Zobrazeno 1 - 10
of 21
pro vyhledávání: '"O. N. Nikitin"'
Publikováno v:
Atomic Energy. 132:14-19
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8b57b8f6fa966df8068e3e666ebc17ff
https://doi.org/10.1007/s10512-022-00896-y
https://doi.org/10.1007/s10512-022-00896-y
Autor:
L. M. Zabud’ko, A. V. Belyaeva, Yu. A. Ivanov, A. N. Kozolup, I. F. Gil’mutdinov, F. N. Kryukov, A. F. Grachev, S. S. Sagalov, M. V. Skupov, O. N. Nikitin
Publikováno v:
Atomic Energy. 129:278-283
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
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::81f552a5803a3fc84f6cff453a1c972d
https://doi.org/10.1007/s10512-021-00748-1
https://doi.org/10.1007/s10512-021-00748-1
Autor:
O. N. Nikitin, M. A. Kuzin, S. V. Abramov, S. V. Kuz’min, L. M. Zabud'ko, A. F. Grachev, A. A. Zherebtsov
Publikováno v:
Chemical Engineering. 22:36-43
The method of carbothermic synthesis produced 260 g tablets of mixed nitrides of uranium, plutonium, americium and neptunium with a mass fraction of americium 0.61%. For the production of tablets were used uranium oxide manufactured by the water meth
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ca2349a0da21aa49958eb3bf18569ad1
https://doi.org/10.31044/1684-5811-2021-22-1-36-43
https://doi.org/10.31044/1684-5811-2021-22-1-36-43
Autor:
Yu. A. Ivanov, F. N. Kryukov, L. M. Zabud’ko, S. I. Porollo, O. N. Nikitin, A. F. Grachev, E. E. Marinenko, E. A. Zvir, M. V. Skupov
Publikováno v:
Atomic Energy. 126:182-190
Reactor tests in BN-600 and post-reactor studies of experimental FA of fuel rods with mixed nitride fuel and different cladding are being conducted in Project Breakthrough. In the present article, the irradiation parameters of fuel rods with mixed ni
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::93bd531d323016e36be07cd6a0f455b4
https://doi.org/10.1007/s10512-019-00534-0
https://doi.org/10.1007/s10512-019-00534-0
Autor:
L. M. Zabud’ko, A. A. Zherebtsov, Yu. A. Ivanov, A. F. Grachev, E. A. Zvir, F. N. Kryukov, O. N. Nikitin, S. I. Porollo, M. V. Skupov
Publikováno v:
Atomic Energy. 125:314-321
The complex program of computational and experimental validation of dense fuel for fast reactors in Project Breakthrough provides for testing of fuel rods with mixed uranium-plutonium nitride fuel in the BOR-60 and BN-600 reactors. The irradiation pa
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b812d15387997f0a23107b9bfe42d9f1
https://doi.org/10.1007/s10512-019-00487-4
https://doi.org/10.1007/s10512-019-00487-4
Autor:
O. N. Nikitin, B.A. Tarasov, A. A. Zherebtsov, L. M. Zabud’ko, M. V. Skupov, Yu. S. Mochalov, A. F. Grachev, S. V. Abramov, A. E. Glushenkov, M. A. Kuzin
Publikováno v:
Nuclear Engineering and Design. 382:111379
The main results and plans for the future in the framework of RD intra-fuel pin heterogeneity and intra-fuel assembly (FA) heterogeneity of minor actinides. At the first stage, the technology of homogeneous transmutation is being tested using dismoun
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d7e1b381de4943ff4914625838075a96
https://doi.org/10.1016/j.nucengdes.2021.111379
https://doi.org/10.1016/j.nucengdes.2021.111379
Autor:
I. F. Gil’mutdinov, F. N. Kryukov, S. V. Kuz’min, O. N. Nikitin, A. V. Belyaeva, I. Yu. Zhemkov, Y. A. Kostyukov, Yu. A. Ivanov
Publikováno v:
Atomic Energy. 122:319-325
Electron-microscopic and electron-probe x-ray spectral studies of nitride fuel microstructure in thin sections and fractures of pellets in correlation with the xenon distribution were conducted in order to obtain data on the particulars of porosity f
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3c903d46108526e751e896ca6f3d543c
https://doi.org/10.1007/s10512-017-0273-5
https://doi.org/10.1007/s10512-017-0273-5
Autor:
O. N. Nikitin, I. F. Gil’mutdinov, M. V. Skupov, A. E. Glushenkov, L. M. Zabud’ko, P. I. Grin, Yu. A. Ivanov, G. A. Kireev, A. F. Grachev, F. N. Kryukov, E. A. Zvir
Publikováno v:
Atomic Energy. 122:185-199
Mixed uranium-plutonium nitride fuel is seen as a promising fuel for fast reactors with a closed fuel cycle. A complex program of computational and experimental validation of this fuel up to 2020 has been developed within the scope of Project Breakth
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::19cd37885c0a56868d1ec99e7fe107d1
https://doi.org/10.1007/s10512-017-0254-8
https://doi.org/10.1007/s10512-017-0254-8
Autor:
B. D. Rogozkin, A. V. Belyaeva, L. M. Zabudko, F. N. Kryukov, O. N. Nikitin, S. V. Kuz’min, N. M. Stepennova, M. G. Shishkov, Yu.Ye. Fedorov
Publikováno v:
Journal of Nuclear Materials. 440:445-456
In the article presented are the results of post-irradiation tests of helium bonded fuel pins with mixed mononitride fuel (U 0.55 Pu 0.45 )N and (U 0.4 Pu 0.6 )N having 85% density irradiated in BOR-60 reactor. Achieved maximum burn-up was, respectiv
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::34828c55c3265951bdc2cb6fc5c9bfe9
https://doi.org/10.1016/j.jnucmat.2013.04.033
https://doi.org/10.1016/j.jnucmat.2013.04.033