A5036944669- Graphite, nuclear technology, radiation studies
- Nuclear Physics and Applications
- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
- Nuclear and radioactivity studies
- Radioactivity and Radon Measurements
- Academic Research in Diverse Fields
- Nuclear Engineering Thermal-Hydraulics
- Radiation Detection and Scintillator Technologies
- Infrared Target Detection Methodologies
- Polymer Nanocomposite Synthesis and Irradiation
- Structural Behavior of Reinforced Concrete
- Radioactive Decay and Measurement Techniques
- Nuclear Issues and Defense
- Spacecraft Design and Technology
- Silicone and Siloxane Chemistry
- Catalytic Processes in Materials Science
- Radiation Shielding Materials Analysis
- Semiconductor Quantum Structures and Devices
- Space exploration and regulation
- Radiative Heat Transfer Studies
- Photopolymerization techniques and applications
- Material Selection and Properties
- Innovations in Concrete and Construction Materials
Military Institute of Engineering
2021-2025
In the present work, transmission factors of γ-rays are determined in bi-layered shields composed lead and steel, through a methodology three distinct parts. The buildup calculation was performed using published by Broder 1962 [1]. A computational simulation used spherical model, total concentric spheres were simulated, with source center spheres. first sphere represents shield its radius is represented thickness this material. second steel sum thicknesses shielding. third vacuum that will...
Abstract The present study seeks to develop a classifier of radioactive sources based on gamma spectroscopy and artificial intelligence, which makes use Keras TensorFlow [, both free open-source technologies. Through these technologies, an neural network (ANN) was developed, supervised machine learning the backpropagation algorithm. trained with dataset spectra from simulations performed by Monte Carlo N-Particle 5 code (MCNP5). To achieve objective functioning as within proposed scope,...
This work investigated the impact of doping Stainless Steel 316 with silicon carbide (SiC) nanoparticles on performance nuclear fuel through computational simulations using MCNP5 software. The results indicated that addition SiC did not significantly affect effective multiplication factor (keff), suggesting this may be a viable strategy to improve properties without compromising its effectiveness. Additionally, inclusion offer additional benefits such as increased thermal stability and...
The study investigated the transmission factor simulated of depleted uranium dioxide for gamma radiation shielding. Depleted is a dense and slightly radioactive material, primarily composed uranium-238, used in various military applications, especially armor-piercing ammunition. However, it also has civilian such as shielding medical facilities, counterweights aircraft ships, protection shielding, stabilizers construction. confirmed its effectiveness from cesium 137 cobalt 60 isotopes.
Several applications were explored, including fuel rod coatings, structural alloys, and cooling materials in nuclear reactors, with a focus on performance, safety, durability improvements. The results revealed that niobium doping provided range of benefits, such as increased corrosion resistance, greater stability high-temperature radiation environments, contributed to reducing criticality elements. These findings underscore the potential strategic material industry, offering promising...
In this study, the importance of simulations conducted in MCNP5 and modifications implemented 316 steel to optimize energy efficiency nuclear power production are explored. Graphene investigated as promising additives due their low absorption cross-section for thermal neutrons, which facilitates a more significant participation neutrons fission heat generation. Through use code, were analyze hypothetical UO2 fuel element with different enrichment zones evaluate its performance. The results...
In this study, the importance of simulations conducted in MCNP5 and modifications implemented 316 steel to optimize energy efficiency nuclear power production are explored. Molybdenum (Mo) is investigated as a promising additive due its low absorption cross-section for thermal neutrons, which facilitates more significant participation neutrons fission heat generation. Through use code, were analyze hypothetical UO2 fuel element with different enrichment zones assess performance. The results...
The research examined the transmission factor for thermal neutrons utilizing Watt spectrum uranium-235 fission with MCNP5 simulations. Throughout analysis, it was found that borated polyethylene performed worse than regular polyethylene. This disparity implies that, while possesses advantageous moderating properties, might introduce features decrease its efficiency in neutron transmission. These findings underscore importance of evaluating not only capabilities materials but also other...
This article addresses the development of a remotely piloted vehicle for chemical, biological, radiological, and nuclear army defense system, able itself to perform radiometric surveys favoring process local mapping investigation possible dispersions radioactive materials in radiological accidents incidents. Tests were carried out verify efficiency developed prototype it can be verified that has great applicability optimizes protection process.
The Argonauta research reactor at the Institute of Nuclear Engineering - IEN operates, under normal conditions, powers ranging from 1.7 to 340 W, developing activities a scientific-technological nature in areas neutron radiography, radionuclide production and conduction experimental practices graduate courses CNEN institutions other Brazilian institutes science technology. During some security operations, presence investigators, students and/or operators inside around main hall is required....
The objective of this paper was the radiometric survey at Materials Engineering Laboratory Military Institute Engineering, in Rio de Janeiro, Brazil. Properties materials are analyzed laboratory using X-rays machines. For development that work, two scintillator detectors were used with their associated electronics. Detector “A” has NaI(Tl) as material and detector “B” CeBr3. In addition to verifying whether measured dose rate is accordance provided by CNEN standard, a comparison made between...
This study describes the use of ionizing radiation detectors in a Brazilian Army reconnaissance vehicle (RV), used area monitoring actions based on occurrence radiological event. Two scintillating detectors, NaI and LaBr3, were to carry out field measurements surveying for different distances from simulated detector position vehicle, order compare energy spectra obtained each measurement system. The Technological Center (Centro Tecnológico do Exército - CTEx) region was chosen measurements....