J.I. Golzarri

Universidad Nacional Autónoma de México

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G. Espinosa

National Institute of Astrophysics, Optics and Electronics

C. Vázquez-López

Instituto Politécnico Nacional

F. Castillo

Universidad Nacional Autónoma de México

V. M. Castaño

Autonomous University of Queretaro

J. Rickards

Universidad Nacional Autónoma de México

R. Fragoso

Instituto Politécnico Nacional

L. Sajo‐Bohus

Simón Bolívar University

J. J. E. Herrera

Universidad Nacional Autónoma de México

R.B. Gammage

Oak Ridge National Laboratory

B. E. Zendejas-Leal

Center for Research and Advanced Studies of the National Polytechnic Institute

Cooperative Institutions

Universidad Nacional Autónoma de México

Instituto Politécnico Nacional

Instituto Nacional de Investigaciones Nucleares

Center for Research and Advanced Studies of the National Polytechnic Institute

Benemérita Universidad Autónoma de Puebla

National Agency for New Technologies, Energy and Sustainable Economic Development

Universidad Autónoma Metropolitana

Universidad Autónoma del Estado de México

University of Padua

Universidad Nacional del Centro de la Provincia de Buenos Aires

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Fast neutron dosimetry using CR-39 track detectors with polyethylene as radiator

Radiation Measurements (2012)

F. Castillo G. Espinosa J.I. Golzarri D. Osorio-González José Alberto Israel Romero Rangel

CR-39

Isotropic etching

Radiator (engine cooling)

10.1016/j.radmeas.2012.09.007

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Citations (49)

Seasonal variation measurements of radon levels in caves using SSNTD method

Radiation Measurements (2008)

G. Espinosa J.I. Golzarri R.B. Gammage L. Sajo‐Bohus José A. Viccon‐Pale

Nuclear track

CR-39

10.1016/j.radmeas.2008.04.033

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Citations (20)

Isotropic and anisotropic components of neutron emissions at the FN-II and PACO dense plasma focus devices

Plasma Physics and Controlled Fusion (2003)

F. Castillo J. J. E. Herrera José Alberto Israel Romero Rangel M. Milanese R. Moroso

The average angular distribution of neutron emissions has been measured in the Fuego Nuevo II (FN-II) dense plasma focus device (5 kJ) by means of CR-39 plastic nuclear track detectors. When pure deuterium is used as the filling gas, the data can be adjusted to a Gaussian function, related to anisotropic emission, superposed on a constant pedestal, related to isotropic emission. When deuterium–argon admixtures are used, the anisotropic contribution is best represented by a parabola. The same analysis is applied to previously reported results, for fewer shots, in pure deuterium from the PACO device, which is similar in size to the FN-II. In both devices the anisotropic component is smaller than the isotropic one, but with different features. In PACO the anisotropic component is concentrated on a large narrow beam around the axis, but its contribution to the total neutron yield is significantly smaller than in the FN-II, where the anisotropic component spreads over a wider range. The neutron flux per shot is monitored in both devices with calibrated silver activation detectors, at 20° and at 90° from the axis. The average values of the neutron flux at these two angles are used, along with the angular distributions obtained form the track detectors, in order to estimate the absolute neutron yield of both the isotropic and the anisotropic contributions. From examining different groups of shots, it is found that the shape of the angular distribution is important in the estimation of anisotropy, and that the value usually reported, as the ratio of neutron counts head-on and side-on, as measured by activation counters, may be misleading.

ASDEX Upgrade

10.1088/0741-3335/45/3/309

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Citations (50)

Digital image counting system for nuclear track detectors

International Journal of Radiation Applications and Instrumentation Part D Nuclear Tracks and Radiation Measurements (1986)

G. Espinosa J.I. Golzarri I. Gamboa L. Tommasino R. V. Griffith

Microdensitometer

Nuclear track

10.1016/1359-0189(86)90578-9

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Citations (8)

Radon detection in conical diffusion chambers: Monte Carlo calculations and experiment

AIP conference proceedings (2015)

J. Rickards J.I. Golzarri C. Vázquez-López G. Espinosa

The operation of radon detection diffusion chambers of truncated conical shape was studied using Monte Carlo calculations. The efficiency was studied for alpha particles generated randomly in the volume of the chamber, and progeny generated randomly on the interior surface, which reach track detectors placed in different positions within the chamber. Incidence angular distributions, incidence energy spectra and path length distributions are calculated. Cases studied include different positions of the detector within the chamber, varying atmospheric pressure, and introducing a cutoff incidence angle and energy.

10.1063/1.4927188

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Citations (1)

Nuclear Tracks in CR-39 Produced by Carbon, Oxygen, Aluminium and Titanium Ions

Radiation Protection Dosimetry (2002)

J. Rickards V. Romo J.I. Golzarri G. Espinosa

This work describes the response of CR-39 (allyl diglycol polycarbonate) to different ions (C, O, Al and Ti) produced by the Instituto de Fisica 3 MV 9SDH-2 Pelletron accelerator and backscattered from a thin Au film on a C support. The ion energies were chosen in series such that the ranges of the different ions in the detector were 2, 3, 4, 5, 6, 7 and 8 microm respectively for each series. Once exposed, the detectors were etched with a solution of 6.25 M KOH at 60 degrees C, and the reading was carried out using a digital image analysis system. An analysis of the measured track diameters of all the types of ions indicates that, for a given range, track kinetics are independent of type of ion, energy and stopping power.

Pelletron

Stopping power

Ion track

Polycarbonate

Carbon fibers

10.1093/oxfordjournals.rpd.a006050

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Citations (0)

Enhancement in the Photoluminescence Properties of SiO2:Ge Embedded in a Polymeric Matrix

Journal of Nuclear Physics Material Sciences Radiation and Applications (2012)

G. Lesly Jiménez C. Falcony C. Vázquez-López J.I. Golzarri G. Espinosa

Polymer films of styrene butadiene copolymer (SBC) mixed with SiO2:Ge powder were successfully obtained by the drop casting method. The SBC concentration (in chloroform solution) was 10%w/v and the SiO2:Ge powder was mixed (mass ratio 80:20 respectively). The thicknesses of the films obtained were 50, 100, and 200 μm. In addition, polymer films of polytetrafluoroethylene (PTFE) preparation (60% dispersion in water), were obtained mixing 2 ml of PTFE and 0.05g of SiO2:Ge powder with a mass relation of 98% polymer and 2% SiO2:Ge. The photoluminescence emission spectra (PL) of SBC doped with SiO2:Ge resulted in similar characteristics to those for SiO2:Ge powders, although their intensity shows an increase 3.5 times approximately, compared with the pure powder. On the other hand, the PTFE films with SiO2:Ge present just one peak in the PL emission at 439 nm but their intensity increases 18 times respect to the powder. The photoluminescence excitation (PLE) spectra of the SiO2:Ge powders show the characteristic peaks at 248 nm (most intense) and at 366 nm. However, when the powder is embedded either in SBC or PTFE the peak at 366 nm shows an important increase which seems to indicate an energy transfer from the polymer to the SiO2:Ge.

Polytetrafluoroethylene

10.15415/jnp.2018.61022

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Citations (1)

A study of commercially-available polyethylene terephthalate (PET) and polycarbonate as nuclear track detector materials

AIP conference proceedings (2014)

G. Espinosa J.I. Golzarri C. Vázquez-López Rosa Trejo K. López

In the study of the sensitivity of materials to be used as nuclear track detectors, it was found that commercial polyethylene terephthalate (PET) from Ciel® water bottles, commercial roof cover polycarbonate, and recycled packaging strips (recycled PET), can be used as nuclear track detectors. These three commercial materials present nuclear tracks when bombarded by 2.27 MeV nitrogen ions produced in a Pelletron particle accelerator, and by fission fragments from a 252Cf source (79.4 and 103.8 MeV), after a chemical etching with a 6.25M KOH solution, or with a 6.25M KOH solution with 20% methanol, both solutions at 60±1°C. As an example, the nitrogen ions deposit approximately 1 keV/nm in the form of ionization and excitation at the surface of PET, as calculated using the SRIM code. The fission fragments deposit up to 9 keV/nm at the surface, in both cases generating sufficient free radicals to initiate the track formation process. However, 5 MeV alpha particles, typical of radon (222Rn) emissions, deposit only 0.12 keV/nm, do not present tracks after the chemical etching process. This valuable information could be very useful for further studies of new materials in nuclear track methodology.

Polycarbonate

Alpha particle

Ion track

Pelletron

10.1063/1.4890700

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Citations (2)

Nuclear Tracks Morphology Study Using Raman Methodology

Journal of Nuclear Physics Material Sciences Radiation and Applications (2016)

Mariana Cerda Z.J.A. Azamar-Barrios C. Lopez Rogelio Fragoso‐Soriano B. E. Zendejas-Leal

In this work, a new methodology for rendering profiles of etched nuclear tracks is presented, using confocal micro-Raman spectrometry instrumentation. The precise profile of etched nuclear tracks with normal and/or angular incidence of the particle can be determined in few minutes, with a great visual and numerical resolution, that means a quantitative and qualitative simultaneous chemical and morphology characterization with the Raman technique. The Raman image routine is designed to acquire at each image pixel a complete Raman spectrum. This is a mapping of the functional groups that form the polymeric structure, which may be broken by the damage caused by the incident radiation and/or the etching process.

10.15415/jnp.2016.41023

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Citations (1)

Radon and progeny alpha-particle energy analysis using nuclear track methodology

Journal of Radioanalytical and Nuclear Chemistry (2008)

G. Espinosa J.I. Golzarri James S. Bogard

Alpha particle

Polycarbonate

Particle (ecology)

10.1007/s10967-008-0720-9

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Citations (3)