Evaluation of the Radiological Consequences of Beyond Design Basis Accident for IRT MEPhI.
- Published in:
- Atomic Energy, 2017, v. 123, n. 2, p. 81, doi. 10.1007/s10512-017-0305-1
- By:
- Publication type:
- Article
Works matching IS 10634258 AND DT 2017 AND VI 123 AND IP 2
Results: 12
1
2
CONV-3D Code Application for CFD-Modeling of Lead-Bismuth Coolant.
- Published in:
- Atomic Energy, 2017, v. 123, n. 2, p. 87, doi. 10.1007/s10512-017-0306-0
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- Publication type:
- Article
3
Operational Efficiency Evaluation of a Setup for Removing Stresses in the Steam Header of PGV-1000 Steam Generator.
- Published in:
- Atomic Energy, 2017, v. 123, n. 2, p. 93, doi. 10.1007/s10512-017-0307-z
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- Publication type:
- Article
4
Nuclear Fuel Based on Uranium-Zirconium Carbonitride.
- Published in:
- Atomic Energy, 2017, v. 123, n. 2, p. 96, doi. 10.1007/s10512-017-0308-y
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- Publication type:
- Article
5
Radwaste Self-Disposal in Geological Formations by Direct γ-Ray Heating of Rock.
- Published in:
- Atomic Energy, 2017, v. 123, n. 2, p. 105, doi. 10.1007/s10512-017-0309-x
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- Publication type:
- Article
6
Choice of Fine Packing for Rectification of Uranium Hexafluoride.
- Published in:
- Atomic Energy, 2017, v. 123, n. 2, p. 111, doi. 10.1007/s10512-017-0310-4
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- Publication type:
- Article
7
Monitoring the Presence and Location of Metallic Components Inside a Fuel Element.
- Published in:
- Atomic Energy, 2017, v. 123, n. 2, p. 117, doi. 10.1007/s10512-017-0311-3
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- Publication type:
- Article
8
Analysis of the Human Biohazard of Long-Lived Fission Products and Actinides for BREST-OD-300 Spent Fuel.
- Published in:
- Atomic Energy, 2017, v. 123, n. 2, p. 122, doi. 10.1007/s10512-017-0312-2
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- Publication type:
- Article
9
Modeling of Fission Product Transport in VVER Loop.
- Published in:
- Atomic Energy, 2017, v. 123, n. 2, p. 127, doi. 10.1007/s10512-017-0313-1
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- Publication type:
- Article
10
Evaluation of Radioactive Aerosol Precipitation on the Inner Surfaces of Steam-Water Lines in Beyond Design Basis Accidents at NPP with RBMK.
- Published in:
- Atomic Energy, 2017, v. 123, n. 2, p. 135, doi. 10.1007/s10512-017-0314-0
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- Publication type:
- Article
11
Determination of the Most Likely Wear Zones of Pipe Bends in the Pulsed Pneumatic Conveyor at the RT-1 Plant.
- Published in:
- Atomic Energy, 2017, v. 123, n. 2, p. 140, doi. 10.1007/s10512-017-0315-z
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- Publication type:
- Article
12
Theoretical Prerequisites for PIK Reactor Subcriticality Control Aided by Spectral Noise Analysis.
- Published in:
- Atomic Energy, 2017, v. 123, n. 2, p. 73, doi. 10.1007/s10512-017-0304-2
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- Publication type:
- Article