Experimental fuel rods with mixed uranium-plutonium nitride fuel are being tested in the BOR-60 reactor as part of collapsible irradiation devices, which are prototypes of fuel rods of the BREST-OD-300 reactor being designed. Currently, reactor tests of fuel rods with a helium sublayer as part of OU-2, as well as lead alloyed with components of EP823-Sh steel as part of OU-4, are continuing. In 2018, one fuel rod was removed from OU-2 and one OU-4 after the first stage of reactor tests with the rods replaced by others from those previously irradiated and post-reactor studies were performed. Information on the features of the radiation swelling of the uranium-plutonium nitride fuel of these fuel rods is presented.

混合铀钚氮化物燃料的实验燃料棒正在 BOR-60 反应堆中作为可折叠辐照装置的一部分进行测试，这是正在设计的 BREST-OD-300 反应堆燃料棒的原型。目前，正在继续对具有氦亚层作为 OU-2 一部分的燃料棒以及与作为 OU-4 一部分的 EP823-Sh 钢成分合金化的铅进行反应堆试验。2018 年，在第一阶段反应堆试验后，一根燃料棒从 OU-2 和一根 OU-4 中取出，用之前经过辐照和反应堆后研究的其他棒代替。介绍了这些燃料棒的铀钚氮化物燃料的辐射膨胀特征的信息。