A5091448016- Nuclear reactor physics and engineering
- Nuclear Engineering Thermal-Hydraulics
- Nuclear Physics and Applications
- Probabilistic and Robust Engineering Design
- Graphite, nuclear technology, radiation studies
- Nuclear Materials and Properties
- Risk and Safety Analysis
- Nuclear and radioactivity studies
- Reliability and Maintenance Optimization
- Magnetic confinement fusion research
- Fractional Differential Equations Solutions
- Statistical Distribution Estimation and Applications
- Heat transfer and supercritical fluids
- Water Systems and Optimization
- Software Reliability and Analysis Research
- Field-Flow Fractionation Techniques
- Risk Perception and Management
- Fluid Dynamics and Mixing
- Fluid Dynamics and Turbulent Flows
- Thermochemical Biomass Conversion Processes
- Thermodynamic and Structural Properties of Metals and Alloys
- Infrastructure Resilience and Vulnerability Analysis
- Thermoelastic and Magnetoelastic Phenomena
- Cavitation Phenomena in Pumps
- Safety Systems Engineering in Autonomy
Universidade Federal do Rio de Janeiro
2013-2024
Federal Center for Technological Education of Minas Gerais
2006
Federal Office for Radiation Protection
2001
National Nuclear Energy Commission
1987-1989
Deep and stable geological formations with low permeability have been considered for high level waste definitive repository. A common problem is the modeling of radionuclide migration in a fractured medium. Initially, we system consisting rock matrix single planar fracture water saturated porous rock. Transport assumed to obey an advection-diffusion equation, while molecular diffusion dominant mechanism transport matrix. The partial differential equations describing movement radionuclides...
An analytical solution of the point kinetics equations to calculate time-dependent reactivity by decomposition method has recently appeared in literature. In this paper, we consider neutron together with temperature feedback effects. To end, is perturbed a equation that depends on density, obtaining second-order non-linear ordinary differential equation. This then solved expanding density series and expressing terms Adomian polynomials. Upon substituting these expansions into equation,...
This paper deals with an alternative numerical method for calculating depletion and production chains of the main isotopes found in a pressurized water reactor. It is based on use exponentiation procedure coupled to orthogonal polynomial expansion compute transition matrix associated solution differential equations describing isotope concentrations nuclear Actually, was implemented automated reactor core design system that uses quick accurate 3D nodal method, Nodal Expansion Method (NEM),...
This paper aims at performing a human reliability analysis using THERP (Technique for Human Error Prediction) and ATHEANA Analysis) to develop qualitative quantitative of the latent operator error in leaving EFW (emergency feed-water) valves closed TMI-2 accident. The accident has revealed series unsafe actions that resulted permanent loss unit. integration between is developed way such as allow better understanding influence operational context on errors. provides also, result, an...
The aim of this paper is to create a panel comparing some the key decision-making support tools used in situations with characteristics problem selecting suitable areas for constructing final deep geologic repository. addressed work are also well known and easy implementation. process matters kind is, general, complex due its multicriteria nature conflicting opinions various stakeholders. Thus, comprehensive study was performed literature subject, specifically documents International Atomic...
Reactor cavity cooling systems (RCCSs) ensure the physical integrity of containment structures in a high-temperature gas-cooled test reactor (HTR-10) and pebble-bed module (HTR-PM). HTR-10 is graphite-moderated helium-cooled prototype designed to demonstrate technical feasibility safety design concept under normal accident conditions. This served as proof for HTR-PM that shares several similarities with HTR-10, including requires owing high core outlet temperature. The RCCS conceived both...
This paper develops a finite difference and semianalytical model to evaluate the thermal behavior of fuel rods during hypothetical reactivity-induced transient (absorber rod ejection) in pressurized water reactor (PWR). The calculations are carried out for two different core designs, namely, typical PWR with modified containing annular rods. overall dimensions internals assemblies unchanged, total number is same both designs. code was verified on results provided by model. In calculations,...
This paper aims to determine, for the period of institutional control (300 yr), probability occurrence net release scenario radioactive waste from a near-surface repository. The focused on in this work is that low and medium activity generated by pressurized water reactor plant. repository divided into eight modules, each which consists six barriers (top cover, upper layer, packages, base, walls, geosphere). system where modules series module active parallel. failure elements obtained Markov...