| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Advanced methods for laser dismantling of spent fuel assemblies and fuel rods in the primary operations of the robotic production in a closed nuclear fuel cycle
|
Zherebtsov, A. A.
|
|
|
136 |
1-2 |
p. 62-67
|
artikel
|
| 2 |
A method for design a linear heat rate ramp limit curve for thermal reactor fuel rods
|
Krupkin, A. V.
|
|
|
136 |
1-2 |
p. 50-56
|
artikel
|
| 3 |
Application of laser technologies for dismantling the pipelines of MIR loop channels
|
Romanov, R. E.
|
|
|
136 |
1-2 |
p. 68-71
|
artikel
|
| 4 |
Concentration of 95–97Mo and production of isotopically modified molybdenum in a multi-step scheme of a square cascade
|
Palkin, V. A.
|
|
|
136 |
1-2 |
p. 84-90
|
artikel
|
| 5 |
Development of a method for measuring the effective fraction of delayed neutrons using a 240Pu spontaneous fission source
|
Grabezhnoy, V. A.
|
|
|
136 |
1-2 |
p. 96-99
|
artikel
|
| 6 |
Digital twins of nuclear energy complexes
|
Fedorovsky, A. Yu.
|
|
|
136 |
1-2 |
p. 44-49
|
artikel
|
| 7 |
Effects of control rod movement parameters on the simulation of VVER-1200 rod ejection accidents
|
Zakharov, M. A.
|
|
|
136 |
1-2 |
p. 20-26
|
artikel
|
| 8 |
Experimental study of the hydrodynamic characteristics of the coolant flow at the outlet of the fuel assembly for the RITM nuclear icebreaker reactor
|
Dmitriev, S. M.
|
|
|
136 |
1-2 |
p. 57-61
|
artikel
|
| 9 |
Feasibility study for industrial conditioning of spent ion-exchange resins by impregnation with a polymer binder
|
Ostashkina, E. E.
|
|
|
136 |
1-2 |
p. 78-83
|
artikel
|
| 10 |
New challenges for the steam-power cycle in power plants based on lead-cooled reactors
|
Kondurov, E. P.
|
|
|
136 |
1-2 |
p. 32-38
|
artikel
|
| 11 |
On the 60th anniversary of the first aperiodic pulsed nuclear reactor in Russia
|
Andreev, S. A.
|
|
|
136 |
1-2 |
p. 13-19
|
artikel
|
| 12 |
Simulation of the removal of radioactive aerosols from the atmosphere of NPP containment by spray system droplets using the MAVR-TA code
|
Savekin, S. S.
|
|
|
136 |
1-2 |
p. 27-31
|
artikel
|
| 13 |
Sorption of Cs, Np, and Pu by the rocks of the Yeniseisky site depending on the temperature and ionic strength of Mg-K-phosphate leaching solutions
|
Rodionova, A. A.
|
|
|
136 |
1-2 |
p. 72-77
|
artikel
|
| 14 |
Surface distribution of tritium in the first wall of a fusion reactor according to the data of neutron measurements
|
Vovchenko, E. D.
|
|
|
136 |
1-2 |
p. 91-95
|
artikel
|
| 15 |
Technical and economic aspects of a nuclear power engineering plant for hydrogen production
|
Fateev, S. A.
|
|
|
136 |
1-2 |
p. 1-12
|
artikel
|
| 16 |
TERMIT technology for developing simulation systems of small nuclear power facilities
|
Lialiuev, D. V.
|
|
|
136 |
1-2 |
p. 39-43
|
artikel
|
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