Works matching IS 10634258 AND DT 2025 AND VI 136 AND IP 5
Results: 17
Forms and compounds of radioactive iodine in emissions of the JSC Karpov Institute of Physical Chemistry.
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- Atomic Energy, 2025, v. 136, n. 5, p. 332, doi. 10.1007/s10512-024-01169-6
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- Article
Simulation of accidental temperature and humidity in the pipeline rooms of the VVER NPP primary circuit.
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- Atomic Energy, 2025, v. 136, n. 5, p. 326, doi. 10.1007/s10512-024-01168-7
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Justification of the CONV-3D code for simulating natural circulation of a lead-bismuth coolant in a hydraulic circuit.
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- Atomic Energy, 2025, v. 136, n. 5, p. 338, doi. 10.1007/s10512-024-01170-z
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- Article
Leakage control of HTGR fuel using a weak irradiation technique.
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- Atomic Energy, 2025, v. 136, n. 5, p. 316, doi. 10.1007/s10512-024-01167-8
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Optimal rotor length of a gas centrifuge.
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- Atomic Energy, 2025, v. 136, n. 5, p. 311, doi. 10.1007/s10512-024-01166-9
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Time to radiological equivalence of radioactive waste and natural uranium feedstock at an increasing content of Np, Am, and Cm in long-lived radioactive waste.
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- Atomic Energy, 2025, v. 136, n. 5, p. 280, doi. 10.1007/s10512-024-01161-0
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Prospects for using lunar soil in the thermal scheme of a nuclear power plant with thermoelectric energy conversion.
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- Atomic Energy, 2025, v. 136, n. 5, p. 272, doi. 10.1007/s10512-024-01160-1
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Experimental justification of a pyrochemical technology for reprocessing of mixed uranium-plutonium nitride spent nuclear fuel.
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- Atomic Energy, 2025, v. 136, n. 5, p. 300, doi. 10.1007/s10512-024-01164-x
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- Article
Study of alkaline coolant boiling in the fuel assemblies of fast reactors in emergency modes with natural convection.
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- Atomic Energy, 2025, v. 136, n. 5, p. 259, doi. 10.1007/s10512-024-01159-8
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Concentration of <sup>72, 74</sup>Ge in the additional product of a square cascade.
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- Atomic Energy, 2025, v. 136, n. 5, p. 307, doi. 10.1007/s10512-024-01165-w
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Magnesium potassium phosphate matrix for solidification of a spent tributyl phosphate—dodecane simulant.
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- Atomic Energy, 2025, v. 136, n. 5, p. 294, doi. 10.1007/s10512-024-01163-y
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- Article
Technetium in a closed nuclear fuel cycle with transmutation.
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- Atomic Energy, 2025, v. 136, n. 5, p. 288, doi. 10.1007/s10512-024-01162-z
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Results of BOR-60 reactor tests and post-reactor studies of experimental fuel rods with mixed uranium-plutonium nitride fuel.
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- Atomic Energy, 2025, v. 136, n. 5, p. 253, doi. 10.1007/s10512-024-01158-9
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- Article
Hydrogen production at a nuclear power engineering plant with a high-temperature gas-cooled reactor (HTGR NPEP).
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- Atomic Energy, 2025, v. 136, n. 5, p. 245, doi. 10.1007/s10512-024-01157-w
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Role of the BOR-60 research reactor in the development of fast reactors.
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- Atomic Energy, 2025, v. 136, n. 5, p. 233, doi. 10.1007/s10512-024-01156-x
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- Article
Evolution of fast reactors. The role of a BN-350 reactor.
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- Atomic Energy, 2025, v. 136, n. 5, p. 222, doi. 10.1007/s10512-024-01155-y
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Fast reactors in the strategic nuclear power development scenarios of the Russian Federation.
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- Atomic Energy, 2025, v. 136, n. 5, p. 215, doi. 10.1007/s10512-024-01154-z
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- Article