nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
1 |
Applying Machine Learning and Neural Networks to Approximate Libraries of Constants in a Few-Group Library of Neutronic Constants to Simulate RBMK-1000
|
Ivanov, I. E. |
|
|
85 |
8 |
p. 1400-1410 |
artikel |
2 |
Applying the UNK Complex to Calculate Elementary Cells Featuring Heterogeneous Vertical Fuel Distribution
|
Blandinskiy, V. Yu. |
|
|
85 |
8 |
p. 1439-1443 |
artikel |
3 |
Benchmark Model of Medium-Sized Metal Fuel Fast Reactor MET-1000_T for Simulating Movement of Control Rods: Calculations Performed by the ShIPR
|
Zizin, M. N. |
|
|
85 |
8 |
p. 1286-1293 |
artikel |
4 |
Challenges and Prospects in Applying Engineering Few-Group RBMK-1000 Reactor Calculations
|
Grushin, N. A. |
|
|
85 |
8 |
p. 1418-1430 |
artikel |
5 |
Computational Analysis of Critical Experiments for Uranium-Water Lattices of VVER Type with a Relatively Highly Enriched Fuel and Erbium Oxide Absorbers
|
Alexeev, N. I. |
|
|
85 |
8 |
p. 1355-1358 |
artikel |
6 |
Critical Experiments for Investigation of VVER Type Uranium-Water Lattices with Relatively Highly Enriched Fuel and Erbium Oxide Absorbers
|
Tsyganov, S. V. |
|
|
85 |
8 |
p. 1359-1364 |
artikel |
7 |
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”
|
Nikolaev, A. A. |
|
|
85 |
8 |
p. 1304-1313 |
artikel |
8 |
Development of Reduced 3D Models for Neutronic Calculations of the ASTRA Critical Facility
|
Nevinitsa, V. A. |
|
|
85 |
8 |
p. 1383-1390 |
artikel |
9 |
Effective Delayed Neutron Fraction in a Molten Salt Reactor with Circulating Fuel
|
Kupriyanov, K. S. |
|
|
85 |
8 |
p. 1391-1399 |
artikel |
10 |
Effect of a Hybrid Fusion Plant Operating in a Fission and Fusion Reactor System on the Fuel Cycle
|
Andrianova, E. A. |
|
|
85 |
8 |
p. 1342-1349 |
artikel |
11 |
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
|
Al-Shamayleh, A. I. |
|
|
85 |
8 |
p. 1279-1285 |
artikel |
12 |
Evaluation of the Water Radiolysis in the Serpentinite Concrete of the VVER-1200 Reactor Shielding
|
Zaritskiy, S. M. |
|
|
85 |
8 |
p. 1411-1417 |
artikel |
13 |
Experimental and Calculation Method for the Determination of the Effective Fraction of Delayed Neutrons in Fast Multiplying Systems
|
Besov, S. S. |
|
|
85 |
8 |
p. 1444-1448 |
artikel |
14 |
Fundamental and Applied Investigations of Thermal Hydraulics for Fast Reactors with Liquid-Metal Coolants
|
Sorokin, A. P. |
|
|
85 |
8 |
p. 1365-1379 |
artikel |
15 |
Influence of Certain Metallurgical Factors on the Lifetime of Weld Joints of Metal of VVER-1000 and VVER-1200 Reactor Vessels
|
Chernobaeva, A. A. |
|
|
85 |
8 |
p. 1323-1334 |
artikel |
16 |
Issue of the Dynamics of the Pulsed Fast Reactor NEPTUN: Comparison of the Calculation Models
|
Rzyanin, M. V. |
|
|
85 |
8 |
p. 1299-1303 |
artikel |
17 |
Light Water Reactors with Thorium–Uranium Heterogeneous Fuel in a Nuclear Energy System
|
Blandinskiy, V. Yu. |
|
|
85 |
8 |
p. 1335-1341 |
artikel |
18 |
Local Disturbance of the Water-Chemical Regime as a Cause of Increased Oxidation of Cladding of VVER-1000 Fuel Elements
|
Ivanov, A. S. |
|
|
85 |
8 |
p. 1314-1322 |
artikel |
19 |
Method for Determining the Time to Attaining the Minimum Controlled Power Level for VVER
|
Al-Shamayleh, A. I. |
|
|
85 |
8 |
p. 1350-1354 |
artikel |
20 |
Monochromatic Neutron Flux at Experimental Facilities of the IR-8 Reactor
|
Strepetov, A. N. |
|
|
85 |
8 |
p. 1294-1298 |
artikel |
21 |
Neutrino Control of Reactors for the Implementation of the IAEA Safeguards Regarding Floating Nuclear Power Units
|
Velikhov, E. P. |
|
|
85 |
8 |
p. 1380-1382 |
artikel |
22 |
Simulation of Recoil Proton Spectrum in a Detector of Proton Telescope Type in Registering DT Neutrons
|
Gaganov, V. V. |
|
|
85 |
8 |
p. 1431-1438 |
artikel |