarily analyzed, and their costs were preliminarily predicted.ResultsThe three major types of heat storage technologies can all select heat storage media suitable for the temperature parameters of the helium cooled breeder blanket in CFETR nuclear fusion power plants. However, chemical heat storage has the potential to be applied in CFETR nuclear fusion power plants due to the temperature difference between its heat absorption and release, which is not conducive to the stability of the system and causes energy loss. Sensible heat storage technology and phase change heat storage technology have smaller temperature differences between their heat absorption and release. The preliminary economic analysis results show that the cost of phase change heat storage is the lowest, followed by molten salt heat storage, and the use of silicon bricks as the heat storage medium in solid-phase sensible heat storage technology. The use of cast steel as the heat storage medium in solid-phase sensible heat storage technology has the highest cost.ConclusionIn thermal storage technology, molten salt thermal storage technology has a high degree of maturity and has a large number of engineering applications, with a cost between phase change thermal storage and solid-phase sensible thermal storage, and has great potential for application. The cost of phase change heat storage is the lowest, and the parameters are suitable for nuclear fusion power generation. However, its technological maturity is relatively low, and it is expected to become a focus of future research.  
        关键词：Nuclear fusion;CFETR;Power generation technology;Energy storage;Heat storage;Economic analysis   
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      • “在电源故障诊断领域，研究者提出了抗噪声小波增强一维卷积神经网络的多分支降噪网络HBD-CNN，有效提高了噪声环境下的故障诊断准确率。”
        HANG Qin,ZHONG Lingpeng,LI Hua,ZHANG Heng
        Vol. 47, Issue 5, Article number: 050015(2024) DOI: 10.11889/j.0253-3219.2024.hjs.47.050015
        摘要：BackgroundData-driven methods for power fault diagnosis heavily rely on the signal data quality of power sensors. The power systems in Tokamak fusion devices often operate in environments with complex electromagnetic field coupling, leading to the mixing of physical characteristic signals with a significant amount of inseparable noise in the collected data.PurposeThis study aims to mitigate the impact of noise on the final diagnostic results by proposing a multi-branch denoising network, termed Hierarchy Branch Denoising Convolutional Neural Network (HBD-CNN) that utilizes noise-resistant wavelet enhancement in conjunction with one-dimensional convolutional neural networks to accomplish power system fault diagnosis tasks under the influence of noise interference.MethodsFirstly, the signal decomposition function of discrete wavelet transform (DWT) was incorporated into the network layer of the convolutional neural network (CNN), and the optimization of the traditional 1D-CNN network structure was deepened alongside the more robust exponentially linear unit (ELU) for noise. Then, a data multi-level structure was constructed based on prior knowledge to leverage and couple it with hierarchical classification modules within the network, hence the generalization capability of HBD-CNN was enhanced. Finally, preliminary validation of the architecture of this model was conducted based on the simulated power supply dataset.ResultsValidation results show that the fault diagnosis accuracy for the power converter reaches 98.31% when the signal-to-noise ratio (SNR) is 10 dB. Even at an SNR of 2 dB, the accuracy remains above 92%.ConclusionsThe results of this study indicate that HBD-CNN demonstrates excellent fault diagnosis performance and potential under noisy conditions.  
        关键词：Discrete wavelet transform;Power converter;Convolutional neural network;Fault diagnosis   
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      • “在托卡马克辅助加热领域，研究揭示了低杂波电流驱动效率受边界密度涨落影响，为提高加热效率提供新思路。”
        YANG Jinghe,DING Bojiang,WU Chenbin,LI Miaohui,WANG Mao,LIU Liang,YAN Guanghou
        Vol. 47, Issue 5, Article number: 050016(2024) DOI: 10.11889/j.0253-3219.2024.hjs.47.050016
        摘要：BackgroundLower hybrid current drive (LHCD) is one of the main auxiliary heating and current driving methods for Tokamak, and studies have shown that the boundary parasitics effect of lower hybrid (LH) wave in scrap-off layer (SOL) significantly decreases current drive efficiency of LH wave. Among these, wave scattering caused by density fluctuation at the boundary results in spectral changes within the SOL, which changes the power deposition location and current drive efficiency.PurposeThis study aims to explore the lower hybrid scattering caused by density fluctuation in the scrap-off layer on the Experimental Advanced Superconducting Tokamak (EAST) device.MethodsBased on the cold plasma dispersion theory and the blob density fluctuation theory, COMSOL Multiphysics was employed to establish a full-wave solution model of lower hybrid scattering in the SOL. Based on the parameters of the EAST device, the influence of low-frequency electron density fluctuation with different characteristics on wave scattering was analyzed.ResultsThe simulation results show that the backscattering direction caused by the density wave packet "blob" is more obvious than the forward scattering, and scattering induced by blob leads to the change of spatial structure of low hybrid power flow. The density fluctuation in the blob mainly affects the amplitude of the wave field disturbance, the radius of the blob mainly affects the spatial range of the wave scattering, the full-field disturbance caused by multiple blobs increases significantly.ConclusionsThe full-wave solution model of the SOL established in this study is reliable. The simulation results using this model show that the density fluctuation will cause lower hybrid scattering, which will change the spatial structure of the power flow.  
        关键词：Lower hybrid current drive;Wave scattering;Full wave solution;Scrap-off layer;Low-frequency density fluctuation   
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      • “在中性束注入加热系统领域，专家提出了基于超级电容储能的逆变型高压电源，实现了中性束调制注入功率的快速切换，为高压电源技术发展提供了新方向。”
        ZHANG Jintao,WANG Yingqiao,TANG Xian,XIA Yuyang,LI Qing
        Vol. 47, Issue 5, Article number: 050017(2024) DOI: 10.11889/j.0253-3219.2024.hjs.47.050017
        摘要：BackgroundThe high voltage power supply is an important part of the neutral beam injection heating system, which determines the beam energy and the quality of the extraction beam current. With the gradual increase of voltage level, the pulse step modulation (PSM) high voltage power supply cannot meet the experimental requirements.PurposeThis study aims to design an inverter high voltage power supply based on super capacitor energy storage to achieve fast switching of injected power for neutral beam modulation.MethodsSuper capacitor energy storage was adopted to reduce the required grid capacity and minimize the impact on the grid. The DC-DC resonant converter structure with soft-switching technology was used to improve the response speed of the power supply and reduce the switching loss of the switching devices. After the design of power module circuit topology,system modeling and calculation based on power supply performance specifications, the charging circuit and main loop PSIM simulation model were established, and the power supply performance indexes were simulated and verified. Finally, a test prototype of inverter power supply module was built to conduct the test of relevant performance indexes. [Results and Conclusions] After simulation and experimental verification, the power module is able to achieve a stable output of 1 600 V/50 A, which meets the design requirements of 6 MW/120 kV.  
        关键词：HL-3 device;Super capacitor;Neutral beam injection;Inverter high-voltage power supply;DC-DC resonant converter   
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      • “在核聚变领域，中国环流三号装置的电子回旋共振加热系统天线设计制造完成，实现了精确快速控制，为核聚变研究提供新方向。”
        ZHENG Wanxin,YE Jiruo,CHEN Gangyu,HUANG Mei
        Vol. 47, Issue 5, Article number: 050018(2024) DOI: 10.11889/j.0253-3219.2024.hjs.47.050018
        摘要：BackgroundElectron cyclotron resonance heating (ECRH) is an important heating and plasma current control method for the HL-3 tokamak. Microwave inject into plasma through the launcher, which is an important part of the ECRH system. The ECRH launcher system of HL-3 tokamak consists of three launchers, including a mid equatorial launcher and two upper launchers. All launchers are located in the same sector, and can work together to complete functions such as heating and Neoclassical Tearing Mode (NTM) control.PurposeThis study aims to design and test the ECRH launcher system of the HL-3 tokamak.MethodsFirst of all, the overall planning was carried out for the launcher system. Subsequently, the transmission path and structure of the launcher were designed, and the effect of microwave injection were calculated by simulation. Then, detail design and implementation for the mid-equatorial launcher and No.1 upper launcher were completed, so did the optical path design for No.2 upper launcher. Finally, the transmission angle and rotation speed of the launcher were tested, and the rotation angle of the launcher was calibrated.ResultsThe full range response time of the mid-equatorial launcher is less than 90 ms. The full range response time of the No.1 upper launcher is less than 190 ms.ConclusionsThe control of the equatorial launcher and the No.1 upper launcher is precise and fast, meeting the requirements for experimental use of the tokamak.  
        关键词：HL-3 tokamak;Launcher;ECRH   
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