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
Works by Mitenkova, E. F.
Results: 10
1
2
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
3
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
4
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
5
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
6
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
7
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
8
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
9
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
10
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
- By:
- Publication type:
- Article