| Area: ENFIR |
[Back] |
463-1 - ABOUT MEASURENTS OF NUCLEAR REACTOR’S ROD WORTH WITH THE ROD DROP TECHNIQUE
Guilherme de Carvalho (UFRJ - Universidade Federal do Rio de janeiro) ; Giovanni Stefani (UFRJ - Universidade Federal do Rio de janeiro)
| Area: ENFIR Keywords: Control Rods, Nuclear Reactor's, shadowing effect, reactivity | [Paper] |
474-1 - ACCIDENT TOLERANT FUELS BASED ON FECRAL ALLOYS FOR PRESSURIZED WATER REACTOR
Isabella Magalhães (UFMG - Universidade Federal de Minas Gerais) ; Patrícia Reis (UFMG - Universidade Federal de Minas Gerais) ; Antonella Costa (UFMG - Universidade Federal de Minas Gerais) ; Clarysson Silva (UFMG - Universidade Federal de Minas Gerais) ; Claubia Pereira (UFMG - Universidade Federal de Minas Gerais)
| Area: ENFIR Keywords: Accident Tolerant Fuels, FeCrAl, RELAP5 | [Paper] |
194-1 - ADAPTATION OF A 10MWE SMALL MODULAR REACTOR FOR THORIUM MOX FUEL
Caio Wichrowski (IME - Instituto Militar de Engenharia) ; Claudio Oliveira (IME - Instituto Militar de Engenharia) ; Sergio Vellozo (IME - Instituto Militar de Engenharia)
| Area: ENFIR Keywords: Monte Carlo, SMR, Thorium | [Paper] |
125-2 - ADS LBE SPALLATION TARGET DESIGN: A REVIEW ON GEOMETRICAL INFLUENCES ON NEUTRONIC AND THERMAL BEHAVIOR
Ivan Umezu (UFMG - Universidade Federal de Minas Gerais) ; José da Silva (UFMG - Universidade Federal de Minas Gerais) ; Antonella Costa (UFMG - Universidade Federal de Minas Gerais) ; Carlos Velasquez (UFMG - Universidade Federal de Minas Gerais) ; Cláubia Pereira (UFMG - Universidade Federal de Minas Gerais)
| Area: ENFIR Keywords: ADS, Spallation Target Design, LBE, Spallation Reaction | [Paper] |
31-4 - ADVANCED NUCLEAR FUELS BASED ON THORIUM MIXED OXIDES
Daniel de Souza Gomes Gomes (IPEN - SÃO PAULO)
| Area: ENFIR Keywords: FRAPCON, High thermal conductivity of thorium fue, (Th-U)O2, (Th-Pu)O2 | [Paper] |
396-2 - ALTERNATIVE METHOD FOR CLASSIFICATION OF STRUCTURES, SYSTEMS AND COMPONENTS FOR DEDICATION IN RESEARCH REACTORS
Alexander Busse (UFABC - Universidade Federal do ABC) ; João Moreira (UFABC - Universidade Federal do ABC)
| Area: ENFIR Keywords: Safety classification, Research reactors, Dedication for research reactors | [Paper] |
31-3 - ANALYSIS OF CHROMIUM OXIDE DOPED PELLET FOR LWRS USING FRAPCON CODE
Daniel de Souza Gomes Gomes (IPEN - SÃO PAULO)
| Area: ENFIR Keywords: ADOPT, ATF, Cr2O3-doped UO2, FRAPCON | [Paper] |
26-1 - ANALYSIS OF THE APPLICATION OF REMOTELY OPERATED UNDERWATER VEHICLES IN NUCLEAR POWER PLANTS
Giovana Ciongoli () ; Flavia Biaty () ; Patricia Paladino () ; Arthur Julião () ; Gaianê Sabundjian ()
| Area: ENFIR Keywords: robotic systems, routine inspections, ROV, safety analysis | [Paper] |
417-1 - ANALYSIS OF THE SWOT/FOFA MATRIX AS A STRATEGY FOR IMPLEMENTING THE AP-TH1000 REACTOR IN BRAZIL
Francky Roger da Silva () ; Giovanni de Stefani ()
| Area: ENFIR Keywords: AP-Th 1000, SWOT, Thorium | [Paper] |
57-1 - AN ESTIMATE OF THE COSTS INVOLVED IN EACH STRATEGY OF DECOMISSION OF NUCLEOELECTRIC PLANTS OF TYPE PWR
Maria Vitória de Oliveira (UFRJ - UNIVERSIDADE FEDERAL DO RIO DE JANEIRO)
| Area: ENFIR Keywords: COSTS, STRATEGY, DECOMISSION, PWR | [Paper] |
522-1 - AN OVERVIEW OF MOLTEN SALT REACTORS AND PRELIMINARY CALCULATIONS
Letícia Gonçalves (UFABC - Universidade Federal do ABC) ; José Maiorino (UFABC - Universidade Federal do ABC) ; Deiglys Monteiro (UFABC - Universidade Federal do ABC) ; Pedro Rossi (UFABC - Universidade Federal do ABC)
| Area: ENFIR Keywords: ANSYS-CFX, Molten Salt Reactor, Neutron Analysis, Thermal fluid dynamics, Thorium | [Paper] |
358-1 - APPLICATION OF A LEVEL 2 PSA METHODOLOGY IN THE EVENT OF LOSS OF COOLANT CIRCULATION ACCIDENT IN THE SPENT FUEL POOL OF A VSMR
Nathália Araújo (USP - LabRisco) ; Maritza Gual (USP - LabRisco) ; Hugo Romberg (USP - LabRisco) ; Marcos Maturana (USP - LabRisco) ; Marcelo Martins (USP - LabRisco)
| Area: ENFIR Keywords: Probabilistic Safety Assessment , Spent Fuel Pool , Very Small Modular Reactors | [Paper] |
187-2 - APPLICATION OF NEUTRON TRANSPORT AND DIFFUSION THEORIES TO HOMOGENEOUS MEDIA
Nicolas Santana (IEAV - Instituto de Estudos Avançados) ; Lamartine Guimarães (IEAV - Instituto de Estudos Avançados) ; Alexandre Caldeira (IEAV - Instituto de Estudos Avançados)
| Area: ENFIR Keywords: neutrons, Transport equation, Diffusion theory, Homogeneous media, criticality | [Paper] |
512-2 - APPLICATION OF THE GRS CORE SIMULATOR KMACS ON ACCIDENT TOLERANT FUELS
Thomas Eisenstecken (GRS - Gesellschaft für Anlagen- und Reaktorsicherheit gGmbH) ; Alexander Aures (GRS - Gesellschaft für Anlagen- und Reaktorsicherheit gGmbH) ; Romain Henry (GRS - Gesellschaft für Anlagen- und Reaktorsicherheit gGmbH) ; Robert Kilger (GRS - Gesellschaft für Anlagen- und Reaktorsicherheit gGmbH)
| Area: ENFIR Keywords: Accident Tolerant Fuel, Nuclear Safety Analysis, Core Simulator | [Paper] |
459-1 - A PWR FUEL ASSEMBLY ANALYSED WITH SERPENT, KENO VI, MCNPX AND NEWT CODES
Víctor Castro (UFMG - Universidade Federal de Minas Gerais)
| Area: ENFIR Keywords: Thorium, Reprocessed Fuel, Neutronic Libraries | [Paper] |
546-2 - A QUALITATIVE APPROACH OF THE REGULATION FOR THE LIFE EXTENSION OF BRAZILIAN NUCLEAR POWER PLANTS
Carla Andrade (IEN - RJ)
| Area: ENFIR Keywords: Long-Term Operation of NPPs, Licensing of NPPs, Technical Note NT-CGRC-007/18, Technical Note NT-CGRC-008/18 | [Paper] |
21-5 - A REVIEW OF THE DETERMINISTIC SOLUTION OF NONCLASSICAL TRANSPORT PROBLEMS
Leonardo Moraes (IPRJ/UERJ - UNIVERSIDADE DO ESTADO DO RIO DE JANEIRO) ; Ricardo Barros (IPRJ/UERJ - UNIVERSIDADE DO ESTADO DO RIO DE JANEIRO) ; Richard Vasques ()
| Area: ENFIR Keywords: neutral particle transport, nonclassical transport, Laguerre spectral approach, discrete ordinates, slab geometry | [Paper] |
281-1 - A REVIEW ON THE FATIGUE CRACK PROPAGATION IN THE THRESHOLD REGION
Carlos A. Miranda (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Luiz Ricardo (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Luiz Ricardo ()
| Area: ENFIR Keywords: Fatigue, Crack propagation, Crack closure models, Design, Threshold | [Paper] |
31-2 - ASSESSMENT OF A UO2-GRAPHENE COMPOSITE FUEL PROPOSED FOR NUCLEAR REACTORS
Daniel de Souza Gomes Gomes (IPEN - SÃO PAULO)
| Area: ENFIR Keywords: carbon nanoparticles, FRAPCON, spark plasma sintering, FRAPCON | [Paper] |
313-1 - CALCULATION OF DEFORMED CROSS SECTIONS APPLYING KANIADAKIS DISTRIBUTION USING FRENDY CODE
João Maciel (UFRJ - Federal University of Rio de Janeiro) ; Willian de Abreu (UFRJ - Federal University of Rio de Janeiro) ; Aquilino Martinez (UFRJ - Federal University of Rio de Janeiro) ; Alessandro Gonçalves (UFRJ - Federal University of Rio de Janeiro)
| Area: ENFIR Keywords: Kaniadakis, FRENDY, deformed cross-sections, Doppler broadening function | [Paper] |
125-1 - CFD ANALYSIS OF AN INFINITE WIRE-WRAPPED LBE-COOLED FAST REACTOR SUB-CHANNEL
Ivan Umezu (UFMG - Universidade Federal de Minas Gerais) ; Antonella Costa (UFMG - Universidade Federal de Minas Gerais) ; André Augusto dos Santos (, UFMG - Universidade Federal de Minas Gerais)
| Area: ENFIR Keywords: CFD, LBE, MYRRHA, Wire-Wrapped | [Paper] |
202-1 - CHANNEL ANALYSIS OF THE AP-TH 1000 REACTOR CONCEPT
Caio Július César Miranda Rodrigues da Cunha (UFPE - Universidade Federal de Pernambuco) ; Daniel González Rodríguez () ; Fernando Roberto de Andrade Lima (UFPE - Universidade Federal de Pernambuco) ; Giovanni Laranjo de Stefani ()
| Area: ENFIR Keywords: AP1000, AP-Th 1000, Thorium, PWR, MOX fuel | [Paper] |
290-1 - CLASSIFICATION OF TWO-PHASE FLOW INSTABILITY PHASES USING CONVOLUTIONAL NEURAL NETWORKS
Sandro Schott (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Marcones da Silva (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Roberto de Mesquista (IPEN - Instituto de Pesquisas Energéticas e Nucleares)
| Area: ENFIR Keywords: Convolutional Neural Neworks, Deep Learning, Two-Phase Flow, Natural Circulation, Artificial Intelligence | [Paper] |
166-2 - COMPARISON BETWEEN TWO THERMOCHEMICAL HYDROGEN PRODUCTION METHODS AND SEAWATER DESALINATION COUPLED TO THE HTR-PM NUCLEAR REACTOR
Daniel González Rodríguez (CRCN - CENTRO REGIONAL DE CIÊNCIAS NUCLEARES DO NORDESTE) ; Fernando de Andrade Lima (CRCN - CENTRO REGIONAL DE CIÊNCIAS NUCLEARES DO NORDESTE) ; Carlos Brayner de Oliveira Lira (CRCN - CENTRO REGIONAL DE CIÊNCIAS NUCLEARES DO NORDESTE)
| Area: ENFIR Keywords: hydrogen production, efficiency, seawater desalination, CPS, exergy | [Paper] |
231-1 - COMPARISON OF UNCERTAINTY PROPAGATION METHODS IN THE SCOPE OF PROBABILISTIC RISK ASSESSMENT
Vanderley Vasconcelos (CDTN/CNEN - Centro de Desenvolvimento da Tecnologia Nuclear) ; Graiciany Barros (CDTN/CNEN - Centro de Desenvolvimento da Tecnologia Nuclear) ; Luiz da Silva (CDTN/CNEN - Centro de Desenvolvimento da Tecnologia Nuclear) ; Cássia Martins (CDTN/CNEN - Centro de Desenvolvimento da Tecnologia Nuclear) ; Keferson Carvalho (CDTN/CNEN - Centro de Desenvolvimento da Tecnologia Nuclear)
| Area: ENFIR Keywords: Probabilistic Risk Assessment, Fault tree, Uncertainty Propagation, Nuclear reactor | [Paper] |
224-1 - COMPUTATIONAL MODEL FOR THERMOHYDRAULIC ANALYSIS OF AN INTEGRAL PRESSURIZED WATER REACTOR WITH MIXED OXIDE FUEL (TH, PU)O2
Mariana Cecilia Betancourt (INSTEC - Instituto Superior de Tecnologías y Ciencias Aplicadas) ; Pedro Moraes Santos () ; Leorlen Rojas Mazaira () ; Carlos García Hernandez (INSTEC - Instituto Superior de Tecnologías y Ciencias Aplicadas) ; Dany Dominguez () ; Jesús Rosales García (INSTEC - Instituto Superior de Tecnologías y Ciencias Aplicadas) ; Carlos Brayner ()
| Area: ENFIR Keywords: Thorium-based fuel, MOX, SMR, CFD | [Paper] |
195-1 - CONTROL AND DATA ACQUISITION SOFTWARE OF A MECHANISM FOR MOVING A NUCLEAR FUEL IRRADIATION CAPSULE: USABILITY ASSESSMENT
Eduardo Stehling Saraiva (CDTN - Centro de Desenvolvimento da Tecnologia Nuclear) ; Vanderley de Vasconcelos (CDTN - Centro de Desenvolvimento da Tecnologia Nuclear) ; Daniel Magalhães Campolina (CDTN - Centro de Desenvolvimento da Tecnologia Nuclear)
| Area: ENFIR Keywords: Usability, Software, Nuclear Fuel, Irradiation Capsule, SCADA | [Paper] |
44-1 - COPPER WATER HEAT PIPE APPLIED FOR STIRLING ENGINE
Ana Santos (ITA - Instituto Tecnológico de Aeronáutica) ; Valéria Leite (, ITA - Instituto Tecnológico de Aeronáutica) ; Lamartine Guimarães (, ITA - Instituto Tecnológico de Aeronáutica) ; Lucía Delfini (ITA - Instituto Tecnológico de Aeronáutica)
| Area: ENFIR Keywords: Heat pipe, Microrreactos, Nuclear energy , Stirling Engine, Heat transfer | [Paper] |
70-1 - DESIGN CONSIDERATIONS FOR RECTANGULAR BOLTED FULL FACE FLANGED JOINTS FOR SURFACE CONDENSERS
Augusto Soave (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Miguel Mattar Neto (IPEN - Instituto de Pesquisas Energéticas e Nucleares)
| Area: ENFIR Keywords: Bolted Joint, Full face, Rectangular flange, Surface condenser | [Paper] |
430-1 - DEVELOPMENT OF A COMPUTER CODE PADPLAC-UMO FOR PERFORMANCE ANALYSIS OF MONOLITHIC URANIUM MOLYBDENUM FUEL PLATE
Regis Reis (UMESP - Universidade Metodista de São Paulo) ; Antonio Silva ()
| Area: ENFIR Keywords: nuclear fuel performance, fuel plate, Uranium-molybdenum, computational simulation, power reactor | [Paper] |
188-1 - DEVELOPMENT OF A METHODOLOGY FOR MANAGEMENT AND PHYSICAL-CHEMICAL CONTROL OF THE COOLING WATER OF THE IPR-R1 TRIGA RESEARCH NUCLEAR REACTOR
João Gabriel Marques (UFMG - Uiversidade Federal de Minas Gerais) ; Antonella Costa (UFMG - Uiversidade Federal de Minas Gerais) ; Claubia Pereira (UFMG - Uiversidade Federal de Minas Gerais) ; Amir Mesquita ()
| Area: ENFIR Keywords: IPR-R1 Triga Research Nuclear Reactor, Management and physical-chemical control, Gamma spectrometry of the water , pH, Electrical conductivity | [Paper] |
437-1 - DOPPLER EFFECT ANALYSIS OF A FAST NEUTRON REACTOR FOR A FUSION-FISSION SYSTEM
Renato Vinícius Marques (UFMG - Universidade Federal de Minas Gerais) ; Carlos Eduardo Velasquez (UFMG - Universidade Federal de Minas Gerais) ; Claubia Pereira (UFMG - Universidade Federal de Minas Gerais)
| Area: ENFIR Keywords: Fusion-Fission Fast Reactor, Doppler Effect, Reprocessed Fuels, Transmutation, Thorium and Depleted Uranium | [Paper] |
431-1 - DYNAMIC ANALYSIS OF A CLAMPED-CLAMPED PIPE CONVEYING SINGLE-PHASE FLUID
Valéria França (UFRJ - Universidade Federal do Rio de Janeiro) ; Jian Su (UFRJ - Universidade Federal do Rio de Janeiro)
| Area: ENFIR Keywords: Flow induced vibration, Fluid-structure interaction, GITT | [Paper] |
128-1 - EFFECT OF MOUNTING ORIENTATION ON TESTING EQUIPMENT ON THE ELASTIC COMPLIANCE OF CLAMPED SE(T) SPECIMENS
Leonardo Ferreira de Andrade (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Gustavo Donato () ; Miguel Neto (IPEN - Instituto de Pesquisas Energéticas e Nucleares)
| Area: ENFIR Keywords: Fracture, Mechanics, SE(T), Clamped, Compliance | [Paper] |
210-1 - ELECTRIC POWER SYSTEM BASED ON KILOPOWER PROJECT
Patryck Ferreira (, IEAV - Instituto de Estudos Avançados) ; Lamartine Guimarães (IEAV - Instituto de Estudos Avançados)
| Area: ENFIR Keywords: Kilopower, Heat transfer, Stirling Machine, Heat Pipe, Microrreactors | [Paper] |
35-1 - ENCAPSULATED OSB ENERGY ABSORPTION POTENTIAL: A PRELIMINARY ANALYSIS
Daniel Carvalho (IPEN-USP - Instituto de Pesquisas Energéticas e Nucleares) ; Miguel Mattar Neto (IPEN-USP - Instituto de Pesquisas Energéticas e Nucleares)
| Area: ENFIR Keywords: shock absorbers, wood, cellular solids, finite elements method, ls-dyna | [Paper] |
21-4 - ESTIMATION OF NEUTRAL PARTICLE LEAKAGE VIA THE ADJOINT DISCRETE ORDINATES TRANSPORT TECHNIQUES
Jesús Curbelo () ; Ricardo Barros (IPRJ/UERJ - UNIVERSIDADE DO ESTADO DO RIO DE JANEIRO)
| Area: ENFIR Keywords: Neutral particle transport, Adjoint transport problem, Discrete Ordinates (Sn), Leakage of particles, X,Y-geometry | [Paper] |
330-1 - EVALUATION OF NEUTRON PRODUCTION IN SPALLATION TARGETS WITH MCNPX AND FLUKA CODES
Jose Silva (UFMG - UNIVERSIDADE FEDERAL DE MINAS GERAIS) ; Carlos Velasquez (UFMG - UNIVERSIDADE FEDERAL DE MINAS GERAIS) ; Claubia Bezerra Lima (UFMG - UNIVERSIDADE FEDERAL DE MINAS GERAIS)
| Area: ENFIR Keywords: Intranuclear cascade, Accelerator-driven systems, Spallation process, Monte Carlo calculation, Thorium | [Paper] |
436-1 - EVALUATION OF PERFORATED PLATES MANUFACTURING WITH 3D PRINTING PROCESS
Wallen de Souza (UFMG - Universidade Federal De Minas Gerais)
| Area: ENFIR Keywords: Perforated plate, CFD , 3D printing | [Paper] |
330-2 - EVALUATION OF TH02U02 FUEL BEHAVIOR AT DIFFERENT TEMPERATURES IN ADS
Jose Silva (UFMG - UNIVERSIDADE FEDERAL DE MINAS GERAIS) ; Natalia Peixoto Lelis (UFMG - UNIVERSIDADE FEDERAL DE MINAS GERAIS) ; Carlos Velasquez (UFMG - UNIVERSIDADE FEDERAL DE MINAS GERAIS) ; Claubia Bezerra Lima (UFMG - UNIVERSIDADE FEDERAL DE MINAS GERAIS)
| Area: ENFIR Keywords: Transmutation, Accelerator-driven systems, hybrid-system, Advanced Fuel Cycle, Thorium | [Paper] |
532-1 - EVALUATION OF THE FEASIBILITY OF SEAWATER DESALINATION USING THE AP1000 NUCLEAR REACTOR AS A ENERGY SOURCE
Maria da Silva (UFPE - Universidade Federal de Pernambuco) ; Daniel Rodríguez () ; Carlos Alberto Oliveira Lira (, UFPE - Universidade Federal de Pernambuco) ; Fernando Andrade Lima (UFPE - Universidade Federal de Pernambuco)
| Area: ENFIR Keywords: Cogeneration, DESALINATION, AP1000 , NUCLEAR REACTOR, ENERGY | [Paper] |
55-1 - EVALUATION OF THE INSERTION OF A TRANSMUTATION LAYER IN THE ARC COMPACT REACTOR
Karytha Corrêa (UFMG - Universidade Federal de Minas Gerais) ; Carlos Velasquez (UFMG - Universidade Federal de Minas Gerais) ; Cláubia Pareira (UFMG - Universidade Federal de Minas Gerais)
| Area: ENFIR Keywords: Compact Reactor, Transmutation layer, High temperature superconductors | [Paper] |
124-1 - EVALUATION OF “SAFETY RELATED” AND “IMPORTANT TO SAFETY” TERMINOLOGY FOR SAFETY CLASSIFICATION OF NUCLEAR INSTALLATION ITEMS IN BRAZIL
Douglas Baroni (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Sad Borsoi (, IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Miguel Neto (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Patrícia de Oliveira (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Marcos Maturana (IPEN - Instituto de Pesquisas Energéticas e Nucleares)
| Area: ENFIR Keywords: Important to Safety, Safety Classification, Safety Related, Safety Terminology | [Paper] |
114-1 - EXPERIMENTAL INVESTIGATIONS OF ADDITIVES ON THE THERMAL CONDUCTIVITY UO2 PELLETS
Denise Camarano (CDTN - Centro de Desenvolvimento da Tecnologia Nuclear) ; Fábio Mansur (CDTN - Centro de Desenvolvimento da Tecnologia Nuclear) ; Ana Maria Santos (CDTN - Centro de Desenvolvimento da Tecnologia Nuclear)
| Area: ENFIR Keywords: Thermal conductivity, UO2 , Doped UO2 , Fuel pellets | [Paper] |
51-1 - EXTENDING THE NODAL EXPANSION METHOD BASIS FUNCTIONS
Sérgio Paixão (UFRJ - Federal University of Rio de Janeiro) ; Fernando da Silva (UFRJ - Federal University of Rio de Janeiro)
| Area: ENFIR Keywords: Nodal Diffusion Methods, Nodal Expansion Method, Higher-Order Expansions, Weighted Residual Techniques, Reactor Core Simulation | [Paper] |
152-1 - EXTERNAL EVENTS PSA - REQUIREMENTS APPLICABLE TO NEW NUCLEAR INSTALLATIONS PROJECTS
Thiago Padilha (CTMSP - Centro Tecnologico da Marinha em Sao Paulo) ; Marcos Maturana (CTMSP - Centro Tecnologico da Marinha em Sao Paulo) ; Miguel Mattar Neto () ; Patricia de Oliveira ()
| Area: ENFIR Keywords: Probabilistic Safety Analysis, External Events, Reactor Lifetime, New Nuclear Installations | [Paper] |
103-1 - FUNCTIONAL ANALYSIS, DIVERSITY AND DEFENSE-IN-DEPTH PRINCIPLE APPLIED FOR INSTRUMENTATION AND CONTROL ARCHITECTURE IN ACCORDANCE WITH U.S.NRC
Claudio Santos (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Luciano Freire (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Delvonei de Andrade (IPEN - Instituto de Pesquisas Energéticas e Nucleares)
| Area: ENFIR Keywords: Instrumentation and control, Functional analysis, Defense in depth, Diversity, U.S.NRC | [Paper] |
323-1 - FUSION-FISSION HYBRID SYSTEM – NEUTRON FLUX ANALYSIS AFTER DIVERTOR INSERTION
Natália Oliveira (UFMG - Universidade Federal de Minas Gerais) ; Carlos Velasquez (UFMG - Universidade Federal de Minas Gerais) ; Claubia Pereira (UFMG - Universidade Federal de Minas Gerais)
| Area: ENFIR Keywords: Divertor, Fusion-Fission Hybrid System, Neutron Spectrum | [Paper] |
374-1 - GRAIN REFINEMENT THROUGH SEVERE PLASTIC DEFORMATION USING MULTIAXIAL FORGING
Rejane Silva (CDTN - Centro de Desenvolvimento da Tecnologia Nuclear) ; Jonnas Peressinotto (CDTN - Centro de Desenvolvimento da Tecnologia Nuclear) ; Jefferson Vilela (CDTN - Centro de Desenvolvimento da Tecnologia Nuclear)
| Area: ENFIR Keywords: Severe plastic deformation, Multiaxial forging, Steel low carbon | [Paper] |
110-1 - HARDWARE FOR IIOT IN MISSION-CRITICAL NUCLEAR APPLICATIONS
Marcos Farias (IEN - Instituto de Engenharia Nuclear) ; Guilherme Jaime (IEN - Instituto de Engenharia Nuclear)
| Area: ENFIR Keywords: FPGA, Industrial Internet of Things, Reliability, Triple Modular Redundancy with spares | [Paper] |
79-4 - HEAT PIPE REACTORS: A REVIEW OF HEAT PIPES IN NUCLEAR REACTORS AND THE ROLE FOR SMALL MODULAR REACTORS AND TO SPACE EXPLORATION
Deiglys Monteiro (UNINOVE - Universidade Nove de Julho) ; João Moreira ()
| Area: ENFIR Keywords: CFD, Heat Pipes, Heat rejection, Small Modular Reactors, Space exploration | [Paper] |
275-1 - HYBRID EMERGENCY POWER SYSTEMS FOR RESEARCH NUCLEAR REACTORS
Marcio Belloni (IPEN - SP) ; Thadeu Conti ()
| Area: ENFIR Keywords: nuclear reactor, research nuclear reactor, UPS, electrical circuits, nobreak | [Paper] |
179-1 - IDENTIFICATION OF DESIGN BASIS ACCIDENTS OF A PWR NUCLEAR POWER PLANT USING LSTM AUTOENCODERS
Marcelo dos Santos (UFRJ - Universidade Federal do Rio de Janeiro) ; Claudio Pereira (, UFRJ - Universidade Federal do Rio de Janeiro) ; Roberto Schirru (UFRJ - Universidade Federal do Rio de Janeiro)
| Area: ENFIR Keywords: Nuclear power plant, Nuclear accidents identification, Autoencoder, LSTM | [Paper] |
27-1 - IEAR1 RENEWED PRIMARY SYSTEM PUMP B1B NOZZLES STRESS ANALYSIS
Altair Faloppa (IPEN/CNEN - INSTITUTO DE PESQUISAS ENERGéTICAS E NUCLEARES) ; Gerson Fainer (IPEN/CNEN - INSTITUTO DE PESQUISAS ENERGéTICAS E NUCLEARES) ; Carolina Figueiredo (IPEN/CNEN - INSTITUTO DE PESQUISAS ENERGéTICAS E NUCLEARES) ; Daniel Carvalho (IPEN/CNEN - INSTITUTO DE PESQUISAS ENERGéTICAS E NUCLEARES) ; Miguel Mattar Neto (IPEN/CNEN - INSTITUTO DE PESQUISAS ENERGéTICAS E NUCLEARES)
| Area: ENFIR Keywords: Research Reactor, Primary Pump, Nozzles , Stress Analysis , IEAR1 | [Paper] |
387-1 - INFLUENCE OF EROSION ON THE MECHANICAL PROPERTIES OF INCONEL 718 JOINTS BRAZED WITH BFM NICRP
Renato Rezende () ; Mauricio Neves ()
| Area: ENFIR Keywords: Inconel 718, Joint, Mechanical , Vacuum, Spacer Grid | [Paper] |
376-1 - INITIAL CRITICALITY OF THE NEW CORE WITH PLATE-TYPE-FUEL ELEMENTS OF THE NUCLEAR REACTOR IPENMB-01
Ulysses Bitelli (IPENCNEN - Instituto de Pesquisas Energéticas e Nucleares) ; Hugo Landim (IPENCNEN - Instituto de Pesquisas Energéticas e Nucleares) ; Rogerio Jerez (IPENCNEN - Instituto de Pesquisas Energéticas e Nucleares) ; Reginaldo Gilioli () ; Luis Bocardo ()
| Area: ENFIR Keywords: Prediction, Criticality, Control Rods, Inverse of Multiplication Factor, neutrons | [Paper] |
124-2 - LICENSING APPROACH FOR NUCLEAR-POWERED SUBMARINES LAND SUPPORT FACILITIES
Douglas Baroni (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Sad Borsoi (, IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Miguel Neto (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Patrícia de Oliveira (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Marcos Maturana (IPEN - Instituto de Pesquisas Energéticas e Nucleares)
| Area: ENFIR Keywords: graded approach , nonreactor nuclear facility, nuclear licensing, nuclear submarine land support facility | [Paper] |
375-1 - LONG-TERM CORROSION KINETICS IN PRESSURIZED WATER LOOP OF AN ACCIDENT TOLERANT FUEL CLADDING CANDIDATE: AISI 348 STAINLESS STEEL
Vanessa Silva (AMAZUL - Amazônia Azul Tecnologias de Defesa S.A.) ; Tiago Turcarelli (AMAZUL - Amazônia Azul Tecnologias de Defesa S.A.) ; Fábio de Camargo (AMAZUL - Amazônia Azul Tecnologias de Defesa S.A.)
| Area: ENFIR Keywords: Accident tolerant fuel cladding, AISI 348 SS, Long-term corrosion , Oxidation kinetic, Solid state diffusion model | [Paper] |
367-1 - LONG TERM COMPARISON BETWEEN REPROCESSED NUCLEAR FUEL CYCLES
Fidellis Estanislau (UFMG - Universidade Federal de Minas Gerais) ; Carlos Velasquez (UFMG - Universidade Federal de Minas Gerais) ; Antonella Costa (UFMG - Universidade Federal de Minas Gerais) ; Claubia Pereira (UFMG - Universidade Federal de Minas Gerais)
| Area: ENFIR Keywords: comparision, MOX, reprocessed nuclear fuel cycles, transuranic | [Paper] |
428-1 - MACROSCOPIC CROSS SECTION GENERATION USING WIMS-ANL/ PARCS 2.4 CODES –-COMPARISON WITH BEAVRS-PWR
Wilmer Coloma (UFMG - MG) ; Patrícia A. Reis (UFMG - MG) ; Clarysson da Silva (UFMG - MG) ; Claubia Pereira (UFMG - MG)
| Area: ENFIR Keywords: Macroscopic Cross Section , WIMS-ANL/ Parcs 2.4 , BEAVRS, PWR | [Paper] |
396-1 - MICRO REACTORS FOR ELECTRICITY GENERATION IN THE 20 KW TO 2 MW RANGE
João Moreira (UFABC - Universidade Federal do ABC) ; Pedro Rossi (UFABC - Universidade Federal do ABC) ; Adolfo Braid ()
| Area: ENFIR Keywords: Micro reactor, heat pipe, fast reactor | [Paper] |
409-1 - MODELLING AND SIMULATION OF DCMD SHELL AND HOLLOW FIBRE MODULE FOR SEAWATER DESALINATION
Paulo Augusto de Sampaio (IEN - Instituto de Engenharia Nuclear)
| Area: ENFIR Keywords: Seawater Desalination, Membrane Distillation, DCMD | [Paper] |
79-1 - MOLTEN SALT REACTOR THERMAL-FLUID DYNAMICS EVALUATION USING A CFD CODE FOR A THEORETICAL POWER DENSITY
Deiglys Monteiro (UNINOVE - Universidade Nove de Julho) ; Letícia Gonçalvez () ; José Maiorino () ; Pedro Rossi ()
| Area: ENFIR Keywords: Molten salt, CFD, Thermal-fluid dynamics, properties | [Paper] |
167-1 - NEUTRONIC ANALYSIS FOR USING ACID BORIC AS A STABILIZER OF REACTIVITY FEEDBACKS IN AN AQUEOUS HOMOGENEOUS SUBCRITICAL SYSTEM
Livan Hernández Pardo (INSTEC - Instituto Superior de Tecnologías y Ciencias Aplicadas) ; Daylen Milian Pérez () ; Daniel Milian Pérez () ; Daniel Milian Lorenzo (INSTEC - Instituto Superior de Tecnologías y Ciencias Aplicadas) ; Carlos Brayner de Oliveira Lira ()
| Area: ENFIR Keywords: subcritical system, uranyl sulfate solution, boric acid, reactivity coefficient, Serpent 2 | [Paper] |
53-1 - NEUTRONIC ANALYSIS OF AN AQUEOUS HOMOGENEOUS REACTOR FOR 99MO ISOTOPE PRODUCTION BASED ON AN AQUEOUS THORIUM SULFATE SOLUTION
Daniel Milian Pérez (UFPE - Universidade Federal de Pernambuco) ; Daylen Milian Pérez () ; Liván Hernández Pardo () ; Daniel Milian Lorenzo () ; Abel Gámez Rodríguez (UFPE - Universidade Federal de Pernambuco) ; Carlos Brayner de Oliveira Lira () ; Antonio Celso Dantas Antonino (UFPE - Universidade Federal de Pernambuco)
| Area: ENFIR Keywords: 99Mo production, Aqueous Homogeneous Reactor, Thorium fuel, MCNP, fuel solution | [Paper] |
455-1 - NEUTRONIC AND TRANSMUTATION ANALYSIS FOR DIFFERENT FUEL MATRICES IN ADS
Márcia Saturnino (UFMG - MG)
| Area: ENFIR Keywords: Accelerator Driven System, transmutation, multiplication factor, criticality, reprocessed fuel | [Paper] |
109-1 - NEUTRONIC COMPARISON OF TRADITIONAL FUEL ASSEMBLIES USING UO2 (URANIUM DIOXIDE) AND UN (URANIUM MONONITRIDE) FUEL IN THE SCALE 6.0 (NEWT) CODE.
Raphael Henrique Silva (UFMG - MG)
| Area: ENFIR Keywords: fuels assemblies , URANIUM DIOXIDE , URANIUM MONONITRIDE | [Paper] |
184-1 - NEUTRONIC EVALUATION OF TH AS ABSORBER ON REPROCESSED FUEL BUNDLES ON DUPIC FUEL CYCLE
Michel Almeida (UFMG - Universidade Federal de Minas Gerais) ; Rochkhudson Faria () ; Clarysson Silva (UFMG - Universidade Federal de Minas Gerais) ; Cláubia Pereira (UFMG - Universidade Federal de Minas Gerais)
| Area: ENFIR Keywords: CANDU, DUPIC, Thorium, Fuel cycles, Reprocessed fuel | [Paper] |
136-1 - NEUTRONIC SIMULATION OF A SMR USING OPENMC CODE
Marco Lima (IEN - Instituto de Engenharia Nuclear)
| Area: ENFIR Keywords: OpenMC, Simulation, SMR | [Paper] |
32-1 - NUCLEAR APPLICATION FOR ECONOMIC SPACE EXPLORATION
Lamartine Guimarães (IEAV - Instituto de Estudos Avançados)
| Area: ENFIR Keywords: Nuclear Space application, Nuclear space propulsion, NTP, NEP, Economics of space exploration | [Paper] |
281-4 - NUMERICAL ANALYSIS OF THE SMALL PUNCH TEST FOR DIFFERENT THEORETICAL MATERIALS
Letícia Pereira (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Miguel Mattar Neto (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Carlos A. Miranda (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; José Lima (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Altair Faloppa (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Arnaldo Andrade (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Mariano Castagnet (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Raquel Lobo (IPEN - Instituto de Pesquisas Energéticas e Nucleares)
| Area: ENFIR Keywords: Small Punch Test, Mesh evaluation, Modelling options, Friction coefficient , HHollomon parameters | [Paper] |
544-1 - NYSTRÖM METHOD APPLIED TO THE NON-HOMOGENEOUS TRANSPORT EQUATION
Luana Lazzari () ; Esequia Sauter () ; Fábio de Azevedo ()
| Area: ENFIR Keywords: Non-homogeneous domain, Nyström method, Transport equation | [Paper] |
78-1 - ONE-GROUP CROSS SECTIONS FOR TH-232, U-233, U-238, U-235 AND PU-239 ISOTOPES AVERAGED OVER OPAL AND TERRA NEUTRON SPECTRA
Renato Silva (ITA - Instituto Tecnológico de Aeronáutica) ; Lamartine Guimarães (ITA - Instituto Tecnológico de Aeronáutica) ; Alexandre Caldeira ()
| Area: ENFIR Keywords: One-group, nuclear data, OPAL, TERRA, Neutron Spectra | [Paper] |
280-1 - ONLINE MONITORING SYSTEM FOR WATER CHEMISTRY IN THE PRIMARY COOLANT CIRCUIT OF TRIGA REACTOR
Vitor Almeida (CDTN - Centro de Desenvolvimento da Tecnologia Nuclear) ; Amir Mesquita (CDTN - Centro de Desenvolvimento da Tecnologia Nuclear) ; Valéria Alcântara E Alves (CDTN - Centro de Desenvolvimento da Tecnologia Nuclear)
| Area: ENFIR Keywords: Online Monitoring System, Primary Coolant Circuit, Water Chemistry, IPR-R1 TRIGA Mark I , Nuclear Research Reactor | [Paper] |
563-1 - ONLINE NEUTRON TRANSPORT PROBLEM SOLVER TOOL
Iram B. Rivas Ortiz (IPRJ - Instituto Politécnico - Universidade do Estado do Rio de Janeiro) ; Dany Sanchez Dominguez () ; Jesus Pérez Curbelo (IPRJ - Instituto Politécnico - Universidade do Estado do Rio de Janeiro) ; Joel Sanchez Dominguez (IPRJ - Instituto Politécnico - Universidade do Estado do Rio de Janeiro) ; Carlos Rafael García Hernández () ; Ricardo Barros (IPRJ - Instituto Politécnico - Universidade do Estado do Rio de Janeiro)
| Area: ENFIR Keywords: neutron transport equation, discrete ordinate approximation, 2D fixed source problems, web application, online simulation tool | [Paper] |
398-1 - ON THE COMMERCIAL FEASIBILITY OF DECOMMISSIONING A NUCLEAR POWER PLANT SHIP
Adalberto Sobreiro (IPEN - Instituto de Pesquisas Energéticas Nucleares)
| Area: ENFIR Keywords: decommissioning, cost, economy, mobile nuclear plant | [Paper] |
187-3 - OPTIMIZATION OF A MICROREACTOR CORE’S DIMENSIONS USING METAHEURISTIC METHODS
Nicolas Santana (IEAV - Instituto de Estudos Avançados) ; Angelo Passaro (IEAV - Instituto de Estudos Avançados) ; Alexandre Caldeira (IEAV - Instituto de Estudos Avançados) ; Lamartine Guimarães (IEAV - Instituto de Estudos Avançados)
| Area: ENFIR Keywords: Multigroup Diffusion, Core optimization, Microreactor, LOF, metaheuristics | [Paper] |
187-1 - OPTIMIZATION OF A MICROREACTOR CORE’S DIMENSIONS USING METAHEURISTIC METHODS
Nicolas Santana (IEAV - Instituto de Estudos Avançados) ; Angelo Passaro (IEAV - Instituto de Estudos Avançados) ; Alexandre Caldeira (IEAV - Instituto de Estudos Avançados) ; Lamartine Guimarães (IEAV - Instituto de Estudos Avançados)
| Area: ENFIR Keywords: Multigroup Diffusion, Optimization, Microreactor, LOF, metaheuristics | [Paper] |
484-1 - OPTIMIZATION OF ANALYSIS METHODOLOGY IN THE DETERMINATION OF CD, IN AND IMPURITIES IN NUCLEAR GRADE SILVER-INDIUM-CADMIUM ALLOYS
Luís Oliveira (CINA - CENTRO INDUSTRIAL NUCLEAR DE ARAMAR) ; Iêda Silva (CINA - CENTRO INDUSTRIAL NUCLEAR DE ARAMAR) ; Elaine Pereira (CINA - CENTRO INDUSTRIAL NUCLEAR DE ARAMAR) ; Érica Santana (CINA - CENTRO INDUSTRIAL NUCLEAR DE ARAMAR) ; Leonardo Iwaki (CINA - CENTRO INDUSTRIAL NUCLEAR DE ARAMAR) ; José Lopes (CINA - CENTRO INDUSTRIAL NUCLEAR DE ARAMAR) ; Guilherme de Oliveira (CINA - CENTRO INDUSTRIAL NUCLEAR DE ARAMAR)
| Area: ENFIR Keywords: Absorber, AgInCd, Control Rod, ICP OES, Spectroscopy | [Paper] |
239-1 - OPTIMIZATION OF PWR NUCLEAR REACTOR RELOAD PROBLEM UTILIZING PARALLELED STRUCTURED PBIL
Flavio Gomes de Castro E Silva ()
| Area: ENFIR Keywords: Nuclear Reactor, Optimization Problem, Reload | [Paper] |
145-1 - OVERVIEW AND CURRENT PERSPECTIVES FOR THE USE OF THE GFR REACTOR IN RESEARCH AND ELECTRICITY GENERATION IN BRAZIL.
Fernando Romano (IPEN - Instituto de Pesquisas Energéticas e Nucleares)
| Area: ENFIR Keywords: GFR, IV Generation, ALLEGRO, GIF, Gas cooled reactors | [Paper] |
519-1 - PARAMETRIC STUDY OF THE HETEROGENEOUS ASSEMBLY WITH THORIUMAPPLIED TO NUSCALE
Diego Manoel Gonçalves (COPPE-UFRJ - UFRJ) ; Giovanni de Stefani (COPPE-UFRJ - UFRJ)
| Area: ENFIR Keywords: Thorium, nuclear fuel , reactors, SMR | [Paper] |
519-3 - PARAMETRIC STUDY OF THE HETEROGENEOUS ASSEMBLY WITH THORIUM APPLIED TO NUSCALE
Diego Manoel Gonçalves () ; Giovanni de Stefani ()
| Area: ENFIR Keywords: Thorium, nuclear fuel , reactors, SMR | [Paper] |
519-2 - PARAMETRIC STUDY OF THE HETEROGENEOUS ASSEMBLY WITH THORIUMAPPLIED TO NUSCALE.
Diego Manoel Gonçalves (COPPE-UFRJ - UFRJ)
| Area: ENFIR Keywords: Thorium, nuclear fuel , reactors, SMR | [Paper] |
381-1 - PASSIVE AUTOCATALYTIC RECOMBINER PERFOMANCE ASSESSMENT USING COCOSYS CODE
Hugo Galvao ((IPEN) - Instituto de Pesquisas Energéticas e Nucleares)
| Area: ENFIR Keywords: COCOSYS V2.4, HR-14 experiment, Passive Autocatalytic Recombiners (PAR), Severe Accident (SA) | [Paper] |
21-3 - PN SYNTHETIC ACCELERATION FOR THE SOURCE ITERATION SCHEME IN SLAB-GEOMETRY DISCRETE ORDINATES TRANSPORT CALCULATIONS
Alan Silva (IPRJ/UERJ - UNIVERSIDADE DO ESTADO DO RIO DE JANEIRO) ; Lisa Enomoto (IPRJ/UERJ - UNIVERSIDADE DO ESTADO DO RIO DE JANEIRO) ; Ricardo Barros (IPRJ/UERJ - UNIVERSIDADE DO ESTADO DO RIO DE JANEIRO)
| Area: ENFIR Keywords: Pn theory, Fixed-source problems, Acceleration of iterative scheme, Slab geometry, Discrete Ordinates (Sn) | [Paper] |
157-1 - PREDICTION OF FAILURES IN ROTATING MACHINES BY VIBRATION SPECTRAL ANALYSIS
Pedro Poveda (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Roberto de Mesquita (IPEN - Instituto de Pesquisas Energéticas e Nucleares)
| Area: ENFIR Keywords: Monitoring and diagnostics, prediction of failures , predictive maintenance, vibration spectral analysis, signal acquisition and processing | [Paper] |
446-1 - PRELIMINARY RESULTS OF MONTE CARLO STUDY OF AN EXPERIMENT TO CALCULATE THERMAL NEUTRON CROSS SECTION USING NEUTRON BEAM FROM THE IEA-R1 REACTOR.
Eduardo - (IPEN - Instituto de Pesquisas Energéticas e Nucleares)
| Area: ENFIR Keywords: Thermal Neutron Cross Section, Simulation, Geant4, IEA-R1, Neutron Activation Analysis | [Paper] |
550-1 - PRIMARY CIRCUIT COOLANT ACTIVATION PRODUCTS DISTRIBUTION IN A SMALL MODULAR REACTOR
Thiago Carluccio (DDNM - Diretoria de desenvolvimento nuclear da marinha) ; Gregorio Souza (DDNM - Diretoria de desenvolvimento nuclear da marinha) ; Priscila Sanchez (DDNM - Diretoria de desenvolvimento nuclear da marinha) ; Pamela Piovezan (DDNM - Diretoria de desenvolvimento nuclear da marinha)
| Area: ENFIR Keywords: water activation, reactor coolant, shielding design | [Paper] |
257-1 - PROBLEMS IN APPLICATION OF LEVEL 2 PROBABILISTIC SAFETY ASSESSMENT FOR NPP IN BRAZIL
Maritza R. Gual (USP - Universidade de São Paulo) ; Marcos C. Maturana (USP - Universidade de São Paulo) ; Nathália N. Araújo (USP - Universidade de São Paulo) ; Hugo da Costa Romberg Júnior (USP - Universidade de São Paulo)
| Area: ENFIR Keywords: PSA, Level 2, NPP | [Paper] |
73-1 - PROGRESS OF IN-CORE FUEL MANAGEMENT SYSTEM FOR PWR REACTORS: USE OF MACROSCOPIC CROSS SECTIONS GENERATED BY SCALE 6.0 IN A DEVELOPED NODAL CODE
Pedro Rodrigues (UFABC - Universidade Federal do ABC) ; José Maiorino (UFABC - Universidade Federal do ABC) ; Roberto Asano Junior (UFABC - Universidade Federal do ABC) ; Patrícia Asano (UFABC - Universidade Federal do ABC)
| Area: ENFIR Keywords: PWR, benchmark, SCALE, in-core fuel management, Nodal Expansion Method | [Paper] |
371-1 - PROPOSAL FOR THERMAL STUDY OF A HIGH TEMPERATURE REACTOR USING A COMPUTATIONAL FLUID DYNAMIC TOOL
Junio de Souza () ; Antonella Costa () ; André dos Santos () ; Mário Ramos ()
| Area: ENFIR Keywords: Thermal Study, Computational Fluid Dynamic, HTR-10, Pebble Bed, Triso | [Paper] |
466-1 - PROPOSED RESOLUTION OF THE IEA-R1 REACTOR RECHARGE OPTIMIZATION PROBLEM USING THE PARTICLE SWARM OPTIMIZATION METHOD
Thiago Augusto Santos (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Giovanni de Stefani () ; Frederico Genezini (IPEN - Instituto de Pesquisas Energéticas e Nucleares)
| Area: ENFIR Keywords: Optimization, PSO, Research Reactor | [Paper] |
248-1 - PSO-BASED MODELING PARTICULATE EMISSION RATES IN NUCLEAR ACCIDENTS
Douglas Brasil (UFRJ/COPPE - Federal University of Rio de Janeiro) ; Andressa Nicolau (UFRJ/COPPE - Federal University of Rio de Janeiro) ; Roberto Schirru (UFRJ/COPPE - Federal University of Rio de Janeiro) ; Claudio Pereira (UFRJ/COPPE - Federal University of Rio de Janeiro)
| Area: ENFIR Keywords: Particle Swarm optimization, Nuclear power plants , Radiological emergency | [Paper] |
254-2 - PSO PLANT
Eduardo Souto (UFRJ - Federal University of Rio de Janeiro)
| Area: ENFIR Keywords: URANIUM HEXAFLUORIDE, SAFETY, PHA, NUCLEAR | [Paper] |
203-1 - PYTHON TOOL FOR PARAMETRIC MODELING AND SIMULATION OF A GENERIC SMR REACTOR CORE WITH THORIUM-URANIUM FUEL.
Salah Eddine Bentridi (UDBKM - UNiversity of Khemis Miliana) ; Hakim Bouzoudar () ; Hossam Makhloufi () ; Imene Guellou () ; Naima Amrani () ; Djelloul Benzaid (UDBKM - UNiversity of Khemis Miliana)
| Area: ENFIR Keywords: Thorium, Python, SMR, Modeling, Simulation | [Paper] |
558-1 - QUALIFICATION OF SYSTEM CODE AC2/ATHLET FOR NEW BUILTS
Thorsten Hollands (GRS - Gesellschaft fuer Anlagen- und Reaktorsicherheit)
| Area: ENFIR Keywords: Qualification, Validation, AC2/ATHLET, New Builts | [Paper] |
161-1 - RADIATION SHIELDING FOR A NUCLEAR FUSION DEVICE WITH INERTIAL ELECTROSTATIC CONFINEMENT
Seung Min Lee (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Eduardo Cabral (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Helio Yoriyaz (IPEN - Instituto de Pesquisas Energéticas e Nucleares)
| Area: ENFIR Keywords: IECF, MCNP, Nuclear Fusion, Radiation Shielding, Neutron interaction | [Paper] |
451-1 - REACTORS FUEL ENRICHMENT PROCESS BY RECONVERSION OF UO2 TO UF6.
Adalberto Gonçalves (UFRJ - Universidade Federal do Rio de Janeiro) ; Giovanni de Stefani (UFRJ - Universidade Federal do Rio de Janeiro)
| Area: ENFIR Keywords: Enrichment Process, Reactors Fuel, Reconversion | [Paper] |
15-1 - RELAP5 CODE SIMULATION OF THE ANGRA2 PRESSURIZER SURGE LINE ACCIDENT
Gaiane Sabundjian (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Rafael Pacheco (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Thadeu Conti (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Andrea Del Pozzo (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Ana Lima (IPEN - Instituto de Pesquisas Energéticas e Nucleares)
| Area: ENFIR Keywords: RELAP5, LOCA, Angra 2 | [Paper] |
162-1 - RELOAD OPTIMIZATION OF NUCLEAR POWER PLANTS USING GA TOTALLY DISCRET TOGETHER WITH THE GENES REACTOR PHYSICS CODE
Alan de Lima (UFRJ - UFRJ) ; Andressa Nicolau (UFRJ - UFRJ) ; Fernando Freire (UFRJ - UFRJ)
| Area: ENFIR Keywords: Genes, Genetic Algorithm Totally Discrete, Nuclear power Plant, Reactor Physics Code, Reload Optimization | [Paper] |
118-1 - RISK-BASED DESIGN OF ELECTRIC POWER SYSTEMS FOR NON-CONVENTIONAL NUCLEAR FACILITIES AT SHUTDOWN MODES
Sad Sandrini Borsoi (USP - UNIVERSITY OF SÃO PAULO) ; Douglas Brandão Baroni () ; Miguel Mattar Neto () ; Patrícia da Silva Pagetti de Oliveira () ; Marcos Coelho Maturana ()
| Area: ENFIR Keywords: Core Damage Frequency, Electric Power Systems, Non-Conventional Nuclear Facilities, Safety Probabilistic Analysis, Station Blackout | [Paper] |
396-4 - ROBOTIC SYSTEM FOR PIPE WALL THICKNESS INSPECTION FOR THE LONG-TERM OPERATION OF ANGRA 1
Rogério Vitalli (UFABC - Universidade Federal do ABC) ; João Moreira (UFABC - Universidade Federal do ABC)
| Area: ENFIR Keywords: robotics, long term operation, pipe inspection , wall thickness | [Paper] |
163-1 - SCREENING AND SELECTION OF STRUCTURES, SYSTEMS AND COMPONENTS TO BE CONSIDERED IN AGEING MANAGEMENT AND PERIODIC SAFETY REVIEW OF THE TRIGA IPR-R1 REACTOR
Keferson Carvalho (CDTN - Centro de Desenvolvimento da Tecnologia Nuclear) ; Graiciany Barros (CDTN - Centro de Desenvolvimento da Tecnologia Nuclear) ; Emanuela Lemos (CDTN - Centro de Desenvolvimento da Tecnologia Nuclear) ; Vanderley Vasconcelos (CDTN - Centro de Desenvolvimento da Tecnologia Nuclear) ; Andre Santos (CDTN - Centro de Desenvolvimento da Tecnologia Nuclear)
| Area: ENFIR Keywords: Ageing Management , Cooling System, SSC selection, TRIGA IPR-R1 | [Paper] |
210-2 - SIMULATION OF AN ELECTRIC POWER SYSTEM BASED ON KILOPOWER PROJECT
Patryck Ferreira (, IEAV - Instituto de Estudos Avançados) ; Lamartine Guimarães (IEAV - Instituto de Estudos Avançados)
| Area: ENFIR Keywords: Kilopower, Heat transfer, Stirling Machine, Heat Pipe, Microrreactors | [Paper] |
79-3 - SIMULATION OF PSBT EXPERIMENT SUBCHANNELS S1 TO S4 USING A CFD CODE AND COMPARISON WITH THE EXPERIMENTAL RESULTS
Deiglys Monteiro (UNINOVE - Universidade Nove de Julho) ; José Maiorino ()
| Area: ENFIR Keywords: CFD, Cooling, Phenomena, Reactor, Subchannel | [Paper] |
79-2 - SIMULATION OF STEAD-STATE AND TRANSIENT OF SLOW LOSS OF COOLING ACCIDENT OF A CHANNEL IN A PLATE TYPE FUEL ELEMENT REACTOR
Deiglys Monteiro (UNINOVE - Universidade Nove de Julho) ; José Maiorino ()
| Area: ENFIR Keywords: CFD, Cooling, Phenomena, Reactor, Transient | [Paper] |
272-1 - SIMULATION OF TRANSIENTS IN A SUB-CRITICAL HETEROGENEOUS SYSTEM IN THREE-DIMENSIONAL GEOMETRY
José Carneiro () ; Alessandro Gonçalves () ; Zelmo de Lima (IEN - Instituto de Engenharia Nuclear)
| Area: ENFIR Keywords: ADS, Spatial kinetic, Transient | [Paper] |
200-1 - SIMULATION OF VIRTUAL RADIATION DETECTORS IN NUCLEAR POWER PLANTS TO SUPPORT EQUIPMENT AGEING STUDIES BASED ON PARTICLE SWARM OPTIMIZATION
Fernando Henrique Cardozo (UFRJ - Universidade Federal do Rio de Janeiro) ; Andressa Nicolau (UFRJ - Universidade Federal do Rio de Janeiro) ; Roberto Schirru (UFRJ - Universidade Federal do Rio de Janeiro) ; Marcos Silva ()
| Area: ENFIR Keywords: Environmental Qualification Program, Long Therm Operation, Nuclear Power Plant, PSO, Radiation | [Paper] |
281-2 - SMALL PUNCH TEST DEVICES IN DEVELOPMENT AT IPEN AIMING TO PERFORM TESTS IN RMB HOT CELLS
Carlos A. Miranda (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; José Lima (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Altair Faloppa (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Arnaldo Andrade (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Miguel Mattar Neto (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Mariano Castagnet (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Raquel Lobo (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Letícia Pereira (IPEN - Instituto de Pesquisas Energéticas e Nucleares)
| Area: ENFIR Keywords: Small Punch Test, Empirical correlations, Hot Cells , Surface roughness, Tensile properties | [Paper] |
281-3 - SMALL PUNCH TESTS WITH A RECENTLY DEVELOPED DEVICE IN IPEN: FIRST RESULTS AND FUTURE PROGRAM AT LOW TEMPERATURES
Carlos A. Miranda (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Arnaldo Andrade (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Mariano Castagnet (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Raquel Lobo (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Altair Faloppa (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Miguel Mattar Neto (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; José Rodrigues (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Letícia Pereira (IPEN - Instituto de Pesquisas Energéticas e Nucleares)
| Area: ENFIR Keywords: Small Punch Test, Fracture toughness, Surface roughness, Planned activities, Numerical simulations | [Paper] |
438-1 - STEADY STATE STUDIES ON ACCIDENT TOLERANT FUELS FOR PRESSURIZED WATER REACTOR
Patricia Reis (UFMG - Universidade Federal de Minas Gerais)
| Area: ENFIR Keywords: ATF, Safety Anaysis, Nuclear Reactor, RELAP5 code | [Paper] |
110-2 - SYSTEM FOR MONITORING CYCLOTRON CV-28 SAFETY PARAMETERS
Marcos Farias (IEN - Instituto de Engenharia Nuclear) ; Guilherme Jaime (IEN - Instituto de Engenharia Nuclear) ; Fabio de Lacerda (IEN - Instituto de Engenharia Nuclear) ; Silas Augusto (IEN - Instituto de Engenharia Nuclear)
| Area: ENFIR Keywords: human factor requirements , Ergonomics, safety parameters monitoring | [Paper] |
337-1 - THE EFFECT OF HOST ROCK TEMPERATURE ON SPENT NUCLEAR FUEL DISPOSAL DENSITY
Raoni Adão Salviano Jonusan (UFMG - Universidade Federal de Minas Gerais) ; Fernando Pereira de Faria (UFMG - Universidade Federal de Minas Gerais) ; Antonella Lombardi Costa (UFMG - Universidade Federal de Minas Gerais) ; Claubia Pereira Bezerra Lima (UFMG - Universidade Federal de Minas Gerais)
| Area: ENFIR Keywords: Spent Nuclear Fuel, Disposal Density, Host Rock Temperature | [Paper] |
22-1 - THE EFFECT OF MASS SCALING AND SPEED INCREASE IN EXPLICIT DYNAMIC SIMULATIONS USING TENSILE TEST
Letícia Pereira (IPEN - Instituto de Pesquisas Energéticas Nucleares) ; Gustavo Donato () ; Miguel Mattar Neto (IPEN - Instituto de Pesquisas Energéticas Nucleares)
| Area: ENFIR Keywords: energy, mass scaling, speed, stress, tensile test | [Paper] |
150-1 - THE FECRAL CLADDING ASSESSMENT UNDER ACCIDENT CONDITION USING TRANSURANUS FUEL PERFORMANCE CODE
Alfredo Abe (IPEN - IPEN/CNEN-SP) ; Caio Melo () ; Tamirys Santos () ; Claudia Giovedi ()
| Area: ENFIR Keywords: Fuel, Performance, ATF, TRANSURANUS, FeCrAl | [Paper] |
268-1 - THE NEED FOR THE EVOLUTION OF THE NUCLEAR EMERGENCY RESPONSE PLAN USING MECHANISMS OF LEARNING, INNOVATION AND COMMUNICATION
André Luiz Lopes Quadros (CNEN - Comissão Nacional de Energia Nuclear) ; Alexandre Gromann de Araújo Góes (CNEN - Comissão Nacional de Energia Nuclear)
| Area: ENFIR Keywords: emergency planning , emergency preparedness and response, innovation, organizational learning, risk communication | [Paper] |
432-1 - THE RADIOACTIVE PARTICLE TRACKING TECHNIQUE FOR VALIDATION OF CFD SIMULATIONS IN SMR DESIGNS
Wilson Vieira (IEN - Nuclear Engineering Institute) ; Jonathan de Melo (IEN - Nuclear Engineering Institute) ; Celso Lapa (IEN - Nuclear Engineering Institute)
| Area: ENFIR Keywords: SMR, CFD SIMULATIONN, VALIDATION, RADIOACTIVE PARTiCLE TRACKING | [Paper] |
435-1 - THERMAL STUDY OF THE MODULAR HIGH-TEMPERATURE GAS-COOLED REACTOR
Mario Ramos (UFMG - Universidade Federal de Minas Gerais) ; Antonella Costa (UFMG - Universidade Federal de Minas Gerais) ; Vitor Silva () ; Claubia Pereira (UFMG - Universidade Federal de Minas Gerais) ; Maria Veloso (UFMG - Universidade Federal de Minas Gerais)
| Area: ENFIR Keywords: MHTGR, RELAP5, Thermal Analysis, GEN-IV, Nuclear Energy | [Paper] |
461-1 - THERMAL STUDY OF THE MODULAR HIGH-TEMPERATURE GAS-COOLED REACTOR
Mario Cerrogrande Ramos (UFMG - universidade federal de minas gerais) ; Antonella Costa (UFMG - universidade federal de minas gerais) ; Vitor Vasconcelos () ; Claubia Pereira (UFMG - universidade federal de minas gerais) ; Maria Auxiliadora Veloso (UFMG - universidade federal de minas gerais)
| Area: ENFIR Keywords: GT-MHR, RELAP5-3D, TRISO | [Paper] |
461-2 - THERMAL STUDY OF THE MODULAR HIGH-TEMPERATURE GAS-COOLED REACTOR_NOVO
Mario Cerrogrande Ramos (UFMG - universidade federal de minas gerais) ; Antonella Lombardi Costa (UFMG - universidade federal de minas gerais) ; Vitor Vasconselo Silva (UFMG - universidade federal de minas gerais) ; Claubia Pereira (UFMG - universidade federal de minas gerais) ; M. A. Veloso (UFMG - universidade federal de minas gerais)
| Area: ENFIR Keywords: RELAP5, TRISO, GT-MHR | [Paper] |
81-1 - THERMOHYDRAULIC ANALYSIS OF THE COOLANT ENTRANCE INTO THE CORE OF PEBBLE BED GAS-COOLED REACTOR.
Abel Gámez Rodríguez (CRCN-NE - Centro Regional de Ciências Nucleares do Nordeste) ; Daniel Milian Pérez () ; Carlos Brayner de Oliveira Lira (CRCN-NE - Centro Regional de Ciências Nucleares do Nordeste)
| Area: ENFIR Keywords: Thermohydraulic analysis , HTR, CFD, Porous media | [Paper] |
399-1 - USE OF PSA DATA FOR THE PERFORMANCE SPECIFICATION OF SAFETY CONTROL SYSTEMS IN NUCLEAR POWER PLANTS
Fernando Schweizer (DDNM - Diretoria de Desenvolvimento Nuclear da Marinha) ; Bruno Warth (DDNM - Diretoria de Desenvolvimento Nuclear da Marinha) ; Marcos Coelho Maturana Maturana (DDNM - Diretoria de Desenvolvimento Nuclear da Marinha)
| Area: ENFIR Keywords: Nuclear Power Plant Design, Probabilistic Safety Assessment, Reliability Analysis | [Paper] |
71-1 - VALIDATION OF A COMPUTACIONAL MODEL OF A NUCLEAR FUEL ASSEMBLY BOTTOM NOZZLE
André Lotto (MARINHA - Marinha do Brasil)
| Area: ENFIR Keywords: Bottom Nozzle, Finite Element, Computacional model | [Paper] |
337-2 - VERIFICATION OF HEAT TRANSFER RESULTS FROM A SPENT FUEL REPOSITORY USING AN ANALYTICAL LINE HEAT SOURCE MODEL
Víctor Faria de Castro (UFMG - Universidade Federal de Minas Gerais) ; Raoni Adão Salviano Jonusan (UFMG - Universidade Federal de Minas Gerais) ; Fernando Pereira de Faria (UFMG - Universidade Federal de Minas Gerais) ; Antonella Lombardi Costa (UFMG - Universidade Federal de Minas Gerais) ; Claubia Pereira Bezerra Lima (UFMG - Universidade Federal de Minas Gerais)
| Area: ENFIR Keywords: Heat Transfer, Analytical Line Heat Source Model, Spent Fuel Repository, Verification | [Paper] |
74-1 - VERY HIGH TEMPERATURE REACTOR (VHTR) – A PROPOSAL TO GENERATION IV REACTORS
Madison Almeida (CNEN - Comissão Nacional de Energia Nuclear) ; Claudia Paixão () ; Juliana Arquinto () ; Paloma Kotani () ; Thayna Marinho () ; Vanessa Alonso () ; Delvonei Andrade ()
| Area: ENFIR Keywords: Generation IV, High Temperature, VHTR | [Paper] |
342-1 - VIABILITY ANALYSIS OF EMPLOYING ULTRASOUND TECHNIQUE FOR BORIC ACID CONCENTRATION MEASUREMENT IN LIQUID MEDIUM
Thiago Roberto () ; Celso Lapa () ; Marcelo Bittencourt () ; Richard Kohara () ; Mário Silva ()
| Area: ENFIR Keywords: Ultrasound Technical Analysis, Pulse-echo concentration of boric acid, path times | [Paper] |
439-1 - WATER BOILING TIME IN A SPENT FUEL POOL WITH ADIABATIC AND NON-ADIABATIC BOUNDARY CONDITIONS
Fernando de Faria (UFMG - Universidade Federal de Minas Gerais) ; Dario Godino () ; Santiago Corzo () ; Damián Ramajo () ; Antonella Costa (UFMG - Universidade Federal de Minas Gerais) ; Claubia Pereira (UFMG - Universidade Federal de Minas Gerais)
| Area: ENFIR Keywords: Spent Fuel, Spent Fuel Pool, Ansys, OpenFoam, Water boiling time | [Paper] |
120-1 - WHOLE BODY DOSE DUE TO STATION BLACKOUT AT ANGRA 2 NUCLEAR POWER PLANT.
Andre Aguiar (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Seung Lee (IPEN - Instituto de Pesquisas Energéticas e Nucleares) ; Gaiane Sabundjian (IPEN - Instituto de Pesquisas Energéticas e Nucleares)
| Area: ENFIR Keywords: Angra 2, wind field , radionuclides transport, • General Emergency, EPZ | [Paper] |