Vol. 85, No. 8, 2022
Estimation of the Pure Condensate Flow Rate in the Starting Range in the Startup to the Minimum Controlled Power Level after the Activation of Emergency Protection
p. 1279 abstract
Benchmark Model of Medium-Sized Metal Fuel Fast Reactor MET-1000_T for Simulating Movement of Control Rods: Calculations Performed by the ShIPR
p. 1286 abstract
Monochromatic Neutron Flux at Experimental Facilities of the IR-8 Reactor
p. 1294 abstract
Issue of the Dynamics of the Pulsed Fast Reactor NEPTUN: Comparison of the Calculation Models
p. 1299 abstract
Development and Testing of Interpolation Procedure Conserving the Order of Accuracy of the Finite Element LD Scheme When Adjacent Tetrahedrons are Joined not “Node-to-Node”
p. 1304 abstract
Local Disturbance of the Water-Chemical Regime as a Cause of Increased Oxidation of Cladding of VVER-1000 Fuel Elements
p. 1314 abstract
Influence of Certain Metallurgical Factors on the Lifetime of Weld Joints of Metal of VVER-1000 and VVER-1200 Reactor Vessels
p. 1323 abstract
Light Water Reactors with Thorium–Uranium Heterogeneous Fuel in a Nuclear Energy System
p. 1335 abstract
Effect of a Hybrid Fusion Plant Operating in a Fission and Fusion Reactor System on the Fuel Cycle
p. 1342 abstract
Method for Determining the Time to Attaining the Minimum Controlled Power Level for VVER
p. 1350 abstract
Computational Analysis of Critical Experiments for Uranium-Water Lattices of VVER Type with a Relatively Highly Enriched Fuel and Erbium Oxide Absorbers
p. 1355 abstract
Critical Experiments for Investigation of VVER Type Uranium-Water Lattices with Relatively Highly Enriched Fuel and Erbium Oxide Absorbers
p. 1359 abstract
Fundamental and Applied Investigations of Thermal Hydraulics for Fast Reactors with Liquid-Metal Coolants
p. 1365 abstract
Neutrino Control of Reactors for the Implementation of the IAEA Safeguards Regarding Floating Nuclear Power Units
p. 1380 abstract
Development of Reduced 3D Models for Neutronic Calculations of the ASTRA Critical Facility
p. 1383 abstract
Effective Delayed Neutron Fraction in a Molten Salt Reactor with Circulating Fuel
p. 1391 abstract
Applying Machine Learning and Neural Networks to Approximate Libraries of Constants in a Few-Group Library of Neutronic Constants to Simulate RBMK-1000
p. 1400 abstract
Evaluation of the Water Radiolysis in the Serpentinite Concrete of the VVER-1200 Reactor Shielding
p. 1411 abstract
Challenges and Prospects in Applying Engineering Few-Group RBMK-1000 Reactor Calculations
p. 1418 abstract
Simulation of Recoil Proton Spectrum in a Detector of Proton Telescope Type in Registering DT Neutrons
p. 1431 abstract
Applying the UNK Complex to Calculate Elementary Cells Featuring Heterogeneous Vertical Fuel Distribution
p. 1439 abstract
Experimental and Calculation Method for the Determination of the Effective Fraction of Delayed Neutrons in Fast Multiplying Systems
p. 1444 abstract