Works matching DE "SODIUM cooled reactors"
Results: 54
An Advanced Sodium-Cooled Fast Reactor Core Concept Using Uranium-Free Metallic Fuels for Maximizing TRU Burning Rate.
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- Sustainability (2071-1050), 2017, v. 9, n. 12, p. 2225, doi. 10.3390/su9122225
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Break-Even Point Analysis of Sodium-Cooled Fast Reactor Capital Investment Cost Comparing the Direct Disposal Option and Pyro-Sodium-Cooled Fast Reactor Nuclear Fuel Cycle Option in Korea.
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- Sustainability (2071-1050), 2017, v. 9, n. 9, p. 1518, doi. 10.3390/su9091518
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- Article
Effects of Nuclear Energy on Sustainable Development and Energy Security: Sodium-Cooled Fast Reactor Case.
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- Sustainability (2071-1050), 2016, v. 8, n. 10, p. 979, doi. 10.3390/su8100979
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- Article
CHARACTERISTICS AND OPTIMIZATION OF SCO<sub>2</sub> BRAYTON CYCLE SYSTEM FOR HIGH POWER SODIUM-COOLED FAST REACTOR ON MARS.
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- Thermal Science, 2021, v. 25, n. 6B, p. 4659, doi. 10.2298/TSCI2106659Z
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Interaction phenomena between ceramic coatings and liquid uranium alloys.
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- Journal of Radioanalytical & Nuclear Chemistry, 2014, v. 300, n. 3, p. 1245, doi. 10.1007/s10967-014-3086-1
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Russia to build 11 new nuclear reactors.
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- TCE: The Chemical Engineer, 2016, n. 903, p. 13
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- Article
China's starts up neutron reactor.
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- TCE: The Chemical Engineer, 2011, n. 843, p. 12
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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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Kinetic study on liquid sodium-silica reaction for safety assessment of sodium-cooled fast reactor.
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- Journal of Thermal Analysis & Calorimetry, 2015, v. 121, n. 1, p. 45, doi. 10.1007/s10973-014-4387-x
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- Article
Modelling of a hydrogen permeation process from gas phase towards liquid sodium and experimental set-up for prototype testing.
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- Chemical Engineering Research & Design: Transactions of the Institution of Chemical Engineers Part A, 2020, v. 159, p. 555, doi. 10.1016/j.cherd.2020.05.012
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Modelling of a CO<sub>2</sub>-gas jet into liquid-sodium following a heat exchanger leakage scenario in Sodium Fast Reactors.
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- Chemical Engineering Research & Design: Transactions of the Institution of Chemical Engineers Part A, 2013, v. 91, n. 4, p. 641, doi. 10.1016/j.cherd.2013.02.011
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- Article
Anomaly Detection in Liquid Sodium Cold Trap Operation with Multisensory Data Fusion Using Long Short-Term Memory Autoencoder.
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- Energies (19961073), 2023, v. 16, n. 13, p. 4965, doi. 10.3390/en16134965
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Low cycle fatigue and creep-fatigue response of the 316Ti stainless steel.
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- Fracture & Structural Integrity, 2019, n. 48, p. 577, doi. 10.3221/IGF-ESIS.48.56
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- Article
Effects of Different Operating Temperatures on the Tensile Properties of the Grid Plate Hardfaced with Colmonoy in a Pool Type Sodium Fast Reactor.
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- Science & Technology of Nuclear Installations, 2017, p. 1, doi. 10.1155/2017/5926105
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- Article
Design and Development of Exhaust Valves for Internal Combustion Engines from the Perspective of Modern Thinking: Part 2 1930-90.
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- International Journal for the History of Engineering & Technology, 2014, v. 84, n. 1, p. 1, doi. 10.1179/1758120613Z.00000000030
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The Second Coming of Nuclear Power.
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- Business & Society Review (00453609), 1988, n. 64
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It's time to give up on breeder reactors.
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- Bulletin of the Atomic Scientists, 2010, v. 66, n. 3, p. 50, doi. 10.2968/066003007
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- Article
Tracer technique to estimate the efficiency of radionuclide trap material in liquid sodium.
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- Journal of Radioanalytical & Nuclear Chemistry, 2024, v. 333, n. 1, p. 175, doi. 10.1007/s10967-023-09179-7
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- Article
Studies on the uptake behavior of nickel from flowing sodium for Mn, Co and Zn.
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- Journal of Radioanalytical & Nuclear Chemistry, 2021, v. 329, n. 2, p. 591, doi. 10.1007/s10967-021-07695-y
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- Article
Validation of a methodology for thermal stratification analysis in sodium‐cooled fast reactors.
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- International Journal of Energy Research, 2018, v. 42, n. 12, p. 3803, doi. 10.1002/er.4108
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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
A comparative physics study for an innovative sodium-cooled fast reactor (iSFR).
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- International Journal of Energy Research, 2018, v. 42, n. 1, p. 151, doi. 10.1002/er.3612
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Core design options of an ultra-long-cycle sodium cooled reactor with effective use of PWR spent fuel for sustainable energy supply.
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- International Journal of Energy Research, 2017, v. 41, n. 6, p. 854, doi. 10.1002/er.3677
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Review of the finite element models for a structural integrity evaluation of the sodium-cooled fast reactor high temperature piping.
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- Journal of Mechanical Science & Technology, 2012, v. 26, n. 9, p. 2807, doi. 10.1007/s12206-012-0737-4
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- Article
Elevated temperature design evaluations for the ABTR internal structure.
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- Journal of Mechanical Science & Technology, 2012, v. 26, n. 2, p. 389, doi. 10.1007/s12206-011-1218-x
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- Article
Measurement of the Residual Stresses and Investigation of Their Effects on a Hardfaced Grid Plate due to Thermal Cycling in a Pool Type Sodium-Cooled Fast Reactor.
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- Science & Technology of Nuclear Installations, 2016, p. 1, doi. 10.1155/2016/8353256
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- Article
Properties of Neutron Noise Induced by Localized Perturbations in an SFR.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/140979
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Development of Tools, Instrumentation and Codes for Improving Periodic Examination and Repair of SFRs.
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- Science & Technology of Nuclear Installations, 2012, p. 1, doi. 10.1155/2012/718034
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- Article
Fast Reactors and Advanced Light Water Reactors for Sustainable Development.
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- Science & Technology of Nuclear Installations, 2012, p. 1, doi. 10.1155/2012/373891
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- Article
Indian fast reactor technology: Current status and future programme.
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- Sādhanā: Academy Proceedings in Engineering Sciences, 2013, v. 38, n. 5, p. 795, doi. 10.1007/s12046-013-0167-8
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基于灵敏度/不确定度方法的快中子裂变的 衰变热不确定度分析.
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- Atomic Energy Science & Technology, 2024, v. 58, n. 12, p. 2556, doi. 10.7538/yzk.2024.youxian.0322
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EBR-Ⅱ停堆余热排出试验SHRT-17分析.
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- Atomic Energy Science & Technology, 2023, v. 57, p. 98, doi. 10.7538/yzk.2023.youxian.0122
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铅铋堆蒸汽发生器传热管破裂事故下铅铋-水相互作用程序开发及验证.
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- Atomic Energy Science & Technology, 2023, v. 57, n. 7, p. 1406, doi. 10.7538/yzk.2022.youxian.0719
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- Article
一体化快堆的内增殖性能研究.
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- Atomic Energy Science & Technology, 2023, v. 57, n. 6, p. 1111, doi. 10.7538/yzk.2022.youxian.0544
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CHALLENGES FOR THE NUCLEAR INDUSTRY.
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- Nuclear Future, 2022, v. 18, n. 6, p. 13
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Generation IV Nuclear Reactors.
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- Advanced Materials & Processes, 2010, v. 168, n. 1, p. 26
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- Article
Experimental and Computational Investigation of the Emission of Radioactive Products from Irradiated Fuel of Fast Sodium-Cooled Reactor.
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- Atomic Energy, 2017, v. 122, n. 6, p. 390, doi. 10.1007/s10512-017-0284-2
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- Article
HYDRA-IBRAE/LM/V1 Thermohydraulic Code Verification Based on BN-600 Experiments.
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- Atomic Energy, 2017, v. 122, n. 5, p. 311, doi. 10.1007/s10512-017-0272-6
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- Article
Subcriticality Monitoring System for the MBIR Reactor.
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- Atomic Energy, 2016, v. 119, n. 3, p. 149, doi. 10.1007/s10512-015-0042-2
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- Article
Modeling Transport of Radioactive Products of Corrosion in Loops with Sodium Coolant.
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- Atomic Energy, 2015, v. 119, n. 1, p. 37, doi. 10.1007/s10512-015-0026-2
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- Article
High-Temperature Nuclear Energy Technology Based on Sodium-Cooled Fast Reactors for Hydrogen Production.
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- Atomic Energy, 2014, v. 116, n. 4, p. 241, doi. 10.1007/s10512-014-9849-5
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- Article
Russian Codes for Safety Analysis of Sodium-Cooled Fast Reactors.
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- Atomic Energy, 2014, v. 116, n. 4, p. 265, doi. 10.1007/s10512-014-9852-x
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- Article
Fast reactors in the energy security for the stable development of Russia.
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- Atomic Energy, 2010, v. 108, n. 4, p. 230, doi. 10.1007/s10512-010-9282-3
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- Article
Concept of an advanced power-generating unit with a BN-1200 sodium-cooled fast reactor.
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- Atomic Energy, 2010, v. 108, n. 4, p. 254, doi. 10.1007/s10512-010-9286-z
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Announcement.
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- Atomic Energy, 2010, v. 108, n. 4, p. 229, doi. 10.1007/s10512-010-9281-4
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- Article
Fuel for advanced sodium-cooled fast reactors: current status and plans.
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- Atomic Energy, 2010, v. 108, n. 4, p. 267, doi. 10.1007/s10512-010-9288-x
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Investigation of the influence of the sodium void effect of reactivity on the technical-economic performance and safety of an advanced fast reactor.
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- Atomic Energy, 2010, v. 108, n. 4, p. 289, doi. 10.1007/s10512-010-9291-2
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Operating experience and prospects for future development of sodium-cooled fast reactors.
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- Atomic Energy, 2010, v. 108, n. 4, p. 240, doi. 10.1007/s10512-010-9284-1
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30 Years of experience in operating the BN-600 sodium-cooled fast reactor.
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- Atomic Energy, 2010, v. 108, n. 4, p. 234, doi. 10.1007/s10512-010-9283-2
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- Article
Core and fuel cycle for an advanced sodium-cooled fast reactor.
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- Atomic Energy, 2010, v. 108, n. 4, p. 260, doi. 10.1007/s10512-010-9287-y
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- Article