A5026596016- Nuclear Physics and Applications
- Radiation Detection and Scintillator Technologies
- Radiation Therapy and Dosimetry
- Nuclear reactor physics and engineering
- Advanced Radiotherapy Techniques
- Radiation Shielding Materials Analysis
- Radiation Dose and Imaging
- Radioactivity and Radon Measurements
- Graphite, nuclear technology, radiation studies
- Advanced X-ray and CT Imaging
- Medical Imaging Techniques and Applications
- Heavy metals in environment
- Luminescence Properties of Advanced Materials
- Atomic and Subatomic Physics Research
- Boron Compounds in Chemistry
- Nuclear Materials and Properties
- Heavy Metals in Plants
- Radioactive Decay and Measurement Techniques
- Heavy Metal Exposure and Toxicity
- Radiation Effects and Dosimetry
- Particle Detector Development and Performance
- Radiopharmaceutical Chemistry and Applications
- Fault Detection and Control Systems
- Neural Networks and Applications
- Digital Radiography and Breast Imaging
Universidad Autónoma de Zacatecas "Francisco García Salinas"
2016-2025
Consejo Nacional de Humanidades, Ciencias y Tecnologías
2021
Instituto Nacional de Investigaciones Forestales Agrícolas y Pecuarias
2021
Weatherford College
2021
Karnatak University
2016
Universidad Simón Bolívar
2015
Universidad de Colima
2011
Instituto Politécnico Nacional
2010
Universidad Tecnológica de Nayarit
2010
Kaohsiung Chang Gung Memorial Hospital
2010
The shielding characteristics of two concrete blocks, widely used in the building industry Mexico have been determined. These include mass interaction coefficients, linear attenuation coefficients and half-value layers. energy-dispersed X-ray fluorescence shows that percentage content each atom sample, atomic volume constituent elements a material, plays an important role its capabilities. total layers were analyzed for set photon energies related to X-rays diagnosis cancer treatment with...
Highlights• Precise detection and quantification of ionizing radiation using TLDs are essential in medical applications.• Hydroxyapatite (HAp) is a well-regarded biomaterial with properties suitable for thermoluminescent (TL) dosimetry.• Incorporation rare-earth dopants HAp enhances its TL response.• The presence neutrons as byproducts applications motivates determining the absorbed neutron dose.• Monte Carlo simulations MCNP6 code provide valuable insights synthesizing dosimetric materials.
Using the difference between responses to neutrons of TLD-600 and TLD-700, three experimental devices were constructed arranged measure thermal neutron fluences, spectra, doses inside treatment room a radiotherapy 18 MV Linear electron accelerator (Linac). Thermal fluences measured with TLD-600/TLD-700 pairs in both bare cadmium (Cd) foil covered methacrylate box. Neutron spectra 26 energy bins by introducing air into middle five polyethylene spheres diameters 3, 5, 8, 10, 12 inches. A PC...
Absorbed photoneutron dose to patients undergoing x‐ray therapy was studied using Monte Carlo simulations based on the MCNPX code. Two separate transport were conducted, one for contribution and another neutron capture gamma rays. The phantom model used of a female patient receiving four‐field pelvic box treatment. Photoneutron doses determinate be higher organs tissues located inside treatment field, especially those closest patient's skin. maximum organ equivalent per achieved within each...