Works by Lopatkin, A. V.

Results: 21

Design and Analysis of Solid Blanket Concept for Hybrid Fusion-Fission Facility.

Published in:

Physics of Atomic Nuclei, 2023, v. 86, p. S112, doi. 10.1134/S1063778823140132

By:

Strebkov, Yu. S.;
Afremov, D. A.;
Arhipov, O. P.;
Vershinin, I. V.;
Danilov, I. V.;
Ivanov, V. O.;
Kozlov, S. A.;
Korostelev, A. B.;
Larionov, I. A.;
Leshukov, A. Yu.;
Loginov, D. Yu.;
Lopatkin, A. V.;
Lukasevich, I. B.;
Mezhina, E. R.;
Poddubnyi, I. I.;
Pulinets, A. A.;
Razmerov, A. V.;
Sviridenko, M. N.;
Sysoev, A. G.;
Cherepnin, Yu. S.

Publication type:

Article

Comparative Evaluations of Nuclear Fuel Breeding Rate in Hybrid Fission-Fusion Reactor with U and Th.

Published in:

Physics of Atomic Nuclei, 2023, v. 86, p. S122, doi. 10.1134/S1063778823140089

By:

Leshukov, A. Yu.;
Lopatkin, A. V.;
Lukasevich, I. B.;
Razmerov, A. V.;
Strebkov, Yu. S.;
Sysoev, A. G.

Publication type:

Article

Conceptual Design of a Hybrid Fusion–Fission Power Reactor with a Tokamak and a Depleted Uranium Blanket.

Published in:

Physics of Atomic Nuclei, 2020, v. 83, n. 7, p. 1029, doi. 10.1134/S1063778820070091

By:

Mirnov, S. V.;
Gladush, G. G.;
Gostev, A. A.;
Lopatkin, A. V.;
Lukasevic, I. B.;
Lyublinsky, I. E.

Publication type:

Article

Time to radiological equivalence of radioactive waste and natural uranium feedstock at an increasing content of Np, Am, and Cm in long-lived radioactive waste.

Published in:

Atomic Energy, 2025, v. 136, n. 5, p. 280, doi. 10.1007/s10512-024-01161-0

By:

Ivanov, V. K.;
Lopatkin, A. V.;
Adamov, E. O.;
Spirin, E. V.;
Solomatin, V. M.

Publication type:

Article

Analysis of criteria for transmutation as an effective method for removing hazardous radioactive waste.

Published in:

Atomic Energy, 2025, v. 137, n. 3, p. 206, doi. 10.1007/s10512-025-01196-x

By:

Golovin, Nikita P.;
Lukasevich, Ivan B.;
Lopatkin, Aleksandr V.

Publication type:

Article

Verification of the TARUSA-9 software for measuring the activity of fission products in the coolant of a pressurized water reactor.

Published in:

Atomic Energy, 2024, v. 136, n. 3/4, p. 171, doi. 10.1007/s10512-024-01148-x

By:

Lopatkin, A. V.;
Nikitin, A. V.;
Mikhaylov, A. V.;
Gordeev, A. A.;
Vasilenko, V. A.;
Gusev, B. A.;
Baev, M. N.

Publication type:

Article

Approaches to slowing down the kinetics of a fast reactor as a means of enhancing its self-protection properties.

Published in:

Atomic Energy, 2024, v. 135, n. 3/4, p. 121, doi. 10.1007/s10512-024-01091-x

By:

Dolgov, Yu. A.;
Lopatkin, A. V.;
Leonov, V. N.;
Lukasevich, I. B.;
Slesarev, I. S.

Publication type:

Article

Calculated demonstration of VVER-1000 SNF actinide transmutation efficiency.

Published in:

Atomic Energy, 2023, v. 134, n. 3/4, p. 190, doi. 10.1007/s10512-024-01042-6

By:

Lopatkin, A. V.;
Golovin, N. P.;
Lukasevich, I. B.

Publication type:

Article

Neutronics Efficacy Evaluations of Lithium-Uranium and Lithium-Thorium Blankets in a Thermonuclear Plant.

Published in:

Atomic Energy, 2022, v. 132, n. 5, p. 298, doi. 10.1007/s10512-023-00951-2

By:

Gladush, G. G.;
Mirnov, S. V.;
Lopatkin, A. V.;
Lukasevich, I. B.

Publication type:

Article

Neutronics Calculations of Performance Enhancement of the Lithium-Uranium Blanket of a Tokamak Reactor.

Published in:

Atomic Energy, 2021, v. 130, n. 6, p. 319, doi. 10.1007/s10512-022-00817-z

By:

Gladush, G. G.;
Mirnov, S. V.;
Lopatkin, A. V.;
Lukasevich, I. B.

Publication type:

Article

Homogenous Transmutation of 237Np, 241Am, 243Am in a Lead-Cooled Fast Reactor.

Published in:

Atomic Energy, 2021, v. 129, n. 6, p. 326, doi. 10.1007/s10512-021-00756-1

By:

Larionov, I. A.;
Lopatkin, A. V.;
Lukasevich, I. B.;
Moroko, V. I.;
Popov, V. E.

Publication type:

Article

Concept of a New High-Flux Periodic-Pulse Source of Neutrons Based on Neptunium.

Published in:

Atomic Energy, 2021, v. 129, n. 4, p. 227, doi. 10.1007/s10512-021-00738-3

By:

Lopatkin, A. V.;
Tret'yakov, I. T.;
Romanova, N. V.;
Goryachikh, A. V.;
Kokorin, N. D.;
Popov, V. E.;
Moroko, V. I.;
Kravtsova, O. A.;
Aksenov, V. L.;
Kulikov, S. A.;
Rzyanin, M. V.;
Shvetsov, V. N.;
Shabalin, E. P.

Publication type:

Article

Conditions for Reaching Radiation Equivalence of Native Raw Materials and Long-Lived Radioactive Waste in Nuclear Energy in Russia.

Published in:

Atomic Energy, 2021, v. 129, n. 4, p. 188, doi. 10.1007/s10512-021-00732-9

By:

Lopatkin, A. V.;
Platonov, I. V.;
Popov, V. E.

Publication type:

Article

Brest Lead-Cooled Fast Reactor: From Concept to Technological Implementation.

Published in:

Atomic Energy, 2021, v. 129, n. 4, p. 179, doi. 10.1007/s10512-021-00731-w

By:

Adamov, E. O.;
Kaplienko, A. V.;
Orlov, V. V.;
Smirnov, V. S.;
Lopatkin, A. V.;
Lemekhov, V. V.;
Moiseev, A. V.

Publication type:

Article

Method of Calculating Fission Product Mass Transfer in Multizone Reactor Problems.

Published in:

Atomic Energy, 2020, v. 128, n. 1, p. 5, doi. 10.1007/s10512-020-00642-2

By:

Lopatkin, A. V.;
Nikitin, A. V.;
Mikhailov, A. V.;
Gordeev, A. A.;
Vasyukhno, V. P.

Publication type:

Article

Analysis of the Fuel-Loop Characteristics of a Molten-Salt Nuclear Reactor with a Cavity Core.

Published in:

Atomic Energy, 2019, v. 126, n. 3, p. 156, doi. 10.1007/s10512-019-00530-4

By:

Ignat'ev, V. V.;
Feinberg, O. S.;
Smirnov, V. P.;
Vanyukova, G. V.;
Lopatkin, A. V.

Publication type:

Article

Influence of pipe steel and welded joint microstructure on failure resistance with testing in hydrogen.

Published in:

Metallurgist, 2024, v. 68, n. 8, p. 1097, doi. 10.1007/s11015-024-01820-4

By:

Nastich, S. Yu.;
Lopatkin, V. A.;
Egorov, V. A.;
Arabey, A. B.;
Mikhalev, A. Yu.

Publication type:

Article

Effect of Hydrogen Gas on Mechanical Properties of Pipe Metal of Main Gas Pipelines.

Published in:

Metallurgist, 2022, v. 66, n. 5/6, p. 625, doi. 10.1007/s11015-022-01369-0

By:

Nastich, S. Yu.;
Lopatkin, V. A.

Publication type:

Article

Expanding the technical potential for producing modern high-strength skelp after reconstruction of the steelmaking and rolling facilities.

Published in:

Metallurgist, 2010, v. 54, n. 1/2, p. 93, doi. 10.1007/s11015-010-9263-8

By:

Pemov, I. F.;
Morozov, Yu. D.;
Yakushev, E. V.;
Naumenko, A. A.;
Zyryanov, V. V.;
Lopatkin, V. A.

Publication type:

Article

Development of steel of strength class 390 and technology for producing rolled product for assembly components of spatial metal structures.

Published in:

Metallurgist, 2010, v. 54, n. 1/2, p. 103, doi. 10.1007/s11015-010-9264-7

By:

Gladshtein, L. I.;
Mosyagin, D. L.;
Pemov, I. F.;
Naumenko, A. A.;
Yakushev, E. V.;
Lopatkin, V. A.

Publication type:

Article

Hydroconversion of C6—C8 Hydrocarbons on Nickel–Containing Zeolites.

Published in:

Chemistry & Technology of Fuels & Oils, 2003, v. 39, n. 6, p. 343, doi. 10.1023/B:CAFO.0000011910.68168.ad

By:

Lopatkin, S. V.;
Stepanov, V. G.;
Ione, K. G.

Publication type:

Article

Works by Lopatkin, A. V.

Design and Analysis of Solid Blanket Concept for Hybrid Fusion-Fission Facility.

Comparative Evaluations of Nuclear Fuel Breeding Rate in Hybrid Fission-Fusion Reactor with U and Th.

Conceptual Design of a Hybrid Fusion–Fission Power Reactor with a Tokamak and a Depleted Uranium Blanket.

Time to radiological equivalence of radioactive waste and natural uranium feedstock at an increasing content of Np, Am, and Cm in long-lived radioactive waste.

Analysis of criteria for transmutation as an effective method for removing hazardous radioactive waste.

Verification of the TARUSA-9 software for measuring the activity of fission products in the coolant of a pressurized water reactor.

Approaches to slowing down the kinetics of a fast reactor as a means of enhancing its self-protection properties.

Calculated demonstration of VVER-1000 SNF actinide transmutation efficiency.

Neutronics Efficacy Evaluations of Lithium-Uranium and Lithium-Thorium Blankets in a Thermonuclear Plant.

Neutronics Calculations of Performance Enhancement of the Lithium-Uranium Blanket of a Tokamak Reactor.

Homogenous Transmutation of <sup>237</sup>Np, <sup>241</sup>Am, <sup>243</sup>Am in a Lead-Cooled Fast Reactor.

Concept of a New High-Flux Periodic-Pulse Source of Neutrons Based on Neptunium.

Conditions for Reaching Radiation Equivalence of Native Raw Materials and Long-Lived Radioactive Waste in Nuclear Energy in Russia.

Brest Lead-Cooled Fast Reactor: From Concept to Technological Implementation.

Method of Calculating Fission Product Mass Transfer in Multizone Reactor Problems.

Analysis of the Fuel-Loop Characteristics of a Molten-Salt Nuclear Reactor with a Cavity Core.

Influence of pipe steel and welded joint microstructure on failure resistance with testing in hydrogen.

Effect of Hydrogen Gas on Mechanical Properties of Pipe Metal of Main Gas Pipelines.

Expanding the technical potential for producing modern high-strength skelp after reconstruction of the steelmaking and rolling facilities.

Development of steel of strength class 390 and technology for producing rolled product for assembly components of spatial metal structures.

Hydroconversion of C<sub>6</sub>—C<sub>8</sub> Hydrocarbons on Nickel–Containing Zeolites.