Concepts and design criteria for the protection of nuclear facilities (and in particular of nuclear power plants) against external impacts in the Federal Republic of Germany

The external impacts which are taken into account for the design of nuclear facilities in the FRG are divided into normal events, accidents and hypothetical events regarding the occurence frequency, and they are correlated as well to the regulations of the radiological protection ordinance of the FRG as to the design practice. The correlations between risk and the design of nuclear facilities are discussed. In greater detail the limits of residual risk are dealt with and the function as an envelope of the design against specific impacts is discussed.     

核动力舰船海上核事故伤员空运后送应急救护

核动力舰船在海上发生核事故时,利用直升机快速转运危重伤员能提升整体救援时效。本文以直8型救护直升机为例,介绍了利用救护直升机开展海上核事故应急救援时应采取的防护措施,以及后送伤员的救护措施。     

核动力潜艇核应急救援中的若干问题研究

介绍了核动力潜艇的事故类别，分析了潜艇核事故应急响应的特点，对海上核救援中的一些特殊问题——应急状态与应急计划区划分、专业技术救援力量的构成及任务、港区烟羽内外复合照射的防护、海上核救援装备与技术保障能力建设、与失事核潜艇处置的相关问题等作了讨论。     

Development of an Atmospheric Dispersion Model for Accidental Discharge of Radionuclides with the Function of Simultaneous Prediction for Multiple Domains and its Evaluation by Application to the Chernobyl Nuclear Accident

A particle random-walk model GEARN for nuclear emergency response system, Worldwide version of System for Prediction of Environmental Emergency Dose Information (WSPEEDI), was improved to predict the atmospheric dispersion of radionuclides in detail around a release point as well as on a regional scale for a transboundary nuclear accident. The main improvement is simultaneous atmospheric dispersion calculations of two nested domains, local and regional areas, achieved by exchanging particle information between the domains. In the application of the model to the Chernobyl accident, the distribution of surface deposition of ¹³⁷Cs was predicted well in the local area around Chernobyl and the European regional area. The improvements were mainly due to the consideration of the reentry of particles from the regional area to the local one and the enhancement of prediction accuracy for precipitation by the nesting calculation in the meteorological model MM5 combined with GEARN. It is concluded that the nesting model developed in this paper is appropriate for nuclear emergencies in which the prediction of both local and regional scale dispersions are required.     

Summary and comparison of current U.S. regulatory standards and foreign standards

This paper presents a summary and comparison of current U.S. regulatory standards, including those developed by industry as well as government, which regulate the construction and operation of nuclear power plants, with those standards in other countries that have developed their own national standards. The countries besides the United States that have been reviewed and surveyed in this paper are Canada, the Federal Republic of Germany (FRG), France, Japan, Sweden, and the United Kingdom (UK). The standards considered are those associated with the areas of siting, mechanical and structural engineering, and materials.     

Some current issues in operational transients

This paper presents a summary and comparison of current U.S. regulatory standards, including those developed by industry as well as government, which regulate the construction and operation of nuclear power plants, with those standards in other countries that have developed their own national standards. The countries besides the United States that have been reviewed and surveyed in this paper are Canada, the Federal Republic of Germany (FRG), France, Japan, Sweden, and the United Kingdom (UK). The standards considered are those associated with the areas of siting, mechanical and structural engineering, and materials.     

日本JCO公司核临界事故的分析与评价

本文介绍了日本JCO公司核临界事故的背景、事故过程、所采取的应急措施等事故情况以及事故的辐射后果。文中还给出了对这起事故直接原因和根本原因的分析以及一些主要结论和看法。这起事故的直接原因是未采用几何临界安全设备及工人的违规操作。而根本原因在于缺乏有效的技术管理。因此,必须充分重视核燃料循环设施中的临界安全问题,提高管理人员和运行人员的安全文化素质。     

福岛核事故后核安全改进行动及安全要求研究

2011年“3·11”日本福岛第一核电厂严重核事故给世界核工业界造成了巨大影响。本文总结了从福岛核事故中汲取的教训,介绍了主要核电国家,如美国、日本、法国以及中国在福岛核事故后十年来实施的一系列核安全改进行动和核安全法规标准修订。阐述了核安全要求和核安全理念在中国的实施现状及实践,包括实际消除早期或大量放射性释放、事故工况划分、纵深防御概念、移动设施配置等,对后续核安全发展方向进行探讨并提出建议。     

Effects of accident management strategy on the severe accident environmental conditions

This paper presents a methodology utilizing an accident management strategy in order to determine accident environmental conditions to be used as inputs to equipment survivability assessments. In the case that there is a well-established accident management strategy for a specific nuclear power plant (NPP), an application of this tool can provide a technical rationale on equipment survivability assessment so that plant-specific and time-dependent accident environmental conditions could be practically and realistically defined in accordance with the equipment and instrumentation required for the accident management strategy or appropriate actions. For this work, three different tools are introduced; probabilistic safety assessment (PSA) outcomes, major accident management strategy actions, and accident environmental stages (AESs). In order to quantitatively investigate an applicability of accident management strategy on equipment survivability, the accident simulation for most likely scenario in Korean standard nuclear power plants (KSNPs) is performed with the MAAP4 code. The accident management guideline (AMG) actions such as the reactor coolant system (RCS) depressurization, water injection into the RCS, the containment pressure and temperature control, and hydrogen concentration control in containment are applied. The effects of these AMG actions on the accident environmental conditions are investigated by comparison to actions from previous normal accident simulation, especially focusing on equipment survivability assessment. As a result, the AMG-involved case shows the higher accident consequences along the accident environmental stages. This implies that plant-specific AMG actions need to be considered in order to determine accident environmental conditions in equipment survivability assessments.     

基于认知模型与故障树的核电厂严重事故下人因失误分析

为分析核电厂应急人员在处理严重事故时可能发生的人因失误,通过建立不同应急人员的认知模型及识别相应的行为影响因子,在认知功能的基础上识别出13种人因失误模式:信息来源不足、信息可靠性不佳、过早结束对参数的获取、重要数据处理不正确、缓解措施负面影响评估失误、选择不适用当前情景的策略、延迟决策、遗漏重要信息/警报、延迟发觉、软操作失误、信息反馈失效、设备安装/连接/操作失误、延迟实施,并基于故障树分析得出人因失误模式的主要根原因:交流失效、时间压力、事故发展的不确定性、信息接收延误、监视失误、人-机界面不佳和环境因素。分析结果可用于预测严重事故缓解进程中可能出现的人因失误,为核电厂实施严重事故管理和技术改进,以及保障严重事故工况下核电厂安全提供参考。      

浅议核电厂应急行动水平制定中环境辐射监测数值的选取

核电厂的应急行动水平是核电厂应急状态的分级依据。环境辐射监测数据在核电厂异常工况和事故情况下对于判断放射性释放水平有着重要作用。本文根据美国核能研究所(NEI)的技术文件并结合国内核电厂的情况,对环境辐射监测数据在应急行动水平制定中存在的问题进行了讨论。     

"切尔诺贝利阴影"与地方核应急心理环境的构建

针对原苏联切尔诺贝利核事故在核应急区人群中产生的心理影响,提出了一个心理学范畴的概念——“切尔诺贝利阴影”,分析了其成因及“阴影”下应急区内社会心理环境的特点,讨论了核应急区内居民和谐心理环境建设的工作重点,为我国地方核电发展创建一个科学、和谐的心理环境提供参考。     

Very high temperature design criteria for nuclear heat exchangers in advanced high temperature reactors

This review summarizes the results obtained in a research programme sponsored by the Ministry of Interior of the FRG on fundamental principles of a structural design code for heat exchanging components in nuclear process heat plants. Materials selection and design data, methods for dimensioning and the limitation of stress, strain, creep fatigue and buckling as well as environmental effects are discussed.     

Role of the man–machine interface in accident management strategies

First, this paper gives a short general review on important safety issues in the field of man–machine interaction as expressed by important nuclear safety organisations. Then follows a summary discussion on what constitutes a modern Man–Machine Interface (MMI) and what is normally meant with accident management and accident management strategies. Furthermore, the paper focuses on three major issues in the context of accident management. First, the need for reliable information in accidents and how this can be obtained by additional computer technology. Second, the use of procedures is discussed, and basic MMI aspects of computer support for procedure presentation are identified followed by a presentation of a new approach on how to computerise procedures. Third, typical information needs for characteristic end-users in accidents, such as the control room operators, technical support staff and plant emergency teams, is discussed. Some ideas on how to apply virtual reality technology in accident management is also presented.     

核电厂安全壳内辐射监测通道读数对一回路屏障功能丧失表征的合理性分析

应急初始条件和行动水平是核电厂应急状态分级的判据。裂变产物屏障功能降级是核电厂应急初始条件和行动水平的识别类之一。本文根据美国的相关技术文件,对国内某核电厂安全壳辐射监测通道读数对一回路屏障功能丧失表征的合理性进行了初步分析。        

内陆代表性厂址事故扩散因子不同估算方法的比较

针对内陆核电选址中小风、静风频率较高的厂址,分别采用美国核管会(NRC)导则推荐方法和运用三维客观诊断风场与Lagrangian烟团模型模拟整年8 760小时逐时排放方法,计算了湖南桃花江厂址事故工况下的大气扩散因子,探讨复杂条件下大气扩散模型的适宜性。研究表明:在非居住区边界概率论方法计算的最大小时事故扩散因子较烟团模型计算方法保守;Lagrangian烟团模型计算的小时事故扩散因子在某些方位大于概率论方法结果,某些远距离子区的扩散因子大于近距离子区;对于释放时间相对较长的情形,导则方法估算结果仍偏小。由此可见,导则推荐方法得到的扩散因子存在不保守的情形,建议在计算复杂地形、小静风频率较高的内陆厂址事故扩散因子时慎重选择扩散模型。     

Safety objectives for next generation reactors: Proving their achievement

Assuming that there is a consensus between regulatory bodies and nuclear operating organizations on safety objectives for future plants, how are we going to demonstrate that they have been achieved, with a reasonable certainty?Right from the beginning, I would like to underline the importance of convincing the public that high level safety objectives will be effectively achieved in future nuclear power plants. The mere fulfillment of administrative requirements might not be sufficient to obtain public acceptance. One has to take into account the changes that have occurred in the public preception of nuclear risks in the wake of the Chernobyl accident. Today public opinion rules out the possibility not only that such a catastrophic accident could recur, but also that any accident with detrimental health consequences off-site could occur. The nuclear industry has to reflect this concern in its safety demonstration, independently of proving the achievement of technical safety goals. The public opinion issue will be readdressed at the end of this paper.     

我国核应急决策支持系统研究开发和现状与展望

国家核应急决策支持系统是以欧洲核应变决策支持系统为技术平台、结合我国核电站的环境特征建立的我国自己的核应急决策支持系统。这个系统可以在发生核事故的情况下,借助于评价模型和有关的环境监测信息,对放射性释放给环境和公众可能产生的风险作出分析和预测,成为决策者确定科学合理的应急防护行为的技术支持工具。本文介绍我国核应急决策支持系统研究与开发工作的组织、进展情况以及今后的应用展望。     

有关核电厂主给水系统设计的探讨

介绍了目前核电厂主给水系统隔离的几种设计方案，从事故进程和核电厂运行事件两个方面阐明了每种设计方案的优劣，得出了符合核安全原则的设计方案，这一分析对核电厂的设计和改造有一定的借鉴作用。     

COSTA: A Computerized Support System for the Emergency Technical Advisory Body in Japan

If an accident resulting in an emergency occurs at a nuclear facility, the emergency technical advisory body (ETAB) is asked to make technical advice to the national government for emergency response. In order for the ETAB to carry out its role, a significant amount of materials containing information on nuclear power plants is prepared in the ETAB. These materials are all paper copies and very voluminous. Therefore it is required that they should be computerized for more effective use. Further, methods should be developed which aid the ETAB to understand the status of the affected facility and to predict potential radioactivity release to the environment.

To support the ETAB's activities in an emergency, the materials have been computerized as databases for more effective and quick use of them, and an expert system has been developed to quickly predict accident progression and environmental fission product release with the multivariate analysis method. The databases and the expert system have been unified to be a system of COSTA. The first phase of developing COSTA has been completed in FY1992. This paper describes the present status of development of COSTA.