Search Results - "Aleeva, T. B."

Analysis of Methods and Technologies for Assessing the Composition of the Corium Formed as a Result of the Accident at the Fukushima Daiichi NPP by Ryzhov, S. N., Bogdanova, E. V., Ryzhkov, A. A., Pugachev, P. A., Tikhomirov, G. V., Ternovykh, M. Yu, Aleeva, T. B.

“…This article analyzes methods and technologies for assessing the way of formation, composition, characteristics, and features of corium, i.e., a mixture of…”
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Analysis of Methods and Technologies for Composition Assessing of Corium Formed as a Result of the Fukushima Daiichi NPP Accident by Ryzhov, S. N., Bogdanova, E. V., Ryzhkov, A. A., Pugachev, P. A., Tikhomirov, G. V., Ternovykh, M. Yu, Aleeva, T. B.

“…This paper analyzes the methods and technologies for assessing the method of formation, composition, characteristics and features of corium, which is a mixture…”
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Mathematical Modeling of the γ-Ray Spectra of Fuel Pins with Uranium-Plutonium Fuel for Development of Fissile-Materials Monitoring Procedures by Khalitov, R. R., Aleeva, T. B., Kozhin, A. F., Bushuev, A. V., Zubarev, V. N., Tarasov, B. A., Denisov, D. V.

“…The application of mathematical modeling in the development of a procedure for gamma-spectrometric monitoring of fuel pins with uranium plutonium fuel is…”
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Gamma-Spectrometric Control of Fissile Mass and Distribution Uniformity in Fuel Pins with Uranium-Plutonium Nitride Fuel by Aleeva, T. B., Kozhin, A. F., Bushuev, A. V., Zubarev, V. N., Khalitov, R. R., Tarasov, B. A., Glushenkov, A. E., Lipatov, A. P., Davydov, A. V., Solomatin, I. D.

“…A non-destructive gamma-spectrometric method of determining the characteristics of fissile materials in fuel pins with uranium-plutonium fuel is presented. The…”
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A setup for active neutron analysis of the fissile material content in fuel assemblies of nuclear reactors by Bushuev, A. V., Kozhin, A. F., Aleeva, T. B., Zubarev, V. N., Petrova, E. V., Smirnov, V. E.

“…An active neutron method for measuring the residual mass of 235 U in spent fuel assemblies (FAs) of the IRT MEPhI research reactor is presented. The special…”
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Radioactive Contamination of Spent Reactor Graphite by Bushuev, A. V., Kozhin, A. F., Zubarev, V. N., Aleeva, T. B., Petrova, E. V., Glagovskii, E. M., Rudenko, V. S., Girke, N. A.

“…The radioactive contamination of the spent graphite of uranium-graphite reactors is analyzed. The formation of the radioactive contamination during irradiation…”
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Gamma-Spectrometric Determination of the Plutonium Mass in Containers by Aleeva, T. B., Bushuev, A. V., Kozhin, A. F., Zubarev, V. N., Verenchikova, M. S., Pavlov, A. M., Syrosev, A. A.

“…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…”
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Methods of Inspecting the Radioactive Contamination of Uranium-Graphite Reactor Masonry by Bushuev, A. V., Kozhin, A. F., Aleeva, T. B., Zubarev, V. N., Khalitov, R. R., Glagovskii, E. M., Rudenko, V. S., Geraskin, N. I.

“…One problem of decommissioning graphite reactors is the evaluation of the radioactive contamination of the graphite. The possible methods of determining the…”
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Determination of the residual content of fissile materials in fuel from spent fuel assemblies with high initial enrichment by the active neutron method by Bushuev, A. V., Kozhin, A. F., Glagovsky, E. M., Zubarev, V. N., Aleeva, T. B., Petrova, E. V., Rudenko, V. S., Smirnov, V. E., Malakhov, M. I.

“…A stand and procedure for measuring the residual content of fissile materials in spent fuel assemblies from research and propulsion reactors are described. The…”
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Gamma spectrometric determination of the isotopic decomposition of plutonium in containers using MGA and FRAM software by Bushuev, A. V., Aleeva, T. B., Kozhin, A. F., Petrova, E. V., Zubarev, V. N., Pavlov, A. M., Myrzin, A. F., Syrosev, A. A.

“…Plutonium dioxide is stored in special containers, holding about 3 kg plutonium each, in a dump at the RT-1 plant of the Industrial Association Mayak. The…”
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Experimental study of the radioactive contamination of graphite masonry in the commercial reactors at the siberian chemical combine by BUSHUEV, A. V, VERZILOV, Yu. M, NIKOLAEV, A. G, BARANOV, I. I, KABANOV, Yu. I, KOLOBOVA, E. N, ZUBAREV, V. N, PETROVA, E. V, ALEEVA, T. B, PROSHIN, I. M, KACHANOVSKII, A. E, DMITRIEV, A. M, ZAKHAROVA, E. V, USHAKOV, S. I

“…The graphite masonry from decommissioned commercial uranium-graphite reactors is contaminated with radionuclides and is a significant fraction of the…”
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Possibility of Salvaging Spent Graphite Sleeves from the Reactors of the Siberian Chemical Combine by Incineration by Bushuev, A V, Aleeva, T B, Petrova, E V, Zubarev, V N, Nikolaev, A G, Semenov, V G, Silin, B G, Dmitriev, A M

“…Several thousand metric tons of spent graphite sleeves, which are being kept at solid-wastes storage facilities, have now been accumulated. The construction…”
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Development of the method of isotopic correlations for determining the relative (242)Pu content in plutonium samples by Aleeva, T B, Bushuev, A V, Kozhin, A F, Zubarev, V N, Myrzin, A F

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Development of the method of isotopic correlations for determining the relative 242Pu content in plutonium samples by Aleeva, T. B., Bushuev, A. V., Kozhin, A. F., Zubarev, V. N., Myrzin, A. F.

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Determination of the plutonium mass in containers with plutonium dioxide according to the γ radiation from spontaneous-fission products by Bushuev, A. V., Kozhin, A. F., Aleeva, T. B., Zubarev, V. N., Myrzin, A. F., Syrosev, A. A., Vlaskin, G. N., Samoilov, A. A.

“…A nondestructive method of determining the mass of large plutonium samples which is based on measuring their characteristic γ radiation is presented. The mass…”
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Numerical simulation of plutonium measurements using an active well coincidence counter (AWCC) by Vladimirov, D. A., Rogozhkin, V. Yu, Gorbunova, A. Yu, Aleeva, T. B., Pugachev, P. A.

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Fission Products and Actinides in Spent Graphite Masonry of the Reactors at the Siberian Chemical Combine by Bushuev, A V, Verzilov, YuM, Zubarev, V N, Kachanovskii, A E, Proshin, I M, Petrova, E V, Aleeva, T B, Dmitriev, A M, Zakharova, E V, Ushakov, SI, Baranov, I I, Kabanov, YuI, Kolobova, EN, Nikolaev, A G

“…The characteristic feature of the investigations performed was the wide-scale and representative selection of samples of graphite masonry from reactors and the…”
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Determination of IRT FA Burnup at Mephi from Total 137Cs Activity by Kozhin, A. F., Bushuev, A. V., Zubarev, V. N., Aleeva, T. B.

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DETERMINATION OF IRT FA BURNUP AT MEPHI FROM TOTAL [sup.137]Cs ACTIVITY by Kozhin, A.F, Bushuev, A.V, Zubarev, V.N, Aleeva, T.B

“…Several series of experiments on developing methods of determining the burnup of spent FA based on passive and active nondestructive measurements using…”
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60Co content in the spent graphite masonry of commercial reactors at the siberian chemical combine by Bushuev, A. V., Verzilov, Yu. M., Zubarev, V. N., Proshin, I. M., Petrova, E. V., Aleeva, T. B., Dmitriev, A. M., Zakharova, E. V., Ushakov, S. I., Baranov, I. I., Kabanov, Yu. I., Kolobova, É. I., Nikolaev, A. G.

“…Some results of comprehensive investigations of the radioactive contamination of graphite masonry from shutdown commercial uranium-graphite reactors at the…”
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