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Results for “RADIATION, GAMMA”

Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.

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At least 19 records

Method and system for calibrating gamma radiation flux levels in a solid state gamma radiation detection system

One aspect of the present disclosure comprises a method for calibrating a drive level of a non-radioactive calibration source. Another aspect of the present disclosure comprises a method for using a non-radioactive calibration source to verify correct operation of a radiation detector. Another aspect of the present disclosure comprises a radiation detection system that comprises a radiation detector and a non-radioactive calibration source that is used to verify correct operation of the radiation detector.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

Aging mechanisms of filled cross-linked polyethylene (XLPE) cable insulation material exposed to simultaneous thermal and gamma radiation

Thermal and simultaneous thermal and gamma radiation aging experiments were conducted on an industry grade cross-linked polyethylene (XLPE) cable insulation material, which is a composite material with XLPE as polymer matrix and various additives and fillers. Reverse engineering was conducted to identify and quantify the material composition given that this information was not revealed by the cable manufacture. Samples were then aged at temperatures of 60, 90, and 115 °C, exposed to gamma radiation for total doses of 0 to 324 kGy, and at dose rates of 0 to 540 Gy/h. Aging mechanisms were studied using various materials characterization techniques including pyrolysis gas chromatography mass spectrometry (Py-GCMS), differential scanning calorimetry (DSC), nuclear magnetic resonance spectroscopy (NMR), and gel-fraction tests. Results show that the flame-retardant components were decomposed into smaller molecules when the material was exposed to gamma radiation, while no changes were observed when the samples were aged thermally without gamma radiation. With exposure to gamma radiation, the crystalline phase of the XLPE were damaged by gamma radiation introducing defects in the crystals, resulting in smaller and less perfect crystals. The dominance of chain scission or chain reformation process largely depends on the chain mobility, which is decided by the aging temperature. Chain scission was seen to dominate when the material was exposed to gamma radiation at 60 °C. Chain cross-linking slightly dominated when the material was exposed to gamma radiation at 90 °C and became more dominant with exposure to gamma radiation at 115 °C. No significant change to the XLPE polymer matrix was observed when the samples were exposed to thermal aging without gamma radiation. Finally, antioxidant is more effective in protecting the XLPE polymer matrix under thermal aging, but less effective with sample exposure to gamma radiation.

38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEA↗

Differential sensitivity of Chironomus and human hemoglobin to gamma radiation

Chironomus ramosus is known to tolerate high doses of gamma radiation exposure. Larvae of this insect possess more than 95% of hemoglobin (Hb) in its circulatory hemolymph. This is a comparative study to see effect of gamma radiation on Hb of Chironomus and humans, two evolutionarily diverse organisms one having extracellular and the other intracellular Hb respectively. Stability and integrity of Chironomus and human Hb to gamma radiation was compared using biophysical techniques like Dynamic Light Scattering (DLS), UV-visible spectroscopy, fluorescence spectrometry and CD spectroscopy after exposure of whole larvae, larval hemolymph, human peripheral blood, purified Chironomus and human Hb. Sequence- and structure-based bioinformatics methods were used to analyze the sequence and structural similarities or differences in the heme pockets of respective Hbs. Resistivity of Chironomus Hb to gamma radiation is remarkably higher than human Hb. Human Hb exhibited loss of heme iron at a relatively low dose of gamma radiation exposure as compared to Chironomus Hb. Unlike human Hb, the heme pocket of Chironomus Hb is rich in aromatic amino acids. Higher hydophobicity around heme pocket confers stability of Chironomus Hb compared to human Hb. Previously reported gamma radiation tolerance of Chironomus can be largely attributed to its evolutionarily ancient form of extracellular Hb as evident from the present study. -- Highlights: •Comparison of radiation tolerant Chironomus Hb and radiation sensitive Human Hb. •Amino acid composition of midge and human heme confer differential hydrophobicity. •Heme pocket of evolutionarily ancient midge Hb provide gamma radiation resistivity.

60 APPLIED LIFE SCIENCES↗

Evaluating Photocatalysts Using Gamma Radiation

A large amount of attention has been given to photocatalysts using UV radiation as the source of excitation; however, little work has been done to study photocatalysis using higher energy excitation sources, such as gamma or x-rays. During excitation, the photocatalyst absorbs light to produce electron-hole pairs (excitons). These excitons can react with absorbed species to yield reactive radical species that can degrade compounds or induce redox (oxidation-reduction) reactions. Common examples of semiconductor photocatalysts include: TiO{sub 2}, ZnO, Fe{sub 2}O{sub 3}, ZrO{sub 2}, and SnS. This project was conducted to investigate the photocatalytic oxidation of iron using gamma irradiation and several different semiconductor photocatalysts. Photometric Measurements: Photometric determination of Fe{sup II} and Fe{sup III} were made using a Cary 60 UV-Vis Spectrometer over a range of 800 - 200 nm at a scan rate of 60 nm/sec. Ferric (Fe{sup III}) ions have no detectable UV-vis spectrum, thus the absence of a peak in iron-based samples was taken as evidence of Fe{sup III} formation. Solution Preparation: Iron II (Fe{sup II}) standards were made by dissolving FeCl{sub 2}.6H{sub 2}O in deionized water using a sonicator. A solution of 1,10- phenanthroline was made by adding 40 mg of 1,10-phenanthroline to 20 mL of deionized water and sonicating for 60 minutes until a clear solution was obtained. Gamma Radiation Tests: Irradiated samples were exposed to Co-60 gamma radiation (1.17 MeV gamma) at a dose rate of ∼1 x 10{sup 5} Rad/hr Co-60. All samples were irradiated in glass scintillation vials. The presence of 30 mg of SnS reduces the amount of Fe{sup II} in solutions under gamma irradiation relative to samples with no SnS added. Fe{sup II} concentration decreases as irradiation time increases. This effect is enhanced when SnS is present. Fe{sup II} appears to decrease linearly with time. We found that the addition of SnS semiconductor, when combined with gamma radiation, oxidized more Fe{sup II} in the FeCl{sub 2} solution than gamma radiation alone. This suggests that SnS can be used as a photocatalyst using gamma radiation as the excitation source, although more detailed experiments are needed to confirm this belief. The next phase of this project would be to refine the preliminary results by determining exact quantities of SnS semiconductor and gamma radiation that induce sufficient redox. Repeated experiments with more samples could also give more data points for a chance at more representative and accurate data with error bars and standard deviations. Also, other semiconductors could possibly be tested to see how their effect on redox chemistry compares to that of SnS. The scope of this project could also be extended to include other metal or organic solutions to see if similar redox could be obtained.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

Detection system for high-resolution gamma radiation spectroscopy with neutron time-of-flight filtering

A .gamma.-radiation detection system that includes at least one semiconductor detector such as HPGe-Detector, a position-sensitive .alpha.-Detector, a TOF Controller, and a Digitizer/Integrator. The Digitizer/Integrator starts to process the energy signals of a .gamma.-radiation sent from the HPGe-Detector instantly when the HPGe-Detector detects the .gamma.-radiation. Subsequently, it is determined whether a coincidence exists between the .alpha.-particles and .gamma.-radiation signal, based on a determination of the time-of-flight of neutrons obtained from the .alpha.-Detector and the HPGe-Detector. If it is determined that the time-of-flight falls within a predetermined coincidence window, the Digitizer/Integrator is allowed to continue and complete the energy signal processing. If, however, there is no coincidence, the Digitizer/Integrator is instructed to be clear and reset its operation instantly.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

Gamma Radiation Effects in Amorphous and Crystalline Polyaryletherketones

This work investigates the effect of gamma radiation on chain scission and crosslinking in polyaryletherketone (PAEK) thermoplastic filaments, namely, polyetheretherketone (PEEK) and polyetherketoneketone (PEKK) that is either semicrystalline (PEKK-c) or highly amorphous (PEKK-a). The PAEK thermoplastic filaments were exposed to total ionizing doses (TID) of gamma radiation from 1 to 8 MGy in the Gamma Irradiation Facility at Sandia National Laboratories. A combination of thermal and FT-IR spectral analysis of the irradiated specimens was used to study the chain scission and crosslinking behavior between PEEK, PEKK-c, and PEKK-a. Crystallinity decreased with increased TID and melt enthalpy decreased. Despite clear indications of changes to melt and crystallization behavior, any change to the glass-transition temperature was minor until a post-irradiation thermal annealing occurred, which caused an increase in crystallinity. Gamma radiation impacted PEKK-a more due to the lower degree of initial crystallinity, where a reduction in melt enthalpy, crystallinity, and crystallization kinetics was observed. Despite these effects, the ability to achieve a higher degree of crystallization (X c < 20%) by annealing was not affected. The results presented here provide important insight into the performance of a class of commercialized PEKK thermoplastics exposed to a harsh radiation environment.

Crystallinity↗

Gamma Radiation Monitoring Data

This dataset contains gamma-ray total counts in counts/minute (cpm), every 15-minutes, from the Gamma Radiation Monitoring campaign at the ENA site (Graciosa, Azores).

54 ENVIRONMENTAL SCIENCES↗

Materials for Gamma Radiation Sensors

Sensors used for spectroscopic measurements of gamma radiation are most often scintillator or semiconductor materials. An overview is provided in this chapter on the materials and development techniques used in producing spectroscopic gamma radiation sensors. Challenges that prevent a perfect sensor are discussed along with the reasons why some sensor materials are ubiquitous despite their performance limitations. The types of sensors commonly used as detectors are discussed along with their key physical properties and electronic characteristics. Materials commonly utilized in radiation detectors are then reviewed to highlight how sensor materials have advanced since the earliest gamma detectors were developed

Johns, Paul M.↗

Development of Hopfield Artificial Neural Network for Anomaly Detection in Environmental Gamma Radiation Background: Consortium on Nuclear Security Technologies (CONNECT) (Q2 Report)

Environmental screening of gamma radiation consists of detecting weak nuisance and anomaly signal in the presence of strong and highly varying background. In a typical scenario, a mobile detector-spectrometer continuously measures gamma radiation spectra in short, e.g., one-second, signal acquisition intervals. The measurement data is a 2D matrix, where one dimension is gamma ray energy, and the other dimension is the number of measurements or total time. In principle, gamma radiation sources can be detected and identified from the measured data by their unique spectral lines. Detecting sources from data measured in a search scenario is difficult due to the highly varying background because of naturally occurring radioactive material (NORM), and low signal-to-noise ratio (S/N) of spectral signal measured during one-second acquisition intervals. The objective of this work is to explore supervised machine learning (ML) algorithms for development of a Hopfield Neural Network (HNN) in conjunction with an image processing algorithm for detection and identification of weak nuisances and anomalies events in the presence of a highly fluctuating background.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

1 H NMR metabolomics study of spleen from C57BL/6 mice exposed to gamma radiation

Due to the potential risk of accidental exposure to gamma radiation, it’s critical to identify the biomarkers of radiation exposed creatures. In the present study, NMR based metabolomics combined with multivariate data analysis to evaluate the metabolites changed in the C57BL/6 mouse spleen after 4 days whole body exposure to 3.0 Gy and 7.8 Gy gamma radiations. Principal component analysis (PCA) and orthogonal projection to latent structures analysis (OPLS) are employed for classification and identification potential biomarkers associated with gamma irradiation. Two different strategies for NMR spectral data reduction (i.e., spectral binning and spectral deconvolution) are combined with normalize to constant sum and unit weight before multivariate data analysis, respectively. The combination of spectral deconvolution and normalization to unit weight is the best way for identifying discriminatory metabolites between the irradiation and control groups. Normalized to the constant sum may achieve some pseudo biomarkers. PCA and OPLS results shown that the exposed groups can be well separated from the control group. Leucine, 2-aminobutyrate, valine, lactate, arginine, glutathione, 2-oxoglutarate, creatine, tyrosine, phenylalanine, π-methylhistidine, taurine, myoinositol, glycerol and uracil are significantly elevated while ADP is decreased significantly. As a result, these significantly changed metabolites are associated with multiple metabolic pathways and may be potential biomarkers in the spleen exposed to gamma irradiation.

1H NMR metabolomics↗

Sterilization of N95 Respirators via Gamma Radiation: Comparison of Post-sterilization Efficacy

This study evaluated gamma irradiation for sterilization and reuse of two models of N95 respirators after gamma radiation sterilization as a method to increase availability of N95 respirators during a shortage. The Sandia National Laboratories Gamma Irradiation Facility was used to irradiate two different models of N95 filtering facepiece respirators at doses ranging from 0 kGy(tissue) to 50 kGy(tissue). The following tests were used to determine the efficacy of the respirator after irradiation sterilization: Ambient Aerosol Condensation Nuclei Counter Quantitative Fit Test, tensile test, strain cycling, oscillatory dynamic mechanical analysis, microscopic image analysis of fiber layers, and electrostatic field measurements. Both of the respirator models exhibited statistically significant changes after gamma irradiation as shown by the Quantitative Fit Test, electrostatic testing and the aerosol testing. The change in electrostatic charge of the filter was correlated with a reduction in capturing particles near the 200 nm size by approximately 40-50%. Both tested respirators showed statistically significant changes associated with gamma sterilization. However, our results indicate that choices in materials and manufacturing methods to achieve N95 filtration lead to different magnitudes of damage when exposed to gamma radiation at sterilization relevant doses. This damage results in lower filtration performance. While our sample size (2 different types of respirators) was small, we did observe a change in electrostatic properties on a filter layer that coincided with the failure on the Quantitative Fit Test and reduction in aerosol filtering efficiency. Key Words: N95 respirators, respirators, airborne transmission, pandemic prevention, COVID-19, gamma sterilization

COVID-19↗

Sterilization of N95 Respirators via Gamma Radiation: Comparison of Post-sterilization Efficacy

This study evaluated gamma irradiation for sterilization and reuse of two models of N95 respirators after gamma radiation sterilization as a method to increase availability of N95 respirators during a shortage. The Sandia National Laboratories Gamma Irradiation Facility was used to irradiate two different models of N95 filtering facepiece respirators at doses ranging from 0 kGy(tissue) to 50 kGy(tissue). The following tests were used to determine the efficacy of the respirator after irradiation sterilization: Ambient Aerosol Condensation Nuclei Counter Quantitative Fit Test, tensile test, strain cycling, oscillatory dynamic mechanical analysis, microscopic image analysis of fiber layers, and electrostatic field measurements. Both of the respirator models exhibited statistically significant changes after gamma irradiation as shown by the Quantitative Fit Test, electrostatic testing and the aerosol testing. The change in electrostatic capability of the filter reduced the efficiency of challenging particles near the 200 nm size by approximately 40-50%. Both tested respirators showed statistically significant changes associated with gamma sterilization. However, our results indicate that choices in materials and manufacturing methods to achieve N95 filtration lead to different magnitudes of damage when exposed to gamma radiation at sterilization relevant doses. This damage results in lower filtration performance. While our sample size (2 different types of respirators) was small, we did observe a change in electrostatic properties on a filter layer that coincided with the failure on the Quantitative Fit Test.

61 RADIATION PROTECTION AND DOSIMETRY↗

Detection of Anomalies in Environmental Gamma Radiation Background with Hopfield Artificial Neural Network - Consortium on Nuclear Security Technologies (CONNECT) Q3 Report

Environmental screening of gamma radiation consists of detecting weak nuisance and anomaly signal in the presence of strong and highly varying background. In a typical scenario, a mobile detector-spectrometer continuously measures gamma radiation spectra in short, e.g., one-second, signal acquisition intervals. The measurement data is a 2D matrix, where one dimension is gamma ray energy, and the other dimension is the number of measurements or total time. In principle, gamma radiation sources can be detected and identified from the measured data by their unique spectral lines. Detecting sources from data measured in a search scenario is difficult due to the highly varying background because of naturally occurring radioactive material (NORM), and low signal-to-noise ratio (S/N) of spectral signal measured during one-second acquisition intervals. The objective of this work is to investigate performance of a Hopfield Neural Network (HNN) in in detection and identification of weak nuisances and anomalies events in the presence of a highly fluctuating background. Performance of HNN algorithm is benchmarked using search data from an environmental screening campaign. One data set contained a 137 Cs source, and another dataset contained a 131 I source.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

Attenuation of Neutron and Gamma Radiation by a Composite Material Based on Modified Titanium Hydride with a Varied Boron Content

The investigations on estimating the attenuation of capture gamma radiation by a composite neutron-shielding material based on modified titanium hydride and Portland cement with a varied amount of boron carbide are performed. The results of calculations demonstrate that an introduction of boron into this material enables significantly decreasing the thermal neutron flux density and hence the levels of capture gamma radiation. In particular, after introducing 1- 5 wt.% boron carbide into the material, the thermal neutron flux density on a 10 cm-thick layer is reduced by 11 to 176 factors, and the capture gamma dose rate – from 4 to 9 times, respectively. The difference in the degree of reduction in these functionals is attributed to the presence of capture gamma radiation in the epithermal region of the neutron spectrum.

61 RADIATION PROTECTION AND DOSIMETRY↗

Regional Shelter Analysis – External Gamma Radiation Exposure Methodology

During normal operations, buildings can protect their occupants from outdoor hazards, including nuclear fallout and other external gamma radiation hazards. Purposeful sheltering can increase this protection. The physics of building protection against external gamma radiation is relatively well understood and we can characterize the protection afforded by individual buildings. However, an operationally efficient, regional-scale methodology to account for building protection effects has not previously been available. Such a method is necessary because (a) the overwhelming majority of the US population is indoors at any given time and (b) a regional-level building protection methodology could better estimate populations truly at risk in emergencies, support improved decision-making (shelter vs. evacuation decisions), and help guide resources towards those most at risk. The Regional Shelter Analysis (RSA) methodology provides a comprehensive, yet operationally efficient method for population-based risk analyses. Specifically, it accounts for (a) building protection distributions (within and among different buildings) and (b) population postures (how people are distributed within and outside of buildings). The RSA method could support a common operating picture by providing user specific results that have the resolution appropriate for individual user’s needs while still being consistent with the information being provided to the other users. The method employs existing building and population databases and is compatible with most modern exposure and injury assessment tools. This report presents the RSA methodology and discusses general operational considerations, with a focus on external gamma radiation exposures. To place this work in the context of prior efforts and current initiatives, a focused literature review is provided that identifies the relevant literature, scientific findings, and datasets from a variety of scientific fields. Other reports in this series will discuss (a) the inhalation exposure pathway and (b) specific RSA implementations.

54 ENVIRONMENTAL SCIENCES↗

Advanced performance and scalability of Si nanowire field-effect transistors analyzed using noise spectroscopy and gamma radiation techniques

High-quality Si nanowire field effect transistors (FETs) were fabricated using thermal nanoimprint and chemical wet etching technologies. FET structures of different lengths demonstrate high carrier mobility with values of about 750 cm{sup 2}/Vs and low volume densities of active traps in the dielectric layers of 5 × 10{sup 17} cm{sup −3} eV{sup −1}. We investigated the transport properties of these n-type channel structures using low-frequency noise spectroscopy before and after gamma radiation treatment. Before gamma irradiation, FET structures with lengths of less than 4 μm exhibited noise from contact regions with 1/(L{sup 2}) dependence for the relative 1/f noise. After gamma radiation, the spectra reflected the priority of channel noise with 1/L dependence for all samples. The transport characteristics show that the fabricated nanowire FETs improved scalability, decreased parameter scattering, and increased stability after treatment. The results demonstrate that these nanowire FETs are promising for nanoelectronic and biosensor applications due to the cost-efficient technology and advanced performance of FETs with improved stability and reliability.

71 CLASSICAL AND QUANTUM MECHANICS, GENERAL PHYSIC↗

The role of gamma radiation on zircaloy-4 corrosion - 2016-0029

A key microstructural feature of irradiated oxide films that form on Zircaloy-4 is the development of significant amounts of interconnected porosity or microcracking, particularly along oxide grain boundaries. This development disrupts the protective nature of the barrier layer, effectively resulting in an increase in the observed post-transition corrosion rates. This observation suggests that some aspect of oxide dissolution may be occurring. It is noteworthy that when exposed to photons with energies greater than that of the oxide band gap, n-type semiconducting oxides are prone to dissolution. Because zirconia (ZrO{sub 2}) is an n-type semiconductor, it is plausible that high-energy photons may play an important role in corrosion. In an operating nuclear reactor, neutron and gamma flux levels are closely interrelated because they arise, for the most part, from the same originating process (i.e., the fissioning of nuclear fuel). Thus, it is difficult to isolate the independent effects of neutron and gamma radiation on corrosion. It is, however, theoretically conceivable to assess the role that gamma radiation may have on corrosion by comparing instances where variations in radiation environment exists; specifically by comparing where variations in gamma flux levels relative to neutron flux levels within different regions of a reactor or from reactor to reactor exist. Comparisons of the corrosion rates obtained between two different reactors (the Halden test reactor and the advanced test reactor [ATR]) that have differing gamma-to-neutron ratios were performed. In addition, an examination of corrosion rate data from the ATR, in which a variation in gamma-to-neutron flux ratio exists, was also conducted. Results are presented, from both assessments, which indicate that gamma radiation plays a role in the irradiated corrosion behavior of Zircaloy-4. In addition to a discussion of experimental data, potential mechanisms associated with photon-induced oxide dissolution of n-type semiconducting oxides, such as zirconia, is also provided. (authors)

36 MATERIALS SCIENCE↗

Neutron and Gamma Radiation Monitoring at The Ion Beam Laboratory Building 720 Sandia/NM

Neutron and gamma radiation spectra and dose rates were measured in and around the Ion Beam Laboratory, Building 720, at Sandia/NM. Measurements were made to support the testing of an enhanced target yielding 14 MeV neutrons from the deuterium-tritium (D-T) fusion reaction. The target room has thick concrete walls but an unshielded ceiling. Neutron and gamma radiation in and around the facility appear to be the result of skyshine. Estimates of neutron/gamma dose rates (per 10 9 source neutrons/s) at six (6) monitoring locations were made. Results indicated the need for enhanced radiological controls due to increased neutron production rates.

61 RADIATION PROTECTION AND DOSIMETRY↗