Zelmo Rodrigues de Lima

ORCID: 0000-0003-4474-8056
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About
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Research Areas
  • Nuclear reactor physics and engineering
  • Nuclear Physics and Applications
  • Nuclear Materials and Properties
  • Nuclear Engineering Thermal-Hydraulics
  • Nuclear and radioactivity studies
  • Radioactivity and Radon Measurements
  • Radiation Dose and Imaging
  • Numerical methods in engineering
  • Graphite, nuclear technology, radiation studies
  • Heat transfer and supercritical fluids
  • 3D Modeling in Geospatial Applications
  • Electromagnetic Simulation and Numerical Methods
  • Augmented Reality Applications
  • Advanced Numerical Methods in Computational Mathematics
  • Superconducting Materials and Applications
  • Thermodynamic and Structural Properties of Metals and Alloys
  • Radioactive contamination and transfer
  • NMR spectroscopy and applications

Nuclear Engineering Institute
2012-2024

National Nuclear Energy Commission
2012

Universidade Federal do Rio de Janeiro
2004-2009

Abstract The detonation of an (hypothetical) improvised nuclear device (IND) can generate atmospheric release radioactive material in the form particles and dust that ultimately contaminate soil. In this study, IND urban area was simulated, its effects on humans were determined. risk solid cancer development due to radiation calculated by taking into account prompt whole-body exposure individuals near site up 10 km. excess relative (ERR) developing evaluated using mathematical relationships...

10.2478/nuka-2019-0005 article EN cc-by-nc-nd Nukleonika 2019-04-24

Abstract A release of radioactive material into the environment can lead to hazardous exposure population and serious future concerns about health issues such as an increased incidence cancer. In this context, a practical methodology capable providing useful basic information from scenario be valuable for immediate decisions risk assessment. For work, simulation radiological dispersal device (RDD) filled with americium-241 was considered. The radiation dose simulated by HotSpot code used...

10.2478/nuka-2019-0016 article EN cc-by-nc-nd Nukleonika 2019-12-01

Cross sections are homogenized over an entire node in nodal model implementation. The presence of a control rod (CR) partially inserted the has occasioned axial heterogeneity and generates homogenization problem. If process is only volume-weighted average for nuclear parameters, calculation multiplication factor power steady-state problems may mean relevant errors time-dependent have caused well-known cusping problem, which arises three-dimensional transient simulations with CR motions....

10.13182/nse10-67tn article EN Nuclear Science and Engineering 2012-01-01

The main purpose of this paper is to perform a numerical analysis the Neutron Spatial Kinetic Equations, subject transients External Source, by applying Implicit Euler Method as well Runge-Kutta in order check which methods are best applicable caused Source. For purpose, one-dimensional ADS reactor with constant external source was simulated based on geometry ANL-BSS-6 for benchmark effects.

10.4236/wjnst.2017.72009 article EN World Journal of Nuclear Science and Technology 2017-01-01

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10.2139/ssrn.4777354 preprint EN 2024-01-01

This work uses the numerical method known as Piecewise Constant Approximation, PCA, to solve equations of modified point kinetics for six groups delayed neutron precursors. The corresponds model without considering approximation derivative logarithm current. Applying PCA approximates reactivity function continuous piecewise functions, and resulting system first-order differential can be solved exactly in each time partition. For validation, simulations are carried out cases constant...

10.15392/2319-0612.2024.2588 article EN cc-by Brazilian Journal of Radiation Sciences 2024-12-20

Accelerator-Driven System, ADS, belong to the new generation of advanced reactors being developed that promise drastically reduce life radioactive waste by, for example, transmutation process. Subcritical reactor designs ADS type have attracted worldwide attention and are subject research development in several countries. The purpose this work is simulate transients associated with ADS. It adopted neutron diffusion model leads spatial kinetics equations. These equations solved by known...

10.15392/bjrs.v9i2b.1417 article EN cc-by Brazilian Journal of Radiation Sciences 2021-07-25

10.29327/vi_sencir.559991 article PT Anais da Semana Nacional de Engenharia Nuclear e da Energia e Ciências das Radiações 2022-12-23

This work proposes to implement the cell calculation considering fuel burning using WIMSD-5B code. The procedure allows determining nuclear parameters present in multi-group neutron diffusion equation and for this purpose transport theory is used a problem with dimensional reduction, but contrast considered large number of groups associated spectrum. There are variety reactor physics codes that determine by solving applied an equivalent representing element. code deterministic solves...

10.15392/bjrs.v9i2a.404 article EN cc-by Brazilian Journal of Radiation Sciences 2021-07-24
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