Works matching DE "NUCLEAR fuel elements"
Results: 277
Batch sequential design of optimal experiments for improved predictive maturity in physics-based modeling.
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- Structural & Multidisciplinary Optimization, 2013, v. 48, n. 3, p. 549, doi. 10.1007/s00158-013-0915-8
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R-Functions in mathematical simulation of physical fields in lattices of fuel elements.
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- Journal of Mathematical Sciences, 2012, v. 185, n. 6, p. 815, doi. 10.1007/s10958-012-0964-3
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Fatigue Testing of Materials under Extremal Conditions by Acoustic Method.
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- Technical Physics Letters, 2004, v. 30, n. 3, p. 180, doi. 10.1134/1.1707160
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КОМПЬЮТЕРНО-ИНТЕГРИРОВАННАЯ СИСТЕМА УПРАВЛЕНИЯ ПЕРЕСТАНОВКАМИ ТВС В АКЗ ВВЭР-1000 С УЧЕТОМ ПОВРЕЖДЕННОСТИ ОБОЛОЧЕК ТВЭЛОВ
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- Automation of Technological & Business Processes / Avtomatizaciâ Tehnologiceskih i Biznes-Processov, 2016, v. 8, n. 1, p. 83, doi. 10.21691/atbp.v8i1.16
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The influence of piperazine diamine templates on the synthesis, structures and properties of uranyl oxalate complex.
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- Radiochimica Acta, 2021, v. 109, n. 9, p. 661, doi. 10.1515/ract-2021-1058
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Dosimetry and methodology of gamma irradiation for degradation studies on solvent extraction systems.
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- Radiochimica Acta, 2021, v. 109, n. 1, p. 61, doi. 10.1515/ract-2020-0040
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Development, characterization and dissolution behavior of calciumaluminoborate glass wasteforms to immobilize rare-earth oxides.
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- Scientific Reports, 2018, p. 1, doi. 10.1038/s41598-018-23665-z
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Laser transmutation of iodine-129.
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- Applied Physics B: Lasers & Optics, 2003, v. 77, n. 4, p. 387, doi. 10.1007/s00340-003-1306-4
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UMo/Al nuclear fuel plate behavior under thermal treatment (425-550°C).
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- Powder Diffraction, 2013, v. 28, n. S2, p. S371, doi. 10.1017/S0885715613000894
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Why natural monazite never becomes amorphous: Experimental evidence for alpha self-healing.
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- American Mineralogist, 2018, v. 103, n. 5, p. 824, doi. 10.2138/am-2018-6447
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Bentonite evolution at elevated pressures and temperatures: An experimental study for generic nuclear repository designs.
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- American Mineralogist, 2014, v. 99, n. 8/9, p. 1662, doi. 10.2138/am.2014.4673
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Ultrasonic method removes deposits from nuclear fuel.
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- Advanced Materials & Processes, 2005, v. 163, n. 12, p. 19
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The development and application of a novel camera system for visual inspection of graphite fuel channels at Magnox nuclear power stations.
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- Insight: Non-Destructive Testing & Condition Monitoring, 2008, v. 50, n. 12, p. 668, doi. 10.1784/insi.2008.50.12.668
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Cancer as Weapon: Sowing Battlefields With Depleted Uranium.
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- CounterPunch, 2023, p. 1
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Method for calculating the duration of vacuum drying of a metal-concrete container for spent nuclear fuel.
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- Journal of Engineering Physics & Thermophysics, 2013, v. 86, n. 4, p. 735, doi. 10.1007/s10891-013-0890-3
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Hydrodynamics and heat transfer of a water flow with supercritical parameters in a vertical assembly of fuel elements.
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- Journal of Engineering Physics & Thermophysics, 2013, v. 86, n. 4, p. 811, doi. 10.1007/s10891-013-0899-7
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Resistance of spherical fills in the case of flow of single- and two-phase media.
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- Journal of Engineering Physics & Thermophysics, 2009, v. 82, n. 2, p. 277, doi. 10.1007/s10891-009-0194-9
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Influence of disturbances in the geometry of the elements of a regularly porous system on the hydrodynamic characteristics of the clusters of fuel elements of a nuclear reactor.
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- Journal of Engineering Physics & Thermophysics, 2008, v. 81, n. 2, p. 388, doi. 10.1007/s10891-008-0047-y
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Numerical analysis of flow-induced deflection of curved nuclear reactor fuel plates under high velocity flows.
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- Journal of Nuclear Science & Technology, 2024, v. 61, n. 9, p. 1177, doi. 10.1080/00223131.2024.2307430
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Thorium cycles and proliferation.
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- Bulletin of the Atomic Scientists, 1979, v. 35, n. 2, p. 16, doi. 10.1080/00963402.1979.11458583
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Hazards of the Nuclear Fuel Cycle.
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- Bulletin of the Atomic Scientists, 1974, v. 30, n. 8, p. 14, doi. 10.1080/00963402.1974.11458150
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COMBUSTIBLES LEÑOSOS EMPLEADOS EN LA LOCALIDAD DE ANTOFAGASTA DE LA SIERRA (CATAMARCA, ARGENTINA).
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- Boletín de la Sociedad Argentina de Botánica, 2020, v. 55, n. 2, p. 311, doi. 10.31055/1851.2372.v55.n2.26419
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RBMK-1500 šilumą išskiriančiuose elementuose vykstančių procesų modeliavimas.
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- Energetika, 2007, n. 4, p. 58
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3D continuum percolation approach and its application to lava-like fuel-containing materials behaviour forecast.
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- Condensed Matter Physics, 2009, v. 12, n. 2, p. 193, doi. 10.5488/CMP.12.2.193
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India designs new reactor.
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- International Power Generation, 1999, v. 22, n. 7, p. 5
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- Article
INVESTIGATION OF EFFECT OF BALLOONED FUEL PINS ON QUENCHING BEHAVIOR: DESIGN OF EXPERIMENT AND PRELIMINARY ANALYSIS.
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- Nuclear Technology, 2015, v. 190, n. 1, p. 52, doi. 10.13182/NT14-31
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UNCERTAINTY ANALYSIS ON REACTIVITY AND DISCHARGED INVENTORY DUE TO <sup>235,238</sup>U, <sup>239,240,241</sup>Pu, AND FISSION PRODUCTS: APPLICATION TO A PRESSURIZED WATER REACTOR FUEL ASSEMBLY.
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- Nuclear Technology, 2014, v. 185, n. 2, p. 174, doi. 10.13182/NT12-154
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EXPERIMENTAL VALIDATION OF THE DARWIN2.3 PACKAGE FOR FUEL CYCLE APPLICATIONS.
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- Nuclear Technology, 2013, v. 184, n. 2, p. 217, doi. 10.13182/NT12-121
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THERMAL-HYDRAULIC ANALYSIS FOR HEU AND LEU TRANSITIONAL CORE CONVERSION OF THE MIT RESEARCH REACTOR.
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- Nuclear Technology, 2013, v. 182, n. 3, p. 315, doi. 10.13182/NT12-81
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FABRICATION OF (U-Pu) MIXED-OXIDE FUEL FOR PRESSURIZED HEAVY WATER REACTORS.
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- Nuclear Technology, 2012, v. 179, n. 2, p. 189, doi. 10.13182/NT12-A14091
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LABORATORY TESTS OF AN ULTRASONIC INSPECTION TECHNIQUE TO IDENTIFY DEFECTIVE CANDU FUEL ELEMENTS.
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- Nuclear Technology, 2011, v. 176, n. 3, p. 452, doi. 10.13182/NT11-A13320
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COMPARISON OF THE HIGH-TEMPERATURE STEAM OXIDATION KINETICS OF ADVANCED CLADDING MATERIALS.
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- Nuclear Technology, 2010, v. 170, n. 1, p. 272, doi. 10.13182/NT10-A9464
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DEVELOPMENT OF THE FISSION PRODUCT RELEASE ANALYSIS CODE COPA-FPREL.
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- Nuclear Technology, 2010, v. 170, n. 1, p. 231, doi. 10.13182/NT10-A9461
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RADIONUCLIDE INVENTORY CALCULATIONS FOR THE MATERIALS TEST STATION.
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- Nuclear Technology, 2009, v. 168, n. 3, p. 957, doi. 10.13182/NT09-A9333
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DISMANTLEMENT OF THE TSF-SNAP REACTOR ASSEMBLY.
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- Nuclear Technology, 2009, v. 166, n. 3, p. 252, doi. 10.13182/NT09-A8839
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INTEGRATED EFFICIENCY TEST FOR PYROCHEMICAL FUEL CYCLES.
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- Nuclear Technology, 2009, v. 166, n. 2, p. 180, doi. 10.13182/NT09-A7404
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- Article
A study on characteristics of end plug resistance welding process in nuclear fuel rods by experiment and numerical simulation.
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- International Journal of Advanced Manufacturing Technology, 2018, v. 98, n. 9-12, p. 2241, doi. 10.1007/s00170-018-2365-3
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Studying Zirconium Surface Oxidation by Active Thermal Method.
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- Russian Journal of Nondestructive Testing, 2021, v. 57, n. 12, p. 1120, doi. 10.1134/S1061830921120032
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German minister takes on greens.
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- Nature, 1994, v. 369, n. 6475, p. 6, doi. 10.1038/369006b0
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Anisotropy of the conductivity of carbon fibre materials.
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- Fibre Chemistry, 2009, v. 41, n. 6, p. 360, doi. 10.1007/s10692-010-9205-z
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Oxidation of a stressed uranium-graphite fuel element.
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- Theoretical Foundations of Chemical Engineering, 2013, v. 47, n. 3, p. 291, doi. 10.1134/S0040579513030068
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The Geochemistry of Strontium-90 in Peatlands of the European Subarctic of Russia.
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- Pollution (2383451X), 2024, v. 10, n. 2, p. 808, doi. 10.22059/poll.2024.371056.2225
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Weak-Edge Extraction of Nuclear Plate Fuel Neutron Images at Low Lining Degree.
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- Applied Sciences (2076-3417), 2023, v. 13, n. 8, p. 5090, doi. 10.3390/app13085090
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Kinetic Modeling and Analysis of Fuel Element Pneumatic Lifting System in Pebble Bed Reactors.
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- Applied Sciences (2076-3417), 2023, v. 13, n. 3, p. 1486, doi. 10.3390/app13031486
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Sparse-View Neutron CT Reconstruction Using a Modified Weighted Total Difference Minimization Method.
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- Applied Sciences (2076-3417), 2021, v. 11, n. 22, p. 10942, doi. 10.3390/app112210942
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Multi-Elemental Coatings on Zirconium Alloy for Corrosion Resistance Improvement.
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- Coatings (2079-6412), 2022, v. 12, n. 8, p. 1112, doi. 10.3390/coatings12081112
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Application and Development Progress of Cr-Based Surface Coating in Nuclear Fuel Elements: II. Current Status and Shortcomings of Performance Studies.
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- Coatings (2079-6412), 2020, v. 10, n. 9, p. 835, doi. 10.3390/coatings10090835
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Application and Development Progress of Cr-Based Surface Coatings in Nuclear Fuel Element: I. Selection, Preparation, and Characteristics of Coating Materials.
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- Coatings (2079-6412), 2020, v. 10, n. 9, p. 808, doi. 10.3390/coatings10090808
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Dead or Alive?
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- Bulletin of the Atomic Scientists, 1961, v. 17, n. 3, p. 95, doi. 10.1080/00963402.1961.11454191
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SCIENCE.
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- Bulletin of the Atomic Scientists, 1959, v. 15, n. 1, p. 48
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- Article