Effect of Laser Radiation on Biomolecules

 

• E. Prieto
  Institute of Physical Sciences-UNAM, Avenida University 1001, Chamilpa, Cuernavaca-62210, Mexico
• L. X. Hallado
  Institute of Physical Sciences-UNAM, Avenida University 1001, Chamilpa, Cuernavaca-62210, Mexico
• A. Guerrero
  Institute of Physical Sciences-UNAM, Avenida University 1001, Chamilpa, Cuernavaca-62210, Mexico
• I. Álvarez
  Institute of Physical Sciences-UNAM, Avenida University 1001, Chamilpa, Cuernavaca-62210, Mexico
• C. Cisneros
  Institute of Physical Sciences-UNAM, Avenida University 1001, Chamilpa, Cuernavaca-62210, Mexico

DOI: https://doi.org/10.15415/jnp.2020.72015

Keywords: Nitrogenous bases, Ionic fragments, Uracil, Adenine

Abstract

Time of flight laser photoionization has been used to study the response of some molecules of biological interest under laser radiation. One of the questions of great interest today is the effect of radiation on DNA and RNA molecules. Damage to these molecules can be caused directly by radiation or indirectly by secondary electrons created by radiation. As response of the radiation field fragmentation process can occur producing different ions with kinetic energies of a few electron volts. In this paper we present the results of the interaction of 355nm laser with the nitrogen bases adenine(A) and uracil(U) using time-of-flight spectrometry and the comparison of experimental results on the effects of laser radiation in (A) and (U) belonging to two different ring groups, purines and pyrimidines respectively, which are linked to form the AU pair of the RNA.

 

References

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Issue

Vol 7 No 2 (2020): Special Issue 

 

How to Cite

E. Prieto; L. X. Hallado; A. Guerrero; I. Álvarez; C. Cisneros. Effect of Laser Radiation on Biomolecules. J. Nucl. Phy. Mat. Sci. Rad. A. 2020, 7, 123-128.

 

Dose rate profile inside the spent fuel storage pool in case of full capacity storage

 

• Amr Abdelhady
  Reactors Department, Nuclear Research Center, Atomic Energy Authority, 13759 Cairo, Egypt

DOI: https://doi.org/10.15415/jnp.2020.81002

Keywords: Radiation dose, Spent fuel, Storage pool

Abstract

This study aims to evaluate the radiation dose rate distribution inside temporary spent fuel open-pool storage. The storage pool is connected to the main pool via transfer channel to facilitate transporting the spent fuel under water that avoiding radiation dose rising in the working area in the reactor. The storage pool was prepared to store 800 spent fuel elements that considering the maximum capacity of storage. The spent fuel elements in the storage pool have different decay times depending on the times of extraction from the core. Assuming conservatively, that the spent fuels of the 5-years decay time would be stored in the lower rack and the spent fuels, of decay time ranged between 10 days and 5 years, would be stored in the upper rack. The dose rate was profiled in the region above the upper rack using SCALE/MAVRIC code applying adjoint flux calculation as a variance reduction technique. The results show that the dose rate values in the region above the pool surface would be lower than the permissible limits.

 

References

A. Abdelhady, Journal of Nuclear Engineering and Radiation Science 4, 021010 (2018). https://doi.org/10.1115/1.4038058

A. Abdelhady, Radiation Protection and Environment 41, 197 (2018). https://doi.org/10.4103/rpe.RPE_67_18

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Issue

Vol 8 No 1 (2020)

 

How to Cite

Abdelhady, A. Dose Rate Profile Inside the Spent Fuel Storage Pool in Case of Full Capacity Storage. J. Nucl. Phy. Mat. Sci. Rad. A. 2020, 8, 7-10.

Homogenization Effects of VVER-1000 Fuel Assembly on Criticality Calculations

 

• Sardar Muhammad Shauddin
  Reactor Physics & Engineering Division, Institute of Nuclear Science & Technology, Atomic Energy Research Establishment, Ganakbari, Savar, Dhaka-1349, Bangladesh

DOI: https://doi.org/10.15415/jnp.2020.81001

Keywords: Homogenization effect, Criticality calculation, Thermal neutron, Point kinetic parameter, VVER-1000

Abstract

Due to cost effective and simplicity homogeneous reactors have been widely used for experimental and research purposes. Parameters which are difficult to get from a heterogeneous reactor system can be easily obtained from a homogeneous reactor system and can be applied in the heterogeneous reactor system if the major parametric differences are known. In this study, homogenization effects of VVER (Water Water Energetic Reactor)-1000 fuel assembly on neutronic parameters have been analyzed with the universal probabilistic code MCNP (Monte Carlo N-Particle). The infinite multiplication factor (k_∞) has been calculated for the reconfigured heterogeneous and homogenous fuel assembly models with 2 w/o U-235 enriched fuel at room temperature. Effect of mixing soluble boron into the moderator/coolant (H₂O) has been investigated for both models. Direct and fission detected thermal to higher energy neutron ratio also has been investigated. Relative power distributions of both models have been calculated at critical and supercritical states. Burnup calculations for both the reconfigured cores have been carried out up to 5 years of operation. Effective delayed neutron fraction (β_eff) and prompt removal lifetime (ℓ) also have been evaluated. All the results show significant differences between the two systems except the average relative power.

 

References

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S. M. Shauddin, M. S. Mahmood and M. J. H. Khan, International Journal of Nuclear Energy Science and Technology 11, 175 (2017). https://doi.org/10.1504/IJNEST.2017.085775

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Issue

Vol 8 No 1 (2020)

 

How to Cite

Shauddin, S. M. Homogenization Effects of VVER-1000 Fuel Assembly on Criticality Calculations. J. Nucl. Phy. Mat. Sci. Rad. A. 2020, 8, 1-6.

A GEANT4 Study of a Gamma-ray Collimation Array

 

• J A López
  Physics Department, University of Texas at El Paso, El Paso, Texas, 79968 U.S.A.
• S S Romero González
  Physics Department, University of Texas at El Paso, El Paso, Texas, 79968 U.S.A.
• O Hernández Rodríguez
  Physics Department, University of Texas at El Paso, El Paso, Texas, 79968 U.S.A.
• J Holmes
  Physics Department, Arizona State University, Tempe, Arizona, 85281 U.S.A.
• R Alarcón
  Physics Department, Arizona State University, Tempe, Arizona, 85281 U.S.A.

DOI: https://doi.org/10.15415/jnp.2020.72028

Keywords: Proton therapy, Collimators, Gamma rays, GEANT4

Abstract

Proton beam therapy uses high-energy protons to destroy cancer cells which are still uncertain about where in the body they hit. A possible way to answer this question is to detect the gamma rays produced during the irradiation and determine where in the body they are produced. This work investigates the use of collimators to determine where the proton interactions occur. GEANT4 is used to simulate the gamma production of a source interacting with a collimator. Each event simulates a number of gammas obtained as a function of the position along the detector. Repeating for different collimator configurations can thus help determine the best characteristics of a detector device.

References

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W. P. Levin, H. Kooy, J. S.Loeffler, T. F., DeLaney, Proton Beam Therapy, British Journal of Cancer 93, 849 (2005). https://doi.org/10.1038/sj.bjc.6602754

James Metz, (2006). “Differences Between Protons and X-rays”. Abramson Cancer Center of the University of Pennsylvania. http://www.oncolink.org/treatment/article.cfm?c=9&s=70&id=210. Accessed 4 February 2018.

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Fiber Optical Networking. http://www.fiber-opticalnetworking.com/getting-know-fiber-collimator.html. Accessed 9 February 2018.

J. T. Bushberg, J. A. Seibert, E. M. Leidholdt, and J. M. Boone, “The Essential Physics of Medical Imaging”, Second ed., Philadelphia: Lippincott Williams & Wilkins, 2006, p. 261. ISBN 9780781780575.

S. S. Romero Gonzalez, (2018). Geant4 study of a gamma-ray collimator for proton therapy. M.S. Thesis, University of Texas at El Paso. https://digitalcommons.utep.edu/dissertations/AAI10822888/. Accessed 10 September 2019. 

 

Issue

Vol 7 No 2 (2020): Special Issue

 

How to Cite

J A López; S S Romero González; O Hernández Rodríguez; J Holmes; R Alarcón. A GEANT4 Study of a Gamma-Ray Collimation Array. J. Nucl. Phy. Mat. Sci. Rad. A. 2020, 7, 217-221.

Graft-Copolymerization of Acrylate Monomers onto Chitosan Induced by Gamma Radiation: Amphiphilic Polymers and Their Behavior at The Air-Water Interface

 

• M. Caldera-Villalobos
  Department of Radiation Chemistry and Radiochemistry, Institute of Nuclear Sciences, National Autonomous University of Mexico. Circuito Exterior, Ciudad Universitaria, 04510, Ciudad de México, México
• B. Leal-Acevedo
  Radiation Safety and Radiation Unit, Institute of Nuclear Sciences, National Autonomous University of Mexico. Circuito Exterior, Ciudad Universitaria, 04510, Ciudad de México, México
• V.M. Velázquez-Aguilar
  Faculty of Sciences, National Autonomous University of Mexico.. Ciudad Universitaria, 04510, Ciudad de México, México
• M. D. P. Carreón-Castro
  Department of Radiation Chemistry and Radiochemistry, Institute of Nuclear Sciences, National Autonomous University of Mexico. Circuito Exterior, Ciudad Universitaria, 04510, Ciudad de México, México

DOI: https://doi.org/10.15415/jnp.2020.72027

Keywords: Ionizing radiation, Graft copolymer, Biobased polymers, Polymer coatings, LB films

Abstract

Graft polymerization induced by ionizing radiation is a powerful tool in materials science to modifying the physical properties of polymers. Chitosan is a biocompatible, biodegradable, antibacterial, and highly hydrophilic polysaccharide. In this work, we report the obtaining of amphiphilic polymers through graft polymerization of acrylic monomers (methyl acrylate, t-butyl acrylate, and hexyl acrylate) onto chitosan. The polymerization reaction was carried out by simultaneous irradiation of monomers and chitosan using a gamma radiation source of ⁶⁰Co. The formation of Langmuir films of amphiphilic polymers was studied at the air-water interface through surface pressure versus main molecular area isotherms (Π-A) and hysteresis cycles of compression and decompression. Finally, it was analyzed the transferring of Langmuir films towards solid substrates to obtaining Langmuir-Blodgett films with potential application as an antibacterial coating. The microstructure of the Langmuir-Blodgett films was characterized by AFM microscopy observing a regular topography with roughness ranging between 0.53 and 0.6 μm.

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Issue

Vol 7 No 2 (2020): Special Issue

 

How to Cite

M. Caldera-Villalobos; B. Leal-Acevedo; V.M. Velázquez-Aguilar; M. D. P. Carreón-Castro. Graft-Copolymerization of Acrylate Monomers onto Chitosan Induced by Gamma Radiation: Amphiphilic Polymers and Their Behavior at The Air-Water Interface. J. Nucl. Phy. Mat. Sci. Rad. A. 2020, 7, 209-215.

Analysis of the Radon-222 Concentration and Physical-chemical Quality, in Drinking Water of Taxco, Guerrero

 

• A. H. Ramírez
  Postgraduate in Natural Resources and Ecology. Autonomous University of Guerrero, Mexico; Faculty of Earth Sciences. Autonomous University of Guerrero A. P. 197, Taxco Guerrero-40200, Mexico
• O. Talavera
  Postgraduate in Natural Resources and Ecology. Autonomous University of Guerrero, Mexico; Faculty of Earth Sciences. Autonomous University of Guerrero A. P. 197, Taxco Guerrero-40200, Mexico
• S. Souto
  Postgraduate in Natural Resources and Ecology. Autonomous University of Guerrero, Mexico; Faculty of Earth Sciences. Autonomous University of Guerrero A. P. 197, Taxco Guerrero-40200, Mexico
• J. I. Golzarri
  Institute of Physics National Autonomous University of Mexico. Scientific Research Circuit s/n, University City. Mexico City-04520, Mexico
• G. Espinosa
  Institute of Physics National Autonomous University of Mexico. Scientific Research Circuit s/n, University City. Mexico City-04520, Mexico

DOI: https://doi.org/10.15415/jnp.2020.72026

Keywords: Drinking water, Spring water, Radon, Chemical composition

Abstract

In this work the determination of radon gas (²²²Rn) and the characterization of chemical elements in drinking water of the city Taxco was carried out. Ingesting or inhaling a small number of radionuclides, as well as water of poor chemical quality, can become a potential public health problem. We are collecting 8 samples of water from a spring, physicochemical parameters were measured in field on different days of the dry season. Measurements of ²²²Rn were performed in the laboratory with an AlphaGUARD equipment. The chemical quality was analyzed in laboratory too by means of mayor and minor ions, by volumetry and colorimetry. The sodium was determined by Flama Atomic Absorption Spectroscopy (FAAS). Trace elements were analyzed by were determined by Atomic Emission Spectroscopy with Plasma Coupled by Induction (ICP-AES). The concentrations of ²²²Rn present an average of 22.06 ± 2.52 BqL^-1. The results obtained from the main ions and field parameters show a type of diluted sodium-calcium-bicarbonate water. The trace elements present are very small and not exceed the limit of quantification. Radon gas is produced by the igneous rock that is the top of the stratigraphic column, of the hydric recharge. Rainwater when descending through the fractures is impregnated with ²²²Rn gas and accumulated in the underlying rock that has sufficient porosity to accumulate water and gas in the Chacualco´s spring.

 

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Measurement of Content of 226Ra in Drinking Water From Some States of Mexican Republic by Liquid Scintillation Method

 

• A. Ángeles
  National Institute of Nuclear Research, Mexico-Toluca Highway, La Marquesa, Ocoyoacac-52750, State of Mexico, Mexico
• E. Quintero
  National Institute of Nuclear Research, Mexico-Toluca Highway, La Marquesa, Ocoyoacac-52750, State of Mexico, Mexico
• I. Gaso
  National Institute of Nuclear Research, Mexico-Toluca Highway, La Marquesa, Ocoyoacac-52750, State of Mexico, Mexico
• C. P. Zepeda
  National Institute of Nuclear Research, Mexico-Toluca Highway, La Marquesa, Ocoyoacac-52750, State of Mexico, Mexico
• T. Palma
  National Institute of Nuclear Research, Mexico-Toluca Highway, La Marquesa, Ocoyoacac-52750, State of Mexico, Mexico
• P. V. Rojas
  National Institute of Nuclear Research, Mexico-Toluca Highway, La Marquesa, Ocoyoacac-52750, State of Mexico, Mexico

DOI: https://doi.org/10.15415/jnp.2020.72025

Keywords: NORM, Radium, Drinking water, Screening, Radiotoxicity

Abstract

To assess the quality of drinking water in respect to the content of radioactivity, usually is carried out an screening program in the locations of interest, that program consist in pick representative samples of drinking water from the wells in that locations, water samples are analyzed to measuring the gross alpha/beta radioactivity by a low background proportional counter or a liquid scintillation system. When some sample exceeds the normative limit then it must be known which radionuclides are in that sample. Expected radionuclides in water are the NORM (normal occurring radioactive material) from the natural radioactive chains. ²²⁶Ra is frequently present in drinking water and is one of most important radionuclide because its “radiotoxicity”, the WHO [World Health Organization, Guidelines for drinking-water Quality, (2016)] recommends a reference level for ²²⁶Ra of 1 Bq/L (the dose coefficient for ²²⁶Ra is 2.8 x 10^-7 Sv/Bq). From a national program of drinking water screening in the Mexican Republic, the samples that exceeded the national normative limits were picked again in the same well and analyzed by LS (liquid Scintillation), using the method of two phases with a not water miscible scintillator cocktail. Results of concentrations of 226Ra from drinking water are presented. In general the content of ²²⁶Ra in drinking water samples was lower that the guide values recommended for the WHO.

 

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Issue

Vol 7 No 2 (2020): Special Issue

 

How to Cite

A. Ángeles; E. Quintero; I. Gaso; C. P. Zepeda; T. Palma; P. V. Rojas. Measurement of Content of 226Ra in Drinking Water From Some States of Mexican Republic by Liquid Scintillation Method. J. Nucl. Phy. Mat. Sci. Rad. A. 2020, 7, 195-201.

 

Structural Variations Induced by Temperature Changes in Rotavirus VP6 Protein Immersed in an Electric Field and Their Effects on Epitopes of The Region 300-396

 

• C. Peña-Negrete
  Molecular Biophysics Laboratory of the Faculty of Sciences, Autonomous University of the State of Mexico, Mexico
• M.A. Fuentes-Acosta
  Molecular Biophysics Laboratory of the Faculty of Sciences, Autonomous University of the State of Mexico, Mexico
• J. Mulia
  Molecular Biophysics Laboratory of the Faculty of Sciences, Autonomous University of the State of Mexico, Mexico
• L.A. Mandujano-Rosas
  Molecular Biophysics Modeling and Prototyping Laboratory, Mexiquense University, S. C., State of Mexico, Mexico
• D. Osorio-González
  Molecular Biophysics Laboratory of the Faculty of Sciences, Autonomous University of the State of Mexico, Mexico

DOI: https://doi.org/10.15415/jnp.2020.72024

Keywords: Rotavirus, VP6, Antigenic determinants

Abstract

Rotavirus diarrhea is an infectious intestinal disease that causes about 215 thousand deaths annually in infants under five years old. This virus is formed by three layers of concentric proteins that envelop its genome, from which VP6 structural protein is the most conserved among rotavirus serotypes and an excellent vaccine candidate. Recent studies have shown that structural proteins are susceptible to losing their biological function when their conformation is modified by moderate temperature increments, and in the case of VP6, its antigen efficiency decreases. We performed an in silicoanalysis to identify the structural variations in the epitopes 301-315, 357-366, and 376-384 of the rotavirus VP6 protein -in a hydrated medium- when the temperature is increased from 310 K to 322 K. In the latter state, we applied an electric field equivalent to a low energy laser pulse and calculated the fluctuations per amino acid residue. We identified that the region 301-315 has greater flexibility and density of negative electrical charge; nevertheless, at 322 K it experiences a sudden change of secondary structure that could decrease its efficiency as an antigenic determinant. The applied electric field induces electrical neutrality in the region 357-366, whereas in 376-384 inverts the charge, implying that temperature changes in the range 310 K-322 K are a factor that promotes thermoelectric effects in the VP6 protein epitopes in the region 300-396.

 

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Development and Validation of an X-ray Imaging Detector for Digital Radiography at Low Resolution

 

• Abdiel Ramírez Reyes
  Department of Physics and Mathematics, Autonomous University of Ciudad Juárez, Av. Del Charro 450 Nte. Col. Romero CP Party 32310, Cd. Juárez, Chihuahua, Mexico
• Gerardo Herrera Corral
  Department of Physics of CINVESTAV-IPN, AP 14-740, Avenida Instituto Politécnico Nacional 2508, Col. San Pedro Zacatenco, Gustavo A. Madero, Mexico City, CP-07360, Mexico
• Elsa Ordoñez Casanova
  Department of Industrial Engineering and Manufacturing, Autonomous University of Ciudad Juárez, Av. Del Charro 450 Nte. Cabbage. Romero Party CP-32310, Cd. Juarez, Chihuahua, Mexico
• Héctor Alejandro Trejo Mandujano
  Department of Physics and Mathematics, Autonomous University of Ciudad Juárez, Av. Del Charro 450 Nte. Col. Romero CP Party 32310, Cd. Juárez, Chihuahua, Mexico
• Uzziel Caldiño Herrera
  Department of Physics and Mathematics, Autonomous University of Ciudad Juárez, Av. Del Charro 450 Nte. Col. Romero CP Party 32310, Cd. Juárez, Chihuahua, Mexico

DOI: https://doi.org/10.15415/jnp.2020.72023

Keywords: X-ray detector, Digital radiography, Scintillator, CCD image sensor, Spatial resolution

Abstract

Digital X-ray detectors are required in different sciences and applications, however many high quality devices are expensive although high-resolution images are not always required. We present an easy way to build a detector capable of forming X-ray digital images and video with a very large area (18×18 cm²). The detector is formed by three main components: scintillator, optics lenses and CCD sensor. Basically, the device converts the X-rays into visible light which is then collected by the CCD sensor. The scintillator is Gadox type, from Carestream®, 18×18 cm², regular type, lambda 547 nm. The optics lenses are generic, with manual focus and widely visual field. The CCD sensor has a size of 1/3″, 752 × 582 pixels, monochrome, 20 FPS, 12 bits ADC and pixel size of 3.8 μm. With the built detector and an X-ray source, we formed an X-ray imaging detection system to generate digital radiographs of biological or inert objects-examples are given-, as well as real-time X-ray video. Additionally, the spatial resolution limit was measured in terms of Modulation Transfer Function by the method of opaque edge from a lead sheet with a result of 1.1 Lp/mm. Finally using a filter, the focal spot of the X-ray source is measured, resulting in a diameter of 0.9 mm (FWHM).

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Issue

Vol 7 No 2 (2020): Special Issue

  

How to Cite

Abdiel Ramírez Reyes; Gerardo Herrera Corral; Elsa Ordoñez Casanova; Héctor Alejandro Trejo Mandujano; Uzziel Caldiño Herrera. Development and Validation of an X-Ray Imaging Detector for Digital Radiography at Low Resolution. J. Nucl. Phy. Mat. Sci. Rad. A. 2020, 7, 181-187.

 

Study of the Erosion of Copper by Hot Plasma

 

• R. S. Monzamodeth
  Chemistry Faculty, National Autonomous University of Mexico (UNAM), PO Box 04510 Mexico City, Mexico
• B. Campillo
  Chemistry Faculty, National Autonomous University of Mexico (UNAM), PO Box 04510 Mexico City, Mexico

DOI: https://doi.org/10.15415/jnp.2020.72022

Keywords: Copper, Hot plasma, Erosion, Hardness, Plasma/Wall interactions, Hydrophobic properties

Abstract

An exhaustive study of the erosion process of a copper cathode exposed to a hot plasma column of 2kJ of energy (T≈0.5-2.0keV) and high electron density (n≈1019-1022cm³) was made, as well as, the radiation field of charged and neutral particles. The characterization of the cumulative damage generated by the plasma/cathode interaction was made by the use of metallographic techniques, scanning electron microscopy (SEM) and by the analysis of mechanical properties. Damage accumulation produced by the impacts of deuterium plasma discharge created in the copper electrode a deep cavity similar to a crater, modifying the morphology of the surface and below it. The microhardness Vickers test was carried out making indentations from the final part of the cavity to cover 1 cm with indentations every 200 μm. Different areas of hardening were observed, the profile suggests a hardening/recovery front and simultaneous recrystallization in the sample, phenomenon associated with the heating/cooling cycles to which the copper cathode is subjected. Images were captured by SEM at different distances from the center of the surface. The region that showed involvement at the macro level corresponds to 2/3 of the radius of the sample from the center to the outside. These phenomena studied are important to understand the nature of the plasma/wall interaction in any fusion device.

 

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Issue

Vol 7 No 2 (2020): Special Issue

 

 

 

How to Cite

R. S. Monzamodeth; B. Campillo. Study of the Erosion of Copper by Hot Plasma. J. Nucl. Phy. Mat. Sci. Rad. A. 2020, 7, 173-179.

 

 

Study of CT Images Processing with the Implementation of MLEM Algorithm using CUDA on NVIDIA’S GPU Framework

 

• T. A. Valencia-Pérez
  Faculty of Physical Sciences Mathematics Benemérita Universidad Autónoma de Puebla, Avenida San Claudio y 18 Sur, Colonia San Manuel, Building FM2-203, Ciudad Universitaria, C.P. 72570, Puebla, Mexico
• J. M. Hernández-López
  Faculty of Physical Sciences Mathematics Benemérita Universidad Autónoma de Puebla, Avenida San Claudio y 18 Sur, Colonia San Manuel, Building FM2-203, Ciudad Universitaria, C.P. 72570, Puebla, Mexico
• E. Moreno-Barbosa
  Faculty of Physical Sciences Mathematics Benemérita Universidad Autónoma de Puebla, Avenida San Claudio y 18 Sur, Colonia San Manuel, Building FM2-203, Ciudad Universitaria, C.P. 72570, Puebla, Mexico
• B. de Celis-Alonso
  Faculty of Physical Sciences Mathematics Benemérita Universidad Autónoma de Puebla, Avenida San Claudio y 18 Sur, Colonia San Manuel, Building FM2-203, Ciudad Universitaria, C.P. 72570, Puebla, Mexico

DOI: https://doi.org/10.15415/jnp.2020.72021

Keywords: Computed tomography, Algorithms, GPU, Reconstruction, Image quality

Abstract

In medicine, the acquisition process in Computed Tomography Images (CT) is obtained by a reconstruction algorithm. The classical method for image reconstruction is the Filtered Back Projection (FBP). This method is fast and simple but does not use any statistical information about the measurements. The appearance of artifacts and its low spatial resolution in reconstructed images must be considered. Furthermore, the FBP requires of optimal conditions of the projections and complete sets of data. In this paper a methodology to accelerate acquisition process for CT based on the Maximum Likelihood Estimation Method (MLEM) algorithm is presented. This statistical iterative reconstruction algorithm uses a GPU Programming Paradigms and was compared with sequential algorithms in which the reconstruction time was reduced by up to 3 orders of magnitude while preserving image quality. Furthermore, they showed a good performance when compared with reconstruction methods provided by commercial software. The system, which would consist exclusively of a commercial laptop and GPU could be used as a fast, portable, simple and cheap image reconstruction platform in the future.

 

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Issue

Vol 7 No 2 (2020): Special Issue

 

How to Cite

T. A. Valencia-Pérez; J. M. Hernández-López; E. Moreno-Barbosa; B. de Celis-Alonso. Study of CT Images Processing With the Implementation of MLEM Algorithm Using CUDA on NVIDIA’S GPU Framework. J. Nucl. Phy. Mat. Sci. Rad. A. 2020, 7, 165-171.

Characterizing a Mini Gamma Detector

 

• E. Márquez-Quintos
  Faculty of Mathematical Physical Sciences, Benemérita Universidad Autónoma de Puebla, C.P. 72570, Puebla, Mexico
• E. Moreno-Barbosa
  Faculty of Mathematical Physical Sciences, Benemérita Universidad Autónoma de Puebla, C.P. 72570, Puebla, Mexico
• J. E. Espinosa
  Faculty of Mathematical Physical Sciences, Benemérita Universidad Autónoma de Puebla, C.P. 72570, Puebla, Mexico
• Benito de Celis Alonso
  Faculty of Mathematical Physical Sciences, Benemérita Universidad Autónoma de Puebla, C.P. 72570, Puebla, Mexico
• Margarita Amaro Aranda
  Faculty of Electronics Sciences, Benemérita Universidad Autónoma de Puebla, C.P. 72570, Puebla, Mexico
• R. Palomino Merino
  Faculty of Mathematical Physical Sciences, Benemérita Universidad Autónoma de Puebla, C.P. 72570, Puebla, Mexico

DOI: https://doi.org/10.15415/jnp.2020.72020

Keywords: Gamma ray, Crystal Scintillator, Spectrophotometer, Calibration

Abstract

There are several types of gamma radiation detectors, which have different characteristics depending on its use. We designed and instrumented a gamma detector for low energies of a small and portable size to obtain spectrum from radioactive sources and from that analyze each spectrum. This instrument basically consists of a scintillator crystal coupled to a SiPM this in turn coupled to a PCB card designed with capacitors and resistors for a better signal, a voltage source of 29 volts. For signal acquisition the system must be connected to an oscilloscope this in turn is controlled by a script developed in Python. For the calibration radioactive isotopes with the same dimensions were used, caesium-137 (Cs-137), cobalto-60 (Co-60), sodium-22 (Na-22) and manganese-54 (Mn-54) as gamma ray emission.

 

References

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Issue

Vol 7 No 2 (2020): Special Issue 

 

 

How to Cite

E. Márquez-Quintos; E. Moreno-Barbosa; J. E. Espinosa; Benito de Celis Alonso; Margarita Amaro Aranda; R. Palomino Merino. Characterizing a Mini Gamma Detector. J. Nucl. Phy. Mat. Sci. Rad. A. 2020, 7, 159-163.

 

 

Analysis of DDM into Gamma Radiation

 

• C. Arellano-Celiz
  Faculty of Mathematical Physical Sciences, Benemérita Universidad Autónoma de Puebla, Apdo. Postal 1152, Puebla, Pue.-72000, Mexico
• A. Avilez-López
  Faculty of Mathematical Physical Sciences, Benemérita Universidad Autónoma de Puebla, Apdo. Postal 1152, Puebla, Pue.-72000, Mexico
• J. E. Barradas-Guevara
  Faculty of Mathematical Physical Sciences, Benemérita Universidad Autónoma de Puebla, Apdo. Postal 1152, Puebla, Pue.-72000, Mexico
• O. Félix-Beltrán
  Faculty of Electronics Sciences, Benemérita Universidad Autónoma de Puebla, Apdo. Postal 542, Puebla, Pue.-72000, Mexico
• F. González-Canales
  Faculty of Electronics Sciences, Benemérita Universidad Autónoma de Puebla, Apdo. Postal 542, Puebla, Pue.-72000, Mexico

DOI: https://doi.org/10.15415/jnp.2020.72019

Keywords: Dark matter, Dipolar dark matter, WIMP, Relic density

Abstract

We are interested in the purpose of a dipolar fermionic particle as a viable candidate of Dark Matter (DDM). Then, we study the annihilation of dark matter into photons, considering it as a neutral particle with non-vanishing magnetic (M) and electric (D) dipolar moments. The total annihilation cross section σ(χ → γ) is computed by starting from a general form of coupling χγ in a framework beyond to Standard Model (BSM). We found that candidates with O(m_χ )∽10²GeV, D≈10⁻¹⁶ e cm are required in order to satisfy the current cosmic relic density.

 

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Issue

Vol 7 No 2 (2020): Special Issue

 

How to Cite

C. Arellano-Celiz; A. Avilez-López; J. E. Barradas-Guevara; O. Félix-Beltrán; F. González-Canales. Analysis of DDM into Gamma Radiation. J. Nucl. Phy. Mat. Sci. Rad. A. 2020, 7, 153-157.

Preliminary Measurements of Be-10/Be-7 Ratio in Rainwater for Atmospheric Transport Analysis

 

• K. de los Ríos
  Physics Institute, National Autonomous University of Mexico. P.O. Box 20-364, Mexico City, Mexico
• C. Méndez-García
  CONACyT Lecturers - Physics Institute, National Autonomous University of Mexico. P.O. Box 20-364, Mexico City, Mexico
• L. Acosta
  Physics Institute, National Autonomous University of Mexico. P.O. Box 20-364, Mexico City, Mexico
• R. García-Martínez
  Atmosphere Science Center, National Autonomous University of Mexico, Mexico City-04510, Mexico
• M. A. Martínez-Carrillo
  Science Faculty, National Autonomous University of Mexico, 04510 Mexico City, Mexico
• M. E. Ortiz
  Physics Institute, National Autonomous University of Mexico. P.O. Box 20-364, Mexico City, Mexico

DOI: https://doi.org/10.15415/jnp.2020.72018

Keywords: Rainwater, Beryllium-7, Beryllium-10, AMS, HP-Ge

Abstract

The meteoric cosmogenic beryllium has been used as an essential geophysical tracer in the analysis of atmospheric flows and erosion soils since 1960. The first measurements Be-7 and Be-10 concentrations in rainwater from Mexico, have been carried out by using gamma decay spectroscopy and AMS techniques, respectively for each isotope. With this it was possible to report a preliminar value for the Be-10/Be-7 isotopic ratio in such environmental samples. The present work described preliminary results related to rainwater collected at mountain and metropolitan areas. Results are compared with predictions and previous measurements for both radioisotopes, observing a very sensible behavior particularly for the case of Be-7 activities.

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Issue

Vol 7 No 2 (2020): Special Issue

 

How to Cite

K. de los Ríos; C. Méndez-García; L. Acosta; R. García-Martínez; M. A. Martínez-Carrillo; M. E. Ortiz. Preliminary Measurements of Be-10/Be-7 Ratio in Rainwater for Atmospheric Transport Analysis. J. Nucl. Phy. Mat. Sci. Rad. A. 2020, 7, 145-151.