| ANALYSIS OF THE NEUTRON FLUX IN AN ANNULAR PULSED REACTOR BY USING FINITE VOLUME METHOD
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2021 |
Silva, Mario |
| EIGENVALUE SENSITIVITY ANALYSIS & UNCERTAINTY QUANTIFICA TION IN SCALE6.2.1 USING CONTINUOUS-ENERGY MONTE CARLO METHOD
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2021 |
Labarile, Antonella |
| EMPIRICAL MODEL FOR MEAN GENERATION TIME ADJUSTMENT FACTOR FOR CLASSIC POINT REACTOR KINETICS EQUATIONS
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2021 |
Goes, David A. B. V. |
| LIQUID METAL COOLANTS FOR FUSION-FISSION HYBRID SYSTEM — A NEUTRONIC ANALYSIS
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2021 |
Pereira, Claubia |
| NEUTRONIC EVALUATION OF TRANSURANICS IN A GFR MODEL USING MCNPX AND SCALE 6.0
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2021 |
Pereira, Claubia |
| SIMULATION OF THE BURNUP IN CELL CALCULATION USING THE WIMSD-5B CODE CONSIDERING DIFFERENT NUCLEAR DATA LIBRARIES
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2021 |
Tavares, Desiree Y. De Sena |
| A THERMAL HYDRAULIC ANALISYS IN PWR REACTORS WITH UO2 OR (U-TH)O2 FUEL RODS EMPLOYING A SIMPLIFIED CODE
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2021 |
Santos, Thiago |
| 5X5 ROD BUNDLE FLOW FIELD MEASUREMENTS DOWNSTREAM A PWR SPACER GRID
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2021 |
Castro, Higor F. P. |
| COMPARISON BETWEEN RELAP5 VERSIONS FOR A TWO-PHASE NATURAL CIRCULATION ANALYSIS
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2021 |
Filho, Francisco Antonio Braz |
| COMPARISON OF DRIFT-VELOCITY AND DRAG COEFFICIENT APPROACHES FOR ONE-DIMENSIONAL TWO-FLUID MODELS IN BUBBLY FLOW REGIME AND VALIDATION WITH EXPERIMENTAL DATA
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2021 |
Quel, Consuelo Gomez-Zarzuela |
| MAIN CONSIDERATIONS FOR MODELLING A STATION BLACKOUT SCENARIO WITH TRACE
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2021 |
Gallardo, Sergio |
| MODERNIZED CDTN’S AIR-WATER EXPERIMENTAL TEST CIRCUIT: INITIAL RESULTS
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2021 |
Pessoa, Marcio Araujo |
| THERMAL-HYDRAULICS ANALYSIS OF A PWR REACTOR USING ZIRCALOY AND CARBIDE SILICON REINFORCED WITH TYPE S FIBERS AS FUEL CLADDINGS - SIMULATION OF A CHANNEL BLOCKAGE TRANSIENT
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2021 |
Pereira, Claubia |
| TRANSIENT HEAT TRANSFER ANALYSIS UP TO DRYOUT IN 3D FUEL RODS UNDER UNIDEAL CONDITIONS THROUGH THE DEVELOPMENT OF A COMPUTER CODE
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2021 |
Martins, Rodolfo I. |
| TRANSIENT MODELLING OF A NATURAL CIRCULATION LOOP UNDER VARIABLE PRESSURE
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2021 |
Vianna, Andre L. B. |
| NYSTROM METHOD APPLIED TO THE INTEGRAL FORMULATION OF NEUTRON IRANSPORT EQUATION IN X-Y GEOMETRY
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2021 |
Azevedo, Fabio S. |
| SOLUTION OF THE MULTIGROUP NEUTRON DIFFUSION EIGENVALUE PROBLEM IN SLAB GEOMETRY BY MODIFIED POWER METHOD
|
2021 |
Zanette, Rodrigo |
| SPECTRAL NODAL METHODOLOGY FOR MULTIGROUP SLAB-GEOMETRY DISCRETE ORDINATES NEUTRON TRANSPORT PROBLEMS WITH LINEARLY ANISOTROPIC SCATTERING
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2021 |
Oliva, Amaury Munoz |
| TRITIUM DISPERSION AROUND THE ANGRA NUCLEAR POWER PLANT: BOUNDARY SIMPLIFICATION BY DIFFEOMORPH CONFORMAL TRANSFORMATIONS
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2021 |
Meneghetti, Andre |
| A MOBILE DOSE PREDICTION SYSTEM BASED ON ARTIFICIAL NEURAL NETWORKS FOR NPP EMERGENCIES WITH RADIOACTIVE MATERIAL RELEASES
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2021 |
Gomes, Kelcio J. |
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