Small and Medium Power Reactors in developing countries — Present status

Introduction of Small and Medium Power Reactors (SMPRs) in the electrical grids of developing Member States is a long standing programme for the International Atomic Energy Agency. This presentation describes the activities of the Agency in this area for the last few years and discusses the advantages of SMPRs for developing countries with small grids. Constraints which hinder the introduction of SMPRs are also described as are suggested ways to overcome the constraints.     

秦山核电二期扩建工程施工安全总体业绩指标及相关性实证研究

对秦山核电二期扩建工程建设期间施工安全总体业绩进行了介绍,对各事故指标之间的相关性情况进行了实证分析,进一步验证了海因利希法则在国内大型核电工程项目施工安全管理中的适用性,对于后续大型核电项目安全事故预防和安全管理水平提升具有借鉴意义。     

Japanese regulatory practices on licensing, inspection, operational supervision and related standards

Japanese view on the safety of nuclear power plants is based on the concept that the primary responsibility for securing safety lies on electric power companies, installers of reactors.Under this concept, the Ministry of International Trade and Industry (MITI), in the course of designing and construction, has been performed an examination of the basic design and the detailed design of nuclear power plants, and in each stage of construction, a pre-operational inspection process. In addition, MITI, in operating stage, has been made throughgoing investigations on the causes of troubles and incidents as well as accidents that may affect operation, forcing utilities to take measures to prevent recurrence, and implementing safety regulation based on the “preventive maintenance” including elaborate checkings and overhaulings at the periodical inspections conducted for a period of three to four months after every 12-month operation cycle under the laws and regulations.This paper discusses the current status of nuclear power development in Japan, safety regulatory systems, views on safety and future prospects of securing safety.     

核电站从设计安全到现实安全的基本思考

文章针对核电站安全提出"设计安全"和"现实安全"的概念,通过分析研究国外核事故与国内核安全质量事件,阐述设计阶段确保核电站安全的设计安全重要性,重点描述了设计安全保障体系内容。并从设计、采购、制造、建造、安装、调试、运行、维护、老化到退役等全生命周期角度分析影响核电站现实安全的关键因素,探讨了全生命周期中的质量保证体系、核安全文化建设、风险指引对策、人因工程管理、信息反馈机制、核安全监管体系等对核电站现实安全的重要意义。     

发挥专业化优势,积极稳步推进核电发展

介绍了华能核电开发有限公司成立以来,在高温气冷堆建设、商用核电站建设和核电站前期选址等方面做的工作;指出了华能核电在管理方式、人才储备和核安全文化方面存在的不足;提出了华能核电应该通过开展核电项目建设积累经验,通过参股建设核电项目更广泛参与核电建设,以及继续开展核电相关产业的项目开发的发展规划。     

核电建安工程辐射安全风险分析及管理实践

建立了核电工程施工领域射线探伤辐射安全故障树模型,采用故障树分析方法全面分析了射线探伤作业过程中发生辐射安全事件的风险。结合我国辐射防护相关法律、法规和标准的具体要求,参考Bechtel和FA3等公司的做法,按照作业工艺流程,制定了一套完整的核电施工现场射线探伤控制措施,从管理制度上和技术手段上杜绝安全事件的发生,规范核电工程施工领域射线探伤的辐射安全防护管理。     

核电扩建工程中的安全管理

近年来,我国的核电站建设处于快速发展时期,核电站建设过程中项目繁多,容易发生事故,所以建设过程的安全生产问题尤为重要。文章根据某项目部安全管理工作的实际内容,结合安全相关的理论基础,对核电站建设过程中的安全生产管理进行了探讨。描述了某扩建工程项目部的部分安全管理工作,利用系统安全方法进行施工过程中的危险源管理。     

加强核电厂建造安全管理

介绍了福岛核事故对核安全的警示,分析了我国核电发展当前的主要问题、在建核电厂存在的问题,以及如何加强在建核电厂监督管理。指出了核电发展必须高度重视安全,核电建设要严格贯彻"安全第一,质量第一"的方针。     

AP1000核电建设安全标准化管理

2002年国家颁布实施了《中华人民共和国安全生产法》,出台了一系列的方针和政策,加大了安全生产监管力度。安全标准化是继安全评价、安全生产许可证制度之后,在安全监管方面采取的一项重大举措,也是一项治本之策。安全标准化工作是一项战略性、长期性、基础性的工作,是实现企业安全科学管理,提高企业本质安全的基本途径。海阳AP1000核电,其模块化、平行法施工及开顶法施工颠覆了传统先土建后安装的建造的理念,缩短建设周期,与此同时特大型模块运输、吊装,立体交叉施工显著增加,对安全管理提出了更高的要求。本文结合海阳AP1000核电工程特点及安全管理难点,提出AP1000核电安全标准化管理的思路和措施,对AP1000核电建设安全管理工作有借鉴意义。     

HTR-10安全功能与设备分级

参照有关的核安全法规,结合我国设计、建造各类研究堆的经验,根据HTR-10的安全特性和对构筑物、系统和部件安全功能的要求,制定了HTR-10的构筑物、系统和部件等物项的安全分级原则和相应的设计、制造要求及验证措施等,对HTR-10的设计和建造具有实际的指导和应用价值,确保了HTR-10的安全与可靠。     

Mechanical design assessment approaches of actual spent fuel and HLW transport package designs

Abstract

In recent years, BAM Federal Institute for Materials Research and Testing finalised the competent authority assessment of the mechanical and thermal package design in several German approval procedures of new spent fuel and high level waste package designs. The combination of computational methods and experimental investigations in conjunction with materials and cask components testing is the most common approach to mechanical safety assessment. The methodology in the field of safety analysis, including associated assessment criteria and procedures, has evolved rapidly over the last years. The design safety analysis must be based on a clear and comprehensive safety evaluation concept, including defined assessment criteria and constructional safety goals. In general, for new package designs, the implementation of experimental package drop tests in the approval process should be obligatory. Additionally, pre- and post-test calculations as well as components or material testing could be important. The extent to which drop tests are necessary depends on the individual package construction, the materials used and identified safety margins in the design.     

辐射安全文化的建立与培育

安全文化是核技术应用单位企业文化的核心。本文介绍了安全文化的定义、内涵和层次,讨论了核技术应用单位和个人应有的安全文化素养,阐述了培育安全文化的关键要素,并提出了安全文化建设的几点思路。     

核电工程造价与核安全保障研究

通过分析核电工程造价的构成,详细分析了核电在批量化、自主化建设的背景条件下,自主化能力的培养、福岛事故后核安全监管当局提出的与核安全相关一系列改进措施、社会成本大幅上涨以及项目安全质量管理日趋严格等因素对工程造价的影响,提出了从源头上维持一定的造价水平是核电工程建设健康、稳步发展以及保障核安全的必要条件的观点,同时对我国核电造价管理国家和企业两个层面应采取的对策提出了相应建议.     

Channel reactors: Status and prospects

Conclusions The prospects for nuclear power plants with channel reactors depend on the significant experience accumulated in building and operating such plants. Among the characteristics of the design and construction of nuclear power plants with RBMK reactors, classified, under deep analysis, as deficiencies in the light of the Chernobyl accident, not one was specific to the channel idea. The MKéR-800 design shows how the deficiencies of the RBMK construction can be avoided and how the advantages of the channel idea can be most fully realized. The current trends in the development of the traditional reactor designs, while certainly increasing the safety of the next generation of nuclear power plants, still do not take into account the materialization of the most severe accidents at the Three Mile Island and Chernobyl nuclear power plants. Therefore we are justified in considering the strategic problem of developing inherently safe reactors (operating on fast neutrons) in order to achieve a radical solution to the problems of safety, wastes, ecology, and the future fuel supply. Scientific-Research and Design Institute of Energy and Fuels. Translated from Atomnaya énergiya, Vol. 76, No. 4, pp. 302–310, April, 1994.     

FISA-2009 Conference on Euratom Research and Training Activities: Nuclear Fission - Past, Present and Future (Generation-II, -III and -IV + Partitioning and Transmutation)

This paper is an introduction to the research and training activities carried out under the Euratom 7th Framework Programme (FP7, 2007-2011) in the field of nuclear fission science and technology, covering in particular nuclear systems and safety, and including innovative reactor systems and partitioning and transmutation. It is based on the more than 40 invited lectures that were delivered by Euratom project coordinators and keynote speakers at the FISA-2009 Conference (FISA, 2009), organised by the European Commission DG Research, 22-24 June 2009, Prague, Czech Republic.The Euratom programme must be considered in the context of current and future nuclear technology and the respective research effort:

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Generation-II (i.e. yesterday, NPP construction 1970-2000): safety and reliability of nuclear facilities and energy independence in order to ensure security of supply worldwide;

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Generation-III (i.e. today, construction 2000-2040+): continuous improvement of safety and reliability, and increased industrial competitiveness in a growing energy market;

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Generation-IV (i.e. tomorrow, construction from 2040) for increased sustainability though optimal utilisation of natural resources and waste minimisation, and increased proliferation resistance.

Consequently, the focus of the lectures devoted to Generation-II and -III is on the major scientific challenges and technological developments needed to guarantee safety and reliability, in particular issues associated with plant lifetime extension and operation.The focus of the lectures devoted to Generation-IV is on the design objectives and associated research issues that have been agreed upon internationally, in particular the ambitious criteria and technology goals established at the international level by the Generation-IV International Forum (GIF). In the future, electricity must continue to be produced competitively, and in addition high temperature process heat may also be required, while exploiting a maximum of fissile and fertile material and recycling all actinides, both safely and reliably. Scientific viability studies and technological performance tests for each Generation-IV system are now being carried out in many European Union (EU) Member States, in collaboration with other laboratories worldwide as part of the inter-governmental GIF agreement. The ultimate phase of commercial deployment will be from 2040, but no one can predict accurately when industry and investors will make firm, often difficult decisions regarding the construction of these very innovative Generation-IV systems. However, to be deployed commercially, it must first be demonstrated that Generation-IV technology can be a beneficial, responsible and sustainable response to the long-term challenges faced by society to establish a low-carbon economy.     

美国核安全管理体制与法律体系探究及启示

美国是重要的核能与核技术利用大国,在核安全监管方面,建立了独立的核安全监督管理部门,并通过建立较为有效的管理体制和完善的核安全法律体系对核能发展实现安全监管.日本福岛核事故后,如何实现核能发展与安全保障之间的平衡,提高我国核与辐射安全水平,成为社会公众关注的焦点.本文对美国现阶段核安全管理体制与法律体系进行了初步探究,...     

Small-sized high temperature reactor (MHR-50) for electricity generation: Plant concept and characteristics

A new concept of Small-sized high temperature reactor (MHR-50) has been investigated toward the earliest commercialization in near future. Features of the MHR-50 are further different from the conventional light water reactors, and the MHR-50 is characterized by high passive safety, high thermal efficiency and smooth operability. When we selected plant basic parameters, we considered minimization of construction unit cost including R&D and of plant construction period as important issues. In the present study, the plant concept of the MHR-50 has been developed based on the above design philosophy.     

Advanced modularity design for the MIT pebble bed reactor

The future of all reactors will depend on whether they can be economically built and operated. One of the major impediments to new nuclear construction is the capital cost due in large part to the length of construction time and complexity of the plant. Pebble bed reactors offer the opportunity to reduce the complexity of the plant because the number of safety systems required is significantly reduced due to the inherent safety of the technology. However, because of its small size, the capital cost per kilowatt is likely to be large if traditional construction approaches are followed. This strongly suggests the need for innovative construction concepts to reduce the construction time and cost. MIT has proposed a modularity approach in which the plant is pre-built in space-frame type modules which are built in factories. These space frames would contain all the equipment contained in a given volume. Once equipment in the space frame is installed, the space frame would then be shipped to the site and assembled “lego-style.” Studies presently underway have demonstrated the feasibility of the concept. Thermal stress analysis has been performed and an integrated design with the space frames has been developed. It is expected that this modularity approach will significantly shorten construction time and expense. This paper proposes a concept for further development, not a final design for the entire plant.     

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.     

核与辐射安全监管信息化顶层设计研究

核与辐射安全监管信息化的顶层设计与规划是一项事关我国核与辐射安全监管事业大局的重大任务和挑战,对提高我国核与辐射安全监管技术水平具有十分重要的意义.本文分析了我国核与辐射安全监管信息化的现状和存在的问题,提出了顶层设计的目标原则,并对顶层设计的具体内容进行了研究和探讨,为我国核与辐射安全监管信息化建设的有序开展提供了参考.