Problems of BN-800 construction and the possibilities of developing advanced fast reactors

The design features and construction status of the BN-800 reactor being built at the Beloyarskaya nuclear power plant and the main scientific and technical problems which will be solved with the construction of this reactor are examined. The most important ones are mastering a closed fuel cycle, checking new technical solutions, and testing improved fuel and construction materials. The directions for improving the technical-economic performance characteristics of fast reactors that the BN-800 and-1800 designs can provide are described. It is shown that economic performance indicators which are at least as good as those of VVéR reactor with close power levels can be achieved. __________ Translated from Atomnaya énergiya, Vol. 102, No. 1, pp. 21–26, January, 2007.     

Radiation Setup with an Electron Accelerator at the Institute of Nuclear Physics of the Ukrainian National Academy of Sciences

The characteristics of a radiation setup which is being put into operation at the Institute of Nuclear Physics of the Ukrainian National Academy of Sciences as a base for scientific research and development of industrial radiation technology are presented. The components of the setup and the special features of the construction of the technical means are described.     

Development and adoption of multichannel measuring systems for startup-adjustment monitoring of the equipment in power-generating units under construction at nuclear power plants with VVÉR-1000 reactors

The problem of developing multichannel measuring systems for nuclear power plants with VVéR-1000 reactors involves many technical problems. In the course of solving these problems, different variants of the construction of distributed systems were tested. In the present article, the most successful configuration, tested on four units of a nuclear power plant, is described. __________ Translated from Atomnaya énergiya, Vol. 99, No. 6, pp. 463–466, December, 2005.     

Western and Asian light water reactors at the millennium threshold

This paper presents the most advanced Western and Asian light water reactor (LWR) designs. The following pressurized water reactor (PWR) and boiling water reactor (BWR) designers are covered: Westinghouse ( ), Babcock and Wilcox (B&W—now part of Framatome), Combustion Engineering (CE—now ABB CE), Siemens (PWR), Framatome, Mitsubishi, General Electric (GE), Asea Brown Boveri (ABB), Siemens (BWR), Hitachi and Toshiba. The motivations that led to the design of the next generation of LWRs are discussed. The technical bases for evolutionary and innovative plants are summarized. Important safety features of some of the most complete (in operation, under construction or certified) evolutionary designs are described detail. Analogous implementations of systems into other advanced designs are given.     

Extraction of radioactive wastes and liquidation of old repositories at the Russian Science Center Kurchatov Institute

The salient features of the organization and execution of the work performed to remove radioactive wastes from and rehabilitate ten old repositories located on a special site of the Institute, which were distinguished by their design and the form and composition of the wastes contained in them, are described. The old repositories were located close to a housing development, so that special attention was devoted to the choice of technologies and technical means used for the rehabilitation. The technical approach and the sequence of operations are presented, and the technology and technical means are described. The problems of providing the proper technological equipment for this work are analyzed. __________ Translated from Atomnaya énergiya, Vol. 103, No. 2, pp. 129–133 August, 2007.     

Inspection and preparation for liquidation of old radwaste repositories at the Russian Science Center Kurchatov Institute

Efforts to develop design materials and preparations for liquidation of old radwaste repositories at the Russian Science Center Kurchatov Institute have revealed problems due to the lack of archived information on the salient structural features of the repositories and the wastes placed there as well as due to the inadequate development of the technical and technological support base for restoration work. The technical approach implemented during the preparation for liquidation of the repositories is described. The sequence of operations is presented, and the technological and technical means are described. The problems of the technological support for inspection of the repositories are analyzed. __________ Translated from Atomnaya énergiya, Vol. 102, No. 6, pp. 374–377, June, 2007.     

Fuel elements based on spherical fuel pellets with a protective coating for enhanced-safety reactors

The principal investigations performed at the Scientific and Industrial Association Luch on the development of fuel elements based on spherical pellets of nuclear fuel with protective ceramic and metallic coatings for HTGR. VVéR, and other types of reactors are reviewed. The main solutions concerning the construction and technical and materials-science aspects of the fabrication of fuel micropellets, fuel microelements, and fuel elements of different modifications (spherical, rod-shaped) are examined. The characteristics of fuel elements and their components at the fabrication and preliminary and reactor testing stages are presented. It is shown that because of additional protective barriers the fuel elements which have been developed effectively confine the fission products and ensure safety. The directions of possible practical utilization of the fuel elements developed for improved enhanced-safety reactors are described. 7 figures, 6 tables, 42 references. Scientific and Industrial Association Luch, Translated from Atomnaya énergiya, Vol. 87, No. 6, pp. 451–462, December, 1999     

PET发展的技术现状及展望

ＰＥＴ扫描仪是当今最昂贵的，最精密的医用诊断设备，本文就与ＰＥＴ扫描仪相关的技术（如闪烁体，光电转换器件，电子学系统，数据采集和图像重建系统以及ＰＥＴ系统设计等）发展的现状做了一个介绍，介绍对ＰＥＴ的发展前景给出了展望。     

Prospects for the BN-1800 Sodium-Cooled Fast Reactor Satisfying 21st Century Nuclear Power Requirements

The BN-1800 power-generating unit is designed to meet the requirements of the strategy for developing atomic energy in Russia in the first half of the 21st century. The development time is the next 15 years and construction could start after 2020. The design is innovative and includes the development of key new technical solutions as compared with the BN-800 reactor which is now under construction.The new technical solutions are based on the substantial positive experience in operating fast reactors in Russia (~125 reactor·years), specifically the BN-600 reactor. The innovations make it possible not only to solve strategic problems, such as increasing safety, improving ecology (including by burning actinides), and nonproliferation but also to make large improvements in economic performance.     

高放废物地质处置安全全过程系统分析研究进展

高水平放射性废物(以下简称“高放废物”)地质处置安全全过程系统分析是对处置库长期安全的综合性系统分析。本文论述了安全全过程系统分析的概念及近20年发展情况,强调了其在高放废物地质处置库规划、选址、设计、建设、运行、关闭和关闭后等各阶段的重要性。以国际原子能机构(IAEA)和经合组织核能署(NEA)技术文件为主,阐述了安全全过程系统分析的背景、安全策略、评价基础、安全评价及综合等核心组成部分,列举了其应用中管理和技术方面的12个关键点,分析了芬兰、瑞典、美国和法国的研究应用现状,并对我国放射性废物地质处置安全全过程系统分析的发展及应用现状进行了探讨。     

船舶交通管理系统雷达电磁辐射环境影响分析评价

根据船舶交通管理系统雷达的工作模式及技术参数, 计算了雷达天线轴向电场强度及磁场强度瞬时峰值和平均场强的分布;分析了电磁辐射环境影响;根据国家有关技术标准的规定, 给出了船舶交通管理系统雷达天线的水平和垂直达标距离;为雷达站选址与建设提供技术依据。     

中国散裂中子源强流质子加速器设计、研制及调试运行

中国散裂中子源（CSNS）是基于强流质子加速器的大科学装置,通过高功率质子束流轰击重金属靶产生高通量中子用于开展中子散射研究,CSNS是世界上第四台、发展中国家第一台脉冲型散裂中子源。CSNS包括高功率强流质子加速器、中子靶站和中子谱仪以及相应的配套设施等。加速器由80 MeV负氢直线加速器、1.6 GeV快循环同步加速器及相应的束流输运线组成。CSNS加速器是我国第一台中高能强流高功率质子加速器,本文将介绍CSNS加速器的设计、关键技术、设备研制以及束流调试过程和其中关键问题。     

压水堆核电厂实时传输重要安全参数的规范化初步研究

核电厂实时安全参数传输和交换对于核电厂日常管理和应急响应都有重要的意义.基于相关法规标准要求和应急响应需要,结合各机组类型的具体参数,并考虑参数的可获得性,提出了相对统一的PWR核电厂实时传输安全重要机组参数和实时环境监测参数,为核电厂安全相关参数传输标准化工作提供了一定的技术基础.     

The status of the ITER design

In parallel with a rapid build up to almost 300 people within the International Organization at Cadarache, the project team, including many from the member countries represented by their domestic agencies (DA), has concentrated its effort on an overall design review of ITER. An updated technical baseline was presented to council at the end of 2007. Several additional improvements were included during spring 2008 and it is probable that the results of the review will be accepted by council. As a result, the ITER design today provides a robust basis for a technical design that allows operation over a wide range of physical parameters, a design that can operate stably with high gain and can exploit the full scientific potential of the device. In the technical area, design changes have been integrated to improve performance, provide more robust subsystems and to minimize technical or operational risks. All of the adaptations required to support the licensing process as a nuclear facility in France have been made. In parallel major components are already under construction within the DAs. A full overview of the status of ITER design and construction, including the detailed discussion of the 2007 ITER baseline, is given. In addition, the construction status and the overall project review is presented.     

The TMI-2 clean-up project collection and databases

A publicly accessible collection containing several thousand of the videotapes, photographs, slides and technical reports generated during the clean-up of the TMI-2 reactor has been established by the Pennsylvania State University Libraries. The collection is intended to serve as a technical resource for the nuclear industry as well as the interested public. Two Internet-searchable databases describing the videotapes and technical reports have been created. The development and use of these materials and databases are described in this paper.     

The Toroidal Magnet of FM-1

The construction features of the toroidal field coil for the FM-1 device are described. The coil is rated at 1.5 × 106 ampere-turns steady and has a field volume of 49 cubic meters. The stored energy of the field is nearly 2 MJ. The coil must be taken apart for insertion of a superconducting ring; the techniques for accomplishing this are described.     

Standardized French PWR programs and the application of mechanical analysis

The implementation of the French PWR construction programs is marked by the following factors:

• - the construction of similar plants by series, together with the standardization of plant layout and component design,

• - the various aspects of the plant operation policy adopted by Electricité de France (EdF), the main client,

• - the special provisions of French licensing regulations,

• - the continuous development of technical experience required to support an active export policy.

The effect of these factors on the organization of the programs and on technical achievements will be examined, with special attention being given to the mechanical aspects, which constitute the main subject of the SMiRT conference.     

Power-generating unit with dual-loop sodium-cooled fast reactor and dual-wall steam generator

The results of a probabilistic analysis performed to validate the safety of AES-2006 designed for the site of the Novovoronezh nuclear power plant are presented. The requirements for the AES-2006 design are examined. The characteristic features of the AES-2006 design for the conditions at the Novovoronezh nuclear power plant site are described, including the diversity of the equipment and operating regime, passive systems, and scheduled maintenance of safety systems with the reactor operating at power. The scope of the probabilistic safety analysis performed at the development stage of the technical design is described. The important problems which must be solved in a probabilistic safety analysis for the designs of new nuclear power plants are discussed. Translated from Atomnaya énergiya,Vol. 106, No. 3, pp. 123–129, March, 2009.     

精密数控高真空电子束焊机的研制

介绍了精密数控电子束焊机的结构、主要技术指标和特点，着重叙述了新型设备的设计原理、特点以及一些关键技术问题的解决方案。