Works matching DE "FAST reactors"
Results: 875
SOME CONSIDERATIONS ON THE CURRENT OPTIONS TO IMPLEMENT SMALL MODULAR REACTORS IN ROMANIA, CONSIDERING THE CONTEXT OF ENERGY MARKET AND CLIMATE POLICIES.
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- EMERG: Energy. Environment. Efficiency. Resources. Globalization, 2023, v. 9, n. 1, p. 46
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ELEMENTS FOR ALFRED PRE-OPERATIONAL MONITORING PROGRAM OF ENVIRONMENTAL RADIOACTIVITY.
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- EMERG: Energy. Environment. Efficiency. Resources. Globalization, 2022, v. 8, n. 1, p. 116
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THE DEVELOPMENT OF THE RESEARCH INFRASTRUCTURE IN SUPPORT OF ALFRED DEMONSTRATOR IMPLEMENTATION IN ROMANIA.
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- EMERG: Energy. Environment. Efficiency. Resources. Globalization, 2021, n. 1, p. 123
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CHEMICAL CLEANING OF SOLIDIFIED LEAD FROM 316 AUSTENITIC STEEL A STRUCTURE CANDIDATE MATERIAL FOR LEAD-COOLED FAST REACTORS.
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- EMERG: Energy. Environment. Efficiency. Resources. Globalization, 2019, n. 12, p. 64
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Evaluation of the relationship between shear wave elastography measurements with laboratory and Doppler US parameters in patients with adult Hashimoto's thyroiditis.
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- Turkish Journal of Medical Sciences, 2021, v. 51, n. 2, p. 778, doi. 10.3906/sag-2008-210
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Measurement of Void Fraction Distribution in a Sphere-Packed Bed Using X-Ray Imaging.
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- Japanese Journal of Multiphase Flow, 2023, v. 37, n. 1, p. 79
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自由界面渦による気相巻き込み現象の定量評価.
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- Japanese Journal of Multiphase Flow, 2022, v. 36, n. 1, p. 63
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バスタブ渦による気泡巻込み量のモデル化.
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- Japanese Journal of Multiphase Flow, 2020, v. 34, n. 1, p. 118
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Preparation of sodium alginate encapsulated anionic polyacrylamide microcapsules with delayed thickening performance.
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- Journal of Macromolecular Science: Pure & Applied Chemistry, 2024, v. 61, n. 3, p. 175, doi. 10.1080/10601325.2024.2311255
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Investigation on Neutronic Parameters of the KLT-40S Reactor Core with U<sub>3</sub>Si<sub>2</sub>-FeCrAl using SCALE Code.
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- Journal of Engineering & Technological Sciences, 2023, v. 55, n. 1, p. 22, doi. 10.5614/j.eng.technol.sci.2023.55.1.3
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Measurement of spectrum-averaged cross sections of the (n,p) and (n,n′) reactions on strontium by fast neutrons of a TRIGA reactor: comparison with integrated data from excitation functions of various data libraries.
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- Radiochimica Acta, 2023, v. 111, n. 9, p. 665, doi. 10.1515/ract-2023-0155
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Comparison of the performance of solvent wash reagents used for the primary cleanup of degraded PUREX solvent.
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- Radiochimica Acta, 2023, v. 111, n. 1, p. 53, doi. 10.1515/ract-2022-0079
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Temperature Evolution and Heating Rates of Biomass undergoing Ablative Pyrolysis.
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- Engineering, Technology & Applied Science Research, 2023, v. 13, n. 2, p. 10301, doi. 10.48084/etasr.5621
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Photocatalytic Oxygenation of Heterostilbenes—Batch versus Microflow Reactor.
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- Catalysts (2073-4344), 2021, v. 11, n. 3, p. 395, doi. 10.3390/catal11030395
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Heterogeneous Photocatalysis Scalability for Environmental Remediation: Opportunities and Challenges.
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- Catalysts (2073-4344), 2020, v. 10, n. 10, p. 1109, doi. 10.3390/catal10101109
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Arsenic metabolism in technical biogas plants: possible consequences for resident microbiota and downstream units.
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- AMB Express, 2019, v. 9, n. 1, p. N.PAG, doi. 10.1186/s13568-019-0902-6
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Preparation of U–Zr–Mn, a Surrogate Alloy for Recycling Fast Reactor Fuel.
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- Advances in Materials Science & Engineering, 2015, v. 2015, p. 1, doi. 10.1155/2015/131704
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Anammox Sludge Preservation Strategies for Short-Term Reactivation.
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- Water, Air & Soil Pollution, 2023, v. 234, n. 4, p. 1, doi. 10.1007/s11270-023-06287-8
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Effects of Different Polymeric Materials on the Bacterial Attachment and Biofilm Formation in Anoxic Fixed-Bed Biofilm Reactors.
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- Water, Air & Soil Pollution, 2023, v. 234, n. 3, p. 1, doi. 10.1007/s11270-023-06174-2
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3D-printed reactor core improves efficiency of solar-fuel production.
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- Chemical Engineering, 2023, v. 130, n. 12, p. 8
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- Article
9Cr–1W steel strengthened by AlN and BN dispersion.
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- Journal of Materials Science, 2022, v. 57, n. 26, p. 12572, doi. 10.1007/s10853-022-07395-2
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The ENBIS‐21 quality and reliability engineering international special issue.
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- Quality & Reliability Engineering International, 2023, v. 39, n. 2, p. 479, doi. 10.1002/qre.3266
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Second‐level global sensitivity analysis of numerical simulators with application to an accident scenario in a sodium‐cooled fast reactor.
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- Quality & Reliability Engineering International, 2023, v. 39, n. 2, p. 500, doi. 10.1002/qre.3157
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Advanced Characterization of Metallic Fuels by Atom Probe Tomography.
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- Microscopy & Microanalysis, 2024, v. 30, p. 1, doi. 10.1093/mam/ozae044.048
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Mass Transfer of Corrosion Products in the Nonisothermal Sodium Loop of a Fast Reactor.
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- Journal of Engineering Physics & Thermophysics, 2014, v. 87, n. 6, p. 1532, doi. 10.1007/s10891-014-1159-1
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Experimental investigations on melt coolability with simulated decay heat—The influence of delay time in flooding.
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- Heat Transfer, 2022, v. 51, n. 1, p. 257, doi. 10.1002/htj.22306
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Numerical study of turbulent heat transfer of annular fuel assembly in a sodium-cooled fast reactor by a SST k-ω-k<sub>θ</sub>-ε<sub>θ</sub> model.
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- Journal of Nuclear Science & Technology, 2024, v. 61, n. 9, p. 1202, doi. 10.1080/00223131.2024.2310563
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Thinning behavior of solid boron carbide immersed in molten stainless steel for core disruptive accident of sodium-cooled fast reactor.
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- Journal of Nuclear Science & Technology, 2024, v. 61, n. 7, p. 911, doi. 10.1080/00223131.2023.2287109
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The Behaviour of Materials in Fast Reactors.
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- Contemporary Physics, 1977, v. 18, n. 6, p. 571, doi. 10.1080/00107517708231510
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N-type fast inactivation of a eukaryotic voltage-gated sodium channel.
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- Nature Communications, 2022, v. 13, n. 1, p. 1, doi. 10.1038/s41467-022-30400-w
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Nuclear power in Japan.
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- Bulletin of the Atomic Scientists, 1983, v. 39, n. 5, p. 33, doi. 10.1080/00963402.1983.11458991
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Breeders interbreeding.
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- Bulletin of the Atomic Scientists, 1980, v. 36, n. 9, p. 5
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Geneva appeal.
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- Bulletin of the Atomic Scientists, 1979, v. 35, n. 6, p. 12
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Nuclear safeguards: A congressional perspective.
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- Bulletin of the Atomic Scientists, 1978, v. 34, n. 3, p. 27, doi. 10.1080/00963402.1978.11458477
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Nuclear power.
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- Bulletin of the Atomic Scientists, 1978, v. 34, n. 3, p. 21, doi. 10.1080/00963402.1978.11458476
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Designing of Hollow Core Grapefruit Fiber Using Cyclo Olefin Polymer for the Detection of Fuel Adulteration in Terahertz Region.
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- Polymers (20734360), 2023, v. 15, n. 1, p. 151, doi. 10.3390/polym15010151
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Design of perforated plate for uniform flow distribution in heat-exchanger unit of SFR steam generator.
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- Journal of Mechanical Science & Technology, 2021, v. 35, n. 8, p. 3469, doi. 10.1007/s12206-021-0719-5
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High temperature design and damage evaluation of a helical type sodium-to-air heat exchanger in a sodium-cooled fast reactor.
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- Journal of Mechanical Science & Technology, 2013, v. 27, n. 9, p. 2729, doi. 10.1007/s12206-013-0718-2
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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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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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Fast breeders.
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- International Power Generation, 1998, v. 21, n. 4, p. 4
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- Article
DEFORMED CORE REACTIVITY EVALUATION WITH MESH PROJECTION-BASED METHOD.
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- Nuclear Technology, 2015, v. 192, n. 1, p. 11, doi. 10.13182/NT14-123
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DESIGNING FOR INHERENT CONTROL IN LIQUID-METAL ADVANCED SMALL MODULAR REACTORS.
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- Nuclear Technology, 2015, v. 191, n. 3, p. 254, doi. 10.13182/NT14-99
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PARAMETRIC STUDY OF SLOSHING EFFECTS IN THE PRIMARY SYSTEM OF AN ISOLATED LEAD-COOLED FAST REACTOR.
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- Nuclear Technology, 2015, v. 190, n. 1, p. 1, doi. 10.13182/NT14-8
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TAGGING-GAS FAILED FUEL DETECTION AND LOCATION SYSTEM FOR SODIUM-COOLED REACTORS.
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- Nuclear Technology, 2015, v. 189, n. 2, p. 143, doi. 10.13182/NT13-161
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SELECTOR-VALVE FAILED FUEL DETECTION AND LOCATION SYSTEM FOR JAPAN SODIUM-COOLED FAST REACTOR.
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- Nuclear Technology, 2015, v. 189, n. 2, p. 111, doi. 10.13182/NT13-156
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DESIGN STUDY ON A FAST REACTOR METAL FUEL ATTAINING VERY HIGH BURNUP.
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- Nuclear Technology, 2014, v. 187, n. 2, p. 198, doi. 10.13182/NT13-105
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URANIUM STARTUP FAST REACTORS WITH METAL FUEL USING ONCE-THROUGH FUEL CYCLE.
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- Nuclear Technology, 2014, v. 186, n. 3, p. 378, doi. 10.13182/NT13-21
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DESIGN STUDIES OF A LOW SODIUM VOID REACTIVITY CORE ABLE TO ACCOMMODATE DEGRADED TRU FUEL.
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- Nuclear Technology, 2014, v. 185, n. 3, p. 270, doi. 10.13182/NT13-38
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AN ASSESSMENT OF COREWIDE COHERENCY EFFECTS IN THE MULTICHANNEL MODELING OF THE INITIATING PHASE OF A SEVERE ACCIDENT IN A SODIUM FAST REACTOR.
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- Nuclear Technology, 2014, v. 185, n. 1, p. 21, doi. 10.13182/NT12-123
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