ETVS fuel assemblies containing nitride fuel rods with different structural implementation and cladding made of different materials are tested in the cores of the BN-600 and BOR-60 reactors in order to substantiate the efficiency of fuel rods with mixed uranium-plutonium nitride fuel used in sodium-cooled (BN-1200) and lead-cooled (BREST-OD-300) reactors. We report here the results of post-reactor studies of BN-600, -800, -1200 and BREST type fuel elements with a helium sublayer after irradiation to maximum burnup 7.5, 6, and 4.5% h.a., respectively, in the composition of 10 ETVS BN-600 fuel assemblies as well BREST type fuel rods with helium and lead sublayer after tests to maximum burnup 5 and 4% h.a. as fuel elements of the BREST type with a helium and lead sublayer after testing to maximum burnup 5 and 4% h.a. in the composition of two ETVS BOR-60 fuel assemblies. The obtained results confirmed that the nitride fuel rods with gas and lead sublayers and EP-823 steel cladding remain efficient at the attained test parameters and, possibly, at higher fuel burnup.

在 BN-600 和 BOR-60 反应堆的堆芯中测试了包含具有不同结构实现的氮化物燃料棒和由不同材料制成的包壳的 ETVS 燃料组件，以证实混合铀钚氮化物燃料的燃料棒在钠冷（BN-1200）和铅冷（BREST-OD-300）反应堆。我们在此报告了 BN-600、-800、-1200 和 BREST 型燃料元件的后反应堆研究结果，该燃料元件在辐照后最大燃耗分别为 7.5、6 和 4.5% ha，在 10 ETVS BN-600 燃料组件以及带氦和铅亚层的 BREST 型燃料棒，在测试至最大燃耗 5% 和 4% 公顷后作为具有氦和铅亚层的 BREST 型燃料元件，在测试至最大燃耗率 5% 和 4% 公顷后 由两个 ETVS BOR-60 燃料组件组成。获得的结果证实，具有气体和铅亚层以及 EP-823 钢包壳的氮化物燃料棒在达到的测试参数下仍然有效，并且可能在更高的燃料燃烧率下。