34 results on '"Silva, A.X."'
Search Results
2. System to detect the interface region and identify products transported by polyducts using artificial intelligence and gamma radiation through MCNP6 code
3. Potential increased radiological risk in cargo scanning activity
4. Use of gamma radiation and artificial neural network techniques to monitor characteristics of polyduct transport of petroleum by-products
5. Simulation of Siemens ONCOR™ Expression linear accelerator using phase space in the MCNPX code
6. Application of digital image processing for the generation of voxels phantoms for Monte Carlo simulation
7. Evaluation of the radiological risk in cargo scanning by comparison with known biological consequences
8. Brazilian two-component TLD albedo neutron individual monitoring system
9. Electronic imaging system for neutron radiography at a low power research reactor
10. Computed radiography simulation using the Monte Carlo code MCNPX
11. Detection of drugs and explosives using neutron computerized tomography and artificial intelligence techniques
12. Diagnostic assessment to estimate and minimize neutron dose rates received by occupationally exposed individuals at cyclotron facilities
13. Monte Carlo simulation of photoneutrons streaming inside radiotherapy treatment rooms as a function of gantry angles
14. Assessment of weld thickness loss in offshore pipelines using computed radiography and computational modeling
15. Dose–image quality study in digital chest radiography using Monte Carlo simulation
16. Methodology for digital radiography simulation using the Monte Carlo code MCNPX for industrial applications
17. The use of high-density concretes in radiotherapy treatment room design
18. Monte Carlo simulation of response function for a NaI(Tl) detector for gamma rays from 241Am/Be source
19. A study of neutron spectra from medical linear accelerators
20. Comparison of simulated and experimental values of self-absorption correction factors for a fast and credible adjust in efficiency curve of gamma spectroscopy
21. Explosives detection using prompt-gamma neutron activation and neural networks
22. Use of thermal neutron tomography for the detection of drugs and explosives
23. Study of a neutron radiography system using 252Cf neutron source
24. Moderator–collimator-shielding design for neutron radiography systems using 252Cf
25. Selective contribution of concrete shielding on the equivalent and effective doses in a prostate radiotherapy treatment
26. Dose and risk evaluation in thoracic radiology using male and female voxel phantoms
27. Characterization of a two-component thermoluminescent albedo dosemeter according to ISO 21909
28. PEDS: SOFTWARE TO ASSESS WALL THICKNESS LOSS AND WELD THICKNESS LOSS IN OFFSHORE PIPELINES THROUGH DIGITAL RADIOGRAPHY
29. Effect of external shielding for neutrons during radiotherapy for prostate cancer, considering the 2300 CD linear accelerator and voxel phantom
30. Dose conversion coefficients for ICRP110 voxel phantom in the Geant4 Monte Carlo code
31. Glucose transport and utilization are altered in the brain of rats deficient in n-3 polyunsaturated fatty acids
32. Studies of isochronal and isothermal annealing of alpha particle tracks in CR-39 polymer detectors
33. Thermal annealing of proton tracks with energies of 4 and 6 MeV in CR-39 polymer detectors
34. Monte Carlo simulation of response function for a NaI(Tl) detector for gamma rays from 241Am/Be source
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