BN-800 design validation and construction status

Information is presented on the BN-800 design, the second design following BN-600, power-generating unit with a fast reactor. The main stages of the development of the design begun in the 1980s, modified in the 1990s after the Chernobyl accident, and accepted for construction within the government program starting in 2000 are presented. The fundamental differences of BN-800 from BN-600 are characterized, and current R&D work is briefly described. Information is presented on the construction of BN-800 at the Beloyarskaya nuclear power plant, where the BN-600 has been operating since 1980.     

Behavior of vibrationally compacted mixed fuel in BN-800

The modified computer code MACROS was used to study the behavior of fuel elements with vibrationally compacted mixed fuel under irradiation in BN-800. Verification calculations were performed for fuel elements irradiated in BN-600 under close to nominal conditions. Attention was focused mainly on the factors playing an important role in their serviceability: swelling, creep, corrosion behavior of cladding, temperature distribution, gas-release, and degree of structural reformation of the fuel core.     

Comparative Operation Risk Assessment for the No. 4 Unit of the Beloyarsk Nuclear Power Plant with a BN-800 Reactor

A quantitative assessment is made of the collective cancer risk for the population in Sverdlovsk oblast due to exposure to radiation during the 30-yr period of normal operation of the No. 4 unit in the Beloyarsk nuclear power plant with a BN-800 reactor and for possible accidents. The estimates are made using the linear zero-threshold concept based on ICRP Publication No. 60.The values obtained are compared with the different forms of cancer risk characteristic for Sverdlovsk oblast (due to radiation and chemical contamination of atmospheric air and drinking water) and the morbidity and mortality risk predominantly due to socioeconomic factors. It is shown that the socioeconomic risk factors determine most cases of death from unnatural causes. Against this background, the health risk due to contamination of the environment by natural radionuclides and chemical carcinogens is negligibly small.The desirability of introducing into domestic practice the health risk assessment methodology developed by the US Environmental Protection Agency is discussed in light of the results obtained.     

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.     

BN-800 as a New Stage in the Development of Fast Sodium-Cooled Reactors

The role of fast reactors in a strategy for developing nuclear power in Russia because of the inevitable exhaustion of natural uranium deposits in the foreseeable future is discussed. The BN-800 reactor, which is under construction and incorporates unique solutions – greatly enhancing the safety of the reactor – to technical and constructional problems, is examined. Cost assessments taking account of the complete life cycle show that fast reactors could be no more expensive than the most widely reactors in the world – water-moderated water-cooled reactors.Closing the BN-800 nuclear fuel cycle will make it possible to solve the problem of utilizing plutonium and actinides. This makes fast reactors safer for the environment.     

The Future of Nuclear Power: Energy, Ecology, and Safety

The results are presented of a bilateral meeting of Russian and US experts on The future of nuclear power: energy, ecology, and safety held on July 22–24, 2002 in Moscow. The subject of discussion was the question of how the US and Russia can provide for a future where nuclear energy will support economic growth, improve living conditions, protect the environment, and ensure nonproliferation of nuclear weapons. Several positive points concerning nuclear fuel cycle which emerged and which encourage a reexamination of the future of nuclear power are noted. It is suggested that a four- or fivefold increase by the middle of this century in the production of nuclear energy be considered and discussed as a problem which is important enough to have a global effect on electricity production, energy safety, and mitigation of the greenhouse effect. A prediction is made for the development of global nuclear power in the 21st century. Specific directions of Russian–American collaboration are proposed without setting priorities. The factors that could effectuate successful collaboration are determined.     

Safety of Nuclear Power: The Present and Guarantees for the Future

The development of approaches to guaranteeing the safety of nuclear power in the Soviet Union and in Russia and the development of safety concepts and the normative base corresponding to them, which rely on international practice, is expounded. The main factors which make it possible to talk about guaranteeing the safety of nuclear power at the next stage of its development are examined.     

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根据国内外经验 ,提出了我国今后新建核电站的若干安全要求 ,包括安全目标、决定论方法和概率论方法、严重事故、安全壳及其系统、氢的控制和停堆状态下的安全问题     

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简单介绍了PRA技术发展的历史,对确定论和概率论安全分析的不确定性进行了简要的比较,并对国内PRA技术在核安全管理应用中要解决的几个问题给出了分析和建议.     

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针对日本福岛核事故发生及演化,提出从核设备设计方面加强核电设计安全性的思考,重点阐述了从建立先进核电标准体系、采用先进设计分析方法、形成完整试验验证体系及合理考虑"超设计基准事件"和加强核安全文化建设等方面提升核安全的重要性,对从事核电设计人员给予启示。     

台山核电厂核岛厂房土建安全设计技术

介绍台山核电厂核岛厂房土建安全设计特点,阐述参考欧洲第三代核电技术(EPR)的核岛厂房在保障核安全,实现核电厂反应性控制、核燃料冷却和放射性物质包容3大基本安全功能上的作用,增强社会大众对CEPR核电厂多层安全防御体系的认识。     

基于未确知测度的核能安全风险评价

本文从风险管理的视角分析了中国核能发展的现状,运用风险管理的方法识别出我国在核能的发展过程中存在的各种风险因素。以山东省某核电厂为研究背景,运用未确知测度模型从自然、技术、经济、管理、法律法规、政策等层面评价我国核能的发展过程中存在的各种风险及其危害程度,以期为政府主管部门的决策、危害评估提供理论参考,探寻中国特色的核能安全风险管理新模式。     

核武器研究的未来

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