Zobrazeno 1 - 10
of 23
pro vyhledávání: '"T. B. Aleeva"'
Autor:
S. N. Ryzhov, E. V. Bogdanova, A. A. Ryzhkov, P. A. Pugachev, G. V. Tikhomirov, M. Yu. Ternovykh, T. B. Aleeva
Publikováno v:
Глобальная ядерная безопасность, Vol 0, Iss 3, Pp 5-21 (2022)
This paper analyzes the methods and technologies for assessing the method of formation, composition, characteristics and features of corium, which is a mixture of nuclear and structural materials of the nuclear reactor core, formed as a result of an
Externí odkaz:
https://doaj.org/article/90c55ee95332468990a5f9a4ad1ed59c
Autor:
S. N. Ryzhov, E. V. Bogdanova, A. A. Ryzhkov, P. A. Pugachev, G. V. Tikhomirov, M. Yu. Ternovykh, T. B. Aleeva
Publikováno v:
Physics of Atomic Nuclei. 85:S90-S102
Autor:
A. V. Davydov, V. N. Zubarev, A. V. Bushuev, A. P. Lipatov, A. E. Glushenkov, I. D. Solomatin, B. A. Tarasov, T. B. Aleeva, R. R. Khalitov, A. F. Kozhin
Publikováno v:
Atomic Energy. 125:103-107
A non-destructive gamma-spectrometric method of determining the characteristics of fissile materials in fuel pins with uranium-plutonium fuel is presented. The measurements were performed with the aid of a scanning apparatus with an ultrapure germani
Autor:
T. B. Aleeva, B. A. Tarasov, D. V. Denisov, A. V. Bushuev, R. R. Khalitov, V. N. Zubarev, A. F. Kozhin
Publikováno v:
Atomic Energy. 125:108-111
The application of mathematical modeling in the development of a procedure for gamma-spectrometric monitoring of fuel pins with uranium plutonium fuel is described. The EffMaker software system was used for modeling the spectra. As a result, a measur
Publikováno v:
Physics of Atomic Nuclei. 79:1362-1366
An active neutron method for measuring the residual mass of 235U in spent fuel assemblies (FAs) of the IRT MEPhI research reactor is presented. The special measuring stand design and uniform irradiation of the fuel with neutrons along the entire leng
Autor:
A. F. Kozhin, A. V. Bushuev, T. B. Aleeva, R. R. Khalitov, N. I. Geraskin, V. N. Zubarev, V. S. Rudenko, E. M. Glagovskii
Publikováno v:
Atomic Energy. 120:44-47
One problem of decommissioning graphite reactors is the evaluation of the radioactive contamination of the graphite. The possible methods of determining the composition, contamination, and radionuclide concentration by means of laboratory analysis of
Autor:
V. N. Zubarev, A. F. Kozhin, A. A. Syrosev, A. M. Pavlov, T. B. Aleeva, M. S. Verenchikova, A. V. Bushuev
Publikováno v:
Atomic Energy. 119:253-257
A method is proposed for determining the mass and isotopic composition of the plutonium warehoused in containers at the RT-1 plant of the Industrial Association Mayak. A single measurement system with a detector based on ultrapure germanium is used f
Publikováno v:
Atomic Energy. 122:213-215
Publikováno v:
Journal of Physics: Conference Series. 1689:012073
In this research radioactive contamination of graphite of the 4th block of the Leningrad NPP was determined using the method of gamma-spectrometric analysis. The obtained results of the specific activity of isotopes were compared with the contaminati
Autor:
L. I. Yakovlev, A. B. Gaiduchenko, A. A. Serebryakov, A. E. Kruglikov, N. I. Geraskin, T. B. Aleeva, D. V. Andreev, S. A. Ozherelev, A. F. Kozhin, M. V. Shchurovskaya, V. P. Alferov
Publikováno v:
Journal of Physics: Conference Series. 1689:012024
Life cycle extension practices for U–Al fuel in Al cladding used at the OR and the IRT MEPhI research reactors are discussed. The IRT MEPhI reactor uses tube type IRT-3M FA with dispersed UO2–Al fuel meat and SAV–1 aluminum alloy as cladding. T