FEATURES OF HYBRID CORE CALCULATIONS AT BFS-62-3A EXPERIMENTS.
- Published in:
- Nuclear Technology, 2013, v. 183, n. 3, p. 446, doi. 10.13182/NT13-A19432
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- Publication type:
- Article
Works by MITENKOVA, E. E.
Results: 21
1
2
End-to-end calculation of the radiation characteristics of VVER-1000 spent fuel assemblies.
- Published in:
- Physics of Atomic Nuclei, 2012, v. 75, n. 13, p. 1603, doi. 10.1134/S1063778812130054
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- Publication type:
- Article
3
Extended one-group cross-section libraries in precision nuclide composition calculations of irradiated steel.
- Published in:
- Atomic Energy, 2023, v. 134, n. 3/4, p. 195, doi. 10.1007/s10512-024-01043-5
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- Publication type:
- Article
4
One-Group Cross-Sections of High-Threshold Reactions for Precision Neutronics Calculations.
- Published in:
- Atomic Energy, 2023, v. 133, n. 4, p. 228, doi. 10.1007/s10512-023-01001-7
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- Publication type:
- Article
5
Spectral Analysis in Neutron Distribution Problems in Weakly Coupled Systems.
- Published in:
- Atomic Energy, 2022, v. 131, n. 4, p. 212, doi. 10.1007/s10512-022-00863-7
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- Publication type:
- Article
6
MZK Program for Solving Stiff Systems in Nuclide Kinetics Problems.
- Published in:
- Atomic Energy, 2021, v. 130, n. 6, p. 344, doi. 10.1007/s10512-022-00822-2
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- Publication type:
- Article
7
Effect of NJOY and Grucon Processing Codes in Nuclear Data Preparation for Steel Nuclides.
- Published in:
- Atomic Energy, 2020, v. 128, n. 3, p. 171, doi. 10.1007/s10512-020-00670-y
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- Publication type:
- Article
8
Calculation of the Neutron Distribution Function in Slabs with Extended Heterogeneous Fuel Zones.
- Published in:
- Atomic Energy, 2019, v. 126, n. 1, p. 16, doi. 10.1007/s10512-019-00507-3
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- Publication type:
- Article
9
MFPR/R-Aided Modeling of Hydrogen and Helium Production in Nuclear Fuel.
- Published in:
- Atomic Energy, 2019, v. 125, n. 6, p. 370, doi. 10.1007/s10512-019-00496-3
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- Publication type:
- Article
10
Development of a Consistent Model in High-Precision Neutronics and Thermohydraulics Calculations Using CFD Codes.
- Published in:
- Atomic Energy, 2018, v. 125, n. 2, p. 139, doi. 10.1007/s10512-018-0456-8
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- Publication type:
- Article
11
Solution of Isotopic Kinetics Problems with the Complete List of Elements in the Fission Product Yield.
- Published in:
- Atomic Energy, 2016, v. 120, n. 3, p. 214, doi. 10.1007/s10512-016-0120-0
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- Publication type:
- Article
12
The radiation characteristics of the transport packages with vitrified high-level waste.
- Published in:
- Physics of Atomic Nuclei, 2015, v. 78, n. 11, p. 1301, doi. 10.1134/S106377881511006X
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- Publication type:
- Article
13
Libraries with Expanded Representation of Fission Product Yields for Calculations of the Nuclide Composition of Fuel in a Fast Spectrum.
- Published in:
- Atomic Energy, 2015, v. 117, n. 6, p. 427, doi. 10.1007/s10512-015-9943-3
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- Publication type:
- Article
14
Distribution of the Fission Reaction rate in a Weakly Coupled System for Testing the Checkerboard Model.
- Published in:
- Atomic Energy, 2014, v. 116, n. 6, p. 421, doi. 10.1007/s10512-014-9873-5
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- Publication type:
- Article
15
MFPR Code Aided Description of Fission Products Transport and Change in the Microstructure of Heterogeneous Fuel during Irradiation.
- Published in:
- Atomic Energy, 2013, v. 114, n. 5, p. 337, doi. 10.1007/s10512-013-9721-z
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- Publication type:
- Article
16
Analysis of secondary fuel accumulation factors in different computational models.
- Published in:
- Atomic Energy, 2013, v. 114, n. 2, p. 115, doi. 10.1007/s10512-013-9680-4
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- Publication type:
- Article
17
Analysis of BN-800 fast reactor in an open fuel cycle with metallic fuel at the initial stage of the transition to a closed cycle.
- Published in:
- Atomic Energy, 2012, v. 113, n. 2, p. 87, doi. 10.1007/s10512-012-9599-1
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- Publication type:
- Article
18
Effect of fission products yield library on the calculation of the nuclide composition of the fuel in sodium-cooled fast reactors.
- Published in:
- Atomic Energy, 2011, v. 111, n. 2, p. 99, doi. 10.1007/s10512-011-9460-y
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- Publication type:
- Article
19
Particulars of neutron-physical calculations of sodium-cooled fast reactors with mixed oxide fuel.
- Published in:
- Atomic Energy, 2011, v. 109, n. 5, p. 309, doi. 10.1007/s10512-011-9361-0
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- Publication type:
- Article
20
Verification of the BONUS module integrated into the SOCRAT code.
- Published in:
- Atomic Energy, 2009, v. 106, n. 5, p. 316, doi. 10.1007/s10512-009-9170-x
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- Publication type:
- Article
21
Computational and experimental investigations of the neutron-physical characteristics of the GT-MHR core.
- Published in:
- Atomic Energy, 2007, v. 102, n. 1, p. 75, doi. 10.1007/s10512-007-0011-5
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- Publication type:
- Article