Evaluation of neutronic performance for the VVER-1000 reactor core with regenerated uranium-plutonium fuel

Viktor V. Semishin
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Abstract

The possibility has been considered for the VVER-1000 reactor fuel loading to be formed based on regenerated fuel with the use of the spent fuel accumulated in reactors of the same type. A study was undertaken to investigate the change in the isotopic composition of the plutonium discharged from a thermal reactor in the course of its multiple reprocessing and recycle in a thermal neutron reactor. To obtain an equilibrium isotopic composition of the reactor-grade plutonium, 3D neutronic calculations were performed for the stationary fuel cycles of a VVER-1000 serial reactor with conventional oxide fuel and oxide fuel based on regenerated uranium and based on an undivided mixture of uranium and plutonium oxides from SNF. The neutronic performance of reactor cores was compared for the above mentioned fuel types in the course of the fuel company, including the following: in-core radial power density shaping, values of reactivity coefficients for various thermal parameters, reactivity control system efficiency, etc.
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使用再生铀-钚燃料的VVER-1000堆芯的中子性能Evaluation
已经考虑了利用同类型反应堆中积累的乏燃料,以再生燃料为基础形成VVER-1000反应堆燃料负荷的可能性。进行了一项研究,以调查从热中子反应堆排出的钚在其多次后处理和再循环过程中同位素组成的变化。为了获得反应堆级钚的平衡同位素组成,对VVER-1000系列反应堆使用传统氧化物燃料、基于再生铀的氧化物燃料和基于SNF中铀和钚氧化物未分离混合物的氧化物燃料进行了三维中子计算。在燃料公司的过程中,对上述燃料类型的堆芯中子性能进行了比较,包括堆芯内径向功率密度成形、各种热参数下的反应性系数值、反应性控制系统效率等。
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