Dynamic Programming Method to Optimize Control Rod Positions in NHR-200

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模糊PID控制在烟酸反应釜温度控制中的应用

文章讨论了烟酸生产过程中反应釜温度控制的设计问题.由于在化学反应过程中反应釜特性不断变化,造成PID控制的困难.结合控制系统的特点,采用了模糊PID控制技术,使PID参数能够根据对象的变化进行适当的参数自整定,解决了烟酸生产中的关键控制难题.     

煤层顶板砂岩高温下超声传播特征分析

通过对鹤壁矿务局煤层项板砂岩试件在高温状态下和高温冷却后的超卢波测试,揭示了砂岩在高温状态下和高温冷却后的超声波传播随温度的变化规律,从声速、振幅和主频几个方面研究了在高温状态下和高温冷却后煤层顶板砂岩内损伤裂纹的发展变化过程。试验结果表明,在高温状态下和高温冷却后,振幅对岩石裂纹状态敏感程度大于声速和主题,振幅和声速随温度变化的曲线上存在着一骤降点,但各自反映的温度点有差异。其研究成果埘煤炭地下气化炉围岩在高温下的节理裂隙演化过程、组构和力学特性研究具有重要的作用和意义。     

高压电机起动的饱和电抗器设计

介绍高压电机起动用饱和电抗器参数的选择及设计方法,并给出了具体例子。     

全球核能科技前沿综述

讨论了核能前沿科技领域所取得的科技研究与重要工程项目进展,重点介绍了核电建设与发展、小型模块堆技术、聚变反应堆、空间动力堆、事故容错燃料,数值反应堆等方面的研究及开发进展。在海、陆、空均有良好应用前景的小型反应堆,将在传统商用核电以外开辟核能利用的新天地。而先进燃料设计、高精度数值模拟等技术则是未来核能安全保障的重要发展方向。随着技术的进一步革新和技术路线的多样化,呈多元化发展态势的核能预期仍将在全球能源结构中占据重要地位。     

高剪切反应器中有机相强化KHCO3/K2CO3溶液吸收CO2研究

在高剪切反应器（HSR）中研究了不同有机分散相对KHCO₃/K₂CO₃溶液吸收CO₂的强化效果，并考察了有机相与有机胺溶液复配使用对CO₂吸收率的影响。实验结果表明：环己烷、正庚烷对KHCO₃/K₂CO₃溶液吸收CO₂的强化效果明显，甲苯、正辛醇对KHCO₃/K₂CO₃溶液吸收CO₂则没有明显的强化效果；CO₂吸收率随HSR转速的增加而增加，随气液比、温度的增加而降低；环己烷对加入二乙醇胺活化的K₂CO₃溶液有较为明显的强化作用，CO₂吸收率最高可提高23%。与文献中不同反应器的对比表明HSR对CO₂具有较高的吸收效率。     

定-转子反应器在水脱氧工艺中的应用研究

在定-转子反应器中采用N₂-水脱氧、CO₂-水脱氧两个体系脱除水中的溶氧，考察了转子转速、液体体积流量以及气体体积流量对脱氧率和传质系数的影响，并对比了两个水脱氧体系的脱氧效果。实验结果表明：脱氧率随转子转速和气体体积流量的增加而升高，随液体体积流量的增加而降低；传质系数随着转子转速、液体体积流量、气体体积流量的增加而增加；此外，N₂-水脱氧体系的脱氧效果要优于CO₂-水脱氧体系。     

Transient pressure analysis for the reactor core and containment of a HTGR after a primary loop pressure boundary break accident

The pressure variances in the reactor core and containment of a High Temperature Gas-cooled Reactor (HTGR) after a primary loop pressure boundary break accident determine the structural integrity and safety of the reactor. Based on mass conservation, energy conservation and state equations, explicit formulae for the transient pressure and temperature variances in the pressure vessels were deduced, and a set of differential equations for the transient pressure and temperature variances in the containment were developed. Numerical simulation was also conducted to investigate the transient pressure and temperature variances in the pressure vessels and containment. The results show that energy transformation due to expansion work cannot be neglected. The maximum pressure in the containment could increase by 40 percent due to blockage caused by air in the containment. Detailed numerical simulations of the transient pressure and temperature variance in the reactor core flow passages were also conducted. The results show that the pressures acting on the reactor core and containment are below acceptable values.     

A brief introduction to neutron activation analysis in China

The history, the major achievements in both methodology and applications, the current trends and future perspectives of neutron activation analysis (NAA) in China are briefly described.     

SCWR for Future LargeScale Nuclear Power Generation

The ambitious nuclear power program motivates the Chinese nuclear community to develop advanced reactor concepts of generation IV, in order to ensure the longterm, stable and sustainable development of nuclear power. The supercritical watercooled reactor (SCWR) has favorable features in economics, sustainability and technology availability. It is the logical extension of the existing PWR technology and has very promising perspectives in largescale power generation in China. This paper describes the main features of SCWR. New designs of SCWR core structure and fuel assemblies are proposed. Preliminary analysis using a coupled neutronphysics/thermalhydraulics method is carried out and shows a good feasibility of the new design proposal.