首页> 外文期刊>Atomic Energy >POSSIBILITY OF IRRADIATING IN RUSSIAN REACTORS THE PLUTONIUM RECYCLED FROM MIXED URANIUM-PLUTONIUM FUEL FABRICATED IN MARCOULE (FRANCE)
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POSSIBILITY OF IRRADIATING IN RUSSIAN REACTORS THE PLUTONIUM RECYCLED FROM MIXED URANIUM-PLUTONIUM FUEL FABRICATED IN MARCOULE (FRANCE)

机译:在俄罗斯反应器中照射的可能性,钚从Marcoule(法国)制造的混合铀 - 钚燃料中再循环

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摘要

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-PuO(2)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.
机译:EDF在2016年2月在BN-600中的测试实验FA的CEA讨论期间,2016年2月在俄罗斯快速反应堆燃料销中照射了俄罗斯快速反应堆燃料销。 EDF提出另外用在PWR中辐照中再处理混合燃料后获得的使用钚制造的几种制造的燃料销。在2017年,制造全规模FA的研究是昂贵的,因此开发了使用在Reprocessing期间获得的钚在Atalante(CEA)的实验室设施中的几十克UO2-Puo(2)中进行了建议。混合燃料,以及BN-600中的几个Astrid型燃料销。这些研究将分三个阶段进行:BOR-60中的小规模辐射,对BN-600中再生钚的10个全规模FA的辐射的计算研究,BN-600的辐照为一到五个实验ASTRID-用再生钚型燃料销。讨论了规定实验的技术问题。

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