EdF’s idea of irradiating in Russian fast reactors fuel pins with recycled plutonium arose in February 2016 during a discussion with CEA of testing experimental FA in BN-600. EdF proposed to additionally irradiated several fuel pins fabricated using plutonium obtained after reprocessing of mixed fuel irradiated in PWR. In 2017, the studies with fabrication of full-scale FA were to expensive, so that proposals were developed for irradiating several tens of grams of UO2–PuO2 in a laboratory facility in Atalante (CEA), using plutonium obtained during reprocessing of mixed fuel, as well as several ASTRID-type fuel pins in BN-600. The studies are to be conducted in three stages: small-scale irradiation in BOR-60, computational studies of the irradiation of 10 full-scale FA with recycled plutonium in BN-600, irradiation in BN-600 of one to five experimental ASTRID-type fuel pins with recycled plutonium. The technical problems of the specified experiments are discussed.

中文翻译：

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在俄罗斯反应堆中辐照从 Marcoule（法国）制造的混合铀-钚燃料中回收的钚的可能性

2016 年 2 月，在与 CEA 讨论在 BN-600 中测试实验性 FA 时，EdF 提出了用回收钚辐照俄罗斯快堆燃料棒的想法。EdF 提议对使用压水堆中辐照的混合燃料后处理后获得的钚制造的几个燃料棒进行额外辐照。2017 年，制造全尺寸 FA 的研究非常昂贵，因此提出了使用混合燃料后处理过程中获得的钚在 Atalante (CEA) 的实验室设施中辐照几十克 UO2–PuO2 的建议，以及 BN-600 中的几个 ASTRID 型燃料棒。这些研究将分三个阶段进行：BOR-60 中的小规模辐照，BN-600 中用回收钚对 10 个全尺寸 FA 进行辐照的计算研究，BN-600 中 1 到 5 个实验性 ASTRID 型燃料棒与回收钚的辐照。讨论了指定实验的技术问题。