1OMW高温气冷实验堆氦气安全阀的设计与性能试验

10Mw高温气冷实验堆(HTR-10)一回路安全泄放系统安装了两台核一级氦气安全阀,对反应堆一回路进行超压保护,是保证HTR-10安全的重要设备之一.本文介绍了氦气安全阀的设计要求、结构特点及性能要求,并按相关规范要求对其性能进行了实验验证.结果表明,安全阀的性能满足设计要求.     

10MW高温气冷实验堆氦气安全阀的设计与性能试验

10MW高温气冷实验堆(HTR-10)一回路安全泄放系统安装了两台核一级氦气安全阀，对反应堆一回路进行超压保护，是保证HTR-10安全的重要设备之一。本文介绍了氦气安全阀的设计要求、结构特点及性能要求，并按相关规范要求对其性能进行了实验验证。结果表明，安全阀的性能满足设计要求。     

物项安全分级中的几个重要问题探讨

本文基于核动力厂物项（包括构筑物、系统和部件）安全分级的目的和意义，结合HAF102—2016《核动力厂设计安全规定》和IAEA导则文件SSG-30关于安全分级的要求，讨论了物项功能失效后果的分级原则，以及用于事故预防和缓解功能的物项在安全分级中的建议。此外，本文还分析了物项安全分级在核动力厂安全评价中的作用，探讨了不同级别物项的设计和建造要求的落实。     

HTR-10一回路放射性石墨粉尘实验系统设计及研究

在10MW高温气冷堆(HTR-10)氦净化系统中,设计并建造了用于取样收集一回路放射性石墨粉尘的实验系统。结合国外已有的研究结果,根据HTR-10氦净化系统的运行参数进行了模拟计算。计算结果表明,该实验系统能有效过滤收集到的放射性石墨粉尘。所设计的取样过滤器便于拆卸和后期测量,可实现对放射性石墨粉尘进行长期系统的研究,给出反应堆不同运行工况下一回路氦净化系统中石墨粉尘及固体裂变核素活度的信息,将为HTR-10高温气冷堆裂变产物行为研究提供大量重要的实验研究数据。     

国际原子能机构SSG-30安全分级方法应用解析

安全分级的目的是确保物项的设计、制造、建造、调试和运行采用恰当的要求,使物项在所有预期的运行工况下有适宜的质量,进而确保安全功能的实现。国际原子能机构（IAEA）2014年颁布的核电厂构筑物、系统和部件（SSC）安全分级导则（SSG-30）,其安全分级原则涵盖核电厂5个纵深防御层次,从设计预防措施和安全功能分类两个维度识别安全相关物项的重要性,考虑核电厂运行工况状态和放射性与运行限值的要求,进而确定物项的安全级别和相关的规范要求。      

10MW高温气冷实验堆运行许可证申请审评

根据现行核安全法规和导则的要求,在10 MW高温气冷实验堆运行许可证申请文件及定期安全审查报告审评过程中,对构筑物、系统和部件的设计及实际状态方面问题、安全分析方面问题、设备合格性管理方面问题、老化管理方面问题、调试和试运行情况、运行阶段质量保证大纲等进行了重点关注。此文着重叙述了对这些重点问题和方面的审评考虑。审评结果显示,这些重点问题和方面均按要求得到了适当的处理。     

HTR-10数字化保护系统的验证与确认

10MW高温气冷实验堆(HTR-10)验证与确认(VerificationandValidation,简称V&V)过程的特点是:和开发过程紧密配合,特别重视设计说明书的V&V、安全软件的V&V、系统功能的完整测试等环节。从而使数字化保护系统成功地通过安全审查并被批准应用于HTR-10上。     

HTR-10分散控制系统改造方案设计

10 MW高温气冷堆(HTR-10)的分散控制系统(DCS)执行对HTR-10的运行监测和控制功能.原DCS在设备可靠性、历史数据存储和转换等方面存在不足.根据HTR-10各工艺系统及控制对象的要求,分析了DCS的系统架构、功能和性能指标等;对I/O通道进行配置;提出以施耐德Quantum 67160系列产品为主要模件的多重冗余硬件平台以及分别以UNITY和iFIX作为系统软件平台和组态工具的配置方案;采用PTO模块完成对棒控和装卸料系统控制,使用智能仪表对交流采样方案进行改进,在通信网络中加设逻辑网关的办法实现第三方通信功能.该设计方案可有效解决HTR-10原DCS存在的问题,满足HTR-10对DCS的要求.     

HTR-10放射性石墨粉尘取样回路中过滤元件的效率研究

10MW高温气冷实验堆(HTR-10)中石墨构件摩擦磨损不可避免地会产生石墨粉尘,其上可吸附固体裂变核素,可能影响反应堆安全正常运行。为研究石墨粉尘的粒径分布、微观形貌以及其表面的吸附特性,在HTR-10一回路氦净化系统入口建造了配置高性能烧结金属粉末过滤元件的放射性石墨粉尘取样回路。为对放射性石墨粉尘的取样过滤结果进行研究,首先对过滤元件的过滤机理、压降特征以及过滤效率进行分析。设计并搭建实验装置对烧结金属粉末过滤元件的过滤效率进行测量,实验结果表明过滤元件能去除气流中的大部分粉尘,实现对HTR-10一回路氦气中放射性石墨粉尘等悬浮物的高效过滤取样。     

核电厂抗震系统的耦合性分析

核电厂设施是由构筑物、管系、设备和部件(SSCs)等组成的十分复杂的系统,抗震I类设施的抗震设计分析是在安全停堆地震(SSE)设计基准事故下确保核电厂安全的重要措施之一。为了将核电厂中复杂的构筑物、系统、部件的抗震分析开展得全面、可靠又深入,最有效和通用的方法是在抗震分析中将整个构筑物、系统、部件合理地分解成若干抗震主系统和子系统。本文从将主、子系统简化为二自由度的基本振动原理出发,论证主、子系统解耦的条件,证实了美国核管会安全分析报告标准审查大纲3.7.2中提出解耦条件的依据。同时又论证了耦合系统中将子系统独立解耦并进行抗震分析时所必须满足的必要条件。本文的结论可为核电厂抗震设计分析工程师以及安全评审人员提供一个重要的设计分析及评审依据。     

Safety functions and component classification for the HTR-10

In the design and construction of the HTR-10, the standards and criteria of design and manufacture for structures, systems and components must be defined. This paper refers to the relative nuclear safety codes to formulate the principles of safety classification and the relative requirements of design and manufacture, according to the safety philosophy and feature of the HTR-10, and the requirements for safety functions of structures, systems and components. We can find practical use and application meaning of this work in the design and manufacture of the HTR-10. It will be used to ensure the safety and reliability of the HTR-10.     

Possible design of PBR for passive decay heat removal

Conditions for design parameters of above-ground and underground, prismatic high-temperature gas-cooled reactor (HTGR)s for passive decay heat removal based on fundamental heat transfer mechanisms were obtained in the previous works. In the present study, analogous conditions were obtained for pebble bed reactors by performing the same procedure using the model for heat transfer in porous media of COMSOL 4.3a software, and the results were compared. For the power density profile, several approximated distributions together with original one throughout the 10-MWt high-temperature gas-cooled reactor-test module (HTR-10) were used, and it was found that an HTR-10 with a uniform power density profile has the higher safety margin than those with other profiles. In other words, the safety features of a PBR can be enhanced by flattening the power density profile. We also found that a prismatic HTGR with a uniform power density profile throughout the core has a greater safety margin than a PBR with the same design characteristics. However, when the power density profile is not flattened during the operation, the PBR with the linear power density profile has more safety margin than the prismatic HTGR with the same design parameters and with the power density profile by cosine and Bessel functions.     

The design features of the HTR-10

The 10 MW High Temperature Gas-cooled Test Reactor (HTR-10) is a modular pebble bed type reactor. This paper briefly introduces the main design features and safety concept of the HTR-10. The design features of the pebble bed reactor core, the pressure boundary of the primary circuit, the decay heat removal system and the two independent reactor shutdown systems and the barrier of confinement are described in this paper.     

A design of in-plant electric power system for the HTR-10

The design of in-plant electric power system for the 10 MW high-temperature gas-cooled reactor-test module (HTR-10) has taken into full consideration the feature of good inherent safety existing with the HTR-10 and has adopted a scheme different from those adopted for ordinary nuclear power plants. This paper gives an introduction to the structure, design objectives of in-plant electric power system, the designing schemes of different subsystems and the main equipment. The result of system test and operation show that the design can meet the demand for power reply from the reactor under any operational conditions. At the same time, it can reduce the system cost and improve the reliability and the safety of the system.     

Experiment and Verification Test of the Once-through Steam Generator of the 10 MW High-temperature Gas-cooled Reactor Flow Stability of the Once-through Steam Generator

In January 2003, the 10MW High-temperature Gas-cooled Reactor (HTR-10) reached its full power for continuous operation of seventy-two hours in the Institute of Nuclear Energy Technology, Tsinghua University. The reactor operated smoothlyqbthe design parameters were successfully attained.

The once-through steam generator (SG) is one of key equipments of the HTR-10 reactor. The SG includes 30 modular heating helical tube assemblies. There are two thermal hydraulic requirements to be satisfied for the once-through steam generator: (1) enough heat transfer surface; (2) qualified steam can be produced under rated electrical generation power, and water-steam two phase flow un-stability can be avoided. In order to obtain the thermal hydraulic characteristics of the SG reliably, before design, a numerical code was developed for the design, and a full-scale test loop with two heating tubes as model was established, and series experiments had been carried out.

The purpose of this paper is to introduce the design of SG and researches on the stability of small bending radius helical coil-pipe used in HTR-10, for exempla, the effects of outlet steam pressure, inlet water sub-cooling degree, thermal power and inlet throttling degree. Up to now, the SG has experienced full power operation smoothly, and approvingly reached its original design requirements.

In the paper, some operational experimental data of the HTR-10 S.G have been presented.     

Characteristic analysis of rotor dynamics and experiments of active magnetic bearing for HTR-10GT

A 10 MW high-temperature gas-cooled reactor (HTR-10) was constructed by the Institute of Nuclear and New Energy Technology (INET) at Tsinghua University of China. The helium turbine and generator system of 10 MW high-temperature gas-cooled reactor (HTR-10GT) is the second phase for the HTR-10 project. It is to set up a direct helium cycle to replace the current steam cycle. The active magnetic bearing (AMB) instead of ordinary mechanical bearing was chosen to support the rotor in the HTR-10GT. This rotor is vertically mounted to hold the turbine machine, compressors and the power generator together. The rotor's length is 7 m, its weight is about 1500 kg and the rotating speed is 15,000 rpm. The structure of the rotor is so complicated that dynamic analysis of the rotor becomes difficult. One of the challenging problems is to exceed natural frequencies with enough stability and safety during reactor start up, power change and shutdown. The dynamic analysis of the rotor is the base for the design of control system. It is important for the rotor to exceed critical speeds. Some kinds of softwares and methods, such as MSC.Marc, Ansys, and the transfer matrix method (TMM), are compared to fully analyze rotor dynamics characteristic in this paper. The modal analysis has been done for the HTR-10GT rotor. MSC.Marc was finally selected to analyze the vibration mode and the natural frequency of the rotor. The effects of AMB stiffness on the critical speeds of the rotor were studied. The design characteristics of the AMB control system for the HTR-10GT were studied and the related experiment to exceed natural frequencies was introduced. The experimental results demonstrate the system functions and validate the control scheme, which will be used in the HTR-10GT project.     

10MW高温气冷堆乏燃料元件转运罐罐盖封压机构的研制

文章主要介绍10MW高温气冷堆（HTR-10）乏燃料元件转运罐罐盖封压机构的结构、功能、设计参数和工作原理。实验室和现场安装后的调试试验以及实际运行操作表明，该机构运行良好、可靠，完全满足HTR-10的使用和安全要求。     

Structural design of ceramic internals of HTR-10

This article describes the structural design requirements, structural arrangement and structural features of the ceramic and metallic internals of the 10 MW high-temperature gas-cooled reactor-test module (HTR-10). The graphite properties used in the ceramic internals are provided, along with the results of an operating stress analysis of the graphite components and the metallic components. Satisfactory results were obtained for the machining and installation of the ceramic components and the stress analysis of the graphite and metallic components of HTR-10.     

基于微机系统的高温气冷堆工程仿真机

基于微机系统的高温气冷堆工程仿真机（HTRSIMU）由清华大学核能技术设计研究院开发完成HTRSIMU运行于Windows98或Windows2000平台上,采用多进程、多显示器结构,具有人机界面友好、结构紧凑、操作方便、易于扩展等特点。它的模型包括10MW高温气冷堆（HTR－10）的一、二回路主要部件,能够对反应堆堆芯、主回路系统和蒸汽发生器等部件做详细的物理和热工分析计算,可以模拟正常运行和各种事故工况过程,仿真结果和蒸汽发生器等部件做详细的物理和热工分析计算,可以模拟正常运行和各种事故工况过程,仿真结果与HTR－10的设计值和安全分析报告符合得很好。利用HTRSIMU系统不仅可以进行高温气冷堆的工程设计、安全分析和人员培训,而且将来可以对HTR－10主控室的操作人员进行现场支持,给实际运行和各项研究提供帮助。