DECAY HEAT CALCULATIONS FOR THE FUEL LOADED IRRADIATION LOOP DEVICE OF THE RMB MULTIPURPOSE BRAZILIAN REACTOR
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2021 |
Campolina, Daniel |
NUCLEAR DATA PROCESSING FOR CROSS-SECTIONS GENERATION FOR FUSION- FISSION, ADS, AND IV GENERATION REACTORS UTILIZATION
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2021 |
Pereira, Claubia |
ON THE NEUTRON SLOWING-DOWN IN MODERATORS
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2021 |
Caldeira, Alexandre D. |
A SIMPLE CAPACITANCE SENSOR FOR VOID FRACTION MEASUREMENT IN GAS-LIQUID TWO-PHASE FLOW
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2021 |
Silva, Luiz Carlos R. Pereira Da |
CRUD FORMATION EVALUATION AT THE ADVANCED FUEL OPERATING IN ANGRA 1 NPP
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2021 |
Palheiros, Franklin L. |
SPENT FUEL POOL THERMAL-HYDRAULIC ANALISYS USING RELAPS-3D
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2021 |
Pereira, Claubia |
TECHNICAL AND ECONOMIC FEASIBILITY STUDY FOR THE REACTIVATION OF THE INTEGRAL TEST FACILITY OF IPEN / CNEN NUCLEAR ENGINEERING CENTER
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2021 |
Biaty, Flavia Paladino |
THERMOHYDRAULIC MODELING OF VERY HIGH TEMPERATUREREACTORS IN REGIMES WITH LOSS OF COOLANT USING CFD
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2021 |
Moreira, Uebert G. |
DEVELOPMENT AND APPLICATION OF THE PCRELAP5 - DATA CALCULATION PROGRAM FOR RELAP 5 CODE
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2021 |
Silvestre, Larissa J B |
CLUSTER PROCESSING BUSINESS LEVEL MONITOR
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2021 |
Muniz, Francisco J. |
DYNAMIC LOAD-BALANCING- EXTENDED GRADIENT MECHANISM - GRAPHIC REPRESENTATION
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2021 |
Muniz, Francisco J. |
PROFESSIONAL CLUSTER MANAGEMENT BY A SMALL SCIENTIFIC TEAM: CHALLENGES, SOLUTIONS AND PERSPECTIVES
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2021 |
Silva, Vitor |
SOLUTION FOR THE MULTIGROUP NEUTRON SPACE KINETICS EQUATIONS BY THE MODIFIED PICARD ALGORITHM
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2021 |
Tavares, Matheus Gularte |
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 |