大亚湾核电站换料大修过程中人因失误及经验反馈

介绍了大亚湾核电站换料作过程中的各类人因失误以及通过事件根本原因分析后所采取的防范措施，大亚湾核电站认为，处理人因失误关键在于发现事件的事实真相，以避免人因失误的重复发生或使事故后果更进一步恶化。大亚湾核电站运动经验证明，增加事件透明度，有利于经验反馈工作的开展生防止重大人因失误。     

对因工作人员走错机组隔间导致的核电厂人因事件的探讨

介绍了一起因走错机组隔间导致误操作继而引发反应堆停堆的运行事件。通过对这一类型事件的深入探讨,找出导致事件发生的原因,提出了改进建议。可为其他核电厂提供参考,以期避免类似事件的重复发生。     

一回路环路流量及堆芯总流量超过机械设计流量的原因分析和改进建议

介绍了国内法系核电机组在首循环出现一回路环路流量及堆芯总流量超过机械设计流量限值的一系列运行事件。通过对这一类型运行事件的深入探讨,找出导致事件发生可能原因,进行安全影响分析,提出了建议纠正的措施。可作为运行机组以及后续新建机组的参考,以期避免类似事件的重复发生     

核电厂堆芯中子通量测量系统典型失效分析

针对核电厂日常运行过程中存在的堆芯中子通量测量系统故障频发问题,研究堆芯中子通量测量系统典型失效事件,包括指套管磨损深度超标、闪发密封组件泄漏报警及中子通量测量探头卡涩问题。通过对典型失效数据和异常事件的收集,分析三类异常事件的发生原因。总结处理类似异常事件的原则和经验,提出了有针对性防范措施和相应的防护对策,避免类似事件的重复发生。     

核电厂走错间隔类人因事件的分析及预防

随着我国核电事业的发展,越来越多的核电机组投入商业运行。在核电机组运行维护过程中,易发生人员走错间隔误动作设备等人因事件,影响核电厂的安全稳定运行和绩效考核指标。为了减少核电厂走错间隔类人因事件的发生,本文结合真实案例分析了三种典型走错间隔类人因事件,归纳了走错间隔类人因事件发生的原因,提出增加技术防范屏障、使用防人因失误工具、实操培训、管理屏障、经验反馈五种实践可行的预防措施,可有效避免走错间隔类人因事件的发生,对核电厂防走错间隔工作有借鉴意义。     

辐射事故

对５０年间的辐射事故分析表明，非常简单的事例，即初始始事件得到立即确认、确定源的情况并加以控制、医疗方面也限于常规处理等，这种情况是不多见的。更多的情形是，直到受害者身上的某些损伤昭示了事故原因与放射有关，才识别到事故是发生了。而在大规律的事故后，事态更为复杂，一方面是由于管理的问题，另一方面是医疗处置方面的原因，或者兼而有之。本文对某些带来严重后果的事件进行了评述，提出这些事故大多原本是可以避免     

国内核电厂堆外核测系统相关运行事件分析

按照堆外核测系统的设计、制造、运行过程,统计分析我国核电机组堆外核测系统相关运行事件;根据设备故障、程序缺陷、设计缺陷、人因失误和环境失控的分类原则,对上述事件的发生原因进行分类统计;从直接原因和根本原因两个方面总结和归纳每起事件研究堆外核测系统的薄弱环节;总结处理类似事件的原则和经验,提出有针对性的防范措施和相应的防护对策,避免类似事件的重复发生。     

大亚湾核电站人因事件分析与预防对策

大亚湾核电站商运三年来，在运行，维护过程中发生的人因事件，总计３６８起，占事件总数的３９％。人因事件主要发生在维修，试验，设备隔离和系统在线过程中，而以大修期间最为突出，文中分析了人因事件的根本原因，误操作，规程缺陷，未遵守规程，培训不足，通讯联络不够，工作组织不力等，提出了预防对策和处理原则，并列举了出相应人因事件的典型实例，最后指出，在预防人因事件过程中，最重要的环节是协调管理，选取最关键岗位     

关于Davis-Besse核电站事件的分析与认识

针对2002年Davis-Besse核电站反应堆压力容器（RPV）上封头腐蚀事件,从4个方面进行了事件原因分析。为避免Davis-Besse事件的重发,提出了几点具体的措施和建议。     

快速关联事件时间分布测量线路设计

对氘／固体系统热循环异常物理现象的研究工作中，骤发中子群的关联事件时间分布测量专用电路的设计、工作过程作了说明。本电路主要用于记录关联主触发事件发生后１２８μｓ时间内，关联事件（骤发中子群）发生的时间和数量。其事件时间分布分辨能力≥０．５μｓ，最大事件计数率为２×１０６ｓ－１。参照逻辑框图，可以对快速关联事件时间分布测量的数据采集过程、实现方法得以了解     

中子活化分析在当代无机痕量分析计量学中的作用Ⅰ.相对法中子活化分析(NAA)作为比较基准法资格的论证

丛三个方面讨论了NAA在现代无机痕量分析计量学中的地位和作用：(1)相对法NAA作为比较基准法资格的论证;(2)参量法NAA作为相对法NAA“辅助”方法的特殊功能;(3)NAA在适用于微分析质量控制的新一代标准物质表征中的作用。作为首篇,本文对NAA,特别是纯仪器NAA(INAA)的原理、不确定度和溯源性作一分析,说明相对法NAA在当前最高水平上满足了“物质量咨询委员会”(Consultative Committee for Amount of Substance,CCQM)关于比较基准法的判据。举例分析了NAA的溯源性和不确定度,进一步证明NAA的比较基准法资格,并讨论了NAA作为比较基准法的优点、当前的适用范围和可能的未来进展。最后列出了几个有关的计量学术语的定义和国际规范。     

铁素体-马氏体钢P92在超临界水中的腐蚀性能

研究了P92钢在550和600℃超临界水中的腐蚀特性,采用扫描电镜、X射线能谱仪和X射线衍射仪分析了氧化膜的表面形貌、组织结构和元素分布。结果表明：P92钢在超临界水中的氧化动力学大致服从立方生长规律,600℃下P92钢的腐蚀增重和氧化膜厚度均为550℃时的3倍。P92钢在超临界水中形成的氧化膜为双层结构,氧化膜外层富Fe,而内层富Cr。600℃时P92钢氧化膜发生了开裂和剥落,其原因主要在于降温过程中基体与氧化物间的热膨胀系数不相匹配而产生的较大热应力。     

Development of HTGR-coated particle fuel technology in Korea

The status of R&D works being carried out for the development of the technology for the coated fuel particles and the achievements in the first phase in Korea is described. Emphasis is given to the development of the laboratory equipment and apparatus and the first results of the experiments carried out for the kernel preparation and coating of PyC and SiC as well as their respective characterizations and relevant quality control (QC) methods. The current status of the in-reactor performance model and the analytical code development are included as well as some preliminary results from the feasibility study on the irradiation test of the fuel specimens in the HANARO research reactor in Korea. Also discussed are the essential involvements in the GIF collaboration and with the IAEA as well as other international collaboration schemes during the development.     

EGS程序光子输运模型研究进展

随着EGS在辐射物理和医学物理等众多方面的广泛应用,其物理内核被EGS开发小组所不断更新,光子的输运模型也越来越完善.本文综述了光子输运模型的进展,包括线性极化光子散射、康普顿散射中的电子约束等效应以及光子截面数据库的更新.     

Overview oil Development of High Reliablility Nuclear Power Plant in Japan with Particular Emphasis on Fuel and Materials

To begin with the concept of nuclear safety in Japan, efforts to achieve power reactor operation with higher reliability and safety have been discribed. More strict regulatory criteria, standards as well as the better quality control with excellent workmanships have led to this world's best performance today.

Successful development work of fuel and materials, in fundamental work as well as in practical work through the co-operation among research organizations, university people, reactor, fuel and cladding tube manufacturers together with electric utilities has contributed a great deal to achieve this.

Improvement and standardization work followed by the development of ALWR and then next-generation LWR have been going on by reflecting our experiences during 18 years of operation as well as the results of our technological development in fuel and materials.     

Source papers in reactor noise

Reactor noise analysis is of practical importance in securing the safety and availability of nuclear power plants. Recognition of this importance is well disseminated among personnel engaged in research and development as well as supply and management of nuclear energy. Many more people will become concerned with and disciplined in reactor noise signature analysis in the future in order to further develop the technique for its application in balance-of-plant surveillance and diagnostics.

Newcomers to any well matured research field are, however, often perplexed by the quantity of relevant scientific papers; the fruits of creative and earnest research work. Noise analysis research originated as early as the 1940s. This presentation of fundamental and initial breakthrough papers will be useful for newcomers, as well as graduate students of nuclear engineering, who will be, hereupon, informed of the most important developments which have led to our present understanding of the subject.

The author sincerely welcomes any specialist of noise analysis to criticize and supplement this article.     

Electrochemical oxygen sensors for on-line monitoring in lead-bismuth alloys: status of development

This paper presents the state of development of oxygen sensors based on the electromotive force (emf) measurement at null current, using yttria stabilized zirconia as solid electrolyte for application in liquid lead-bismuth eutectic (LBE), which is envisaged as a nuclear coolant or as a spallation target in accelerator driven system (ADS) for nuclear waste transmutation. The assembly procedure, the calibration method, as well as the summary of the various validation tests undergone in both static and loop facilities are presented so as to define a real state of achievement and the basics needs for further studies. The sensors are efficient, accurate, rapid and reliable for research loops. However, the poor mechanical resistance as well as the effect of traces of impurities, promoting an increasing time-drift under certain conditions, are to be further studied to improve the sensor reliability for a nuclear use. The oxygen and chromium solubilities were reassessed in the process of the sensor testing, those relations are also given and discussed.     

Criteria for seismic analysis of nuclear plant structures and substructures

This paper encompasses criteria used for seismic analysis of nuclear power plant structures such as supporting structures founded on ground, as well as substructures. Nuclear power plant equipment and systems can be treated as substructures. Modeling of structures and substructures is described. Since instructure response spectra play an important role in the design and analysis of nuclear power plant equipment, systems and components, methods for development of instructure response spectra as well as variations of input parameters considered in determining these spectra are described.When the principal contribution to the equipment response is due to flexibility of the supporting substructures, an analytical approach to the problem for obtaining reduced stiffness and associated mass matrices of supporting substructures with finite element representation for use in the dynamic analysis of equipment and supporting structures is presented. When supporting structures and equipment, that have inherently different damping properties, are included as intergral parts of the dynamic models, the approximate evaluation of the modal damping based on the weighted damping according to the modal energy stored in each component is outlined. Use of time history and response spectrum analyses is presented. The effects of relative displacements due to different motion of the support points of substructures in each significant mode of the supporting structures as well as procedures of combining modal responses are detailed.     

Mechanisms and theory of physical sputtering by particle impact

This article summarizes theoretical work on sputtering during the past decade, with the emphasis on elemental sputtering in the linear cascade and spike regimes as well as alloy sputtering. The sputtering of molecules and clusters, and electronic sputtering of insulators and biomolecular materials are discussed more briefly, and topics like charge and excitation states of sputtered particles as well as surface topography are left out, in view of contemporary summary papers in this issue and elsewhere. The paper is nontutorial and assumes some general knowledge of the field on the part of the reader, based e.g. on ref. [1] or ref. [2]. The discussion emphasizes principles and methods as well as open problems rather than quantitative results. A few general recommendations for efficient utilization of computer simulation conclude the paper.