ABSTRACT The flexible fuel cycle initiative system (FFCI system) has been developed to reduce spent fuel (SF) amounts, to keep high availability factor for the reprocessing plant and to increase the proliferation resistance for the recovered plutonium (Pu). The system separates most uranium (U) from the SF at first and the residual material called recycle material (RM) which contains Pu, minor actinides (MA), fission products (FP) and remaining U will go to Pu(+U) recovery from the RM for Pu utilizing reactor. If there is a delay of the Pu utilization reactor deployment, the RM will go to temporary storage until its deployment. The Pu utilizing reactor is fast breeder reactor (FBR) or light water reactor (LWR) with mixed oxide (MOX) fuel. The RM is the buffer material between SF reprocessing and Pu utilizing reactor with compact size and high proliferation resistance, which can suppress the amount of relatively pure Pu. The innovative technologies of FFCI are most U separation and temporary RM storage. They are investigated by the literature survey, fundamental experiments using simulated material and analyses using simulation code. This paper summarizes the feasibility confirmation results of FFCI.

中文翻译：

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用于有效管理钚的灵活燃料循环系统

摘要 灵活的燃料循环倡议系统（FFCI 系统）已被开发用于减少乏燃料（SF）的数量，保持后处理厂的高可用性系数，并增加回收的钚（Pu）的抗扩散性。该系统首先将大部分铀 (U) 从 SF 中分离出来，被称为回收材料 (RM) 的残余物质包含 Pu、次锕系元素 (MA)、裂变产物 (FP) 和剩余的 U 将进入 Pu(+U) 回收来自利用 Pu 反应器的 RM。如果 Pu 利用反应堆部署出现延迟，RM 将进入临时存储，直到其部署。利用 Pu 的反应堆是使用混合氧化物 (MOX) 燃料的快中子增殖反应堆 (FBR) 或轻水反应堆 (LWR)。RM是SF后处理和Pu利用反应器之间的缓冲材料，体积小，抗增殖能力强，可以抑制相对纯Pu的量。FFCI的创新技术是U型分离和临时RM存储。它们通过文献调查、使用模拟材料的基础实验和使用模拟代码的分析进行研究。本文总结了FFCI的可行性确认结果。