HTR-10安全功能与设备分级

参照有关的核安全法规,结合我国设计、建造各类研究堆的经验,根据HTR-10的安全特性和对构筑物、系统和部件安全功能的要求,制定了HTR-10的构筑物、系统和部件等物项的安全分级原则和相应的设计、制造要求及验证措施等,对HTR-10的设计和建造具有实际的指导和应用价值,确保了HTR-10的安全与可靠。     

10MW高温气冷实验堆安全分析要素的定期安全审查

10 MW高温气冷实验堆(简称HTR-10)是我国第一座模块式高温气冷堆,由清华大学核能与新能源技术研究院(核研院)设计。按照我国核安全法规的要求,并经过国家核安全局的批准,核研院于2012年开始对10 MW高温气冷实验堆进行定期安全审查(简称PSR),安全分析是本次审查的重点安全要素之一。本文对安全分析要素审查的主要内容作了概述,并给出了核研院对本次审查的内部评价。     

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。     

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.     

HTR-10安全负压通风系统的设计

由于高温气冷堆具有固有安全性,因此在高温气冷堆的设计中采用通风式包容体替代了密封承压式安全壳,在供暖,通风与空调（HVAC）系统中相应采用了安全负压通风系统,以保证包容体在正常工况或事故工况下都能满足与安全相关的一切功能,本文介绍了10MW高温气冷实验堆（HTR－10）安全负压通风系统的设计与评价。     

10MW高温气冷堆的应急计划与应急准备

为了保护环境、公众和工作人员，按照核设施纵深防御的原则．10MW高温气冷堆(HTR—10)必须制定应急计划．并在此基础上作好应急淮备，以便在事故情况下可以采取快速有效的应急响应行动，减轻事故的后果。本文依照研究堆的核安全法规和导则，并根据HTR—10的安全特性，完成了HTR—10应急计划的制定、应急准备及装科前的场内综合应急演习等工作．保证了HTR—10在2000年建成并达到临界。     

HTR-10的调试管理

10MW高温气冷实验堆（HTR－10）属于研究堆类型，但又具有小型核动力堆的运行模式；HTR－10的调试队伍由设计者、运行者和合同单位有关人员组成。针对HTR－10自身的特点和调试队伍人员组合的特点，确定了调试管理模式。本文重点介绍了HTR－10调试管理中的调试组织的规范化和试验活动的程序化，并给出了试验活动程序流程图。     

Modeling of the Helium-Heated Steam Reformer for HTR-10

In this study, based on the pseudo-homogeneous one-dimensional model, a steady-state model of the helium-heated steam reformer planned to be connected with the 10 MW high temperature gas cooled reactor (HTR-10) has been developed. Good agreement is shown between the simulating results and experimental data. The influence of main process parameters on the performance with respect to the methane conversion and the hydrogen yield is investigated and discussed. The performance increases remarkably with the increase in the inlet helium temperature when it is lower than 1,000°C. Whereas, the effect becomes weak when the temperature is higher than 1,000°C. The influence of the inlet helium flow rate is not as evident as that of the temperature. The inlet helium pressure and inlet process gas temperature have almost no influence on the performance. The performance increases with the decrease in the inlet process gas pressure. The influence of the inlet process gas flow rate and steam-to-carbon ratio (S/C) is complicated. Optimal values should be chosen for them to obtain a high performance.     

Manufacture and characteristics of spherical fuel elements for the HTR-10

The R&D of spherical fuel elements for the 10 MW high temperature gas-cooled reactor (HTR-10) started in 1986 in China. A process known as cold quasi-isostatic molding was used for manufacturing spherical fuel elements, and about 20,540 spherical fuel elements were produced in 2000 and 2001. Fabrication technology and graphite matrix materials were investigated and optimized. Cold properties of the spherical fuel elements met the design specifications. The mean free uranium fraction of 44 batches was 4.57 × 10⁻⁵. In-pile irradiation test results showed that irradiation did not lead to apparent change in linear dimensional, geometrical density, porosity and strength of matrix graphite samples. No cracks and blisters were observed in spherical fuel elements. This indicated that matrix graphite and spherical fuel elements of HTR-10 met the requirement of design specifications.     

Design and experiment of hot gas duct for the HTR-10

A horizontal coaxial double-tube hot gas duct is a key component connecting the reactor pressure vessel and the steam generator pressure vessel for the 10 MW High Temperature Gas-cooled Reactor—Test Module. Hot helium gas from the core outlet flows into the steam generator through the liner tube, while helium gas after being cooled returns to the core through a passage formed between the inner tube and the duct pressure vessel. Thermal insulation material is packed into the space between the liner tube and the inner tube to resist heat transfer from the hot helium to the cold helium. The thermal compensation structure is designed in order to avoid large thermal stress because of different thermal expansions of the duct parts under various conditions. According to the design principal of the hot gas duct, the detailed structure design and strength evaluation for it has been done. A full-scale duct test section was then made according to the design parameters, and its thermal performance experiment was carried out in a helium test loop. With helium gas at pressure of about 3.0 MPa and a temperature over 900 °C, the continuous operation time for the duct test section lasted 98 h. At a helium gas temperature over 700 °C, the cumulative operation time for the duct test section reached 350 h. The duct test section also experienced 20 pressure cycles in the pressure range of 0.1–3.4 MPa, 18 temperature cycles in the temperature range of 100–950 °C. Thermal test results show an effective thermal conductivity of the hot gas duct thermal insulation is 0.47 W m⁻¹ °C⁻¹ under normal operation condition. In addition, a hot gas duct depressurization test was carried out; the test result showed that the pressure variation occurred on the liner tube was not more than 0.2 MPa for an assumed maximum gas release rate.     

10MW高温气冷实验堆信息管理系统

１０ＭＷ高温气冷实验堆信息管理系统（ＲＥＭＩＳ）的开发基于客户／服务器体系;数据服务器采用运行于ＷｉｎｄｏｗｓＮＴ上的ＳＱＬ Ｓｅｒｖｅｒ６．５;客户前端采用Ｃ＾＊＊Ｂｕｉｌｄｅｒ,基于Ｗｉｎｄｏｗｓ９５／９８图形化交互界面;网络操作协议选用ＴＣＰ／ＩＰ。系统（１．１版本）收集了１０ＭＷ高温气泠实验堆４个方面的信息,即反应堆资料、设计参数、设备部件资料、反应堆系统流程图资料,并探讨了系统扩展的方向     

10MW高温气冷实验堆电力系统

10MW高温气冷堆电力系统是为保障反应堆完成其安全目标和运行目标而设置的重要系统,本文介绍了10MW高温气冷堆电力系统的组成结构和配置,描述了电力系统在不同工况下的运行方式。     

IR-360 nuclear power plant safety functions and component classification

The IR-360 nuclear power plant as a 2-loop PWR of 360 MWe power generation capacity is under design in MASNA Company. For design of the IR-360 structures, systems and components (SSCs), the codes and standards and their design requirements must be determined. It is a prerequisite to classify the IR-360 safety functions and safety grade of structures, systems and components correctly for selecting and adopting the suitable design codes and standards. This paper refers to the IAEA nuclear safety codes and standards as well as USNRC standard system to determine the IR-360 safety functions and to formulate the principles of the IR-360 component classification in accordance with the safety philosophy and feature of the IR-360. By implementation of defined classification procedures for the IR-360 SSCs, the appropriate design codes and standards are specified. The requirements of specific codes and standards are used in design process of IR-360 SSCs by design engineers of MASNA Company. In this paper, individual determination of the IR-360 safety functions and definition of the classification procedures and roles are presented. Implementation of this work which is described with example ensures the safety and reliability of the IR-360 nuclear power plant.     

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.     

HTR-10物理实验方法及数据处理

针对高温气冷实验反应堆（HTR－10）的实际情况，重点介绍了周期法的原理以及在各项物理实验中的应用，特别分析了实验数据的选取和处理原则，利用Excel强大的数据处理能力进行数据处理和分析的方法，并用多种方法分析了测量数据的有效性。     

HTR-10智能化数字式过球计数系统

所介绍的过球数字化处理系统,采用智能的信号处理技术,实现了连续、准确的燃料球计数,并具有广泛的适应性、良好的界面、与堆上其他系统的兼容性、完善的诊断功能、低廉的成本、良好的可运行性和维护性。     

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-10一体化换热装置和联合循环

10MW高温气冷实验堆 (HTR 10 )有两个突出的特点 :(1)采用气体轮机和汽轮机联合循环 ,可以提高其发电效率 ,并且能保持较低的堆芯入口温度 (30 0℃ )。 (2 )中间换热器和蒸汽发生器一体化设计 ,减少了一个壳体和一个热气导管 ,提高了安全性和经济性。描述了一体化的中间换热器和蒸汽发生器以及气体轮机和蒸汽轮机联合循环的设计特点。     

HTR-10全厂断电试验

10MW高温气冷实验堆在电气系统的设计中,针对全厂断电设计基准事故采取了相应的处理措施,在10MW高温气冷实验堆热态性能调试期间进行了全厂断电试验,用以验证10MW高温气冷实验堆应急供电系统的功能,结果表明,在发生全厂断电的设计基准事故时,由蓄电池组支持的不间断交流电源装置可以可靠地保证各专设安全设施完成其安全功能,并能为反应堆事故监测提供20小时的电力供应。     

Thermal hydraulic calculation of the HTR-10 for the initial and equilibrium core

The thermal hydraulic calculations of the 10 MW high temperature gas-cooled-test module (HTR-10) are among the most important indications to judge the reactor performance under design conditions. The power distribution, the temperature distribution and the flow distribution of the HTR-10 are calculated for initial and equilibrium core in this paper. The temperature distribution includes the temperature parameters of fuel elements, the helium coolant and the main components in the reactor. In the temperature calculation of fuel elements, several uncertain factors are considered carefully, including non-uniform burnup, power distribution deviation, manufacture deviation of fuel elements, graphite balls mixed with fuel balls in the core, calculation deviation of heat transfer and so on. In the flow distribution calculation, the conservative pebble bed core flow value is selected. The results show that the maximum fuel temperature is much lower than the limitation and the flow distribution can meet the cooling requirement in the reactor core.