Works matching IS 10634258 AND DT 2020 AND VI 127 AND IP 4
Results: 11
Application of Dynamic Cross-Flow Filtration for Solving the Technological Problems of Project Breakthrough.
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- Atomic Energy, 2020, v. 127, n. 4, p. 228, doi. 10.1007/s10512-020-00615-5
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Investigation of Aerosol-Deposition Induced Changes in Heat-Exchanger Material Properties During a Severe Accident at NPP.
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- Atomic Energy, 2020, v. 127, n. 4, p. 223, doi. 10.1007/s10512-020-00614-6
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Cabaret-Sc1 Code Validation in Experiments on Hydrogen Explosion Safety at NPP.
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- Atomic Energy, 2020, v. 127, n. 4, p. 216, doi. 10.1007/s10512-020-00613-7
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Radiation Monitoring During Decommissioning of the Research Campus B at Vniinm.
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- Atomic Energy, 2020, v. 127, n. 4, p. 259, doi. 10.1007/s10512-020-00620-8
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Updated State Primary Special Standard of Units of Neutron Flux Density and Neutron Fluence for Nuclear-Physics Facilities.
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- Atomic Energy, 2020, v. 127, n. 4, p. 237, doi. 10.1007/s10512-020-00616-4
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Perturbation Theory in the Method of Characteristics.
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- Atomic Energy, 2020, v. 127, n. 4, p. 255, doi. 10.1007/s10512-020-00619-1
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Population Dose Loads in Primorskii Krai from the Nuclear Accident on a Submarine in Bukhta Chazhma.
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- Atomic Energy, 2020, v. 127, n. 4, p. 244, doi. 10.1007/s10512-020-00617-3
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Modeling of Iter Equatorial Neutron Diagnostics Equipment.
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- Atomic Energy, 2020, v. 127, n. 4, p. 251, doi. 10.1007/s10512-020-00618-2
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Effect of Oxygen Content on Heat Transfer in Steam-Generating Tubes in Transverse Flow of Heavy Liquid-Metal Coolant.
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- Atomic Energy, 2020, v. 127, n. 4, p. 207, doi. 10.1007/s10512-020-00612-8
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Modeling of the Wear of Tube–Spacer Comb Interfacing in the Steam Generator of a Lead-Cooled Reactor.
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- Atomic Energy, 2020, v. 127, n. 4, p. 202, doi. 10.1007/s10512-020-00611-9
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Simulation of a Transient Process in VVER-1200 by Means of the Athlet/BIPR-VVER Coupled Neutronics and Thermohydraulic Code.
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- Atomic Energy, 2020, v. 127, n. 4, p. 197, doi. 10.1007/s10512-020-00610-w
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- Article