Zobrazeno 1 - 10
of 21
pro vyhledávání: '"V. I. Nalivaev"'
Autor:
Tim Haste, Mirco Grosse, N. Vér, Martin Steinbrück, Juri Stuckert, A. E. Kisselev, Zoltán Hózer, L. Sepold, J. Birchley, A. V. Goryachev, V. P. Semishkin, V. I. Nalivaev, M.S. Veshchunov, A.V. Boldyrev
Publikováno v:
Progress in Nuclear Energy. 52:19-36
This paper gives an overview on the status of knowledge of high-temperature oxidation of the two zirconium alloys Zircaloy-4 and E110 with special emphasis on results obtained during the SARNET period. The tin-bearing alloy Zircaloy-4 and the niobium
Autor:
P. M. Gavrilov, N. A. Piskunova, I. I. Fedik, A. M. Dmitriev, N. N. Khrennikov, V. I. Nalivaev, V. P. Deniskin
Publikováno v:
Atomic Energy. 103:675-680
The salient features of using a solid substance to cool the core of a nuclear reactor and the associated advantages and limitations are examined. Conceptual proposals concerning the core design and the arrangement of the in-reactor space of a high-te
Publikováno v:
Atomic Energy. 99:792-798
A validation of the possibility of developing and the basic advantages of a high-temperature nuclear reactor where the first-loop coolant is a solid are presented. The basic requirements for a solid coolant are formulated, a technology for fabricatin
Autor:
A. M. Nikolotov, B. A. Gabaraev, Yu. I. Mityaev, V. P. Deniskin, V. K. Vikulov, F. E. Ermoshin, I. I. Fedik, M. I. Rozhdestvenskii, V. I. Nalivaev, S. S. Gavrilin, A. A. Romenkov
Publikováno v:
Atomic Energy. 98:233-241
The concept of a direct-flow channel reactor with supercritical-pressure water (CR-SCP) is presented. Neutron-physics, thermohydraulic, and strength calculations are used to substantiate the fundamental core design with a heavy-metal moderator which
Publikováno v:
Atomic Energy. 96:219-227
A computational-experimental procedure for performing a bench simulation of the first and second stages of an accident are described. Experiments studying the behavior of fuel elements and model fuel assemblies under conditions simulating the first s
Autor:
N. E. Kukharkin, V. S. Konstantinov, V. P. Deniskin, I. I. Fedik, Y.-U. G. Dragunov, V. I. Nalivaev, I. I. Konovalov, V. I. Subbotin, S. S. Gavrilin, N. N. Ponomarev-Stepnoi, S. B. Ryzhov, V. P. Spasskov
Publikováno v:
Atomic Energy. 96:250-259
The results of development work on a new generation of fuel elements based on microfuel for VVER reactors using the basic data from post-reactor investigations and bench tests in experiments simulating LOCA for existing fuel elements with ceramic fue
Autor:
Alexander V. Palagin, Andreas Schumm, Francesco Oriolo, Juri Stuckert, M. Hugon, Sevostian Bechta, V. Zhdanov, S. Weber, Manfred Fischer, Peter Hofmann, D. Bottomley, B. Clément, A. E. Kiselev, C. Journeau, V. Baklanov, Eberhard Altstadt, A. V. Goryachev, M. Krause, Zoltán Hózer, V.B. Khabensky, L. Tocheny, V. I. Nalivaev, M.S. Veshchunov, S. Guentay, Luis E. Herranz
Publikováno v:
Nuclear Engineering and Design
Nuclear Engineering and Design, 2012, 252, pp.226-241. ⟨10.1016/j.nucengdes.2012.07.006⟩
Nuclear Engineering and Design 252(2012), 226-241
Nuclear Engineering and Design, 2012, 252, pp.226-241. ⟨10.1016/j.nucengdes.2012.07.006⟩
Nuclear Engineering and Design 252(2012), 226-241
The paper has two following objectives: - To describe the organization of complex, international, experimental and analytical research of material processes under extreme conditions similar to those of severe accidents in nuclear reactors and, - To i
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::b63b47e36e54a14cf2ba1efe1fe508bf
https://hal.archives-ouvertes.fr/hal-02920212
https://hal.archives-ouvertes.fr/hal-02920212
Publikováno v:
Heat Transfer Research. 32:7
Autor:
B. A. Gabaraev, V. K. Vikulov, F. E. Ermoshin, Yu. I. Mityaev, A. M. Nikolotov, M. I. Rozhdestvenskii, A. A. Romenkov, I. I. Fedik, S. S. Gavrilin, V. P. Deniskin, V. I. Nalivaev
Publikováno v:
Atomic Energy; Apr2005, Vol. 98 Issue 4, p233-241, 9p
Publikováno v:
Atomic Energy; Apr2004, Vol. 96 Issue 4, p219-227, 9p