Zobrazeno 1 - 5
of 5
pro vyhledávání: '"E. E. Marinenko"'
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:
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
Publikováno v:
Atomic Energy. 121:415-423
The results of an investigation of gas release and swelling of uranium mononitride fuel after irradiation in standard and experimental fuel assemblies in the BR-10 reactor in the burnup range 3.4–8.4% h.a. are presented and analyzed. The results ob
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b46693e43ab3b4df6b507bf744fed4a7
https://doi.org/10.1007/s10512-017-0221-4
https://doi.org/10.1007/s10512-017-0221-4