The State of Nuclear Power Stations with Fast-Neutron Reactors and Prospects for Their Future Development

V. M. Poplavskii

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The State of Nuclear Power Stations with Fast-Neutron Reactors and Prospects for Their Future Development

机译：带有快中子反应堆的核电站的现状及其未来发展前景

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The results from an analysis of the state and prospects for future development of nuclear power stations with fast-neutron reactors are presented. The basic trends of their development are considered. A comparison between the technical and economic characteristics of power units with different coolants is performed.

机译：提出了对具有快速中子反应堆的核电站的现状和未来发展前景的分析结果。考虑了其发展的基本趋势。对具有不同冷却剂的动力装置的技术和经济特性进行了比较。

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《Thermal engineering》 |2004年第8期|p.597-604|共8页
作者
V. M. Poplavskii;
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作者单位

State Scientific Center of the Russian Federation, The Leipunskii Institute of Energy Physics, pl. Bondarenko 1, Obninsk, Kaluga oblast, 249033 Russia;

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正文语种 eng
中图分类发电、发电厂;
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1. Thermal-Hydraulics, Physical Chemistry, and Technology at Nuclear Power Stations Equipped with Fast-Neutron Sodium-Cooled Reactors [J] . V. V. Alekseev, A. D. Efanov, F. A. Kozlov, Thermal engineering . 2007,第12期

机译：配备快中子钠冷反应堆的核电站的热工，物理化学和技术
2. Prospects for Development of Nuclear Power Stations Equipped with WER Reactors [J] . Yu.M.Semchenkov, V.A.Sidorenko Thermal engineering . 2011,第5期

机译：配备WER反应堆的核电站的发展前景
3. Hybrid systems for transuranic waste transmutation in nuclear power reactors: state of the art and future prospects [J] . Yurov D. V., Prikhodko V. V. Physics - Uspekhi . 2014,第11期

机译：核动力反应堆中超铀废物trans变的混合系统：最新技术和未来前景
4. 39th JAIF Annual Conference, JapanCurrent Status and Future Prospects of Nuclear Power Development in India [C] . S.K.Jain JAIF annual conference . 2006

机译：JAIF第39届年会，日本印度核电发展的现状和未来展望
5. "Life without nuclear power": A nuclear plant retirement formulation model and guide based on economics. San Onofre Nuclear Generating Station case: Economic impacts and reliability considerations leading to plant retirement. [D] . Wasko, Frank. 2015

机译：“没有核能的生活”：基于经济学的核电站退役制定模型和指南。 San Onofre核电站的案例：经济影响和可靠性考虑因素导致工厂退役。
6. Development of an automatedchemistry control system forsecondary coolant circuits inCANDU nuclear power reactors [O] . J. R. Dean, R. B. Stewart 1979

机译：开发自动化化学控制系统二次冷却液回路坎杜核电反应堆
7. Activites futures d'Euratom. Annexe technique no. 17, Travaux sur demande et contre remuneration: Action technologique dans le cadre de l'assistance aux exploitants de centrales nucleaires, propulsion navale nucleaire, sources d'energie pour les stations de mesure oceanographiques, contribution dans le domaine de la conversion directe, et developpement des caloducs = Euratom's future activities. Technical annex no. 17, Work undertaken on request and against remuneration: Action in the context of technological assistance to operators of nuclear power plants, nuclear naval propulsion, energy sources for measuring oceanographic stations, contribution in the field of direct conversion and development of heat pipes. COM (69) 350 final/technical annex 17, 30 April 1969 [O] . 1969

机译：活动期货d'Euratom。附件技术没有。 17，Travaux sur demande et contre reuneration：action technologique dans le cadre de l'assistance aux exploitants de centrales nucleaires，propulsion navale nucleaire，sources d'energie pour les stations de mesure oceanographiques，contribution dans le domaine de la conversion directe，et developpement des caloducs = Euratom未来的活动。技术附件编号17，根据要求和反对报酬开展的工作：在向核电厂运营商提供技术援助，核海军推进，海洋测量站测量能源，直接转换和热管开发领域的贡献方面采取的行动。 COm（69）350最终/技术附件17，1969年4月30日
8. Technology, Safety and Costs of Decommissioning a Reference Boiling Water Reactor Power Station. Addendum 4: Comparison of Two Decommissioning Cost Estimates Developed for the Same Commercial Nuclear Reactor Power Station. [R] . Konzek, G. J., Smith, R. I. 1990

机译：退役参考式沸水堆电站的技术，安全和成本。附录4：为同一商用核反应堆电站开发的两项退役成本估算的比较。

The State of Nuclear Power Stations with Fast-Neutron Reactors and Prospects for Their Future Development

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