Author:
Grachev A. F.,Zabudko L. M.,Mochalov Yu. S.,Belyaeva A. V.,Kryukov F. N.,Gilmutdinov I. F.,Skupov M. V.,Ivanov Yu. A.
Publisher
Springer Science and Business Media LLC
Subject
Nuclear Energy and Engineering
Reference4 articles.
1. V. M. Troyanov, A. F. Grachev, L. M. Zabudko, and M. V. Skupov, “Prospects for using nitride fuel in fast reactors with a closed fuel cycle,” At. Energ., 117, No. 2, 69–75 (2014).
2. A. F. Grachev, L. M. Zabudko, Yu. A. Ivanov, et al., “Results of a study of BN-600 reactor fuel rods with mixed uranium-plutonium nitride fuel and ChS68-ID steel cladding,” At. Energ., 126, No. 3, 160–166 (2019).
3. A. F. Grachev, A. A. Zherebtsov, L. M. Zabudko, et al. “Investigation of BREST-type fuel rods with mixed uranium-plutonium nitride fuel irradiated in BOR-60 and BN-600,” At. Energ., 125, No. 5, 278–284 (2018).
4. E. O. Adamov, L. M. Zabudko, Yu. S. Mochalov, et al., “Development of a fuel rod with uranium-plutonium nitride fuel and a liquid metal sublayer,” At. Energ., 127, No. 5, 255–262 (2019).
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