Works matching DE "NUCLEAR reactor reactivity"
Results: 59
Cuadraturas de Gauss-Legendre para resolver numéricamente la ecuación inversa de la cinética puntual.
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- Información Tecnológica, 2022, v. 33, n. 3, p. 43, doi. 10.4067/S0718-07642022000300043
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Effects of human contact and vagal regulation on pain reactivity and visual attention in newborns.
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- Developmental Psychobiology, 2006, v. 48, n. 7, p. 561, doi. 10.1002/dev.20150
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RBMK-1500 reaktoriaus neutroninės-fizikinės charakteristikos vykdant aktyviosios zonos modifikacijas 2004-2009 m.
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- Energetika, 2011, v. 57, n. 2, p. 71, doi. 10.6001/energetika.v57i2.2062
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Ignalinos AE galios ir garo reaktyvumo koeficientų dinaminis modeliavimas.
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- Energetika, 2009, n. 1, p. 6
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REACTIVITY SWING AS A FUNCTION OF BURNUP FOR URANIUM-FUELED FAST REACTORS.
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- Nuclear Technology, 2015, v. 190, n. 1, p. 11, doi. 10.13182/NT14-30
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DEPLETION REACTIVITY BENCHMARKS--II: UTILIZATION IN PWR SPENT-FUEL POOL CRITICALITY ANALYSIS.
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- Nuclear Technology, 2014, v. 185, n. 1, p. 57, doi. 10.13182/NT13-28
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DEPLETION REACTIVITY BENCHMARKS--I: EXPERIMENTAL BENCHMARKS FOR QUANTIFYING PWR FUEL REACTIVITY DEPLETION UNCERTAINTY.
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- Nuclear Technology, 2014, v. 185, n. 1, p. 39, doi. 10.13182/NT13-31
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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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DEVELOPMENT OF ERBIA-CREDIT SUPER-HIGH-BURNUP FUEL: EVALUATION OF MINIMUM ERBIA CONTENT FOR CRITICALITY SAFETY ANALYSES.
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- Nuclear Technology, 2012, v. 180, n. 1, p. 18, doi. 10.13182/NT12-A14516
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ISOTHERMAL TEMPERATURE COEFFICIENT EVALUATION FOR THE MONJU RESTART CORE.
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- Nuclear Technology, 2012, v. 179, n. 2, p. 286, doi. 10.13182/NT12-A14099
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CONTROL ROD WORTH EVALUATION FOR THE MONJU RESTART CORE.
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- Nuclear Technology, 2012, v. 179, n. 2, p. 266, doi. 10.13182/NT12-A14098
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EFFECTS OF FUEL RELOCATION FOR TRANSPORT CASKS.
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- Nuclear Technology, 2012, v. 179, n. 2, p. 180, doi. 10.13182/NT12-A14090
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NEUTRONIC DESIGN AND ANALYSIS OF A SMALL NUCLEAR REACTOR TO SUPPLY DISTRICT HEATING AND ELECTRICAL ENERGY TO CANADIAN FORCES BASES LOCATED IN THE ARCTIC OR THE NORTHERN REMOTE COMMUNITIES.
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- Nuclear Technology, 2011, v. 176, n. 3, p. 315, doi. 10.13182/NT11-A13311
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VALIDATION OF THE MONTE CARLO MODEL OF THE GREEK RESEARCH REACTOR CORE.
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- Nuclear Technology, 2010, v. 170, n. 3, p. 460, doi. 10.13182/NT10-A10331
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FEASIBILITY STUDY ON AN UPGRADED FUTURE MONJU CORE CONCEPT WITH EXTENDED OPERATION CYCLE LENGTH OF ONE YEAR AND INCREASED FUEL BURNUP.
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- Nuclear Technology, 2009, v. 167, n. 2, p. 254, doi. 10.13182/NT09-A8962
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Determination of the relative power density distribution in a heterogeneous reactor from the results of measurements of the reactivity effects and the neutron importance function.
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- Physics of Atomic Nuclei, 2012, v. 75, n. 13, p. 1586, doi. 10.1134/S1063778812130017
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Introduction of corrections taking into account interdependence of multigroup constants to the results of multigroup perturbation theory calculations.
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- Physics of Atomic Nuclei, 2012, v. 75, n. 13, p. 1557, doi. 10.1134/S1063778812130066
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Comparison between the measured and calculated reactivity in measuring the effectiveness of the emergency protection at the stage of physical start-up of unit no. 3 at the Kalinin nuclear power plant.
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- Physics of Atomic Nuclei, 2012, v. 75, n. 13, p. 1596, doi. 10.1134/S1063778812130030
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Measurements of control rod worth by modified inverse kinetic method.
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- Physics of Atomic Nuclei, 2011, v. 74, n. 14, p. 1917, doi. 10.1134/S106377881114002X
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Calculation of reactivities using ionization chamber currents with different sets of kinetic parameters for reduced scram system efficiency in the VVER-1000 of the third unit of the Kalinin nuclear power plant at the stage of physical start-up.
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- Physics of Atomic Nuclei, 2011, v. 74, n. 14, p. 1908, doi. 10.1134/S1063778811140110
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Using the procedure of spectral projection for reactivity determination in physically large nuclear reactors.
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- Physics of Atomic Nuclei, 2011, v. 74, n. 14, p. 1900, doi. 10.1134/S1063778811140031
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Reactivity effects in VVER-1000 of the third unit of the kalinin nuclear power plant at physical start-up. Computations in ShIPR intellectual code system with library of two-group cross sections generated by UNK code.
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- Physics of Atomic Nuclei, 2010, v. 73, n. 14, p. 2256, doi. 10.1134/S1063778810140036
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Improvements in the procedure of determining the void reactivity coefficient of a reactor of the RBMK type.
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- Physics of Atomic Nuclei, 2010, v. 73, n. 13, p. 2214, doi. 10.1134/S1063778810130077
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Consideration of spatial effects in reactivity measurements.
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- Physics of Atomic Nuclei, 2010, v. 73, n. 13, p. 2209, doi. 10.1134/S1063778810130065
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Reactivity Measurement in the Prompt-Jump Approximation for the Neutron Flux.
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- Atomic Energy, 2020, v. 128, n. 3, p. 182, doi. 10.1007/s10512-020-00672-w
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Reactivity Calibrator.
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- Atomic Energy, 2019, v. 125, n. 3, p. 157, doi. 10.1007/s10512-018-00459-0
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Measurement of the Power Coefficient of Reactivity of VVR-Ts in a Wide Power Range.
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- Atomic Energy, 2017, v. 122, n. 4, p. 226, doi. 10.1007/s10512-017-0260-x
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Computational Validation of the Spectral Projection Method Using Models of the RBMK Critical Stand.
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- Atomic Energy, 2016, v. 119, n. 4, p. 234, doi. 10.1007/s10512-016-0053-7
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Change in the Temperature Coefficient of Reactivity in Light-Water Reactors During Fuel Burnup.
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- Atomic Energy, 2014, v. 116, n. 1, p. 1, doi. 10.1007/s10512-014-9808-1
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Front Cover Image.
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- International Journal of Energy Research, 2019, v. 43, n. 2, p. i, doi. 10.1002/er.4408
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Void reactivity aspect and fuel conversion potential of heavy water cooled thorium reactor.
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- International Journal of Energy Research, 2018, v. 42, n. 1, p. 171, doi. 10.1002/er.3594
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Electron backscatter diffraction: applications for nuclear materials.
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- Journal of Microscopy, 1999, v. 195, n. 3, p. 233, doi. 10.1046/j.1365-2818.1999.00580.x
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Mugwort-Sensitized Individuals from North Europe, South Europe and North America Show Different IgE Reactivity Patterns.
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- International Archives of Allergy & Immunology, 2011, v. 154, n. 2, p. 164, doi. 10.1159/000320231
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Evaluation of accelerator-driven subcritical systems for transmutations of nuclear waste.
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- International Journal of Energy Research, 2000, v. 24, n. 11, p. 935, doi. 10.1002/1099-114X(200009)24:11<935::AID-ER633>3.0.CO;2-A
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A Comprehensive Approach to Elimination of Highly-Enriched-Uranium From All Nuclear-Reactor Fuel Cycles.
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- Science & Global Security, 2004, v. 12, n. 3, p. 137, doi. 10.1080/08929880490518045
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DEPENDENCIA DE LOS LAPLACIANOS Y LAS ECONOMIAS DEL REFLECTOR RADIAL CON LA TEMPERATURA Y EL BORO PARA LOS RETICULADOS TIPO VYER.
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- Nucleus, 1990, n. 9, p. 13
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Two-Group Theory of the Feynman-Alpha Method for Reactivity Measurement in ADS.
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- Science & Technology of Nuclear Installations, 2012, p. 1, doi. 10.1155/2012/620808
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Calculation of the Effective Delayed Neutron Fraction by Deterministic and Monte Carlo Methods.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/584256
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Dynamics of Fluid Fuel Reactors in the Presence of Periodic Perturbations.
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- Science & Technology of Nuclear Installations, 2008, v. 2008, p. 1, doi. 10.1155/2008/816543
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RBMK Reactivity coefficients at minimum controllable power.
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- Atomic Energy, 2013, v. 113, n. 5, p. 380, doi. 10.1007/s10512-013-9649-3
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Study of the Doppler reactivity effect for samples of reactor materials in critical assemblies.
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- Atomic Energy, 2013, v. 113, n. 3, p. 201, doi. 10.1007/s10512-012-9617-3
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Important processes during fuel burnup in fast reactors with low excess reactivity.
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- Atomic Energy, 2012, v. 112, n. 6, p. 458, doi. 10.1007/s10512-012-9585-7
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Experimental assessment of the temperature effect of reactivity with extracted control rods.
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- Atomic Energy, 2010, v. 108, n. 5, p. 389, doi. 10.1007/s10512-010-9306-z
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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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Use of a priori information for obtaining the inverse solution of the equation of point kinetics.
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- Atomic Energy, 2008, v. 104, n. 3, p. 224, doi. 10.1007/s10512-008-9020-2
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Assessment of core damage frequencies for intact circuit faults on a PWR plant.
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- Nuclear Future, 2008, v. 4, n. 2, p. 115
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FEASIBILITY OF DESIGNING THE ENCAPSULATED NUCLEAR HEAT SOURCE REACTOR WITH NEGATIVE VOID REACTIVITY FEEDBACK.
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- Nuclear Technology, 2007, v. 160, n. 3, p. 257, doi. 10.13182/NT07-A3898
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FERTILE-FREE FUELS IN PRESSURIZED WATER REACTORS: DESIGN CHALLENGES AND SOLUTIONS.
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- Nuclear Technology, 2007, v. 157, n. 2, p. 157, doi. 10.13182/NT07-A3810
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AN ASSESSMENT OF FUEL DAMAGE IN POSTULATED REACTIVITY-INITIATED ACCIDENTS.
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- Nuclear Technology, 2006, v. 155, n. 3, p. 293, doi. 10.13182/NT06-A3763
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ACCURACY OF MONTE CARLO CRITICALITY CALCULATIONS DURING BR2 OPERATION.
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- Nuclear Technology, 2005, v. 151, n. 2, p. 201, doi. 10.13182/NT05-A3644
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