Spatial frequency analysis of fluorescent nuclear track detectors irradiated in mixed neutron–photon fields

A new image processing method for the dosimetry of mixed neutron–photon fields using fluorescent nuclear track detectors (FNTDs) is investigated. Images obtained from FNTDs were processed using spatial frequency analysis to determine doses for both low and high LET radiations. Spatial frequency analysis extended the dynamic range of detectible neutron doses from 4 orders of magnitude for track counting only to at least 6 orders of magnitude by combining track counting with the new image processing method. Two different converters of indirectly ionizing radiation to secondary charged particles were used in conjunction with image processing to separate signals induced by neutron and gamma fields.     

FNTD radiation dosimetry system enhanced with dual-color wide-field imaging

At high neutron and photon doses Fluorescent Nuclear Track Detectors (FNTDs) require operation in analog mode and the measurement results depend on individual crystal color center concentration (coloration). We describe a new method for radiation dosimetry using FNTDs, which includes non-destructive, automatic sensitivity calibration for each individual FNTD. In the method presented, confocal laser scanning fluorescent imaging of FNTDs is combined with dual-color wide field imaging of the FNTD. The calibration is achieved by measuring the color center concentration in the detector through fluorescence imaging and reducing the effect of diffuse reflection on the lapped surface of the FNTD by imaging with infra-red (IR) light. The dual-color imaging of FNTDs is shown to provide a good estimation of the detector sensitivity at high doses of photons and neutrons, where conventional track counting is impeded by track overlap.     

High-accuracy fluence determination in ion beams using fluorescent nuclear track detectors

We present an approach to use Al₂O₃:C,Mg-based fluorescent nuclear track detectors (FNTDs) and confocal laser scanning microscopy as a semiautomatic tool for fluence measurements in clinical ion beams. The method was found to cover a linear energy transfer (LET) range from at least L_∞(Al₂O₃) = 0.5 keV/μm to 61,000 keV/μm with a detection efficiency ≥99.83% (20 MeV protons) at particle fluences up to at least 5 × 10⁷ per cm². Our technique allows to determine the spatial fluence distribution on a microscopic scale and enables detailed track-by-track comparison studies between different fluence detectors.     

An imaging spectrometer based on high resolution microscopy of fluorescent aluminum oxide crystal detectors

Fluorescent Nuclear Track Detector (FNTD) technology was tested as an imaging, spectroscopic tool for radionuclide analysis. This investigation intended to distinguish between characteristic α-particles of ²³⁹Pu (5.2 MeV), ²³⁴U (4.8 MeV) and ²³⁸U (4.2 MeV). FNTDs are Al₂O₃:C,Mg single crystals with color centers that undergo radiochromic transformation. FNTD readout is non-destructive and is performed with fluorescence laser scanning confocal microscopy. Ionization events register in the detector as bright fluorescent features on a weak fluorescent background. Images were acquired at several incrementing depths in the detector to produce 3D datasets. Spectroscopic information was obtained by measuring α-particle range in the detector after 3D image reconstruction. The resolution of this technique is fundamentally limited by particle range straggling (about 3.8% (k = 1) at these α-particle energies). The spectroscopic line-width as full width at half maximum (FWHM) was determined to be 0.4 MeV enabling discrimination between the isotopes of interest.     

Fluorescent nuclear track detectors as a tool for ion-beam therapy research

Fluorescent nuclear track detectors based on Al₂O₃:C,Mg with their excellent efficiency for detection of heavy charged particles and full 3D information from laser scanning microscopy allow a multitude of issues related to ion-beam cancer therapy to be tackled. A recently established read out protocol enables the utilization of a commercial microscope similar to those available in many life-science environments. This contribution illustrates the approach, its potential and limitations, as well as applications in clinical ion beams.     

Neutron response study using poly allyl diglycol carbonate

The results of an experimental work aimed at improving the performance of the CR-39 nuclear track detector for neutron dosimetry applications are reported. A set of CR-39 plastic detectors was exposed to ²⁵²Cf neutron source, which has the emission rate of 0.68 × 10⁸ s⁻¹, and neutron dose equivalent rate 1 m apart from the source is equal to 3.8 mrem/h. The detection of fast neutrons performed with CR-39 detector foils, subsequent chemical etching and evaluation of the etched tracks by an automatic track counting system was studied. It is found that the track density increases with the increase of neutron dose and etching time. The track density in the detector is directly proportional to the neutron fluence producing the recoil tracks, provided the track density is in the countable range. This fact plays an important role in determining the equivalent dose in the field of neutron dosimetry. These results are compared with previous work. It is found that our results are in good agreement with their investigations.      

Nuclear emissions during self-nucleated acoustic cavitation

A unique, new stand-alone acoustic inertial confinement nuclear fusion test device was successfully tested. Experiments using four different liquid types were conducted in which bubbles were self-nucleated without the use of external neutrons. Four independent detection systems were used (i.e., a neutron track plastic detector to provide unambiguous visible records for fast neutrons, a detector, a NE-113-type liquid scintillation detector, and a NaI gamma ray detector). Statistically significant nuclear emissions were observed for deuterated benzene and acetone mixtures but not for heavy water. The measured neutron energy was 相似文献   

Fluorescent Aluminum Oxide Crystals for Volumetric Optical Data Storage and Imaging Applications

New fluorescent aluminum oxide crystals (Al₂O₃:C,Mg) for volumetric optical data storage and imaging applications were investigated. Magnesium impurity and double oxygen vacancy aggregate defects are responsible for the main optical properties of the new material. Spectroscopic investigation of these defects in different charge states was performed. Optical absorption, excitation-emission spectra and fluorescent lifetime of the new fluorescent medium were studied. Quantum yield of fluorescence from Al₂O₃:C,Mg crystals was measured in comparison with standard laser dyes.     

The influence of Fe,Cu, SiO<Subscript>2</Subscript>, TiO<Subscript>2</Subscript>, and Al<Subscript>2</Subscript>O<Subscript>3</Subscript> nanoparticles in aqueous solution on proton relaxation times

Measurements of proton nuclear spin-spin and spin-lattice relaxation times are applied for determining the concentration of solid-phase nanoparticles in nanofluids. This approach is tested for metal oxides SiO₂, TiO₂, Al₂O₃ and metal-carbon nanoparticles of 3d-metals Fe and Cu. It is shown that the sensitivity of the method for determining concentrations of 3d-metals is much higher than for oxides (by 2–4 orders of magnitude). It is revealed that measurement of the proton spin-spin relaxation time allows one to determine the concentration of Cu nanoparticles to 0.0001 mg/ml and that of Fe nanoparticles to 0.00001 mg/ml.     

The improvement of Al2O3/AlGaN/GaN MISHEMT performance by N2 plasma pretreatment

This paper discusses the effect of N 2 plasma treatment before dielectric deposition on the electrical performance of a Al2O3 /AlGaN/GaN metal-insulator-semiconductor high electron mobility transistor(MISHEMT),with Al2O3 deposited by atomic layer deposition.The results indicated that the gate leakage was decreased two orders of magnitude after the Al2O3 /AlGaN interface was pretreated by N 2 plasma.Furthermore,effects of N 2 plasma pretreatment on the electrical properties of the AlGaN/Al2O3 interface were investigated by x-ray photoelectron spectroscopy measurements and the interface quality between Al2O3 and AlGaN film was improved.     

Study of fission track registration efficiency of γ-irradiated polyester track detector in solution medium

The fission track registration efficiency (K _wet) of the Garware polyester track (GPF) detector in solution has been determined with respect to the Lexan detector whose K _wet is very well known in the literature. The K _wet is found to be (1.2 ± 0.1) 10⁻³ cm. The track registration efficiency of the GPF detector in solution is better than the efficiencies of other nuclear track detectors reported in the literature. This implies that the threshold energies for track registration are different for different detectors and that GPF detector has a lower threshold-energy value. The effects of gamma irradiation in the dose range of 5–51 Mrad on the fission track registration efficiency (K _wet) of this track detector from the solution medium are also investigated. The results show that the K _wet values for the gamma-irradiated detectors in the above dose range in 2M HNO₃ solution medium decreases by ∼7–15%. The changes induced in the gamma-irradiated detectors as a function of gamma dose have also been studied by bulk-etch rate measurements.     

Color changes in CR-39 nuclear track detector by gamma and laser irradiation

A study of the effect of gamma and laser irradiation on the color changes of polyallyl diglycol (CR-39) solid-state nuclear track detector was performed. CR-39 detector samples were classified into two main groups. The first group was irradiated with gamma doses at levels between 20 and 300 kGy, whereas the second group was exposed to infrared laser radiation with energy fluences at levels between 0.71 and 8.53 J/cm². The transmission of these samples in the wavelength range 300–2500 nm, as well as any color changes, was studied. Using the transmission data, both the tristimulus and the coordinate values of the Commission Internationale de l'Eclairage (CIE) LAB were calculated. Also, the color differences between the non-irradiated samples and those irradiated with different gamma or laser doses were calculated. The results indicate that the CR-39 detector acquires color changes under gamma or laser irradiation, but it has more response to color changes by gamma irradiation. In addition, structural property studies using infrared spectroscopy were performed. The results indicate that the irradiation of a CR-39 detector with gamma or laser radiations causes the cleavage of the carbonate linkage that can be attributed to the ?H abstraction from the backbone of the polymer, associated with the formation of CO₂ and ?OH with varying intensities.     

Thermoluminescence of Al2O3:Cr3+ films synthesized by the nonaqueous sol–gel method

The thermoluminescence (TL) properties of Al₂O₃:Cr³⁺ thin films prepared by the nonaqueous sol–gel method were evaluated. The obtained thin films were characterized by scanning electron microscope and energy dispersive spectrometry. They were irradiated with ⁶⁰Co gamma rays of the different doses. TL glow curves exhibited two peaks centered at 197°C and 322°C.The heights of peaks were found to be sensitive to exposures of ionizing irradiation and the integral area of the TL signals had a linear response in the dose range of 5–60 Gy.This remarkable result suggests that Al₂O₃:Cr³⁺ films might potentially be used for radiation dosimetry.     

Preliminary study on development and characterization of high sensitivity LiAlO2 optically stimulated luminescence material

Preliminary results of an attempt to prepare LiAlO₂ material with high optically stimulated luminescence (OSL) sensitivity are reported. LiAlO₂ was prepared by melting a stoichiometric mixture of Li₂CO₃ and Al₂O₃ powders in a RF heating furnace. CW-OSL signal as recorded on Risoe TL/OSL reader using blue (470 nm) stimulation was found to be up to 16 times of that of Al₂O₃:C. The promising characteristics of LiAlO₂, open up a possibility of an improved material not only for passive dosimetry of mixed fields of neutron and gamma rays but also for online measurements and dose mapping/imaging applications.     

Gamma and neutron dose measurements with solid state nuclear track detectors

An attempt has been made to explore the possibility of using solid state nuclear track detectors for the estimation of gamma and neutron doses based on the use of changes in activation energy of degradation of these detectors, due to irradiation (gamma-neutron), as a means of dosimetry. Thermogravimetry (TG) has been applied as a tool for these studies carried out on Lexan and CR-39 track detectors. A linear relationship observed between the decrease in activation energy and the dose (gamma-neutron) received by the detectors suggests the possibility of the use of these detectors as gamma and neutron dosimeters.      

Study of directionally solidified ceramics by neutron diffraction methods

The effect of the growth rate of directionally solidified Al₂O₃-Y₃Al₅O₁₂ ceramics on the structural perfection of the two-phase material is studied by low-angle neutron scattering, as well as by constant-wavelength and time-of-flight neutron diffraction methods. When the growth rate is high, the orientation and size of Y₃Al₅O₁₂ needles remain unchanged, while the Al₂O₃ matrix phase decomposes into crystallites. Neutron diffraction methods are viewed as an effective tool for flexible crystal growth control.     

Comparison between blue and green stimulated luminescence of Al2O3:C

This paper presents a systematic comparison of OSL signals from Al₂O₃:C when stimulated with blue and green light. Al₂O₃:C detectors were irradiated with various doses and submitted to various bleaching regimes using yellow, green and blue light. Most of the investigations were carried out using Luxel?-type detectors used in the commercial Luxel? and InLight? dosimetry systems (Landauer Inc.). Al₂O₃:C single crystals and Al₂O₃:C powder were also used to complement the investigations. The results show that, although blue stimulation provides faster readout times (OSL curves that decayed faster) and higher initial OSL intensity than green stimulation, blue stimulation introduced complicating factors. These include incomplete bleaching of the dosimetric trap when the Al₂O₃:C detectors are bleached with yellow or green light and the OSL is recorded with blue light stimulation, and an increased residual level due to stimulation of charge carriers from deep traps. The results warrant caution when using blue stimulation to measure the OSL signal from Al₂O₃:C detectors, particularly if the doses involved are low and the detectors have been previously exposed to high doses.     

Remarks on “Piezonuclear neutrons from fracturing of inert solids”

Carpinteri et al. [F. Cardone, A. Carpinteri, G. Lacidogna, Physics Letters A 373 (2009) 4158] reported that by the sudden fracture of granite blocks under pressure P?94.4 MPa ejects a stream of neutrons catch by a ³He detector and displayed by a “BD” dosimeter. As claimed, these neutrons come from the fission reaction being the compound Fe₂O₃ present at 3% in granite. We would like to point out the inconsistency of this endothermic nuclear reactions. No gamma rays measurements associated with any nuclear reactions and no radioactive isotopes in fractured granite blocks are reported. It is claimed strictly radiation-less reactions (except for the neutrons). Our remarks are related to the incompleteness of experimental set-up and data speculation. Mistake in the analysis of neutron detection due to intense acoustic signal or charged particle emitted in fractoemission phenomena is suggested.     

Environmental gamma-ray dose rate measurement by using ultra-high sensitive LiF:Mg,Cu,Si TLD

Environmental gamma-ray dose rates were measured by using ultra-high sensitive LiF:Mg,Cu,Si thermoluminescence dosimeters (TLDs) during short-term burial. The resultant gamma-ray dose rates were compared with those measured by using optically stimulated luminescence (OSL) of Al₂O₃:C and assessed by using HPGe spectrometer. Regardless of the short-term burial and the change of environmental conditions as well as the mismatch of the effective atomic number (Z_eff) with the soil (mainly SiO₂), good agreement was observed between the doses measured by TLDs and OSL dosimeters or the assessed doses. LiF:Mg,Cu,Si TLD has been found to be an effective alternative for the measurement of environmental gamma-ray annual dose rates for use in optical dating.     

A new method for measuring tracks density in CR-39 detectors by compensating for overlapping tracks

CR-39 nuclear track detectors have been used as an efficient radon monitoring system. Exposing these detectors to radon would result in tracks where ever particles hit the surface of the detector. Natural radioactivity of alpha particles (radon concentration) is measured based on the count of these tracks on CR-39 detector. Counting these tracks by eye is not an easy task especially when the density of the tracks is high. Automated tracks counting systems are attractive solution for this problem. However, as the density of tracks increases the accuracy of these methods deteriorates. This is due to the fact that overlapped tracks are counted as one track during the segmentation process resulting in an underestimation of the real count of the tracks. This work proposes a new image processing based automated approach for tracks counting. This new automated approach solves the problem of counting overlapping tracks by approximating their number and then adjusting the final count of tracks by compensating for those uncounted tracks. The experimental results show that the proposed approach reduces the counting percentage error from 5.64% to 2.54% by solving the counting problem of the overlapped tracks.