CRITICALITY ANALYSIS FOR MIXED THORIUM-URANIUM FUEL IN THE ANGRA 2 PWR REACTOR USING KENO-VI
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2021 |
Wichrowski, Caio C. |
THE TSALLIS STATISTICS APPLIED TO THE CALCULATION OF ABSORPTION CROSS SECTION OF 238U, 232TH AND 240PU ISOTOPES
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2021 |
Almeida, Guilherme Guedes De |
A COMPARATIVE STUDY OF BORON TRANSPORT MODELS IN NRC THERMAL-HYDRAULIC CODE TRACE
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2021 |
Olmo-Juan, Nicolas |
ANALYSIS OF TRANSIENT HEAT CONDUCTION IN A PWR FUEL ROD BY AN IMPROVED LUMPED PARAMETER APPROACH
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2021 |
Dourado, Eneida Regina G. |
BREAK LOCATION INFLUENCE IN PRESSURE VESSEL SBLOCA SCENARIOS
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2021 |
Gallardo, Sergio |
EFFECT OF HIGH DOSES OF GAMMA RADIATION ON THERMOPHYSICAL PROPERTIES OF ZRO2 NANOFLUIDS IN AQUEOUS BASE
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2021 |
Rocha, Marcelo Da Silva |
SIMULATION OF A PASSIVE AUXILIARY FEEDWATER SYSTEM WITH TRACE5
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2021 |
Gallardo, Sergio |
THERMAL HYDRAULIC CORE SIMULATION OF THE MYRRHA REACTOR IN STEADY STATE OPERATION
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2021 |
Costa, Antonella L. |
TWO-DIMENSIONAL TRANSIENT THERMAL ANALYSIS OF A FUEL ROD BY FINITE VOLUME METHOD
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2021 |
Costa, Rhayanne Yalle Negreiros |
APPROXIMATE ALBEDO BOUNDARY CONDITIONS FOR ENERGYMULTIGROUP X, Y- GEOMETRY DISCRETE ORDINATES NUCLEARGLOBAL CALCULATIONS
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2021 |
Silva, Davi Jose Martins |
GENERALIZATION OF SPECTRAL GREEN'S FUNCTION NODAL METHOD FOR SLAB-GEOMETRY FIXED-SOURCE ADJOINT TRANSPORT PROBLEMS IN SN FORMULATION
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2021 |
Curbelo, Jesus Perez |
NYSTROM METHOD IN TRANSPORT THEORY
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2021 |
Dalmolin, Debora |
THERMAL-HYDRAULIC CODE FOR ESTIMATING SAFETY LIMITS OF NUCLEAR REACTORS WITH PLATE TYPE FUELS
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2021 |
Castellanos, Duvan Alejandro |
A COLLABORATIVE VIRTUAL ENVIRONMENT FOR TRAINING OF SECURITY AGENTS IN NUCLEAR EMERGENCIES
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2021 |
Fernandes, Sara Isnardo |
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 |