Zobrazeno 1 - 10
of 25
pro vyhledávání: '"M. A. Kamnev"'
Autor:
B. A. Vasil’ev, V. V. Patrunin, M. A. Kamnev, O. B. Samoilov, S. V. Babushkin, A. M. Bakhmet’ev, S. N. Pichkov, N. G. Kodochigov, D. L. Zverev, N. G. Sandler
Publikováno v:
Atomic Energy. 129:66-73
Testing and experimental substantiation are a significant and integral part at all phases of the life cycle of reactor equipment. The Research and Testing Complex (RTC) operates at OKBM Afrikantov to ensure that these tasks are successfully fulfilled
Publikováno v:
Atomic Energy. 127:60-63
Neutronics measurements are regularly conducted during operation in order to evaluate the physical characteristics of the core. A nonstandard reactimeter connected to a backup neutron detector is used to perform the measurements. A calculation of the
Publikováno v:
Atomic Energy. 125:213-218
Experimental and computational methods of determining the physical power of a critical assembly are proposed. The experimental conditions and results on determining the coefficient of proportionality of the indications of the SCS apparatus and the po
Publikováno v:
Atomic Energy. 125:165-171
The basic results of computational and experimental studies of passive systems of emergency heat removal in application to ship and portable reactor facilities are presented. The methodological correlations for calculations of heat removal systems wi
Publikováno v:
Atomic Energy. 123:1-9
Severe accidents in NPP with VVER can be accompanied by hydrogen entering the containment space. The aim of the present work is an experimental and computational study of the possibility of hydrogen stratification in the containment in a scenario rep
Publikováno v:
Atomic Energy. 121:397-401
A high-efficiency once-through steam generator is used in the RITM-200 reactor for the universal nuclear icebreaker. The new design necessitated experimental validation of the technical characteristics of the steam generator taking into account the i
Publikováno v:
Atomic Energy. 108:343-348
In the designs of the new-generation reactor facilities, including floating nuclear heat and electricity plants, new passive containment safety systems are used to increase operational safety. The objective of the present work is to validate experime
Publikováno v:
Atomic Energy. 97:858-861
Publikováno v:
Atomic Energy; Jul2023, Vol. 134 Issue 3/4, p169-174, 6p
Autor:
M Iu, Burkovskiĭ, V I, Vorobtsov, S M, Viazenkin, I M, Isakov, M I, Kamnev, Iu A, Pytel', A M, Staroverov, E M, Semeniako
Publikováno v:
Urologiia i nefrologiia. 31(2)