核电厂运行人员资格

核电厂运行人员的素质是安全运行的重要问题之一,本文就核电厂的组织机构、岗位、运行人员的能力、培训、考核和人员管理等方面进行论述。     

反应堆操纵员培训及考核的有关问题

反应堆操纵员是核电厂安全稳定运行的基本保证,对操纵员的筛选、培训和考核尤为重要。但随着核电的发展,以及社会民众对电厂安全性要求的提高,目前我国的反应堆操纵员的培训与考核在某些方面已逐渐不能适应我国核电发展的需求。笔者分析了现阶段我国操纵员考核制度、培训手段、选拔方式等方面的不足,结合我国核电发展对操纵人员的要求,提出操纵人员考核及管理体系可优化性、加强复杂工况培训以及重视操纵员心理素质等方面的一些观点。     

海阳核电厂设备监造管理实践

本文基于山东海阳核电厂设备监造管理的实践,对营运单位的监造组织机构、监造人员培训与授权、监造文件体系、监造分级管理、经验反馈与信息化建设、监造人员派驻和对监造单位的评价与考核等方面进行了详细的阐述,对核电厂设备监造管理具有借鉴作用.     

核电厂应急操作规程的几个问题

本文介绍了作者多年在核电厂模拟机事故培训中所积累的一些亲身体会，其中包括如何正确理解的使用应急规程，以及应急规程使用中对核电厂操纵人员的要求等。     

核电厂DCS模拟机中数据回放技术的设计与实践

在核电厂操作员培训时,为了使教员能检测操作员的操作过程是否正确,需要分散控制系统（DCS）模拟机具备数据回放功能。该功能是模拟机与实际DCS最大的区别,也是模拟机实现的难点。本文论述了数据回放技术的设计与实现方法,通过对系统中的数据、事件、鼠标键盘操作分别进行存储和查询来实现数据回放的目的。该技术已经在核电厂DCS模拟机产品SpeedySim中实现,并在阳江核电站5号、6号机全范围模拟机系统中得到了良好的应用,可以推广到其他模拟机产品和模拟机系统应用中。      

田湾核电站多机组模拟机管理系统设计与研发

田湾核电站全范围模拟机主要用于机组主控室运行人员的培训与授权,是主控室操纵员培训的重要工具和手段,需要最大限度地保证与机组的一致性和可用率。为了使田湾核电站模拟机管理系统符合国家能源行业标准,同时能够实现模拟机的电子化全方位管理,中国核动力研究设计院设计和开发了多机组模拟机管理系统。该系统保证了模拟机的维护和管理符合行业标准,提高了核电厂模拟机管理水平。目前,该系统已成功应用于田湾核电站1/2号机组模拟机管理,并可在将来直接应用于3/4号、5/6号机组模拟机。同时,该系统可通过少量定制开发的方式向其他在役及新建核电机组供货。     

美俄联手为科拉4核电站开发全规模模拟机

【英国《国际核工程》2000年8月刊报道】 反应堆操作人员在核电站性能方面的培训和技术知识是提高核电站运行安全的关键因素。众所周知,模拟机为核电站制定可行的培训计划发挥着极其重要的作用。 全规模模拟机和分析模拟机对于反应堆的操纵员来讲就是这样的培训工具。这两种模拟机都需要与模拟模型相同的规模。一台全规模模拟机带有控制面板,它是操纵员和模拟计算机之间接口的实际控制板的复制品。分析模拟机用个人机作为操纵员和模拟计算机之间的接口。核电站通过这些工具对反应堆的操纵员进行正常和异常运行以及应急和事故响应能力方面的…     

广东大亚湾核电站基本原理模拟机投入运行

我国第一台核电站基本原理模拟机已于1988年11月25日投入运行。由目前我国最大的商用核电站——广东大亚湾核电站——从法国引进的这套基本原理模拟机(BASICPRINCIPLE SIMULATOR)是按该电站两台900MW 压水堆机组的简化模型设计、生产的。主要用于对核电站运行岗位人员的初始培训,以便于他们理解和掌握核电站运行中产生的各种物理过程。随后,他们将在全范围模拟机(FULL SCOPE SIMULATOR)上进一步培训,以掌握核电站正常和异常工况下进     

后处理主工艺操纵人员持照岗位设置探讨

乏燃料后处理设施主工艺操纵人员是关系设施核与辐射安全的重要专业技术人才,有必要对安全重要的操纵岗位实行操纵人员持照管理。在乏燃料后处理设施主工艺的首端、铀钚分离、铀尾端和钚尾端四大工序中,对其所执行的安全功能、潜在事故以及历史发生的人因事故开展了分析和比较。研究发现:首端、铀钚分离、铀尾端和钚尾端四个工序均执行了预防临界、放射性物质包容和外照射防护的安全功能;历史发生的人因事故更多地集中在铀钚分离、铀尾端或钚尾端三类工序;首端、铀钚分离、铀尾端和钚尾端四大工序的操纵岗位都有必要设置相应的持照岗位并开展操纵人员资质管理。     

核电厂操纵员态势感知方法研究

通过对人员进行心理培训和在操纵室中搭建数字化信息模型,可以减少操纵员的人为差错,从而有效的防止事故的发生.基于这些年来国内外对人因失误展开的研究,提出在影响人员操作方面存在的问题,如操纵人员的感知错误、信息呈现方式复杂、报警装置失效,信息传递失效等.并对此类问题给出相应解决方法:不同信息呈现方式获取操纵员的态势感知变化...     

Recent Training Technology of BWR Operators Using Full Scope Simulators

Nuclear power plants are being operated at high standards now in Japan. There are far few opportunities for operators to perform in challenging situations. To maintain skill and refinement, the simulator training is indispensable for them.

BWR Operator Training Center (BTC) provides training courses according to the grade and duty of the operators. The training force constitutes of personnel from utilities', manufacturers' and also BTC-hired personnel.

One of the big features of BTC training is composite team type. In this form of training, men from different plants make a team and help each other study.

On the human factor viewpoint, error experience on simulators is one of the important items. Training on recognizing subtle symptom is an example of a recent development. Team training for actual crew is effective from various viewpoints.     

Development of severe accident management advisory and training simulator (SAMAT)

The most operator support systems including the training simulator have been developed to assist the operator and they cover from normal operation to emergency operation. For the severe accident, the overall architecture for severe accident management is being developed in some developed countries according to the development of severe accident management guidelines which are the skeleton of severe accident management architecture. In Korea, the severe accident management guideline for KSNP was recently developed and it is expected to be a central axis of logical flow for severe accident management. There are a lot of uncertainties in the severe accident phenomena and scenarios and one of the major issues for developing a operator support system for a severe accident is the reduction of these uncertainties. In this paper, the severe accident management advisory system with training simulator, SAMAT, is developed as all available information for a severe accident are re-organized and provided to the management staff in order to reduce the uncertainties. The developed system includes the graphical display for plant and equipment status, the previous research results by knowledge-base technique, and the expected plant behavior using the severe accident training simulator. The plant model used in this paper is oriented to severe accident phenomena and thus can simulate the plant behavior for a severe accident. Therefore, the developed system may make a central role of the information source for decision-making for a severe accident management, and will be used as the training simulator for severe accident management.     

核电工作人员模拟机培训和考核方法探讨

核电厂操作员模拟机培训和考核，是核电厂运行安全中极为重要的问题，本文介绍了清华大学核电厂模拟培训中心自１９８８年建成以来举办的各种类型的核电工作人员培训班，并详细分析了各类培训班，老操作员在职再培训班和各种类型核电管理人员培训班等的不同特点，详细介绍了清华大家核电厂模拟培训中心对不同培训班的课程设置、考核方法和评分标准等问题。     

大亚湾核电站工作人员体表放射性沾污的控制

核电站运行和检修作业具有一定的体表放射性沾污风险。本文从污染源控制，隔离，工作过程管理，人员培训和经验反馈等几个方面，介绍了广东大亚湾核电站对工作人员体表放射性污染的控制和防护，并通过核电站大修中发生的几起体表沾污事件的分析，对防护措施进行了讨论。     

Nuclear power plant licensing and supervision in the Federal Republic of Germany

This paper briefly describes nuclear power plant licensing and supervision in the Federal Republic of Germany (FRG). Peculiarities due to the federal structure of the FRG are outlined paying due regard to the long tradition of using consultation by qualified and independent technical experts. The participating authorities, commissions, expert organizations, vendors, utilities and the public as well as their respective competences are mentioned. Also, the hierarchy in nuclear legislation by means of ordinances, administrative regulations, guidelines and technical standards is pointed out. Typical examples are presented. The paper ends in mentioning important items concerning the evaluation of operating experience, recurrent tests, backfitting, lessons learned from the Chernobyl accident, safety research concerning accident management measures, on-site and off-site emergency planning, as well as qualification and occupational training of the responsible shift personnel.     

状态报告管理在HFETR上的应用分析

状态报告是核电厂开展经验反馈的基础,通过学习和借鉴核电厂状态报告管理方法可以完善高通量工程试验堆(HFETR)的经验反馈制度,提高HFETR运行的安全性和日常运营管理水平。本文首先对核电厂状态报告体系开展了初步的分析;然后结合HFETR运维管理水平分析了相应的状态报告实施策略和组织接口,建立了HFETR状态报告事件分级准则,并完成了相关事件分级工作;最后本文为HFETR实际实施状态报告开发出模板,建立了状态报告流程,并提出了后续工作的重点内容。本文的研究为推动HFETR建立状态报告管理体系奠定了基础。     

核电厂在役检查技术验证方法对比

以基于ASME规范的验证方法和ENIQ验证方法为对象,讨论2种在役检查技术验证方法的特点及其各自存在的问题。ASME规范要求的验证方法侧重于某一类部件检测技术的验证,强调盲测试验和判定验证的统计学证据的重要性;对于某些特定部件检测技术的验证,ASME规范XI卷附录Ⅷ中的相关规定不够明确。ENIQ验证方法强调通过技术论证和实际测试的结合进行验证,适应性较强。通过比较2种验证方法的特点,对我国的在役检查技术验证提出建议。     

核电厂蒸汽发生器多功能模拟体研制

在压水堆核电厂蒸汽发生器的在役检查和维修中，需要使用蒸汽发生器模拟体，预先对检修工器具进行调试、验证以及人员的培训。基于蒸汽发生器模拟体的功能需求和设计要求，研制了一种可满足多种需求的蒸汽发生器模拟体，模拟体总体结构设计为原型二分之一，选用复合材料，并设置有观察窗。模拟体具有结构紧凑、经济性高、可观测等特点。功能试验验证结果表明，本文所述蒸汽发生器模拟体可有效用于核电厂蒸汽发生器的检修培训。      

Safety experience on EDF's PWRs

Following a brief presentation of the safety organization in France and of the safety implications of the standardization policy adopted for the PWRs programme, the paper will review the safety experience acquired in France on this programme.The prevention of severe accidents following Three Mile Island in 1979 was considered a first priority in the French safety approach. EDF has developed an ultimate procedure based on the characterization of every possible cooling state of the core which allows the operators to prevent severe core degradation. Ultimate safety features, such as filtered-venting of the containment's atmosphere, aim at mitigating the consequences for the environment of any core melt accident.Today our first objective is to keep the highest possible level of safety in operation. The first issue is personnel training. Due to the complexity of nuclear power plants, the human factor plays a significant role in all incidents and accidents. We have learnt the importance of specific training for accidental situations, making use of sophisticated simulators. The second issue is operational experience feedback. The system set up by EDF will be described.Although not all data relative to the Chernobyl accident are known, the lessons learnt from that very important event will be described, as used to improve the safety of French nuclear power plants, especially on radioactive accidents' management.