HTR-10燃料元件装卸系统冷态调试

10MW高温气冷实验堆（HTR－10）是一座球床堆，由燃料元件装卸系统实现燃料元件的装卸和循环，且不需要停堆，为保证HTR－10的正常运行，燃料元件装卸系统必须安全，可靠，为此，必须对燃料元件装卸系统进行周密，细致的调试试验和验证，本文介绍了燃料元件装卸系统冷调试的主要调试项目，调试方法和调试结果。     

10MW高温气冷堆燃料元件装卸系统的控制系统设计

１０ＭＷ高温气冷实验堆（ＨＴＲ－１０）是一座球床型反应堆，燃料元件的装卸和循环不需要停堆，由燃料元件装卸系统自动实现。为保证ＨＴＲ－１０的正常运行，燃料元件装卸系统必须安全可靠运行。为此，控制系统根据ＨＴＲ－１０燃料装卸系统热实验装置控制系统的设计和运行经验，采用了欧姆龙（ＯＭＲＯＮ）Ｃ２００Ｈ可编程控制器（ＰＬＣ）作为核心部件。本文介绍了控制系统的设计方案、控制过程和ＰＬＣ控制的特点以及用其实现     

10 MW高温气冷实验堆燃料元件装卸系统研制

根据国际上类似系统的设计和运行经验，彻底改进了10MW高温气冷实验堆(HTR-10)燃料元件装卸系统的单列器、碎球分离器、提升器、控制系统，以使系统变得更为简单、可靠。改进后的设备均在全尺寸实验装置上进行过试验。系统的调试试验和初装料运行表明：该系统的性能满足HTR-10的要求。     

10MW高温气冷堆球形燃料元件虚拟仪器式探测系统的研制

介绍了一种基于虚拟仪器技术研铜开发的高温堆燃料元件探测系统，该系统有效地解决了10MW高温气冷堆燃料元件装卸过程中现场复杂过球信号的计数判断问题，很大程度地消除了外界干扰，保证了计数的准确性，方便地实现了整个系统的智能管理。     

基于控制Petri网的高温气冷堆燃料装卸过程控制系统设计方法

介绍了一种基于控制Petri网(CPN)的控制系统设计方法,通过将库所与输出和操作关联,将变迁与输入和条件关联,并引入了宏库所和宏操作,实现了对复杂控制系统的分层次设计.在分析燃料元件装卸系统(FHS)基本功能和装卸流程的基础上,利用CPN对其进行了分层设计.根据变迁的触发条件,设计的CPN可直接转换为PLC的LAD程序;该程序在FHS模拟控制系统试验台上进行了验证.应用结果表明,该方法具有设计结构清晰,描述严格准确,程序设计高效等优点,可以很好地满足球床式高温气冷堆(HTGR)燃料装卸过程控制系统的设计要求.     

HTR-10燃料球和石墨球反应性当量测量实验

10MW高温气冷实验堆（HTR－10）是球床型反应堆，燃料元件的装卸和循环可不停堆，为了保证其安全运行，必须准确地知道燃料元件的装卸和循环过程可能引起的反应性变化，尤其是向堆芯装料时引入的反应性变化，HTR－10首次临界后对燃料球和石墨球的反应性价值进行了测量，本文介绍了燃料球和石墨球反应性当量刻度的方法，给出了初始装载截芯和空气气氛下的燃料球和石墨球反应性当量实验测量结果。     

HTR-10燃料装卸控制系统的改进

为满足10MW高温气冷试验堆(HTR-10)长期运行的要求,对燃料装卸控制系统进行了改进.利用OMRON C200HS可编程控制器,完成了系统自动化流程的设计;在保留操作台结合模拟屏进行监控的基础上,使用FIX6.15组态软件,实现了监控方式的数字化.本次改进有效地提高了燃料装卸系统的工作效率和安全性.     

10 MW高温气冷堆燃料元件辐照后检验

为了评价10 MW高温气冷堆(HTR-10)用燃料元件的性能,从第1和第2生产批次中分别随机抽取两个球形燃料元件进行辐照考验.辐照考验在俄罗斯的IVV-2M堆内进行,采用动态辐照试验的方法,可分别控制每个辐照盒中燃料元件的温度和测量气态裂变产物的释放.辐照后检验包括外观检查、尺寸测量、固体裂变产物在基体石墨内的分布测量、包覆燃料颗粒破损率测量和金相观察.辐照后检验结果表明辐照没有引起燃料元件中包覆燃料颗粒的破损, 生产的燃料元件满足10 MW高温气冷堆的设计要求.     

板型燃料元件燃耗自动测量系统设计

现有的板型燃料元件的燃耗无损测量自动化水平较低,只适用于单点测量。结合板型燃料元件的结构特点及燃耗测量要求,设计板型燃料元件自动测量系统。自动测量系统集成了交互式测点规划、运动系统控制、γ能量谱仪控制、数据处理及结果可视化功能,实现了板型燃料元件多点、分段、自动化、无损燃耗测量。系统运行结果表明:该系统可靠性高,操作简单,能够有效地提高测量效率、精度,降低操作人员的工作量。     

HTR-10燃料元件的气体输送

为了保证高温气冷实验堆球形燃料元件可靠地输送，采用了传递管输送方法，本文介绍了10MW高温气冷堆（HTR－10）燃料元件气体输送系统的关键设备，管路设计及输送气体流量计算，通过初装料的运行，证明该系统运行良好。     

Challenges and Innovative Technologies On Fuel Handling Systems for Future Sodium-Cooled Fast Reactors

The reactor refuelling system provides the means of transporting, storing, and handling reactor core subassemblies. The system consists of the facilities and equipment needed to accomplish the scheduled refuelling operations. The choice of a FHS impacts directly on the general design of the reactor vessel (primary vessel, storage, and final cooling before going to reprocessing), its construction cost, and its availability factor. Fuel handling design must take into account various items and in particular operating strategies such as core design and management and core configuration. Moreover, the FHS will have to cope with safety assessments: a permanent cooling strategy to prevent fuel clad rupture, plus provisions to handle short-cooled fuel and criteria to ensure safety during handling. In addition, the handling and elimination of residual sodium must be investigated; it implies specific cleaning treatment to prevent chemical risks such as corrosion or excess hydrogen production. The objective of this study is to identify the challenges of a SFR fuel handling system. It will then present the range of technical options incorporating innovative technologies under development to answer the GENERATION IV SFR requirements.     

Design and full scale test of the fuel handling system

In the 10 MW High Temperature Gas-cooled Reactor-Test Module (HTR-10) fuel elements move through the core driven by gravity. To reach their design burn-up the fuel elements are re-shuttled five times. This transportation outside the core is mainly achieved pneumatically. Although, adopting the international experience at design and operation of similar systems some key components were improved so that the fuel handling system (FHS) becomes simpler and more reliable. The improved components were tested in full-scale testing facilities. The debugging test and the first loading operation for the FHS indicate that the FHS meets the demands of the HTR-10. In this paper, the functions, design parameters, technological processes, main components and design characteristics of the FHS are described in detail. The flow schemes, design parameters of the full-scale testing facilities and the experimental results are briefly introduced.     

320 kV全离子综合实验平台控制系统升级

本文对320 kV全离子综合实验平台的控制系统升级进行了研究。升级后的控制系统采用分布式系统模型构建。硬件采用串口服务器、PLC及伺服电机等部件实现了所有被控设备的远程监测及控制。软件通过建立EPICS IOC动态数据库,实现了对所有被控设备的集成。用户操作界面层采用CSS开发,实现了操作人员对所有被控设备的透明访问。该控制系统已成功连续运行约10 000 h。目前该控制系统运行稳定、可靠,完全满足320 kV全离子综合实验平台的运行及物理实验的需求。     

除氧器水位控制的人-机接口设计研究

基于人因工程（HFE）的设计原则,以核电厂二回路主给水除氧器系统为例进行性能需求分析,得到不同层次的静态功能数据库,确定了主给水除氧器系统运行所需的基本信息流及其处理要求。为应对核电厂冷态启动、低负荷和高负荷工况下的操作要求,通过建立给水加热和除氧功能（F01）模块图和运行模式表,明确与控制室有关的功能因素。基于功能分配原则对除氧器水位控制进行研究,实现水位控制的无扰动过渡方案,通过了人-机接口设计验证,为国内开展HFE分析研究提供借鉴。      

北京Q3D磁谱仪控制系统的研制

本文简要介绍了北京Ｑ３Ｄ磁谱仪的计算机算动控制系统的实现方法及工作原理。     

氢等离子体裂解煤制乙炔稳态控制系统的设计与实现

为实现2MW氢等离子体裂解煤制乙炔实验装置的安全稳态运行,提高乙炔收率,构建了一套功能完备的控制系统.系统中,采用分时间片方式完成了重要信号的长时间高速持续采集;利用积分分离控制算法改善控制效果,实现了稳态控制;将C/S与B/S模式结合,为本地及异地实验人员提供了快速、直观的数据支持.实验表明,系统具有良好的实时性、稳定性及可用性.     

Thermo-mechanical analysis of RMP coil system for EAST tokamak

Resonant magnetic perturbation (RMP) has been proved to be an efficient approach on edge localized modes (ELMs) control, resistive wall mode (RWM) control, and error field correction (EFC), RMP coil system under design in EAST tokamak will realize the above-mentioned multi-functions. This paper focuses on the thermo-mechanical analysis of EAST RMP coil system on the basis of sensitivity analysis, both normal and off-normal working conditions are considered. The most characteristic set of coil system is chosen with a complete modelling by means of three-dimensional (3D) finite element method, thermo-hydraulic and thermal-structural performances are investigated adequately, both locally and globally. The compromise is made between thermal performance and structural design requirements, and the results indicate that the optimized design is feasible and reasonable.     

反应堆控制棒驱动机构模拟负载系统的研制

介绍了反应堆控制棒驱动机构(CRDM)模拟负载装置的设计原理和方法,研制出了一种新型的模拟负载系统,用来模拟反应堆棒控系统对控制棒的控制过程。对设计的模拟负载系统进行了功能性试验和性能参数测试,并与实际运行系统进行比较后,发现该系统达到了各项功能控制要求,且性能稳定可靠,模拟负载的电磁线圈散热性能与负载特性良好,各项性能指标达到了设计要求。     

Progress on the ITER ECRH upper launcher steering mirror identification and control

The main objective of the ITER ECRH upper launcher (UL) is to control magnetohydrodynamic activity, in particular neoclassical tearing modes (NTMs), by driving several MW of EC current near the q = 1, 3/2, 2 flux surfaces, where NTMs are expected to occur.The steering of the EC power is done by the steering mechanism assembly (SMA) that comprises a reflecting mirror and a frictionless and backlash free pneumo-mechanical system actuated with pressurised helium gas. The control requirements for this component in terms of steering accuracy and speed are reviewed. With respect to these requirements, the performance of the first SMA prototype is assessed in a mock up of the UL pneumatic configuration.The expected design characteristics of the SMA have been verified and an overall satisfactory performance has been assessed. Furthermore, the main challenges for the future work, such as the pressure and angular position control, have been identified.