Zobrazeno 1 - 10
of 61
pro vyhledávání: '"A. F. Grachev"'
Autor:
E. O. Adamov, A. F. Grachev, L. M. Zabudko, E. V. Lachkanov, Yu. S. Mochalov, A. V. Belyaeva, F. N. Kryukov, Yu. A. Ivanov, M. V. Skupov, E. E. Marinenko, S. I. Porollo
Publikováno v:
Atomic Energy. 131:268-273
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4f169b6a02e63313a2e2bce98d7ea3dc
https://doi.org/10.1007/s10512-022-00877-1
https://doi.org/10.1007/s10512-022-00877-1
Autor:
A. F. Grachev, L. M. Zabud’ko, M. V. Leont’eva-Smirnova, I. A. Naumenko, F. N. Kryukov, E. V. Chertopyatov, E. E. Marinenko, S. I. Porollo
Publikováno v:
Atomic Energy. 130:323-327
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d0d27e9a0335b20a6bf84f851da8a7e5
https://doi.org/10.1007/s10512-022-00818-y
https://doi.org/10.1007/s10512-022-00818-y
Autor:
Yu. A. Ivanov, I. F. Gil’mutdinov, F. N. Kryukov, L. M. Zabud’ko, M. V. Skupov, A. V. Belyaeva, Yu. S. Mochalov, A. F. Grachev
Publikováno v:
Atomic Energy. 129:320-325
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 mi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::36b9988a979369858886ce8d78ae8e07
https://doi.org/10.1007/s10512-021-00755-2
https://doi.org/10.1007/s10512-021-00755-2
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:
E. E. Marinenko, M. V. Skupov, F. N. Kryukov, V. G. Teplov, L. M. Zabud’ko, A. F. Grachev, S. I. Porollo
Publikováno v:
Atomic Energy. 129:103-107
The results of an investigation of fission gas release from mixed nitride fuel after irradiation to maximum burnup 7.5% h. a. in 10 experimental FA in BN-600 are reported. It is shown that gas release commences at burnup >2% h.a. and increases with i
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8de5c43ffb938237b79ea443d3a441ff
https://doi.org/10.1007/s10512-021-00712-z
https://doi.org/10.1007/s10512-021-00712-z
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:
E.V. Lachkanov, M. V. Skupov, A. A. Zherebtsov, L. M. Zabud’ko, E. A. Zvir, Yu. A. Ivanov, F. N. Kryukov, Yu. S. Mochalov, A. F. Grachev
Publikováno v:
Nuclear Engineering and Design. 384:111430
Within the framework of the “PRORYV” project the “The comprehensive program for the calculation and experimental justification of fuel pins with mixed uranium-plutonium nitride fuel of BN-1200 and BREST reactors for the period up to 2020” has
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1ba95dec300a9b96e738482d73214c41
https://doi.org/10.1016/j.nucengdes.2021.111430
https://doi.org/10.1016/j.nucengdes.2021.111430