多道分析器数据的远程实时压缩传送

对多道数据的特性和压缩传送问题进行了详细研究,提出了用动态比压缩方法和等计数压缩方法完成多道数据的远程实时无损压缩传送,给出了方法原理和实验结果。     

多道分析数据的远程实时压缩传送

对多道数据的特性和压缩传送问题进行了详细研究，提出了用动态比压缩方法和等计数压缩方法完成多道数据的远程实时无损压缩传送，给出了方法原理和实验结果。     

核物理多参数数据获取系统中的触发模式字单元

简要介绍了多参数数据获取系统中采用触发模式字单元的重要性，其工作原理和使用方法，列表型数据读出的方法和意义。     

多道电子束流能谱描迹仪

介绍了用一种多条金属靶传感器测量直线加速器电子束流能谱的方法 ,主要讨论其原理和电路设计时应考虑的问题     

多道电子速流能谱描迹仪

介绍了用一种多条金属靶传感器测量直线加速器电子束流能谱的方法,主要讨论其原理和电路设计时应考虑的问题。     

脉冲中子测井存在的局限性和发展方向

文章简述了脉冲中子测井方法的原理,总结了脉冲中子测井方法的分类及在石油测井中所起的作用,指出了当前脉冲中子测井存在测井数据质量不高、测井速度慢、影响因素多、解释困难、纵向分辨率低、适应性差等不足,并从硬件、软件、方法和原理四个方面阐述了脉冲中子测井的发展方向.     

煤田γ能谱测井仪设计

本文论述了煤田γ能谱测井仪的原理、方法、自稳峰系统、数字编码、多路传输系统、主要用途及特点和技术指标等,是现代煤田测井的新一代能谱测井仪器。     

多路TDC同时事件不丢失的一种编码方法

本文介绍起始—多停止原理的多路时间—数字变换器中路址编码所采用的一种方法,它对于各路同时存在的事件不会造成丢失。     

计算机编制Young图技巧

一、引言多粒子空穴系统的能态密度中泡利不相容原理的效应最近才找到严格求解方法。证实了泡利原理在低激发态或多粒子空穴数的状态下起着相当重要的作用。能态密度中泡利原理修正项是用一套Young图表示,由于Young图的个数是随粒子数或空穴数加大而剧增,若在实际计算中用手写方式输入计算机势必把问题变得十分烦杂。本文通过Young图的性质,找出一套方法,解决了计算机自动编制Young图的途径。     

一种用多并口获取数据的方法

提出一种利用多个通用并行接口组成的接口电路,实现计算机多道脉冲分析系统数据获取的方法,介绍了它的电路设计、工作原理及性能分析。     

The laboratory investigation of the experimental nuclear reactor VVR-S

Results are given in this paper of the laboratory investigation of the characteristics of the experimental reactor VVR-S undertaken with the aim of studying the neutron and physical parameters which are the most important for putting the reactor into operation and for its exploitation. As the result of the experimental work carried out, the critical mass and the maximum and operating fuel charges were found, the compensating capacity of the control and emergency rods was determined, the influence of the various factors (variation in the temperature of the water in the active zone, variations in the properties of the reflector, etc.) on the reactivity was studied, the distributions of neutron density with height and along the radius of the active zone were measured, and the operating time of the control rods was obtained.In conclusion the authors express their gratitude to T. N. Zubarev for discussion of the results and to O. I. Liubimtsev and I. V. Koptev for help in the work.     

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.     

轴承摩擦磨损对柔性支承转子动力响应特性的影响

柔性支承转子中唯一的动静接触组件为轴承,由轴和窝组成。轴和窝之间的摩擦对转子的动力响应特性有直接影响,研究其影响机理是轴承设计和优化的重要前提。本文建立了轴承的非刚性连接模型,并将其引入柔性支承转子模型中;从理论上研究不同轴承摩擦磨损程度对转子动力响应的影响;计算并分析了轴承摩擦磨损状态下转子的动力响应特性;分析了轴承磨损导致转子进动失效时转子释放的最大能量。研究结果表明,随着轴承摩擦磨损程度的加深,转子的振幅增大,转子出现二阶进动现象,磨损严重时伴随出现拟周期运动。轴承摩擦磨损可能导致转子出现不同的失效模式,转子做二阶进动和拟周期运动时会使失效转子释放的最大能量大幅增加。研究结果可为柔性支承转子的轴承优化设计提供理论依据。     

Hastelloy C-276/316L脉冲激光异质焊接微观组织研究

为评价激光焊接AP1000部件工艺的可靠性,探究Hastelloy C-276与316L异质焊接焊缝的元素偏析及组织结构,利用Nd:YAG脉冲激光进行焊接,借助光学显微镜和电子探针X射线微区分析仪等分析测试仪器,对焊缝显微组织、元素成分及金相形貌进行分析。结果表明：焊缝组织晶粒细化,焊缝中部以细小等轴晶为主、边缘以柱状晶为主,且焊接接头两侧热影响区极窄;依据元素宏观分布,焊缝可分为3个区域,焊缝两侧元素成分急剧变化,中部均匀;元素存在微观偏析,晶界处Mo元素富集。焊缝组织以γ奥氏体为主,并未发现明显δ铁素体生成。     

核电站设备可靠性数据库的建立与应用

以大亚湾核电站为例,论述了核电站设备可靠性数据的采集与处理、可靠性参数的分析计算方法及可靠性数据库的建立与应用等。数据源涉及到设备的设计信息、运行信息、维修信息、定期试验记录等。在大亚湾核电站运行经验的基础上,形成了大亚湾核电站设备可靠性数据库,为深入地、客观地记录核电站各类设备的运行历史和现状、监控电站设备,特别是与安全相关设备的状态,提供了有效的工具;为加强设备的可靠性与可用性管理、确保电站的安全经济运行,提供了非常有实用价值的信息;同时还为核电站的安全管理、可靠性分析、概率安全评价、以可靠性为中心的维修及经济性管理等领域里的新技术在核电站的应用研究与开发,提供了必不可少的数据。     

Decommissioning of the TVR Research Heavy-Water Reactor at the Institute of Theoretical and Experimental Physics

The key work on decommissioning of the TVR research heavy-water reactor at the Institute of Theoretical and Experimental Physics is described. The processes involved in the preparation for hauling away the spent nuclear fuel, mothballing the high-activity heavy water, salvaging the contaminated water in the holding pond, and removal of radioactive contaminants from the holding pond are described. Special attention is devoted to selecting a variant of decommissioning of the TVR and solving the problems associated with the implementation of decommissioning. The processes of dismantling the connecting pipes of the horizontal experimental channels inside the reactor vessel and preparing the fittings and equipment for performing this work are described.It is reported that work has been performed on the dismantling of the heavy- and light-water and gas loops of the reactor and on the dismantling of the experimental setups operating on the neutron beams of the horizontal and vertical channels of the reactor.     

高温气冷堆石墨构件的碰撞力学行为研究

高温气冷堆的反射层和隔热层主要由数量庞大的石墨砖和碳砖组成,在地震或冲击载荷作用下,部件之间可能发生滑移和碰撞,影响其结构完整性。简化的数值分析模型是研究这种大规模散体结构的重要手段,而其中模拟碰撞的非线性连接单元参数对分析的收敛性和结果的准确性至关重要。本文对高温气冷堆中石墨构件的3种典型碰撞形式进行了实验研究,测量得到了各碰撞模式下碰撞时间和恢复系数与碰撞速度的关系。针对碰撞实验中边界条件与堆内实际构件的差别,采用商业有限元分析软件ABAQUS对不同碰撞形式进行了数值分析,进一步获得了更为准确的碰撞特性,并通过改进的Hertz碰撞模型对实验和数值结果进行分析,得出了非线性碰撞连接单元的等效刚度系数和等效阻尼系数。最后利用数值分析方法进行了与堆内构件设计相关的质量和间隙尺寸对碰撞单元等效刚度系数和等效阻尼系数的详细研究,为高温气冷堆石墨和碳堆内构件的设计提供参考。     

蒸汽发生器传热管破损叠加全船断电事故放射性分析

以严重事故分析程序MELCOR为计算工具,研究了某型船用堆发生蒸汽发生器传热管破损叠加全船断电事故,针对传热管破损所导致的放射性物质向其他舱室的泄漏,着重分析了惰性气体和CsI的释放、迁移、滞留特点及其在舱室内的分布。计算结果表明:二回路蒸汽管道会发生超压失效,氢燃导致堆舱邻舱的超压失效。至计算结束,约占累积总量99.61%的Xe和49.96%的CsI从堆芯释放出来。舱室Ⅰ和Ⅱ内Xe的分布份额分别为38%和18%,CsI的分布份额分别为22.2%和2.7%,CsI主要存在于舱底水池中,且泄漏至舱室Ⅱ的份额微少。本文分析结果可为进一步的源项剂量分析及船内外应急提供依据。     

PBMR radionuclide source term analysis validation based on AVR operating experience

The determination of radionuclide source terms is vital for any reactor design and licensing safety evaluation. This paper provides an overview of the PBMR analysis tools with specific focus on the modelling of mobile and deposited radionuclide source terms within the pressure boundary of a typical pebble-bed high temperature reactor (HTR). The main focus is on the Dust and Activity Migration and Distribution (DAMD) software code system that models the activation, migration and time-dependent distribution of dust and atomic particles in an HTR such as the AVR and PBMR. Since DAMD provides a time-dependent systems integrated model of HTR designs, most of the obvious physical phenomena relevant to source terms are at play. These include the neutron flux, activation cross-sections, radioactive decay, dust production rates, dust impurity levels, dust filter capabilities, dust particle size distributions, thermal-hydraulic parameters influencing the migration and distribution of particles throughout the main power system and subsystems, and helium coolant leakage and make-up rates.At this stage the DAMD calibration and validation is mainly based on the operational data, experiments and measurements made during 21 years of operating life of the AVR. The comparisons of the DAMD results with various AVR measurements provide confidence in the use of DAMD for the PBMR design and safety evaluations. In addition, sensitivity analyses are performed with DAMD to determine the bounding system parameters that drive the migration and distribution of radionuclides. The use of DAMD to evaluate design configurations, e.g. the effect of the introduction and placement of filters on the radionuclide distribution, is also shown.In conclusion, the importance of a systems modelling approach for radionuclide transport and distribution within the pressure boundary of a typical HTR system, is demonstrated. Since the DAMD code system is calibrated and validated against the AVR measurements it can be concluded that the radionuclide source term phenomena in the AVR, resulting in the measured AVR contamination levels, is taken into account in the design and safety evaluation of the PBMR.     

Reactivity effects in a BN-350 reactor

Conclusions The experiments were the first check on values of the temperature and power reactivity effects and the depletion effect for a fast power reactor. These results and their theoretical analysis enable us to estimate the reactivity balance in a BN-350 reactor, and to check and refine the methods of calculation. The models and methods used for calculations in designing fast power reactors turned out to be effective and gave quite satisfactory results.Calculations of the temperature and power reactivity effects somewhat underestimate their values (by 15%). The largest error in the temperature effect comes from the Doppler and sodium components, and in the power effect from the Doppler effect and the indeterminacy in temperature field calculations.Calculations give a fairly good estimate of the depletion effect also, although in this case obvious care has to be exercised in choosing the method of calculation. This fact is connected with the necessity of correctly allowing for nonuniformity of fuel depletion and the accumulation of plutonium.Investigation of the reactivity effect for prolonged use of the reactor is of great practical and theoretical interest. The effect of depletion and change in structure of the fuel pellets on the temperature and power effects, the nonlinear nature of the power effect, and the influence of plutonium accumulation on the reactivity effects in the reactor, all these are questions of reactor physics the study of which allows us to increase the accuracy of physical calculations in designing fast power reactors.Translated from Atomnaya Énergiya, Vol. 42, No. 1, pp. 3–8, January, 1977.