A. Lopatkin

发表

TRANSMUTATION OF LONG-LIVED NUCLIDES IN THE FUEL CYCLE OF BREST-TYPE REACTORS

V. Orlov, A. Lopatkin, A. Filin, 2001 .

Indicators of reactors in large-scale nuclear power in Russia

V. Orlov, A. Lopatkin, E. Adamov, 1998 .

The degree of attainment of radiation equivalency of highly active waste and natural uranium in the fuel cycle of nuclear power plants in Russia

V. Orlov, A. Lopatkin, E. Adamov, 1996 .

ICONE11-36021 THE THREE-TARGET CHANNEL-TYPE URANIUM-WATER FAST REACTOR WITH DIRECT FLOW OF SUPERCRITICAL WATER TO SOLVE THE PROBLEMS OF WEAPON-PLUTONIUM AND POWER GENERATION AT HIGH EFFICIENCY

A. Lopatkin, V. Reshetov, I. Ganev, 2003 .

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

V. V. Orlov, V. V. Lemekhov, A. V. Kaplienko, 2021, Atomic Energy.

Reducing high-level wastes to a minimum during the operation of large-scale nuclear power in Russia

V. Orlov, A. Lopatkin, E. Adamov, 1997 .

The effect of a transmutational fuel cycle on the attainment of radiation equivalency of highly active waste and natural uranium in Russian nuclear power plants

V. Orlov, A. Lopatkin, E. Adamov, 1996 .

ITER reference breeding blanket design

W. Gulden, A. Lopatkin, G. Celentano, 1999 .

Models of the development of large-scale nuclear power in Russia with a transmutation nuclear fuel cycle and attainment of radiation equivalence of high-level wastes and natural uranium

V. Orlov, A. Lopatkin, E. Adamov, 1997 .

Plasma-physical and electrophysical aspects of the compact stationary neutron source on the basis of a tokamak

G. G. Gladush, R. Khayrutdinov, V. Dokuka, 2005 .

Self-consistent model of nuclear power development and fuel cycle

V. Orlov, A. Lopatkin, E. Adamov, 1999 .

Model and Mockup of DEMO Ceramic Breeding Zone for Testing in the IVV-2M Reactor

A. Lopatkin, V. Gorokhov, A. Shikov, 2001 .

Modernization of the IBR-2 pulsed research reactor

I. B. Lukasevich, N. V. Romanova, A. Lopatkin, 2012 .

Handling Irradiated RBMK-1000 and VVÉR-1000 Fuel during the Growth of Nuclear Power

V. Orlov, A. Lopatkin, V. Smirnov, 2001 .

Effect of Burnup and Holding Time of Irradiated Nuclear Fuel on the Mass Ratio of Am, Cm, Np, and Fissioning Plutonium

V. Orlov, A. Lopatkin, I. Ganev, 2004 .

Activation analysis of ITER blanket first wall

A. Lopatkin, V. Muratov, 1998 .

Breeding zone models of demo ceramic helium cooled blanket test module for reactor in-pile testing

A. Lopatkin, V. Muratov, D. Davydov, 2004 .

Conceptual framework of a strategy for the development of nuclear power in Russia to 2100

E. O. Adamov, A. V. Lopatkin, V. V. Orlov, 2012 .

Contribution of the Research and Design Institute of Electrical Technology to the formulation of a strategy for the development of nuclear power in Russia

A. V. Dzhalavyan, V. Orlov, A. Lopatkin, 2007 .

Conceptual framework of a strategy for the development of nuclear power in Russia to 2100

V. V. Orlov, A. V. Dzhalavyan, R. M. Aleksakhin, 2012, Atomic Energy.

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

I. B. Lukasevich, G. G. Gladush, A. Lopatkin, 2022, Atomic Energy.

Radiation Characteristics of Spent Nuclear Fuel and Wastes in Nonaqueous Reprocessing Methods

V. Orlov, A. Lopatkin, E. Adamov, 2000 .

Tokamak based hybrid systems for fuel production and recovery from spent nuclear fuel

I. B. Lukasevich, G. G. Gladush, A. Lopatkin, 2011 .

The concept of the volumetric neutron source on the basis of the JUST-T tokamak for minor actinides transmutation

G. G. Gladush, R. Khayrutdinov, V. Dokuka, 2003 .

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

G. G. Gladush, A. Lopatkin, S. Mirnov, 2020, Physics of Atomic Nuclei.