Zobrazeno 1 - 10
of 15
pro vyhledávání: '"I. Yu. Novoselov"'
Autor:
A. G. Karengin, A. A. Karengin, S. Yu. Kuznetsov, I. Yu. Novoselov, A. E. Tikhonov, N. I. Golovkov
Publikováno v:
Russian Physics Journal. 65:677-682
Publikováno v:
Atomic Energy. 131:135-139
Publikováno v:
Atomic Energy. 131:46-49
Publikováno v:
Journal of Surface Investigation: X-ray, Synchrotron and Neutron Techniques. 14:176-183
The article is dedicated to analyzing the concentration processes of the long-lived 36Cl radionuclide in irradiated graphite of uranium-graphite nuclear reactors. The 36Cl radionuclide is one of the most important isotopes for assessing the safety of
Publikováno v:
Nuclear Materials and Energy, Vol 27, Iss, Pp 101018-(2021)
The article is devoted to the study of irradiated graphite-bakelite paste formed during the restoration of graphite stack and the operation of uranium-graphite reactors. It was shown that irradiation of graphite-bakelite paste in the reactor leads to
Publikováno v:
Journal of Nuclear Materials. 515:303-311
This paper is concerned with determination of parameters associated with release of the energy accumulated in irradiated graphite. These parameters define the conditions and possible consequences of the release – the heat effects, both in the cours
Publikováno v:
Solid Fuel Chemistry. 52:328-335
It was demonstrated that thermal treatment and decontamination methods can be used for the processing of irradiated nuclear graphite. Special features of the treatment of the irradiated graphite surface with an oxidizing agent were considered. A math
Publikováno v:
Thermophysics and Aeromechanics. 25:109-117
The paper describes a problem of accumulation of irradiated graphite due to operation of uranium-graphite nuclear reactors. The main noncarbon contaminants that contribute to the overall activity of graphite elements are iso-topes 137Cs, 60Co, 90Sr,
Publikováno v:
Journal of Physics: Conference Series. 1989:012005
This paper presents the results of experimental studies on the process of plasmachemical synthesis of fuel oxide compositions for plutonium-thorium dispersion nuclear fuel. Precursors were simulated water-organic nitrate solutions, which have a lower
Publikováno v:
Atomic Energy. 122:400-405
The aim of the present work is mathematical modeling of the heat and mass transfer of 137Cs under the action of low-temperature equilibrium plasma flow on sections of graphite contaminated by radionuclides. The methods of investigation are calculatio