船用核动力的发展特点与启示

美国、前苏联/俄罗斯船用核动力技术长期保持世界领先,其发展经验和技术脉络具有极高的参考价值。本文通过对美国、前苏联/俄罗斯船用核动力发展的主要历程和技术进行分析研究,创新总结归纳出其反应堆系统基本型、通用试验平台、差异化配置等共同发展规律,并从管理模式、技术路线以及发展趋势等方面挖掘提炼出美国和前苏联/俄罗斯船用核动力技术遵循的一系列共性特点和差异化特征,可为船用核动力发展提供一定的参考和启示。      

Seismic re-evaluation of nuclear facilities worldwide: overview and status

Existing nuclear facilities throughout the world are being subjected to severe scrutiny of their safety in the event of an earthquake. In the United States, there have been several licensing and safety review issues for which industry and regulatory agencies have cooperated to develop rational and economically feasible criteria for resolving the issues. Currently, all operating nuclear power plants in the United States are conducting an Individual Plant Examination of External Events, including earthquakes beyond the design basis. About two-thirds of the operating plants are conducting parallel programs for verifying the seismic adequacy of equipment for the design basis earthquake. The U.S. Department of Energy is also beginning to perform detailed evaluations of their facilities, many of which had little or no seismic design. Western European countries also have been re-evaluating their older nuclear power plants for seismic events often adapting the criteria developed in the United States. With the change in the political systems in Eastern Europe, there is a strong emphasis from their Western European neighbors to evaluate and upgrade the safety of their operating nuclear power plants. Finally, nuclear facilities in Asia are also being evaluated for seismic vulnerabilities. This paper focuses on the methodologies that have been developed for re-evaluation of existing nuclear power plants and presents examples of the application of these methodologies to nuclear facilities worldwide.     

美、俄两国核电与铀工业的现状及走向

介绍了美国和俄罗斯的核电、铀生产现状及未来走向。美国与俄罗斯是世界上最早拥有核电的国家。历经40多年的发展，美国的核发电量占全美总发电量的20％，俄罗斯则为11％(2001年）。美国核电用铀的6％出自本土；而俄罗斯的铀产量的近一半用来出口。美国的未来核电用铀在很大程度上将依从于国际市场和各级、各类铀的库存；在安民兴国的氛围中，俄罗斯依托其殷实的铀资源，确立了核发电宏图。可以认为，尽管美国与俄罗斯两国核电、铀工业的走向会对世界铀矿地质勘查和铀生产产生重要的影响，但全球铀工业在近10a里仍将呈现供、需基本平衡的态势。     

General review of recent activities in acoustic emission technology in Italy

This paper describes the present situation in Italy in the field of Acoustic Emission researches and applications.Information on the level of instrumentation development is given. Both multichannel and multiparameter systems for large structure examination in real time and data logging systems for continuous surveillance purposes are considered.The expertise accumulated in the application of AE to pressure vessel examination during hydrotest is mentioned, this being oriented to pressure components of conventional power stations and chemical plants.Particular attention is recently paid to mechanical fatigue tests. These were conducted on intermediate PWR nuclear pressure vessel, reduced scale offshore nodes and full scale prototype aircraft.A considerable activity has been carried out on application of AE technique to the detection of fluid leakages in power plant components. Both intrusive and non-intrusive methods have been considered. Many boilers and pre-heaters of thermal power plants have been instrumented for an on-line AE monitoring during operation. The problem of the loose part monitoring has been also considered.Several basic researches for material characterization by AE have been also conducted. Different composite material, carbon and austenitic steels, metal alloys have been studied.     

理想的空间电源—空间核反应堆

本文对空间电源、空间核动力反应堆进行了讨论,重点介绍了美国、前苏联和法国在空间电源领域的空间核动力反应堆技术的现状及发展。     

Preservice and inservice requirements for containment structures in the United States - A status report

Assuring the lifetime integrity of containment structures for nuclear power plants is becoming increasingly important as existing design criteria are reexamined, as new requirements for containment inspection and testing are formulated, and as today's operating nuclear plants are growing older.The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code contains requirements for the design and construction and for the preservice and inservice requirements for nuclear power plant systems and components in the United States. Section III of the ASME Code contains the rules for design and construction of nuclear systems and components. Rules for the preservice examination, inservice inspection, system pressure testing, repair, modification and replacement of nuclear systems and components are contained in Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components. Compliance with the rules of the ASME Code in the United States is mandated by the federal government in Title 10, Part 50 of the Code of Federal Regulations (10CFR50).Section XI of the ASME Code contains separate rules for metal (Class MC) and concrete (Class CC) containments. Requirements for Class MC containments have been published in Subsection IWE, Requirements for Class MC Components of Light-Water Cooled Power Plants, of Section XI. Rules for Class CC containments are currently being developed and will be published in Subsection IWL, Requirements for Class CC Components of Light-Water Cooled Power Plants, of Section XI.First published in 1981, Subsection IWE has been adopted by a number of state jurisdictions in the United States and is presently being reviewed by the United States Nuclear Regulatory Commission. Federal regulations that will require mandatory compliance by nuclear plant owners are forthcoming. When implemented, the requirements in Subsection IWE and Subsection IWL will provide a reasonable and systematic basis for assuring the integrity of metal and concrete containment structures during their service lifetime.This paper presents an overview of the preservice and inservice requirements for containment structures in Section XI of the ASME Code with consideration of the practical factors that should accompany user compliance.     

252Cf生产关键技术及展望

²⁵²Cf是一种重要的超钚元素,可用于核反应堆启动、中子照相、中子活化分析、地质勘探等核技术应用及基础科研,目前世界上只有美国和俄罗斯具备²⁵²Cf生产能力。本研究对²⁵²Cf基本性质、国外²⁵²Cf生产现状进行介绍,提出²⁵²Cf生产需攻克的关键技术。     

内陆核电建设的主要环境问题解析

通过对同时拥有滨海和内陆核电厂的国家（美国、法国、德国和西班牙等）关于这两类厂址的放射性流出物排放管理限值的对比,对我国内陆核电站放射性流出物的排放限值的制定提出了相应的建议。然后对这几个国家的内陆核电厂冷却方式进行分类统计,调查、分析了采用完全一次直流冷却方式的内陆厂址的自然水文条件,将其与国内主要的河流和湖泊等内陆水体水文条件进行比较,并针对我国首批内陆厂址的水文条件,提出冷却方式选择的初步建议。最后,对我国内陆核电建设的主要环境问题（放射性污染问题、热污染问题和废水管理中的其他问题）进行分析,并提出相关的建议。     

Lifetime integrity requirements for containments in the United States

Assuring the lifetime integrity of containment structures for nuclear power plants is becoming increasingly important as existing design criteria are reexamined, as new requirements for containment inspection and testing are formulated, and as today's operating plants grow older. Regulatory requirements for containments in the United States are contained in the Code of Federal Regulations and in the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code. New requirements for the preservice examination and inservice inspection of Class MC (metal) containments have been published in Section XI, Subsection IWE, of the ASME Boiler and Pressure Vessel Code. Requirements for Class CC (concrete) containments have been published in Subsection IWL. Federal regulations that will require mandatory compliance with the ASME Code by nuclear plant owners in the United States are forthcoming. Parameters for extending the life of current United States nuclear plants beyond the 40 year design lifetime are presently being formulated. Two pilot plant life extension (PLEX) studies, one for a BWR and one for a PWR, serve as models for extending the life of today's aging plants.This paper presents an overview of the regulatory requirements for containments in the United States and the new preservice examination, inservice inspection and related requirements for Class MC and Class CC containments in the ASME Boiler and Pressure Vessel Code. Operational and life extension considerations for containment structures, including the findings from pilot studies of typical PWR and BWR containments, are also discussed. Together, the regulatory and Code requirements and recommendations from the plant life extension studies provide a basis for improved lifetime integrity for containments in the United States.     

福岛核事故后核电厂安全改进行动分析

介绍了福岛核事故后世界上主要核电国家相继开展的核电厂安全检查、再评价行动,并得出相应的检查和测试结论。法国、美国和中国等国家分别提出了福岛核事故后改进核电厂安全的建议、要求和行动,并制定了具体工程措施：在极端外部事件的设防,严重事故预防和缓解,水、电、通风实体改进,限制严重事故下的放射性释放和应急准备等主要方面开展的安全改进行动,将会提高核电厂的安全水平并提升缓解严重事故的能力。反思福岛核事故,总结福岛核事故对核电安全技术改进的促进作用,对未来核电安全技术的发展进行了展望。     

核电项目组织机构体系的探讨

为了落实国家"积极推进核电建设"的方针,推进我国核电建设自主化、专业化发展,实现核电工程管理与国际接轨,我国先后组建成立了多家核电工程公司,并承担了商用核电项目工程建设任务。通过对我国核电工程公司在核电建设中的角色及其项目组织机构的调研和分析,并结合国外有关工程公司在组织架构等方面的比较,对优化我国核电工程公司项目组织机构体系等方面进行了探索,旨在使我国核电工程公司早日成为国际一流的工程公司,并具备承担大型非核工程总承包的能力,为进入国际市场打下良好基础。     

核电厂通用老化经验报告分析与编制建议

美国核管会编制发布的通用老化经验报告是美国核电厂运行执照更新的基石文件,对指导核电厂设计、运行和延寿,包括水化学管理、在役检查等老化管理工作具有重要意义.同时国际原子能机构也组织各成员国共同开发国际通用老化经验报告,而国内尚未编制中国核电厂通用老化经验报告.本文从报告适用性、老化经验积累与反馈、老化管理和科研水平提升等...     

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.     

Seismic IPEEE industry insights

The United States Nuclear Regulatory Commission initiated a formal review of the seismic margin of all operating nuclear power plants in the US with the issuance in 1991 of Generic Letter 88-20, Supplement 4 (‘Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities’). Virtually all of the US nuclear utilities have submitted their responses for seismic IPEEE and these submittals are in the process of being reviewed by the NRC. The objective of this paper is to provide an industry perspective on the results and the insights obtained from the utility seismic IPEEE submittals.     

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.     

Repair materials and techniques for concrete structures in nuclear power plants

The paper summaries portions of work of the Structural Aging Program, sponsored by the Nuclear Regulatory Commission (NRC). The paper addresses the assessment and repair of concrete structures in nuclear power plants. It presents the results of a survey of the the nuclear power plants in the United States to identify susceptible concrete components, rates of occurrence of deterioration, and to determine the durability of repairs. The paper describes deterioration mechanisms and discusses their effect. Repair techniques are described. Evaluation techniques and nondestructive test techniques are also discussed.     

Westinghouse AP1000 advanced passive plant

The Westinghouse AP1000 Program is aimed at making available a nuclear power plant that is economical in the US deregulated electrical power industry in the near-term. The AP1000 is a two-loop 1000 MWe pressurizer water reactor (PWR). It is an uprated version of the AP600. Passive safety systems are used to provide significant and measurable improvements in plant simplification, safety, reliability, investment protection and plant costs. The AP1000 uses proven technology, which builds on over 35 years of operating PWR experience. The AP1000 received Final Design Approval from the United States Nuclear Regulatory Commission in September 2004; the AP1000 has also received Design Certification by the USNRC in December 2005. The AP1000 and its predecessor AP600 are the only nuclear reactor designs using passive safety technology licensed anywhere in the world. The safety performance of AP1000 has been verified by extensive testing, safety analysis and probabilistic safety assessment. AP1000 safety margins are large and the potential for accident scenarios that could jeopardize public safety is extremely low.Simplicity is a key technical concept behind the AP1000. It makes the AP1000 easier and less expensive to build, operate, and maintain. Simplification also provides a hedge against regulatory driven operations and maintenance costs by eliminating equipment subject to regulation. The AP1000's greatly simplified design complies with NRC regulatory and safety requirements and the EPRI advanced light water reactor (ALWR) utility requirements document.Plans are being developed for implementation of the AP1000 plant. Key factors in this planning are the economics of AP1000 in the de-regulated US electricity market, and the associated business model for licensing, constructing and operating these new plants.     

核电AE组织形式、特点与产业价值

文章以中广核工程有限公司扁平化、分权化、柔性化组织为研究对象,分析中广核工程有限公司通过构建设计建造一体化的平台,整合产业链相关资源,有效保证核电站建设的整体性能与安全质量,发挥系统集成与行业引领的作用;通过建立跨边界质量管控的全面质量伙伴关系,促进产业链企业质量管理水平的提升;通过开展技术协同创新,推动产业链技术进步。最后探讨了中广核工程有限公司推进核电AE组织变革对当前国企改革、工程施工企业产业升级的借鉴意义。     

俄罗斯氧化物乏燃料电沉积流程研究进展

高温熔盐干法后处理以熔盐作为电解质，通过电解精炼和电沉积回收核燃料中的铀和钚。目前，俄罗斯、美国、日本、韩国和欧盟等国均在积极发展乏燃料高温熔盐干法后处理技术的研究，其中俄罗斯的金属氧化物核燃料电沉积流程是经典的流程之一。本文对俄罗斯原子反应堆研究所（Research Institute of Atomic Reactors,RIAR）发展的氧化物乏燃料高温熔盐电沉积干法后处理的发展现状、流程及特点进行了综述。     

浅谈我国核电厂重要厂用水系统换热器隔离阀门与放射性监测仪表配置优化

对于运行核电厂来说,重要厂用水系统与质量和安全密切相关.核电厂重要厂用水系统用于导出设备冷却水系统所传输的热量,将其输送到海水中,因此是核岛的最终热阱.本文描述了当前我国大部分核电厂重要厂用水系统换热器隔离阀门与放射性监测仪表的配置现状,分析了包括美国、法国以及国际原子能机构对于重要厂用水系统设计要求的相同点与不同点,...