Search Results - "Pavlyuk, A. O."

Technical and Methodological Support for Studies of Radioactive Graphite-containing Sludge in Technological Reservoirs by Pavlyuk, A. O., Kotlyarevsky, S. G., Zaderyaka, A. A., Kuzov, V. A., Shevchenko, O. M., Zakharova, E. V., Volkova, A. G.

“…The article reflects the problem of graphite-containing sludge accumulated, as deposit, in technological systems during the operation of uranium-graphite…”
Get full text

Radionuclides in Irradiated Graphite of Uranium–Graphite Reactors: Decontamination of Sleeves Using Liquid Reagents by Volkova, A. G., Zakharova, E. V., Pavlyuk, A. O., Shiryaev, A. A.

“…To examine the possibility of disposal of irradiated graphite in ground near-surface repositories, the concentration and spatial distribution of radionuclides…”
Get full text

Study of the Process of Leaching of Long-Lived Radionuclides 14С and 36Сl from Irradiated Graphite by Pavlyuk, A. O., Kotlyarevskii, S. G., Kan, R. I., Volkova, A. G., Zakharova, E. V.

“…The release of long-lived radionuclides 14 C and 36 Cl , which are key products for assessment of disposal variants (near-surface, buried, or deep) of…”
Get full text

Analysis of the Causes of Irregular 36Cl Radionuclide Distribution in Irradiated Nuclear Graphite by Bespala, E. V., Pavlyuk, A. O., Kotlyarevskiy, S. G., Novoselov, I. Yu

“…— The article is dedicated to analyzing the concentration processes of the long-lived 36 Cl radionuclide in irradiated graphite of uranium-graphite nuclear…”
Get full text

Electrochemical Decontamination of Irradiated Nuclear Graphite of Uranium-Graphite Nuclear Reactors by Pavlyuk, A. O., Bespala, E. V., Kotlyarevskii, S. G., Zagumennov, V. S., Zakharova, E. V., Volkova, A. G., Rodygina, N. I.

“…Work has been performed as part of the implementation of measures to reduce the hazard of irradiated graphite during the decommissioning of uranium-graphite…”
Get full text

Radionuclides in Irradiated Graphite of Uranium–Graphite Reactors: Decontamination by Thermochemical Methods by Volkova, A. G., Zakharova, E. V., Rodygina, N. I., Pavlyuk, A. O., Shiryaev, A. A.

“…Graphite samples from blocks and sleeves are characterized by extremely heterogeneous spatial distribution of radionuclides on the scale of tens and hundreds…”
Get full text

Heat Treatment of Irradiated Graphite in an Oxidizing Atmosphere by Bespala, E. V., Pavlyuk, A. O., Kotlyarevskii, S. G., Novoselov, I. Yu, Bespala, Yu. R.

“…It was demonstrated that thermal treatment and decontamination methods can be used for the processing of irradiated nuclear graphite. Special features of the…”
Get full text

Study of evaporating the irradiated graphite in equilibrium low-temperature plasma by Bespala, E. V., Novoselov, I. Yu, Pavlyuk, A. O., Kotlyarevskiy, S. G.

“…The paper describes a problem of accumulation of irradiated graphite due to operation of uranium-graphite nuclear reactors. The main noncarbon contaminants…”
Get full text

Determination of Parameters of Porous Structure Affecting the Release Mechanisms of Long-Lived Radionuclides from Irradiated Graphite in Contact with Liquid Media by Pavlyuk, A. O., Kotlyarevskii, S. G., Kan, R. I., Volkova, A. G., Zolotov, D. A., Pakhnevich, A. V., Zakharova, E. V., Shiryaev, A. A.

“…Specific features of the porous structure of irradiated and virgin reactor graphite of Russian brands have been analyzed. The porosity parameters affecting the…”
Get full text

Heat and Mass Transfer in Cesium Evaporation from Graphite Surface in Argon by Bespala, E. V., Myshkin, V. F., Pavlyuk, A. O., Novoselov, I. Yu

“…The aim of the present work is mathematical modeling of the heat and mass transfer of 137 Cs under the action of low-temperature equilibrium plasma flow on…”
Get full text

Technology and Facility for Incinerating Irradiated Reactor Graphite by Kashcheev, V. A., Ustinov, O. A., Yakunin, S. A., Zagumennov, V. S., Pavlyuk, A. O., Kotlyarevskii, S. G., Bespala, E. V.

“…The USG-1 facility was developed to incinerate spent reactor graphite. It is equipped with a monitoring and control system; its maximum capacity is 10 kg/h…”
Get full text