减少热堆和快堆两部分系统镅生产的一些经济问题

A. Gulevich, V. Usanov, V. Dekusar, V. A. Eliseev, A. Moseev, E. S. Khnykina
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引用次数: 0

摘要

文章分析了在从基于开放燃料循环中热反应堆的单组分核能系统(NES)向包含封闭核燃料循环中热反应堆和快堆的双组分系统过渡期间减少镅生产的经济方面。模拟了到本世纪末俄罗斯发展这些系统的情景。考虑了两种方法,以减少带有快钠反应堆的双组份核燃料循环系统中的镅产量。第一种方法是关闭 SFR 型 BN 反应堆中的钚燃料循环,其基础是使用从热反应堆乏核燃料中分离出来的钚,以尽可能短的时间(根据技术规范)制备和使用 MOX 燃料,从而防止钚-241 的主要部分衰变为镅。第二种方法是镅的嬗变。这项研究使用了为封闭式核燃料循环(NFC)核能源系统建模而设计的数学代码 CYCLE。论文中使用的技术和经济数据来自俄罗斯专家发表的研究报告和国际原子能机构/INPRO SYNERGIES 项目中欧盟专家提供的材料。研究结果表明,在快钠堆的混合氧化物燃料中使用来自热反应堆的钚来关闭核燃料循环的效率与本文所考虑的均相嬗变的效率相当。镅积累预防方法和嬗变方法的结合可能会显著降低核能系统中的镅积累率,但所考虑的均相嬗变的估计成本会显著恶化钠快堆的经济性能。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Some economic aspects of reducing americium production in a two-component system of thermal and fast reactors
The article analyzes the economic aspects of reducing the production of americium during the transition from a single-component nuclear energy system (NES) based on thermal reactors in an open fuel cycle to a two-component system with thermal and fast reactors in a closed nuclear fuel cycle. Scenarios for the development of these systems in Russia up to the end of the century are modeled. Two methods are considered for reducing the production of americium in a two-component NES with fast sodium reactors. The first method, closing the fuel cycle for plutonium in BN reactors of SFR type, is based on the use of plutonium separated from spent nuclear fuel of thermal reactors with the shortest possible (according to technical specifications) time for MOX fuel preparation and use thus preventing the main part of plutonium-241 from decay into americium. The second way is transmutation of americium. The study was carried out by using the mathematical code CYCLE designed for modeling of the NES with closed nuclear fuel cycle (NFC). The technical and economic data used in the paper was taken from published studies of Russian specialists and materials of European Union specialists presented in the IAEA/INPRO SYNERGIES project. The results of the research show that the efficiency of closing the NFC by using plutonium from thermal reactors in MOX fuel of fast sodium reactors is comparable to the efficiency of the homogeneous transmutation considered in the paper. The combination of the americium accumulation prevention method and transmutation method might significantly reduce the rate of the americium accumulation in a nuclear energy system, but the estimated costs of the considered homogeneous transmutation can significantly worsen the economic performance of sodium fast reactors.
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