核设施抗爆炸分析综述

本文分析了国内外在核设施抗爆炸分析方面的研究情况,介绍了在有限元分析发展过程中几种重要的数值方法并重点分析了中心差分法,介绍了几种可用于分析设施爆炸的软,总结了中国核设施的结构特点,列出了钢筋混凝土的三种建模方法并分析了优缺点。     

300^#反应堆乏燃料元件源项估算方法研究

本文阐述了300^#反应堆燃料元件芯体的主要元素成分，分析了裂变产物及其特性，给出了乏燃料元件源项估算的基本原理，初步选择了源项估算的基本原理，初步选择了源项估算程序，描述了输入数据的形成及其统计、计算方法，表明了计算及结果处理方法。     

大亚湾核电站的核安全文化建设探讨

论述了核电站管理中安全文化的概念及安全文化的发展阶段。重点分析了大亚湾核安全文化形成的背景及过程 ,阐述了大亚湾核安全文化的核心理念 ,提出了核电站安全文化指标 ,总结了大亚湾核电站实施核安全文化的主要措施 ;描述了透明度的普及 ,并对大亚湾核电站核安全文化实施的效果进行了系统分析。     

硝酸体系中锕的三烷基氧膦萃取

本文研究了TRPO-煤油对硝酸体系中的锕的萃取,确定了萃取络合物的组成;测定了表观平衡常数;并研究了各种因素对Ac的萃取的影响。在实验基础上推导出了计算Ac的分配比的经验公式。还研究了TRPO-煤油对常量La的萃取,并讨论了使用TRPO萃取实现La,Ac分离的可能性。     

聚合物辐射老化降解效应研究进展

对4种高能辐射作用了聚合物材料导致材料发生了老化降解进行了评述，同时分析了影响辐射老化的几种因素。阐述了2种辐射加速老化的方法，指出了聚合物辐射老化研究面临的困难和发展的方向。     

一种快速中值滤波算法在集装箱检查系统中的应用

讨论了一种新的中值滤波算法，有效地降低了传统中值滤波算法的时间复杂度，提高了计算效率和运算速度。该算法在大型集装箱检查图像处理中的应用，取得了良好的效果，提高了图像处理的速度，增强了图像处理的实时性。     

各向异性散射的卡尔森S_N程序GYSNF

GYSNF程序是在DJS—8机上用FORTRAN语言编制的一维球形几何卡尔森S_N程序。本文在理论上将各向同性散射的卡尔森S_N方法推广到了各向异性散射。本程序改进了散射矩阵的处理方法,节省了70%的数存单元;改进了群内迭代的收敛判据,在计算决裂变系统时收敛速度快了一倍;实现了连续运算,解决了合理地选取初始分布问题,有效地加速了收敛。     

核电厂多样化保护系统设计中验收准则的分析确定

阐述了核电厂多样化保护系统(DAS)信号设计的流程、方法,对DAS保护信号设置的验收准则的分析确定过程进行了论述,明确了验收准则确定的方法,针对不同工况确定了不同的验收准则。以福建福清核电厂预想事故为实例开展了相关验证,确保了验收准则的有效性与适用性,为后续工作奠定了基础。     

提高核电站DCS机柜中保险丝检测效率的一种方法研究

本文对核电站分布式控制系统(DCS)中的机柜保险丝安装缺陷进行了调研,使用控制图的方法对DCS机柜中的保险丝安装缺陷进行了统计分析,对当时工程应用的DCS机柜保险丝安装检查工序进行了总结,对诱发的问题进行了分析,使用因果图对生产制造检验过程等工序中的末端原因进行分析,对要因进行确认,制定了要因对策表,采取了纠正行动和措施,开发了一种保险丝专用检查工具代替原始的人工检查方法,缩短了保险丝检查时间,提高了检查效率,使机柜的质量得到了有效控制,原来存在的保险丝混装、漏装等问题得到了有效解决,保险丝检查流程得到优化。本文通过100%的检查准确率及核安全文化宣贯,彻底解决了保险丝安装缺陷率的问题。     

研究性重水反应堆(HWRR-3)最大允许功率的确定和监测

反应堆运行功率是一个重要的监测参数。本文扼要地叙述了HWRR-3最大允许功率的确定和监测。描述了计算方法,给出了计算结果和误差分析。该工作使重水反应堆实现了在线计算和实时监测,它使反应堆得到了实时的、可靠的监督,方便了运行人员,增加了运行的安全性。     

定位绕丝结构对棒束通道热工水力特性影响数值分析

定位绕丝设计广泛应用于金属快堆堆芯设计及气冷快堆堆芯设计中,本文基于三维精细化绕丝定位棒束通道网格模型模拟分析了定位绕丝螺距、定位绕丝数量及定位绕丝形状对超临界二氧化碳在棒束通道中流动换热的影响。模拟结果表明定位绕丝螺距比定位绕丝数量及定位绕丝形状对温场流场的影响更大,定位绕丝螺距小于200 mm时,进出口压降大幅增加,表面换热系数增加,温度不均匀度大幅降低;随着定位绕丝数量增加,进出口压降线性增加,表面换热系数变化不大;圆形定位绕丝可以以较小截面积达到与方形定位绕丝相似的效果,梯形定位绕丝对流场影响不如矩形定位绕丝。     

油气工业中放射性废物的处理和处置

油气的开采会产生大量的放射性废物,对放射性废物的处理与处置事关公众和环境的辐射安全问题。本文从油气工业放射性废物的源项和存在形式等特征出发,对放射性废物的临时贮存、污染设备的去污及放射性废物的处理、处置过程中涉及的技术方法和相关管理要求进行了介绍,为实践中选择合理可行的处理、处置方案以及建立油气工业放射性废物监管体系提供借鉴和参考。     

Compatibility of fuel-element cladding materials with gallium-containing uranium and uranium–plutonium oxide fuel

Powders of uranium oxide powder and mixed fuel containing 5 and 20 mass % plutonium and 0.4 and 5 mass % gallium were prepared by coprecipitation from nitrate solutions. Pelleted samples for testing were made by cold pressing and sintering. The compatibility of uranium oxide fuel and mixed uranium–plutonium fuel, containing 0.4 and 5 mass % gallium, with the zirconium alloy E-110 at 400 and 500°C and ChS-68 corrosion-resistant steel at 650 and 750°C over periods of 1000, 2000, and 3000 h was investigated. Metallographic and x-ray spectral microprobe analyses of diffusion samples established that there was no interaction and penetration of gallium into the zirconium alloy and steel. In addition, the diffusion coefficient of metallic gallium in zirconium alloy and the distribution of the elements on interaction of gallium with ChS-68 steel were evaluated.     

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.     

历史见证了X射线发现125周年之辉煌

适值伦琴射线发现 125周年之际,在人类科技史上这空前伟大的划时代成就,深刻地影响和改变了世界,给科技进步和社会文明带来了无比辉煌的硕果。抚今追昔,紧密结合国内、外相关领域由其所持续绵延激发出的杰出成就,谨从四大方面追踪评述相关发展状况与趋势,聊表崇敬与缅怀之情,祈盼获得宝贵的启迪与裨益。鉴往知来,基于电离辐射技术是把双刃剑,由此深感能不懈为发展核科学技术及其广泛应用保驾护航是非常荣幸的。     

Multipurpose ANSYS FE procedure for welding processes simulation

ANSYS FE procedures and 3D models for thermal and mechanical simulation of both Laser and TIG welding processes are presented. The special features are the applicability to a non uniform gap and the use of a fast iterative procedure that assures the constancy of the fixed maximum temperature along the single pass and between each pass and the following, apart from their shapes and sizes. All the thermal and mechanical material properties of both INCONEL 625 and AISI 316 are described till to liquid phase; convection and radiation effects are considered. The 3D ANSYS models use both brick and non linear contact elements and elastic and elastic–plastic materials.Two full simulation are presented: a laser welding test (taken from ENEA) and a TIG welding one (source W7-X) with the root seam plus 14 passes; thermal and mechanical results are reported in the two cases and for the latter an extensive sensitivity analysis, changing mesh size of the filling material, welding speed and material properties, is explained with results and comparisons. This large sensitivity analysis has been executed for TIG welding because in this case (multi-pass welding) the reduction of CPU time is a strong requirement; but some conclusions are helpful for laser welding too. The mechanical calculation results very sensitive to the mesh shape: this fact implies very fine and regular meshes. The specimens are first restrained and then welded with the foreseen welding procedure; after that it is released and the final linear and angular shrinkages are calculated. The ANSYS birth and death procedure is used and the CPU time was strongly reduced.     

管道清洗装置自控系统研制

工业管道在长时间使用过程中,会积聚杂质影响产能,所以需要进行管道清洗。管道清洗装置依次接入工业管路中,清洗各管道杂质。为实时监测管道清洗装置的各项参数,实现人机交互,研制了一套自控系统。该系统选择泓格控制器、研华一体机配合LabVIEW的软硬件架构,缩短系统开发时间,实现系统小型化;采用“双背板”结构、快接插件设计,满足结构的小型化以及快速拆装要求;设计自动关断电动阀,发生紧急情况时,实现与设备的快速截断隔离以防止破空,增强整个系统的安全防护。该自控系统实现了工艺参数的监测、控制、报警、存储、查询、数据导出等功能,拆装方便、可移动,可满足现场的使用要求,同时保障了设备的稳定运行。目前该自控系统已正式投入使用,运行安全稳定。     

Developments and needs in nuclear analysis of fusion technology

Nuclear analyses provide essential input to the conceptual design, optimisation, engineering and safety case of fusion technology in current experiments, ITER, next-step devices and power plant studies. Calculations are intricate and computer-intensive, typically requiring detailed geometry models, sophisticated acceleration algorithms, high-performance parallel computations, and coupling of large and complex transport and activation codes and databases. This paper reports progress on some key areas in the development of tools and methods to meet the specific needs of fusion nuclear analyses. In particular, advances in the production and modernisation of reference models, in the preparation and quality assurance of acceleration algorithms and coupling schemes, and in the evaluation and adaptation of alternative transport codes are presented. Emphasis is given to ITER-relevant activities, which are the main driver of advances in the field. Discussion is made of the importance of efforts in these and other areas, considering some of the more pressing needs and requirements. In some cases, they call for a more efficient and coordinated use of the scarce resources available.     

Dynamic analysis and evolution of mixed materials bombarded with multiple ions beams

Materials modification and response to the impact of energetic particles is an important ongoing research area in several applications. This includes both experimental and theoretical work. We updated and improved our models for the simulation of Ion Transport in Materials and Compounds (ITMC-DYN), part of HEIGHTS package, to now include dynamic changing of materials composition as result of multiple ion beams bombardment and target atoms mixing, segregation, and diffusion. Implemented models consider detail processes of simultaneous and multiple ions penetration and mixing, scattering, reflection, physical and chemical sputtering of composite material atoms, dynamic surface evolution/modification, thermal diffusion, and surface segregation and recombination of species in multicomponent alloys. For benchmarking of the models we compared our simulations results with several recent experimental data for nanoapplications and for the developments of future fusion energy systems. Simulation of tungsten surface evolution and modification under the impact of hydrogen ions with carbon impurities demonstrated good agreement with recent experiments. Details of surface erosion and conditions for blisters formation as a function of fluence and material temperature were also analyzed and explained.     

The Role of Atomic Collisions in Space Phenomena

Collisions involving electrons, photons, and atomic systems are important in upper atmospheric and astrophysical phenomena and in the exploration of space. Some of these types of reactions are enumerated and described. Examples are given of their significance with respect to diffusion in the atmosphere; radio communications and radar tracking; the excitation and study of the airglow and aurorae; the Van Allen radiation belts; estimation of densities, composition, and temperatures of nebulae and stellar atmospheres; the mapping of hydrogen in interstellar space; and the erosion of space vehicles and planets. Some of the work at the Georgia Institute of Technology on ion mobilities, ion-molecule reactions, ionization, and charge transfer is described.