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Studying Dynamical and Hydraulic Characteristics of the Hydraulically Suspended Passive Shutdown Subassembly (HS-PSS) and Validating with a Prototypic Test Sample.
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- Energies (19961073), 2024, v. 17, n. 20, p. 5038, doi. 10.3390/en17205038
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- Article
Thermal decomposition of perlite concrete under different water vapor pressures.
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- Journal of Thermal Analysis & Calorimetry, 2022, v. 147, n. 11, p. 6309, doi. 10.1007/s10973-021-10917-w
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- Article
Influence of atmospheric CO<sub>2</sub> on the thermal decomposition of perlite concrete.
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- Journal of Thermal Analysis & Calorimetry, 2022, v. 147, n. 10, p. 5801, doi. 10.1007/s10973-021-10916-x
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- Article
Thermal behavior and kinetics of the reaction between liquid sodium and calcium hydroxide.
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- Journal of Thermal Analysis & Calorimetry, 2022, v. 147, n. 7, p. 4635, doi. 10.1007/s10973-021-10856-6
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- Article
Thermal behavior of perlite concrete used in a sodium-cooled fast reactor: Multistep reaction kinetics and melting for safety assessment.
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- Journal of Thermal Analysis & Calorimetry, 2019, v. 138, n. 2, p. 983, doi. 10.1007/s10973-019-08351-0
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- Article
Comparative study on the thermal behavior of structural concretes of sodium-cooled fast reactor: Siliceous concretes.
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- Journal of Thermal Analysis & Calorimetry, 2019, v. 137, n. 4, p. 1211, doi. 10.1007/s10973-019-08045-7
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- Article
Thermal behavior of sodium hydroxide-structural concrete composition of sodium-cooled fast reactor.
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- Journal of Thermal Analysis & Calorimetry, 2018, v. 131, n. 1, p. 301, doi. 10.1007/s10973-017-6236-1
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- Article
Thermal analysis of high-temperature fast reactions in energetic materials.
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- Journal of Thermal Analysis & Calorimetry, 2011, v. 106, n. 1, p. 39, doi. 10.1007/s10973-010-1271-1
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- Article
Get 20–2014: State Primary Standard of Unit of Activity and Unit of Volume Activity of Nuclides in Beta-Active Gases.
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- Measurement Techniques, 2020, v. 62, n. 10, p. 849, doi. 10.1007/s11018-020-01704-4
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- Article
Modeling representative Gen‐IV molten fuel reactivity effects in the ZEPHYR ZPR ‐ LFR analysis.
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- International Journal of Energy Research, 2019, v. 43, n. 2, p. 829, doi. 10.1002/er.4313
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- Article
Conceptual core design study of an innovative small transportable lead‐bismuth cooled fast reactor (SPARK) for remote power supply.
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- International Journal of Energy Research, 2018, v. 42, n. 11, p. 3672, doi. 10.1002/er.4119
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- Article
Preliminary design of a medium‐power modular lead‐cooled fast reactor with the application of optimization methods.
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- International Journal of Energy Research, 2018, v. 42, n. 11, p. 3643, doi. 10.1002/er.4112
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- Article
Sub‐channel analysis for Pb‐Bi‐cooled direct contact boiling water fast reactor.
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- International Journal of Energy Research, 2018, v. 42, n. 8, p. 2643, doi. 10.1002/er.4046
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- Article
Modeling representative Gen‐IV molten fuel reactivity effects in the ZEPHYR fast/thermal coupled ZPRs. Part I—Assembly level.
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- International Journal of Energy Research, 2018, v. 42, n. 5, p. 1950, doi. 10.1002/er.3991
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- Article
Neutronics optimization and characterization of a long-life SCO<sub>2</sub>-cooled micro modular reactor.
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- International Journal of Energy Research, 2017, v. 41, n. 7, p. 976, doi. 10.1002/er.3686
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- Article
Power flattening study of ultra-long cycle fast reactor using thorium fuel.
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- International Journal of Energy Research, 2016, v. 40, n. 12, p. 1662, doi. 10.1002/er.3552
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- Article
Coupling of an innovative small PWR and advanced sodium-cooled fast reactor for incineration of TRU from once-through PWRs.
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- International Journal of Energy Research, 2016, v. 40, n. 2, p. 216, doi. 10.1002/er.3456
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- Article
Feasibility study on ultralong-cycle operation and material performance for compact liquid metal-cooled fast reactors: a review work.
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- International Journal of Energy Research, 2015, v. 39, n. 14, p. 1859, doi. 10.1002/er.3384
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Nano-Restructuration of Carbon Materials under High Temperature Heat Treatment for Environmental Application and Energy Storage.
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- CET Journal - Chemical Engineering Transactions, 2019, v. 73, p. 91, doi. 10.3303/CET1973016
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- Article
Effect of the Inclusion of the Detailed Geometry of the Reactor Core on the Calculated Antineutrino Flux from a VVER-1000 Reactor.
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- JETP Letters, 2024, v. 119, n. 3, p. 158, doi. 10.1134/S0021364023604025
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- Article
强化型硫铁矿自养反硝化工艺深度处理城市二沉尾水研究.
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- Journal of Dalian University of Technology / Dalian Ligong Daxue Xuebao, 2023, v. 63, n. 5, p. 454, doi. 10.7511/dllgxb202305003
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Analysis of particles containing alpha-emitters in stagnant water at torus room of Fukushima Dai-ichi Nuclear Power Station's Unit 2 reactor.
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- Scientific Reports, 2022, v. 12, n. 1, p. 1, doi. 10.1038/s41598-022-11334-1
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- Article
Complementary catalysis and analysis within solid state additively manufactured metal micro flow reactors.
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- Scientific Reports, 2022, v. 12, n. 1, p. 1, doi. 10.1038/s41598-022-09044-9
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- Article
Concept of a fast breeder reactor to transmute MAs and LLFPs.
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- Scientific Reports, 2021, v. 11, n. 1, p. 1, doi. 10.1038/s41598-021-01986-w
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- Article
Assessment of Vapor Formation Rate and Phase Shift between Pressure Gradient and Liquid Velocity in Flat Mini Heat Pipes as a Function of Internal Structure.
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- Micromachines, 2023, v. 14, n. 7, p. 1468, doi. 10.3390/mi14071468
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- Article
Numerical Investigation of Special Heat Transfer Phenomenon in Wire-Wrapped Fuel Rod of SFR.
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- Micromachines, 2022, v. 13, n. 6, p. 935, doi. 10.3390/mi13060935
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- Article
Analysis of Mixing Efficiency in a Stirred Reactor Using Computational Fluid Dynamics †.
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- Symmetry (20738994), 2024, v. 16, n. 2, p. 237, doi. 10.3390/sym16020237
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- Article
A Phased Development of Breed-and-Burn Reactors for Enhanced Nuclear Energy Sustainability.
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- Sustainability (2071-1050), 2012, v. 4, n. 10, p. 2745, doi. 10.3390/su4102745
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- Article
Modular Lead-Bismuth Fast Reactors in Nuclear Power.
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- Sustainability (2071-1050), 2012, v. 4, n. 9, p. 2293, doi. 10.3390/su4092293
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- Article
Effects of Orthogonal Heat Treatment on Microstructure and Mechanical Properties of GN9 Ferritic/Martensitic Steel.
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- Chinese Journal of Mechanical Engineering, 2023, v. 36, n. 1, p. 1, doi. 10.1186/s10033-023-00984-5
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- Article
Use of Erbium as a Burnable Absorber in VVER-Type Reactors in a Closed Fuel Cycle.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 12, p. 2569, doi. 10.1134/S1063778823120049
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- Article
Selecting Burnup Algorithms in OpenMC Using the Calculated Benchmark of LEU Assembly and MOX Fuel.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 11, p. 2396, doi. 10.1134/S1063778823110431
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- Article
Use of Eutectic Na–Tl Coolant in a Modular Fast Reactor.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1928, doi. 10.1134/S1063778823080239
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- Article
Using the Am Fraction of Minor Actinides for the Production of Plutonium Suitable for Radioisotope Thermoelectric Generators.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 9, p. 1965, doi. 10.1134/S1063778823090223
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- Article
On Radiocarbon in Uranium Graphite Reactors.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1902, doi. 10.1134/S1063778823080033
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- Article
Beyond Design Basis Accident with Blackout of the RBMK. Analysis of the Possibility of Recriticality Occurrence.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1907, doi. 10.1134/S1063778823080082
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- Article
Fuel Cycle of the LiF–BeF<sub>2</sub> Molten Salt Actinide Burner Reactor.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1894, doi. 10.1134/S1063778823080276
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- Article
Evaluation of the Possibility of Using the Full Load of MOX Fuel in the VVER-600 Reactor.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1856, doi. 10.1134/S1063778823080148
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- Article
Computational Analysis of the Possible Location of Ionization Chambers in Fast Reactors.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1838, doi. 10.1134/S1063778823080288
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- Article
Study on Minor Actinide Incineration in Molten Salt Reactors with Uranium or Plutonium Loadings.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1887, doi. 10.1134/S1063778823080227
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- Article
Raw Material Effect on the Characteristics of the Fission and Fusion Reactor System.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1882, doi. 10.1134/S1063778823080173
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- Article
Analysis of Benefits and Risks of Thorium and <sup>233</sup>U Introduction in the VVER-1200 Fuel Cycle in the Fusion-Fission Reactor System.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1874, doi. 10.1134/S1063778823080215
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- Article
Peculiarities of Changes in the Isotopic Composition of Pilot Fuel Elements of a VVER-SKD Reactor under Successive Irradiation in a Fast and Thermal Neutron Spectrum.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1849, doi. 10.1134/S1063778823080185
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Fundamental and Applied Investigations of Thermal Hydraulics for Fast Reactors with Liquid-Metal Coolants.
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- Physics of Atomic Nuclei, 2022, v. 85, n. 8, p. 1365, doi. 10.1134/S1063778822080208
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- Article
Light Water Reactors with Thorium–Uranium Heterogeneous Fuel in a Nuclear Energy System.
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- Physics of Atomic Nuclei, 2022, v. 85, n. 8, p. 1335, doi. 10.1134/S1063778822080051
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On the Radioecological Consequences of the Closure of the Nuclear Fuel Cycle.
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- Physics of Atomic Nuclei, 2022, v. 85, n. 7, p. 1109, doi. 10.1134/S1063778822070080
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- Article
Acceptability of the Closed Fuel Cycle of Nuclear Power Engineering.
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- Physics of Atomic Nuclei, 2022, v. 85, n. 7, p. 1103, doi. 10.1134/S1063778822070134
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- Article
Issue of the Dynamics of the Pulsed Fast Reactor NEPTUN: Comparison of the Calculation Models.
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- Physics of Atomic Nuclei, 2022, v. 85, n. 8, p. 1299, doi. 10.1134/S1063778822080099
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- Article
Benchmark Model of Medium-Sized Metal Fuel Fast Reactor MET-1000_T for Simulating Movement of Control Rods: Calculations Performed by the ShIPR.
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- Physics of Atomic Nuclei, 2022, v. 85, n. 8, p. 1286, doi. 10.1134/S1063778822080117
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The Use of Burnable Absorbers in Vver-Type Reactors to Reduce the Fraction of the Reactivity Margin Compensated by a Liquid System During Extended Campaigns.
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- Physics of Atomic Nuclei, 2022, v. 85, n. 2, p. S80, doi. 10.1134/S1063778822140113
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- Article