Use of REMIX Spent Mixed Fuel Plutonium in the BN-1200 Reactor

Q4 Energy
N. Kovalyov, A. M. Prokoshin, A. S. Kudinov, V. Nevinitsa
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引用次数: 0

Abstract

The VVER-1000 thermal neutron reactor can operate on mixed uranium-plutonium fuel with a content of reactor-grade plutonium up to 5% with a 100% loaded core. In this case, plutonium burns up to 56% of odd isotopes. The energy potential of such plutonium is very low, and its further use in thermal reactors is impractical. However, such plutonium can be used in fast neutron reactors. The paper presents the results of investigating the possibility for such isotopic plutonium composition to be used in the BN-1200 thermal neutron reactor and its value be increased for the plutonium recycle in the reactor. For this purpose, a precision model of the BN-1200 reactor has been developed using the Serpent Monte Carlo code. The model has been verified against the reference values of the nuclear fuel burnup and breeding ratios. The study has shown that such plutonium can be used in the BN-1200 reactor MOX fuel. Maintaining the operating cycle length requires the plutonium fraction in the MOX fuel to be increased up to 2%. In the BN-1200 reactor, the isotopic composition has been found to improve for the further recycle of plutonium in the thermal reactor, i.e. odd plutonium isotopes increase. The fewer odd plutonium isotopes at the beginning of the BN-1200 operating cycle, the greater their increase. It can be seen as the result of the calculation that plutonium from VVER-1000 spent mixed fuel must be loaded into the BN-1200 reactor at least twice to increase the fraction of odd isotopes to the level of reactor-grade plutonium.
BN-1200反应堆中废混合燃料钚的再混合使用
VVER-1000热中子反应堆可以在反应堆级钚含量高达5%的混合铀-钚燃料上运行,堆芯负荷为100%。在这种情况下,钚燃烧了多达56%的奇数同位素。这种钚的能量潜力非常低,在热反应堆中进一步使用是不切实际的。然而,这种钚可以用于快中子反应堆。本文介绍了在BN-1200热中子反应堆中使用这种同位素钚成分的可能性的研究结果,以及在反应堆中钚循环利用中增加其值的研究结果。为此,利用Serpent蒙特卡罗代码开发了BN-1200反应堆的精确模型。用核燃料燃耗比和增殖比的参考值对模型进行了验证。研究表明,这种钚可以用于BN-1200反应堆的MOX燃料。维持运行周期长度需要将MOX燃料中的钚含量提高到2%。在BN-1200反应堆中,发现同位素组成改善了钚在热堆中的进一步循环,即奇数钚同位素增加。BN-1200运行周期开始时,奇数钚同位素越少,它们的增加就越大。可以看出,计算结果表明,从VVER-1000用过的混合燃料中提取的钚必须至少两次装载到BN-1200反应堆中,才能将奇数同位素的比例提高到反应堆级钚的水平。
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来源期刊
Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika
Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika Energy-Nuclear Energy and Engineering
CiteScore
0.40
自引率
0.00%
发文量
30
期刊介绍: The scientific journal Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika is included in the Scopus database. Publisher country is RU. The main subject areas of published articles are Nuclear Energy and Engineering, Физика, Приборостроение, метрология и информационно-измерительные приборы и системы, Информатика, вычислительная техника и управление, Энергетика. Before sending a scientific article, we recommend you to read the section For authors. This will allow you to prepare an article better for publication, to make it more interesting for the readers and useful for the scientific community. By following these steps, you will greatly increase the likelihood of your scientific article publishing in journals included in international citation systems (e.g., Scopus). Then you may choose a different journal, select the journal included to list of SAC Russia journal list, or send your scientific work for review and publication.
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