The ASTRID French project aimed at designing, building and operating a sodium fast reactor cooled with liquid sodium. One of the goals of the project was to demonstrate the feasibility of the plutonium multi-recycling in a fast spectrum. Commissariat à l’énergie atomique et aux énergies alternatives (CEA - Atomic & Alternative Energies Commission) has recently announced the abandon of the project which involves that no sodium fast reactor project is planned in France. As a consequence, there is a real interest in assessing technical feasibility for alternative plutonium management. In this work, the plutonium multi-recycling in PWR is assessed from fuel cycle simulations performed with the library CLASS developed by CNRS/IN2P3. The technical conditions for plutonium incineration and stabilization are investigated. It is shown that plutonium can be stabilized with 30% of PWR using multi-reprocessed plutonium in MOX fuel, the rest being composed by PWR loaded with UOX. The transuranic (plutonium and minor actinides) stabilization involves a plutonium incineration. For this reason, around 50% of PWR using multi-reprocessed plutonium is required and the nuclear power has to decrease. In this paper, the methodology and the output analysis are described in detail.

法国的ASTRID项目旨在设计，建造和运行以液态钠冷却的钠快堆。该项目的目标之一是证明在快速光谱中进行multi多次回收的可行性。替代能源委员会（CEA-原子与替代能源委员会）最近宣布放弃该项目，该项目涉及法国没有计划的钠快堆项目。结果，人们真正对评估替代alternative管理的技术可行性感兴趣。在这项工作中，通过使用CNRS / IN2P3开发的CLASS库执行的燃料循环模拟，评估了PWR中的multi多次再循环。研究了p焚烧和稳定化的技术条件。结果表明，在MOX燃料中使用多处理p，可以用30％的PWR稳定p，其余部分由装有UOX的PWR组成。超铀（（和次act系元素）的稳定化涉及a的焚化。因此，需要使用多处理p的压水堆的约50％，并且核电必须降低。在本文中，详细介绍了方法和输出分析。