束剖面是CRAFT(Comprehensive Research Acility for Fusion Technology)负离子源中性束注入系统(Negative ion based neutral beam injection system,NNBI)引出束流的关键参数之一,其可以直接反映NNBI的运行状态,为NNBI装置的运行参数...束剖面是CRAFT(Comprehensive Research Acility for Fusion Technology)负离子源中性束注入系统(Negative ion based neutral beam injection system,NNBI)引出束流的关键参数之一,其可以直接反映NNBI的运行状态,为NNBI装置的运行参数调节提供依据。传统的基于热电偶的束流截止靶、一维碳纤维复合材料(Carbon Fibre Composite,CFC)红外诊断靶、钨丝诊断靶不能同时满足长脉冲(≥100 s)、高束功率(2~5MW)情况下高时间分辨率(ms级)的诊断要求。为了满足上述诊断要求,利用二次电子发射原理在功率测量靶后方采用半嵌入的方法安装分布式的探针阵列,并基于LabVIEW软件设计了一套实时信号采集单元,实现了NNBI MW级束流引出下的二次电子信号实时采集、数据存储和波形回放,利用MATLAB编程实现了数据处理和分析。结果表明,研发的系统能够满足NNBI束剖面诊断需求,实现了不同运行参数下的束剖面分析。展开更多
Phoebus作为实验物理与工业控制系统(Experimental Physics and Industrial Control System,EPICS)生态中的核心图形化开发工具,在大型科学装置控制系统开发中面临安全性挑战,其开放性访问机制缺乏细粒度权限控制,存在操作越界、误触操...Phoebus作为实验物理与工业控制系统(Experimental Physics and Industrial Control System,EPICS)生态中的核心图形化开发工具,在大型科学装置控制系统开发中面临安全性挑战,其开放性访问机制缺乏细粒度权限控制,存在操作越界、误触操作风险。本文针对Phoebus的安全访问权限功能缺陷,提出集成用户访问控制功能的解决方案:通过扩展控件属性模型,实现基于角色层级的权限约束;构建用户认证流程以绑定操作行为与责任主体;设计运行时动态鉴权机制确保权限策略执行的有效性。测试表明,该方案能有效隔离不同权限用户的操作范围,保障控件属性绑定与持久化的可靠性,显著提升了Phoebus在复杂实验环境中的安全性。展开更多
The EHL-2 spherical torus is designed to demonstrate proton-boron(p-11B)fusion within a compact spherical tokamak.Its planned heating system includes a negative ion-based neutral beam injection(N-NBI),two positive ion...The EHL-2 spherical torus is designed to demonstrate proton-boron(p-11B)fusion within a compact spherical tokamak.Its planned heating system includes a negative ion-based neutral beam injection(N-NBI),two positive ion-based NBI systems(P-NBI),electron cyclotron resonance heating(ECRH),ion cyclotron resonance heating(ICRH),and high harmonic fast wave(HHFW),with a total power output of 31 MW.According to scaling law estimates,the device is capable of achieving H-mode operation.The plasma density,,n_(e,min)at the minimum L-H power threshold,P_(lh),is estimated to be 4.4×10^(19)m^(-3).The pedestal parameters were calculated using the REPED model.Assuming B as the primary impurity ion,the predicted pedestal width and height are lower compared to the typical case with carbon impurities.The pedestal collisionality for EHL-2 is estimated to range between 0.06 and 0.17,indicating the potential for significant energy loss due to edge localized modes(ELMs).The heat flux on the divertor plate has been calculated using the JOREK code.The peak heat fluxes during ELM bursts are approximately 31.0 MW/m^(2)at the lower inboard target and 39.5 MW/m^(2)at the lower outboard target.A preliminary design of the resonant magnetic perturbation(RMP)coils has been completed to both control type-I ELMs and correct error fields.The system comprises 16 coils arranged into 24 pairs.In ELM control mode,a 14/2 component is generated at 1.7 G/kAt,with a current of 4.9 kA required to achieveσChirikow=1 at the resonant surface,where the normalized poloidal magnetic flux is 0.85.In error field(EF)modulation mode,2/1 and 3/1 components are generated at 3.5 G/kAt and 2.8 G/kAt,respectively.展开更多
This study analyzes fast ion losses in the EHL-2 fusion device,focusing on both beam ions and alpha particles as p-11B fusion reaction products.Using the Monte Carlo orbit-following code TGCO,we evaluate particle conf...This study analyzes fast ion losses in the EHL-2 fusion device,focusing on both beam ions and alpha particles as p-11B fusion reaction products.Using the Monte Carlo orbit-following code TGCO,we evaluate particle confinement under various operational scenarios,including co-injected tangential neutral beam injection at beam energies of 60 keV,80 keV,and 200 keV.Our simulations estimate the heat load driven by lost beam ions and find it to be within acceptable material limits for a plasma current on the order of mega-amperes.Additionally,we simulate the distribution of fusion products and observe a higher particle loss fraction for alpha particles compared to beam ions.However,due to the relatively low fusion power,these lost alpha particles are unlikely to significantly impact the plasma-facing materials.To assess the impact of the magnetic ripple,we compute the ripple field distribution by modelling the toroidal field(TF)coils as current filaments.The results indicate that the ripple field effect on particle confinement is minimal,primarily due to the large distance of over 1 m between the TF coils and the plasma on the low-field side.The analysis based on the test particle model is a foundational step in ensuring the basic safety aspects of the new device,which is essential for developing a robust design,optimizing performance,and maintaining safe operation.展开更多
文摘束剖面是CRAFT(Comprehensive Research Acility for Fusion Technology)负离子源中性束注入系统(Negative ion based neutral beam injection system,NNBI)引出束流的关键参数之一,其可以直接反映NNBI的运行状态,为NNBI装置的运行参数调节提供依据。传统的基于热电偶的束流截止靶、一维碳纤维复合材料(Carbon Fibre Composite,CFC)红外诊断靶、钨丝诊断靶不能同时满足长脉冲(≥100 s)、高束功率(2~5MW)情况下高时间分辨率(ms级)的诊断要求。为了满足上述诊断要求,利用二次电子发射原理在功率测量靶后方采用半嵌入的方法安装分布式的探针阵列,并基于LabVIEW软件设计了一套实时信号采集单元,实现了NNBI MW级束流引出下的二次电子信号实时采集、数据存储和波形回放,利用MATLAB编程实现了数据处理和分析。结果表明,研发的系统能够满足NNBI束剖面诊断需求,实现了不同运行参数下的束剖面分析。
文摘Phoebus作为实验物理与工业控制系统(Experimental Physics and Industrial Control System,EPICS)生态中的核心图形化开发工具,在大型科学装置控制系统开发中面临安全性挑战,其开放性访问机制缺乏细粒度权限控制,存在操作越界、误触操作风险。本文针对Phoebus的安全访问权限功能缺陷,提出集成用户访问控制功能的解决方案:通过扩展控件属性模型,实现基于角色层级的权限约束;构建用户认证流程以绑定操作行为与责任主体;设计运行时动态鉴权机制确保权限策略执行的有效性。测试表明,该方案能有效隔离不同权限用户的操作范围,保障控件属性绑定与持久化的可靠性,显著提升了Phoebus在复杂实验环境中的安全性。
基金the auspices of National Natural Science Foundations of China(Nos.12075284 and 12205157)supported by the High-End Talents Program of Hebei Province,Innovative Approaches towards Development of Carbon-Free Clean Fusion Energy(No.2021HBQZYCSB006).
文摘The EHL-2 spherical torus is designed to demonstrate proton-boron(p-11B)fusion within a compact spherical tokamak.Its planned heating system includes a negative ion-based neutral beam injection(N-NBI),two positive ion-based NBI systems(P-NBI),electron cyclotron resonance heating(ECRH),ion cyclotron resonance heating(ICRH),and high harmonic fast wave(HHFW),with a total power output of 31 MW.According to scaling law estimates,the device is capable of achieving H-mode operation.The plasma density,,n_(e,min)at the minimum L-H power threshold,P_(lh),is estimated to be 4.4×10^(19)m^(-3).The pedestal parameters were calculated using the REPED model.Assuming B as the primary impurity ion,the predicted pedestal width and height are lower compared to the typical case with carbon impurities.The pedestal collisionality for EHL-2 is estimated to range between 0.06 and 0.17,indicating the potential for significant energy loss due to edge localized modes(ELMs).The heat flux on the divertor plate has been calculated using the JOREK code.The peak heat fluxes during ELM bursts are approximately 31.0 MW/m^(2)at the lower inboard target and 39.5 MW/m^(2)at the lower outboard target.A preliminary design of the resonant magnetic perturbation(RMP)coils has been completed to both control type-I ELMs and correct error fields.The system comprises 16 coils arranged into 24 pairs.In ELM control mode,a 14/2 component is generated at 1.7 G/kAt,with a current of 4.9 kA required to achieveσChirikow=1 at the resonant surface,where the normalized poloidal magnetic flux is 0.85.In error field(EF)modulation mode,2/1 and 3/1 components are generated at 3.5 G/kAt and 2.8 G/kAt,respectively.
基金supported by ENN Group and ENN Energy Research Institute.
文摘This study analyzes fast ion losses in the EHL-2 fusion device,focusing on both beam ions and alpha particles as p-11B fusion reaction products.Using the Monte Carlo orbit-following code TGCO,we evaluate particle confinement under various operational scenarios,including co-injected tangential neutral beam injection at beam energies of 60 keV,80 keV,and 200 keV.Our simulations estimate the heat load driven by lost beam ions and find it to be within acceptable material limits for a plasma current on the order of mega-amperes.Additionally,we simulate the distribution of fusion products and observe a higher particle loss fraction for alpha particles compared to beam ions.However,due to the relatively low fusion power,these lost alpha particles are unlikely to significantly impact the plasma-facing materials.To assess the impact of the magnetic ripple,we compute the ripple field distribution by modelling the toroidal field(TF)coils as current filaments.The results indicate that the ripple field effect on particle confinement is minimal,primarily due to the large distance of over 1 m between the TF coils and the plasma on the low-field side.The analysis based on the test particle model is a foundational step in ensuring the basic safety aspects of the new device,which is essential for developing a robust design,optimizing performance,and maintaining safe operation.
