Normalization of discharges and emissions of radionuclides and harmful substances into the environment

All-Union Scientific-Research Institute of Nuclear Power Plants. Odessa Polytechnical University. Chernobyl Nuclear Power Plant. Beloyarsk Nuclear Power Plant. Ministry of the Environment, Ukraine. TSMSCH-5, Ukraine. Translated from Atomnaya énergiya, Vol. 76, No. 6, pp. 522–526, June, 1994.     

Assessment of the radioactive state of ground waters near the chernobyl nuclear power plant

All-Union Scientific-Research Institute of Nuclear Power Plants. Chernobyl Nuclear Power Plant. Translated from Atomnaya énergiya, Vol. 77, No. 5, pp. 386–391, November, 1994.     

Analysis of the operational reliability of VVÉR-1000 fuel elements and bundles in a three-year fuel cycle

Institute of Nuclear Reactors, Kurchatov Institute, Russian Science Center. A. A. Bochvar All-Union Scientific Research Institute of Inorganic Materials. All-Union Scientific Research Institute of Nuclear Power Plants. Novo-Voronezh Nuclear Power Plant. Production Association, Novosibirsk Chemical Concentrate Factory. Translated from Atomnaya Énergiya, Vol. 74, No. 6, pp. 482-486, June, 1993.     

M310堆型及其改进型核电厂中压移动电源设置的有效性分析

参考岭澳核电站二期在移动电源方面的设计方案,使用概率安全分析（PSA）方法对《福岛核事故后核电厂改进行动通用技术要求（试行）》中中压移动电源设置的有效性进行分析。通过定性、定量分析,认为中压移动电源在功率和停堆工况下对全厂断电事故有较为明显的缓解效果,并对《福岛核事故后核电厂改进行动通用技术要求（试行）》提出了改进建议。      

An international scale for assessing the danger of nuclear plant events

State Nuclear Power Supervisory Committee Scientific and Technical Center for Industrial and Nuclear Power. Translated from Atomnaya Énergiya, Vol. 70, No. 1, pp. 3–8, January, 1991.     

Experimental investigation of temperature stratification in the coolant flow at the input and output of BN-600 intermediate heat exchangers

Beloyarsk Nuclear Power Plant. Special Design Office for Mechanical Design. Power Physics Institute. Translated from Atomnaya Énergiya, Vol. 71, No. 3, pp. 266–268, September, 1991.     

核电运行数据库的研制与应用

核电运行数据库由国内外核事件定级数据库，国外核电厂异常事件库，国外核电运行可靠性数据库的通用数据库和秦山核电厂运行异常事件库四个分库组成。主要内容是数据收集，数据分析，结构设计，代码词典的研究和管理软件的确定。本文还介绍了利用电运行数据库为已投入商业运行的核电厂提供安全分析服务的反馈情况。     

Summary of a four-year run with highly enriched fuel in the WWER-440

I. V. Kurchatov Institute of Nuclear Energy. Hydraulic Press Special Design Office. Kol'skií Nuclear Power Plant. Translated from Atomnaya Énergiya, Vol. 71, No. 3, pp. 209–214, September, 1991.     

秦山核电厂核空气净化系统试验与运行

本文介绍了秦山核电厂核空气净化系统的设置,系统功能及运行方式,净化部件的性能参数。文章着重叙述安装工作完成后所进行的现场试验的项目、目的、方法和评价标准。已完成的现场试验证实,秦山核电站核空气净化系统将是可靠高效率的,文章最后介绍了运行管理的要点,指出强化运行管理是核空气净化系统能否发挥预定功能的关键。目前,秦山核电站正向满功率进军,核空气净化系统运行正常,满足了秦山核电厂安全运行的要求。     

A two-dimensional thermohydraulic calculation on the core of pressurized water reactor

Nuclear Research and Nuclear Power Institute, Bulgarian Academy of Sciences. Translated from Atomnaya Énergiya, Vol. 73, No. 5, pp. 397–400, November, 1992.     

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。     

A test-rig study of the startup modes of the I. V. Kurchatov Nuclear Power Station,Beloyarsk

The results are given of an experimental investigation carried out on a test-rig of the hydrodynamic stability of the coolant flow in the channels of the first and second reactors of the Beloyarsk Nuclear Power Station. The choice of methods of startup of the Nuclear Power Station units, which are aceptable to the experimental final adjustments, is justified. The results are given of a study of the startup modes.Translated from Atomnaya Énergiya, Vol. 19, No. 3, pp. 261–268, September, 1965     

大亚湾核电站继电器机架支撑改造初步力学分析

针对大亚湾核电站继电器机架橡胶减震器因老化破裂而影响机架的抗震性能、日常运行和维修等问题而提出支撑改造方案,采用谱分析法对改造前后的各种支撑结构进行初步力学分析.比较了大亚湾继电器机架改造前后支撑的抗震性能,以及大亚湾和岭澳两种继电器机架支撑结构在同一地震载荷作用下的力学响应,为大亚湾核电站继电器机架支撑的加固改造提供参考.     

核电站电缆选择要点技术

安全级电缆对核电站的安全运行和安全停堆起着十分重要的作用,核电站用的电缆一般具有以下特殊性能,如长期工作寿命、耐辐射、耐潮湿、低烟、无卤、阻燃等要求,因而对所采用电缆绝缘和护套材料以及试验都提出了很高的要求,本文针对核电站电缆选择时的一些要点进行了探讨。     

Examination of the first unit at the armenian nuclear power station after the end of operation

Moscow Physics Research Institute. State Atomic Inspectorate Scientific Center. Moscow Special Research Institute. Armenian Nuclear Power Station. Institute for Atomic Energy. Dekom Cooperative. All-Union Nuclear Materials Research Institute. Gidropress Special Designs Office. Translated from Atomnaya Énergiya, Vol. 72, No. 4, pp. 345–353, April, 1992.     

Monitoring of the tightness of the seal of steam generators in nuclear power plants with VVER-1000 reactors after reconstruction of the water feed and purge systems

All-Russian Scientific-Research Institute of Nuclear Power Plants. Translated from Atomnaya énergiya, Vol. 79, No. 5, pp. 350–353, November, 1995.     

秦山第二核电厂场内医学应急救护计划

核电站发生核事故时的应急响应是一项十分复杂而庞大的系统工程,本文从医学应急救护的角度,参照《秦山第二核电厂场内应急计划》,并结合广东大亚湾核电站和秦山第一核电厂的经验反馈,探讨了秦山第二核电厂医学应急救护体系及其救护行动,并对做好场内医学应急救护准备工作提出了若干建议。     

田湾核电站全尺寸模拟机维护维修策略与措施分析

介绍了田湾核电站全尺寸模拟机的软硬件情况,给出了全尺寸模拟机维护维修的一般策略,并详细分析了田湾核电厂全尺寸模拟机维护维修的具体实施方法和应对措施.     

秦山核电厂一回路辅助工艺系统调试

本文叙述了秦山核电厂一回路主要调试项目以及在预运运行试验和初始启动试验阶段的实施情况。调试结果表明，系统已具备所要求的功能，运行参数达到了设计要求，能安全、可靠地配合反应堆冷却剂系统，满足各种工况的运行要求。     

Determining the three-dimensional energy output field in an RBMK-1500 fuel assembly

Ignalina Nuclear Power Plant. Translated from Atomnaya Énergiya, Vol. 70, No. 4, pp. 246–248, April, 1991.