HTR-10球形燃料元件制造工艺

10MW高温气冷实验模块堆球形燃料元件的制造技术的研究始于1986年。球形燃料元件的制造使用橡胶模具冷准等静压工艺。目前已完成了制造技术和石墨基体材料的研究和最佳化。已生产了25批,约11000个燃料元件。石墨基体材料的冷态性能符合设计指标,25批燃料元件的平均自由铀含量为5×10-5。     

HTR-10球形燃料元件模型分析

中国的高温气冷堆(HTR-10)属球床型高温气冷堆,采用球形燃料元件.在运行工况下,由于温度和辐照引起的应力变化会使燃料元件发生失效,对其进行分析可更多了解燃料元件内的情况.本文主要介绍了球形燃料元件的基本结构,以及燃料元件的温度分布、应力分析、破损率计算模型,并计算了在一定堆工条件下的温度和应力分布.     

HTR-10燃料元件装卸系统的集散控制

依据10MW高温气冷实验堆（HTR－10）燃料元件装卸系统的控制要求，对燃料元件装卸系统的集散控制进行了研究，设计了集散控制系统，包括硬件设计，软件设计，步进电动机精确定位闭环控制和无位置传感器转子位置检测的设计，并进行了模拟实验，实验表明，系统的性能稳定可靠，达到了控制要求。     

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。     

10MW高温气冷堆包覆燃料颗粒的研制

我国10MW高温气冷堆采用全陶瓷型包覆颗粒球形燃料元件。TRISO型包覆燃料颗粒由燃料核芯、疏松热解碳层、内致密热解碳层、碳化硅层和外致密热解碳层组成。采用丙烯和乙炔混合气体制备致密热解碳层以及四层连续包覆的新工艺,开展生产工艺条件试验,系统地研究了生产工艺和性能之间的关系,摸索出最佳生产工艺条件。用化学气相沉积方法在150mm流化床沉积炉系统中批量生产出TRISO型包覆燃料颗粒。用扫描电镜观察分析了包覆燃料颗粒的微观结构,包覆燃料颗粒的制造破损率为3.4×10-6,冷态性能达到我国10MW高温气冷堆设计要求。包覆燃料颗粒辐照考验结果(放射性裂变产物释放率R/B为1×10-6左右)表明,包覆燃料颗粒的质量可以满足10MW高温气冷堆安全运行的要求。     

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.     

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     

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。     

用全胶凝法生产HTR-10陶瓷UO_2燃料核芯

对用全胶凝法生产HTR-10临界量陶瓷UO2燃料核芯进行了系统的总结,给出了陶瓷UO2产品的检测结果:密度>98%理论密度,氧铀比=2.00,不圆度<1.05,直径=500±50μm,标准偏差<15μm,提供了主要工序的控制参数。通过对温度、水解速度、胶液铀浓度、脱碳速度、还原-烧结升温程序、气氛等的控制,使质量达到了HTR-10燃料元件的设计要求,为工业化生产奠定了基础。本文还就若干关键技术:溶胶的质量控制、多喷嘴均匀分散、三功能回转真空干燥机等进行了介绍。     

用全胶凝法生产HTR—10陶瓷UO2燃料核芯

对用全胶凝法生产HTR-10临界量陶瓷UO2燃料核芯进行了系统的总结,给出了陶瓷UO2产品的检测结果密度＞98%理论密度,氧铀比=2.00,不圆度＜1.05,直径=500±50μm,标准偏差＜15μm,提供了主要工序的控制参数.通过对温度、水解速度、胶液铀浓度、脱碳速度、还原-烧结升温程序、气氛等的控制,使质量达到了HTR-10燃料元件的设计要求,为工业化生产奠定了基础.本文还就若干关键技术溶胶的质量控制、多喷嘴均匀分散、三功能回转真空干燥机等进行了介绍.     

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 full core first criticality analysis with MCNP

Experimental facilities like HTR-10, HTTR, and ASTRA serve as the source of information for the currently designed high temperature gas-cooled nuclear reactors. It is also desired to verify the existing codes against the data obtained in such facilities. In this study, first criticality calculations of a pebble bed gas-cooled reactor, HTR-10, is performed with MCNP-4B, a code system for Monte Carlo particle transport simulation. HTR-10 has rather unique characteristics in terms of the randomness in geometry as in the case of all pebble bed reactors. The geometrical model of the full reactor is obtained by using lattice and universe facilities provided by MCNP. Modeling details are discussed with necessary simplifications. Results obtained by Monte Carlo simulations are compared with available data. It is observed that Monte Carlo simulations yield sufficiently accurate results in terms of initial criticality of the HTR-10 reactor.     

Fuel management of the HTR-10 including the equilibrium state and the running-in phase

The mode of fuel management of the HTR-10 was studied, including the simulation of the fuel shuffling process and the measurement of the burnup of a fuel element. The prior consideration was the design of the equilibrium state. Based on this the fuel loading of the initial core and the fuel shuffling mode from the initial core through the running-in phase into the equilibrium state were studied. The code system VSOP was used for the physical layout of the HTR-10 at the equilibrium state and in the running-in phase. For the equilibrium state, in order to lessen the difference between the peak and the average burnup, 5-fuel-passage-through-the-core was chosen for the fuel management. The average burnup of the spent fuel for the equilibrium core is 80 000 MWd t⁻¹, and the peak value of it is less than 100 000 MWd t⁻¹ when the burnup of the recycled fuel element is under 72 000 MWd t⁻¹. The mixture of fuel element and graphite element was used for the initial core loading, the volume fractions of the fuel and the graphite elements were 0.57 and 0.43, respectively. During the running-in phase, the volume fraction of graphite will decrease with the fresh fuel elements being loaded from the top of the core and the graphite elements discharged from the bottom of the core. The fuel shuffling mode is similar to that of the equilibrium state. The burnup limit of recycled fuel element is also 72 000 MWd t⁻¹ and the peak burnup is less than 100 000 MWd t⁻¹. Finally the core will be full of fuel elements with a certain profile of burnup and reaches the equilibrium state. According to the characteristics of the pebble-bed high temperature gas-cooled reactor, a calibrating method of concentration of ¹³⁷Cs was proposed for the measurement of fuel burnup.     

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。     

蒙特卡罗方法用于HTR-10首次临界燃料装料预估的校算

在10MW球床式高温气冷实验堆(HTR—10)首次临界前．达到首次临界的堆芯燃料球装量预估是物理设计的一项重要任务．为了确保物理设计的可靠性．引入蒙特卡罗程序MCNP对VSOP程序的计算结果进行校验。根据HTR—10的特点对燃料元件和堆结构．设计出近似而合理的MCNP描述;再选择合理的计算特征值问题的参数,包括跳过的周期数、每周期标定的源数目和得到特征值的周期数;研究燃料球结构的不同描述对κeff的影响;确定较优的计算方案。该方案的计算结果表明,在27℃、空气气氛下,MCNP和VSOP程序预估的达到首次临界的总球数分别为16864个和16821个,相对误差为0．25％。HTR-10的首次临界实验表明．预估与实验的结果相对误差小于1．0％。     

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.     

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。     

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.     

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.