| DECAY HEAT CALCULATIONS FOR THE FUEL LOADED IRRADIATION LOOP DEVICE OF THE RMB MULTIPURPOSE BRAZILIAN REACTOR
|
2021 |
Campolina, Daniel |
| NUCLEAR DATA PROCESSING FOR CROSS-SECTIONS GENERATION FOR FUSION- FISSION, ADS, AND IV GENERATION REACTORS UTILIZATION
|
2021 |
Pereira, Claubia |
| ON THE NEUTRON SLOWING-DOWN IN MODERATORS
|
2021 |
Caldeira, Alexandre D. |
| A SIMPLE CAPACITANCE SENSOR FOR VOID FRACTION MEASUREMENT IN GAS-LIQUID TWO-PHASE FLOW
|
2021 |
Silva, Luiz Carlos R. Pereira Da |
| CRUD FORMATION EVALUATION AT THE ADVANCED FUEL OPERATING IN ANGRA 1 NPP
|
2021 |
Palheiros, Franklin L. |
| SPENT FUEL POOL THERMAL-HYDRAULIC ANALISYS USING RELAPS-3D
|
2021 |
Pereira, Claubia |
| TECHNICAL AND ECONOMIC FEASIBILITY STUDY FOR THE REACTIVATION OF THE INTEGRAL TEST FACILITY OF IPEN / CNEN NUCLEAR ENGINEERING CENTER
|
2021 |
Biaty, Flavia Paladino |
| THERMOHYDRAULIC MODELING OF VERY HIGH TEMPERATUREREACTORS IN REGIMES WITH LOSS OF COOLANT USING CFD
|
2021 |
Moreira, Uebert G. |
| DEVELOPMENT AND APPLICATION OF THE PCRELAP5 - DATA CALCULATION PROGRAM FOR RELAP 5 CODE
|
2021 |
Silvestre, Larissa J B |
| CLUSTER PROCESSING BUSINESS LEVEL MONITOR
|
2021 |
Muniz, Francisco J. |
| DYNAMIC LOAD-BALANCING- EXTENDED GRADIENT MECHANISM - GRAPHIC REPRESENTATION
|
2021 |
Muniz, Francisco J. |
| PROFESSIONAL CLUSTER MANAGEMENT BY A SMALL SCIENTIFIC TEAM: CHALLENGES, SOLUTIONS AND PERSPECTIVES
|
2021 |
Silva, Vitor |
| SOLUTION FOR THE MULTIGROUP NEUTRON SPACE KINETICS EQUATIONS BY THE MODIFIED PICARD ALGORITHM
|
2021 |
Tavares, Matheus Gularte |
| A CONTINUOUS ENERGY NEUTRON TRANSPORT MONTE CARLO SIMULATOR PROJECT: DECOMPOSITION OF THE NEUTRON ENERGY SPECTRUM BY TARGET NUCLEI TAGGING
|
2021 |
Barcellos, Luiz Felipe F. Chaves |
| ANALYSIS OF BURNUP OF ANGRA 2 PWR NUCLEAR REACTOR WITH ADDITION OF THORIUM DIOXIDE FUEL USING ORIGEN-ARP
|
2021 |
Goncalves, Isadora C. |
| ARTIFICIAL NEURAL NETWORKS FOR SPATIAL DISTRIBUTION OF FUEL ASSEMBLIES IN RELOAD OF PWR REACTORS
|
2021 |
Pereira, Claubia |
| ASSESSMENT OF THE INSERTION OF REPROCESSED FUEL SPIKED WITH THORIUM IN A PWR CORE
|
2021 |
Pereira, Claubia |
| MODIFIED MEAN GENERATION TIME PARAMETER IN THE NEUTRON POINT KINETICS EQUATIONS
|
2021 |
Diniz, Rodrigo C. |
| NEUTRONIC ANALYSIS OF A FUEL ELEMENT WITH VARIATIONS IN FUEL ENRICHMENT AND BURNABLE POISON
|
2021 |
Pereira, Claubia |
| SENSIBILITY ANALYSIS OF FUEL DEPLETION USING DIFFERENT NUCLEAR FUEL DEPLETION CODES
|
2021 |
Pereira, Claubia |
Tag hinzufügen