Calculation of a squared-off cascade for simultaneous concentration of intermediate components.
- Published in:
- Atomic Energy, 2025, v. 137, n. 3, p. 250, doi. 10.1007/s10512-025-01201-3
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- Publication type:
- Article
Works matching IS 10634258 AND DT 2025 AND VI 137 AND IP 3
Results: 15
1
2
Testing of the CABARET-COMBUSTION CFD code using data from experiments on accelerated combustion of hydrogen-air mixtures in a Big Mock-up Tube facility.
- Published in:
- Atomic Energy, 2025, v. 137, n. 3, p. 241, doi. 10.1007/s10512-025-01200-4
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- Article
3
Superconducting technologies for main power transmission lines and power output systems.
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- Atomic Energy, 2025, v. 137, n. 3, p. 233, doi. 10.1007/s10512-025-01199-8
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- Article
4
Comparative tests of chemical absorbents for neutralization of fluoride gases under low pressure conditions.
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- Atomic Energy, 2025, v. 137, n. 3, p. 223, doi. 10.1007/s10512-025-01198-9
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- Publication type:
- Article
5
Assessment of external radiation doses to herbage under various distribution of radionuclides in the vertical soil profile.
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- Atomic Energy, 2025, v. 137, n. 3, p. 214, doi. 10.1007/s10512-025-01197-w
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- Publication type:
- Article
6
Analysis of criteria for transmutation as an effective method for removing hazardous radioactive waste.
- Published in:
- Atomic Energy, 2025, v. 137, n. 3, p. 206, doi. 10.1007/s10512-025-01196-x
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- Publication type:
- Article
7
Global release of tritium into the environment: NPP reactor type contribution.
- Published in:
- Atomic Energy, 2025, v. 137, n. 3, p. 198, doi. 10.1007/s10512-025-01195-y
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- Article
8
Experience of creating an in situ biogeochemical barrier in contaminated groundwater at nuclear fuel cycle facilities. part 1.
- Published in:
- Atomic Energy, 2025, v. 137, n. 3, p. 190, doi. 10.1007/s10512-025-01194-z
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- Article
9
Justification of a protective container for a Tc-99m generator.
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- Atomic Energy, 2025, v. 137, n. 3, p. 180, doi. 10.1007/s10512-025-01193-0
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- Publication type:
- Article
10
Simplified estimation of accumulated strain at ratcheting.
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- Atomic Energy, 2025, v. 137, n. 3, p. 174, doi. 10.1007/s10512-025-01192-1
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- Article
11
Effects of spent nuclear fuel on neutron and physical characteristics of a fast reactor core.
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- Atomic Energy, 2025, v. 137, n. 3, p. 167, doi. 10.1007/s10512-025-01191-2
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- Publication type:
- Article
12
Features of the coolant flow in a fuel rod bundle of the fuel assembly for the RITM-200S reactor of a modernized floating power unit.
- Published in:
- Atomic Energy, 2025, v. 137, n. 3, p. 161, doi. 10.1007/s10512-025-01190-3
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- Article
13
Online convergence forecast for axial xenon oscillations of the power density in VVER-1000 and -1200 reactors.
- Published in:
- Atomic Energy, 2025, v. 137, n. 3, p. 154, doi. 10.1007/s10512-025-01189-w
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- Publication type:
- Article
14
Thermal-hydraulic model of the heavy liquid metal coolant—steam-water mixture flow.
- Published in:
- Atomic Energy, 2025, v. 137, n. 3, p. 147, doi. 10.1007/s10512-025-01188-x
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- Publication type:
- Article
15
Analytical simulation of sustainable development scenarios for global two-component nuclear power industry. Part 1. Thermal reactor scenarios.
- Published in:
- Atomic Energy, 2025, v. 137, n. 3, p. 137, doi. 10.1007/s10512-025-01187-y
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- Publication type:
- Article