nuclear fuel

Влияние библиотек оцененных ядерных данных на результаты расчёта выгорания топлива с минорными актинидами в реакторе ВВЭР

6/22/2023 2023 - #02 Fuel cycle and nuclear waste management

Karpovich G.V. Kazansky Yu.A. Bakhantsov K.A. Isanov K.A. Kushnir N.O.

Use of REMIX Spent Mixed Fuel Plutonium in the BN-1200 Reactor

3/28/2023 2023 - #01 Fuel cycle and nuclear waste management

Kovalev N.V. Prokoshin A.M. Kudinov A.S. Nevinitsa V.A.

Computational Simulation of Minor Actinide Burning in a BN-600 Reactor with Fuel without Uranium and Plutonium

9/23/2022 2022 - #03 Modelling processes at nuclear facilities

Korobeynikov V.V. Kolesov V.V. Ignatiev I.A.

Minor Actinides Transmutation in Pressurized Water Reactors. 1. Multiple Recycling of Minor Actinides on the Example of One VVER Reactor

9/23/2021 2021 - #03 Fuel cycle and nuclear waste management

Kazansky Yu.A. Karpovich G.V.

Rapid Preliminary Modeling of Floating NPP Cores

11/19/2020 2020 - #04 Physics and technology of nuclear reactors

Korolev V.I.

A new approach to spent nuclear fuel recycling for light water reactors in the frame of remix concept

3/19/2020 2020 - #01 Fuel cycle and nuclear waste management

Kovalev N.V. Zilberman B.Ya. Goletskiy N.D. SinyukhinA.B. 

Ontologies and databases on thermophysical properties of nuclear reactor materials

3/25/2019 2019 - #01 Current issues in nuclear energy

Chusov I.A. Kirillov P.L. Pronyaev V.G. Erkimbaev A.O. Zitserman V.Yu. Kobzev G.A. Fokin L.R.

A new generation information controlling system for refueling machine

10/02/2017 2017 - #03 Modelling processes at nuclear facilities

Korobkin V.V. Povarov V.P.

Specifics of initial fuel charge of the innovative power unit of AES-2006 design

10/02/2017 2017 - #03 Nuclear power plants

Prytkov A.N. Tereshchenko A.B. Golubev E.I. Boev I.A.

Development of the structured relational database for civil plutonium in Russia and its implementation

3/22/2017 2017 - #01 Fuel cycle and nuclear waste management

Pshakin G.M. Moseev P.A. Korobeynikov V.V. Moseev A. L.

Calculations and experimental investigation of the irradiation rig with a fuel heater for the BOR-60 reactor

3/28/2016 2016 - #01 Physics and technology of nuclear reactors

Varivtcev A.V. Zhemkov I.Yu. Boev A.V. Ishunina O.V. Naboyshchikov Yu.V. Poglyad N.S. Sharonova M.G.

Specifics of calculation of heat rate in oxide nuclear fuel during tests in reactor BOR-60

12/29/2014 2014 - #04 Thermal physics and thermal hydraulics

Varivtcev A.V. Zhemkov I.Yu.