Works matching IS 10634258 AND DT 2024 AND VI 137 AND IP 1
Results: 16
Regulatory aspects and practice of radioactive waste management in the Republic of Kazakhstan.
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- Atomic Energy, 2024, v. 137, n. 1, p. 121, doi. 10.1007/s10512-025-01185-0
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Innovative technologies for immobilizing the sodium primary coolant of fast neutron reactors and processing liquid radioactive waste generated during reactor operation.
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- Atomic Energy, 2024, v. 137, n. 1, p. 129, doi. 10.1007/s10512-025-01186-z
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Calculation and experimental studies for substantiating the design of BREST-OD-300 reactor sampler.
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- Atomic Energy, 2024, v. 137, n. 1, p. 110, doi. 10.1007/s10512-025-01184-1
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Carbon oxides in fuel particles with uranium dioxide kernels.
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- Atomic Energy, 2024, v. 137, n. 1, p. 102, doi. 10.1007/s10512-025-01183-2
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Calculation and experimental substantiation of thermal-hydraulic characteristics for the emergency cooldown system of BN-800 reactor.
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- Atomic Energy, 2024, v. 137, n. 1, p. 94, doi. 10.1007/s10512-025-01182-3
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Combined diagnostics of the technical state of mobile reflector in IBR-2 research reactor.
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- Atomic Energy, 2024, v. 137, n. 1, p. 87, doi. 10.1007/s10512-025-01181-4
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Distribution of the effective dose of ionizing radiation in the central hall of the IGR reactor after startups.
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- Atomic Energy, 2024, v. 137, n. 1, p. 31, doi. 10.1007/s10512-025-01174-3
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Fire protection system for sodium equipment rooms of BN reactors: operating experience and development trends.
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- Atomic Energy, 2024, v. 137, n. 1, p. 78, doi. 10.1007/s10512-025-01180-5
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Neutron codes for calculating advanced reactor plants with a liquid metal coolant.
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- Atomic Energy, 2024, v. 137, n. 1, p. 62, doi. 10.1007/s10512-025-01178-z
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Local system for purifying process gases from volatile compounds of cesium and iodine at high-temperature stages of spent nuclear fuel reprocessing.
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- Atomic Energy, 2024, v. 137, n. 1, p. 55, doi. 10.1007/s10512-025-01177-0
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Tritium distribution between the primary circuit and associated systems of a VVER NPP power unit.
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- Atomic Energy, 2024, v. 137, n. 1, p. 47, doi. 10.1007/s10512-025-01176-1
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Experimental determination of the element release from aqueous media of spent nuclear fuel reprocessing into the gas phase under violated equipment integrity.
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- Atomic Energy, 2024, v. 137, n. 1, p. 38, doi. 10.1007/s10512-025-01175-2
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Validation of the steam generator model in the RASNAR-GAZ software for calculating the dynamics of a gas-cooled reactor plant.
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- Atomic Energy, 2024, v. 137, n. 1, p. 71, doi. 10.1007/s10512-025-01179-y
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Optimization of spent nuclear fuel reprocessing for reducing radioactive waste.
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- Atomic Energy, 2024, v. 137, n. 1, p. 24, doi. 10.1007/s10512-025-01173-4
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Nuclear power in accelerated economic growth scenarios.
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- Atomic Energy, 2024, v. 137, n. 1, p. 12, doi. 10.1007/s10512-025-01172-5
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Critical factors of an integrated approach to the economics of small modular reactors.
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- Atomic Energy, 2024, v. 137, n. 1, p. 1, doi. 10.1007/s10512-025-01171-6
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