Application Of Neutron Activation Analysis Research Articles

Preliminary results on the applicability of neutron activation analysis (NAA) to identify cherts from the Munsungun Lake Formation, Maine, USA

AbstractRed chert attributed to the Munsungun Lake Formation, Maine, USA is common in late Pleistocene fluted‐point‐period archaeological sites located throughout the New England states and Quebec, appearing more frequently than any other material type in the region. Despite the assumed association between red Munsungun chert and fluted‐point‐period sites, until recently, it was not possible to link red chert artifacts from these sites to a specific source area within the Munsungun Lake Formation because outcrops of this material associated with direct evidence of past use were not documented. Here, we report the first results of a neutron activation analysis (NAA) study of red Munsungun chert from two quarry areas within the Munsungun Lake Formation. These results suggest that NAA can distinguish between chert source areas within the Munsungun Lake Formation and lookalike materials from the wider region. Additional analyses are required to include more comparative samples and evaluate the efficacy of less destructive geochemical techniques in characterizing cherts from the region. Despite the need for additional research, these results suggest that NAA will be useful for re‐evaluating past identifications of chert from the Munsungun Lake Formation, providing an important foundation for additional geochemical research in the region.

Yield calculation for delayed gamma-ray neutron activation analysis

Predicting the analysis sensitivities of interested elements is one of the major concerns in various applications of neutron activation analysis (NAA). As the specific gamma-ray yield after the neutron irradiation could be affected by the irradiating neutrons’ spectrum, which can hardly be constant for NAA applications of different interested elements (and matrix elements) that need their own customized optimal neutron moderators, a calculator for predicting the analysis sensitivities of NAA should be able to consider all the contributions of neutrons with different energies. In this study, a MATLAB-based code, named as CYANUS (the Calculator for Yield Analysis of NeUtron Activation) is developed to quantitatively evaluate the specific yields of delayed gamma-rays released from the neutron irradiated objects. The comparison between the results calculated by CYANUS and those from other currently available online programs demonstrates that this work shows the smallest relative error with respect to the experimentally measured results, indicating that CYANUS is promising to provide an accurate evaluation of the specific gamma-ray yields when the object is irradiated by customized neutron spectrum in the NAA applications.

Neutron activation analysis in Mediterranean Archaeology: current applications and future perspectives

This paper, jointly written by participants of a workshop held in 2021, argues for an increased recognition and application of neutron activation analysis (NAA) in the archaeology of the ancient Mediterranean. Discussing the methodological strengths and challenges, it highlights the great potential NAA has for collecting proxy data from ceramics in order to develop progressive concepts of archaeological research within and beyond the Mediterranean Bronze and Iron Age, pointing out opportunities to revisit long-held assumptions of scholarship and to refine visual/macroscopic provenance determinations of pottery. To take full advantage of NAA’s strengths toward a better understanding of the socioeconomic background of ceramics production, distribution, and consumption, the paper emphasises the need for both interdisciplinary collaboration and basic data publication requirements.

Reevaluation of Spectral Parameters and Neutron Fluxes in IC-7 Irradiation Channel of TRIGA MARK I IPR-R1 Research Nuclear Reactor

Abstract The core configuration of the Training Research Isotopes General Atomics (TRIGA) MARK I IPR-R1 nuclear research reactor at Nuclear Technology Development Centre (CDTN), Belo Horizonte, Brazil, has been modified six times since the first criticality and the neutron fluxes have been determined using experimental and semitheoretical methodologies determining the neutron fluxes in different irradiation channels and devices, applying different procedures and materials. This reactor operates at 100 kW; however, after new configuration for 250 kW in 2001, the carousel no longer rotates during irradiations aiming at preserving the rotation mechanism. In 2003, the spectral parameters were determined experimentally by the “Cd-ratio for multimonitor” in five specific channels aiming at the application of neutron activation analysis (NAA) k0-standardized method. The determinations were repeated applying the same procedure in 2016, 2018, and 2019. Values for thermal and epithermal neutron fluxes as well as f and α spectral parameters were determined. The experimental results for certified reference material BCR-320R were calculated by the k0-method of NAA, using the spectral parameters for irradiation channel IC-7 obtained in 2003, 2016, 2018, and 2019 and evaluated by En-score. The values showed that the differences in the results compared to those in 2003 were lower than 2.5%, inside the uncertainty of the method. It shows that the k0-method installed in CDTN is reliable and useful for various purposes. The results of the spectral parameter f presented small differences, in a period of 16 years, pointing out the stability of operation of the reactor TRIGA MARK I IPR-R1.

Application of neutron activation analysis for the comparison of eleven trace elements contents in thyroid tissue adjacent to thyroid malignant and benign nodules

Application of neutron activation analysis for the comparison of eleven trace elements contents in thyroid tissue adjacent to thyroid malignant and benign nodules

Neutron spectrum determination of accelerator-driven d(10)+Be neutron source using the multi-foil activation technique

New neutron field of the compact accelerator-driven fast neutron source based on the cyclotron and beryllium target station was studied and developed at the NPI CAS. Neutrons were generated using the deuteron bombardment on 8 mm thick beryllium layer by the 10.3 MeV deuteron beam. Broad neutron energy spectra of the d(10)+Be source reaction at two source-to-sample distances (14 mm and 154 mm) were determined for the first time at the NPI. Sets of eight activation materials comprising Au, Co, Ti, In, Al, Fe, Ni, and Nb were irradiated in the d(10)+Be neutron field, and activated dosimetry foils were analysed using the nuclear gamma-spectroscopy technique (HPGe detector) and reaction rates were measured. Neutron energy spectra of the d + Be source reaction for 10.3 MeV deuterons were reconstructed employing the modified version of the SAND-II unfolding code. For 9.7 μA deuteron beam, the fast neutron flux of developed d(10)+Be neutron field reached the value of 1.4 × 1010 cm−2s−1 at a distance of 14 mm from the source target and 4.1 × 108 cm−2s−1 at a distance of 154 mm. The novel d(10)+Be neutron field with energy range up to 15 MeV is convenient for neutron cross-section data validation, experimental simulation of the fast neutron spectrum of experimental nuclear reactors, applications of neutron activation analysis, and radiation hardness tests of materials important for nuclear energetics.

Neutronic feasibility study of using a multipurpose MNSR for BNCT, NR, and NAA

In this study, the conceptual design of a multipurpose research reactor for boron neutron capture therapy (BNCT), neutron radiography (NR) and neutron activation analysis (NAA) applications has been performed. Specifically, a suitable epithermal neutron flux (φEpi) of about 1×109 (n.cm−2.s−1) for BNCT and high quality thermal neutron flux (φTh) of above 1×106 (n.cm−2.s−1)for NR are carried out based on our LEU reactor core designing. The UO2 fuel with density of 10.5 g/cm3 and enrichment of 12.4% is applied as an appropriate LEU fuel. The reactor safety is assured by designing the safety control rod system with two banks. A fission converter facility (FCF) consists of 19 fuel rods of UO2 is used to increase φEpi for BNCT treatment. Furthermore, a unique thermal column of heavy water is used to increase φTh for NR purpose. Four internal irradiation sites, two external irradiation sites, and one large thermal column irradiation site are considered at the reactor which can be used for NAA application. The results of neutronic calculations show that the reactor meets the neutronic design limits for a low power research reactor.

A feasibility study on the determination of 90Sr food-chain transfer using stable strontium as a surrogate and neutron activation analysis

We evaluated the applicability of neutron activation analysis for investigating the potential mobility of 90Sr in a pasture area in Hungary. To measure strontium concentrations, we made use of the 84Sr(n,γ)85Sr radiative capture reaction using neutron activation analysis and performed gamma spectroscopy using Compton-suppression techniques on the resulting 514.0 keV gamma ray. Our values for soil-to-plant transfer factors value of 1.6 (2.2) kg kg−1 were in agreement with recommended values from the ICRP and IAEA, as well as similar studies performed by independent researchers. Our values for plant-to-animal transfer coefficients and concentration ratios varied from suggested values by several orders of magnitude to agreement with other values. Based on our results the utilized transfer of stable strontium could not be regarded as a convenient substitute to help clarify the long-term transfer of radioactive strontium in the environment, because short term dosing was applied. Neutron activation analysis provides a unique niche as a technique with very little chemical processing and short sample analysis times.

A PMT gating circuit design for real-time baseline restoration on prompt gamma neutron activation analysis application

Baseline shift seriously affects the accuracy of elemental analyzing when prompt gamma neutron activation analysis (PGNAA) technique is used in industry fields. Baseline is affected by signal pile-ups and environmental factors. We propose a photomultiplier tube (PMT) gating method to eliminate the effects of the environmental factors. The detector system updates the baseline before each single measurement starts. We propose an algorithm to restore the baseline shift caused by signal pile-ups. Test result shows that with the gating method, the hydrogen characteristic peak position fluctuation is reduced by half of the original value. And the resolution does not increased by the using of the gating method.

Hair elemental analysis for forensic science using nuclear and related analytical methods

In this review, we explore determination of element contents in hair with neutron activation analysis (NAA) and particle induced X-ray emission (PIXE). Here we discuss factors that influence the accuracy and credibility of results, and conclusions drawn for forensic science. Hair structure, growth phase, deposition of trace elements in hair, sampling and washing procedures are important factors before analysis, whereas the availability of reference values or ranges of hair elemental composition for non-exposed populations, and toxicological considerations are vitally important for results interpretation. We present here selected applications of NAA and PIXE for testing hypothesis of criminal poisoning with toxic elements. In conclusion, we would like to emphasize the importance of future NAA and PIXE applications for accurate determination of toxic elements and for spatially resolved element contents in hair, respectively.

Combined application of neutron activation analysis using IECF device and neural network for prediction of cement elements

Gamma spectrum of a cement sample is not straightforward to analyze as a result of peak overlapping produced by Compton effect of gamma rays radiated from activated elements in the neutron activation process and also because of the change into the neutron energy spectrum in the target sample during activation. Artificial neural network (ANN) is an excellent solution for complex and nonlinear systems. Consequently, the use of ANN for quantitative analysis of major cement elements including Ca, Si, Al, and Fe would be very advantageous. Iranian inertial electrostatic confinement fusion device is a fast, monoenergetic and steady neutron generator. It was simulated as a high-energy neutron source for performing neutron activation analysis. In the present study, a library of 29 members of delayed gamma-ray spectra of knowing cement samples were generated via MCNPX version 2.7. Specific photo-peaks related to Ca, Si, Al and Fe obtained from these spectra were used as inputs for ANN (21 of them for training and 8 for testing). Then, using MLP architecture, an ANN model has been presented to model the system to predict the percentages of the elements in cement. The ANN model is optimized to have only a hidden layer with five neurons. The comparison between modeling data and results of proposed MLP network shows that there is a good consistency between them. The MAE of training set for Ca, Si and Fe outputs were 0.0351, 0.0656 and 0.0660, respectively, and the MAE of testing set for mentioned outputs were 0.0997, 0.3046 and 0.8699, respectively. Overall, it can be concluded that the defined dispensable errors show that this modeling is a good one as a prediction tool for the mentioned purpose.

The role of analytical techniques in the determination of metals and metalloids in dietary supplements: A review

This review is focused to cover the application of different analytical techniques for the determination of metals and metalloids in different categories of dietary supplements. Atomic spectrometric methods based on flame atomic absorption spectrometry, electrothermal atomic absorption spectrometry, atomic fluorescence spectrometry, X–ray fluorescence spectrometry and plasma–based techniques such as inductively coupled plasma optical emission spectrometry and inductively coupled plasma–mass spectrometry are reviewed because a considerable amount of research is presently performed in this field. Even when much less reported in the literature, the application of neutron activation analysis, isotope dilution mass spectrometry and hyphenated methodologies for speciation studies based on the use of separative techniques in combination with specific detectors are also discussed. This survey contains 46 references and covers mainly the literature published over the last fifteen years.

New generation non-stationary portable neutron generators for biophysical applications of Neutron Activation Analysis

BackgroundNeutron sources are increasingly employed in a wide range of research fields. For some specific purposes an alternative to existing large-scale neutron scattering facilities, can be offered by the new generation of portable neutron devices. Scope of reviewThis review reports an overview for such recently available neutron generators mainly addressed to biophysics applications with specific reference to portable non-stationary neutron generators applied in Neutron Activation Analysis (NAA). Major conclusionsThe review reports a description of a typical portable neutron generator set-up addressed to biophysics applications. General significanceNew generation portable neutron devices, for some specific applications, can constitute an alternative to existing large-scale neutron scattering facilities. Deuterium-Deuterium pulsed neutron sources able to generate 2.5MeV neutrons, with a neutron yield of 1.0×106n/s, a pulse rate of 250Hz to 20kHz and a duty factor varying from 5% to 100%, when combined with solid-state photon detectors, show that this kind of compact devices allow rapid and user-friendly elemental analysis. "This article is part of a Special Issue entitled "Science for Life" Guest Editor: Dr. Austen Angell, Dr. Salvatore Magazù and Dr. Federica Migliardo".

Application of neutron activation analysis to micro gram scale of solid samples

An instrumental neutron activation analysis (INAA) procedure for analyzing extremely small samples was developed and applied to two kinds of extraterrestrial samples. A few mg of the Allende meteorite as well as the JB-1 basalt can work well as a reference sample for a relative method. To evaluate the applicability of this INAA procedure, detection limits are presented and compared with the elemental contents in a potential sample to be analyzed. The possibility of reuse of neutron-irradiated samples for mass spectrometry was noted by indicating degree of increase in isotopic abundance for noble gas and long-lived radioactive nuclides.

New Developments of Neutron Activation Analysis Applications

Neutron Activation Analysis is the most sensitive analytical technique used to determine concentration of elements in a sample. Methods of neutron activation analysis have been known for quite a long time, since 1936. However, active development of this method in its technological applications has been started together with recent developments of powerful and safe sources of neutrons, precise and fast gamma detectors, high speed electronics, increased processing ability of the computers and growing demands for industrial processes automation quality control. We discuss as these latest developments influenced performance and utility of different Neutron Activation Analysis techniques and first of all accuracy and stability of analytical results. As a result of the mentioned improvements wide variety of neutron analysis devices has been employed recently for reliable and precise control in cement and coal industry, borehole logging, security monitoring, industrial elemental analysis for production automation and quality control, nondestructive testing. Company RatecLab Ltd develops universal detection system of high resolution gamma spectroscopy for tagged neutron analysis with time-of-light filtering (Skolkovo Grant 2014-2015). Such high resolution detection platform would address the shortcuts and problems associated with conventional detection systems that utilize detectors with relatively low resolution prone to high background problem and slow response time. We perform thorough research of new potential applications of such precise and fast Neutron Activation Analysis system for some unresolved demanding problems of industries such as gas and oil industry. In our opinion there are multiple new possibilities to apply systems with neutron interrogation for industrial production control, nondestructive pipe inspection, neutron radiography etc.

Application of Neutron Activation Analysis for Determination of As, Cr, Hg, and Se in Mosses in the Metropolitan Area of the Valley of Toluca, Mexico

This research presents a study of environmental monitoring at different sampling sites from the Metropolitan Area of the Valley of Toluca (MAVT), Mexico, using mosses (Leskea angustata(Tayl.) andFabronia ciliaris(Brid.)) and soil samples. The epiphytic mosses and soils were sampled in two campaigns within two periods of the year, a rainy and dry-cold season. The selected sampling sites included urban regions (UR), transitional regions (TR), and protected natural areas (PA). The samples were analyzed by the Instrumental Neutron Activation Analysis (INAA) to determine As, Cr, Hg, and Se principally. However, due to the versatility of the analytic technique used, other elements including Cs, Co, Sc, Sb, Rb, Ce, La, Eu, and Yb were also detected. Statistical analysis (As, Cr, Hg, and Se) was carried out with principal components and cluster analysis methods; this revealed that a good correlation exists between metal content in mosses and the degree of pollution in the areas sampled. The obtained results in mosses showed that the concentrations of As, Cr, Co, Cs, Rb, Ce, La, and Yb increased with respect to the concentrations obtained during the first sampling, whereas Se, Sc, Sb and Eu, concentrations were decreased. For As and Hg, the concentrations were similar in both sampling periods. The soil samples present the most significant concentration.

The First Test of the New Neutron Generator at the Všb / Technical University of Ostrava První Test Nového Neutronového Generátoru Na Všb-Tu Ostrava

Abstract The compact neutron generator MP320 (Thermo Scientific Inc.) operating on the principle of a deuterium-tritium reaction was tested before its planned application as the neutron source for the purpose of Fast Neutron Activation Analysis applications. Plates made from Al, Fe, Sn and Si were irradiated by a 14 MeV neutron beam and typical neutron induced reactions were identified.

A software architectural framework specification for neutron activation analysis

Neutron Activation Analysis (NAA) is a sensitive multi-element nuclear analytical technique that has been routinely applied by research reactor (RR) facilities to environmental, nutritional, health related, geological and geochemical studies. As RR facilities face calls to increase their research output and impact, with existing or reducing budgets, automation of NAA offers a possible solution. However, automation has many challenges, not the least of which is a lack of system architecture standards to establish acceptable mechanisms for the various hardware/software and software/software interactions among data acquisition systems, specialised hardware such as sample changers, sample loaders, and data processing modules. This lack of standardization often results in automation hardware and software being incompatible with existing system components, in a facility looking to automate its NAA operations. This limits the availability of automation to a few RR facilities with adequate budgets or in-house engineering resources. What is needed is a modern open system architecture for NAA, that provides the required set of functionalities. This paper describes such an “architectural framework” (OpenNAA), and portions of a reference implementation. As an example of the benefits, calculations indicate that applying this architecture to the compilation and QA steps associated with the analysis of 35 elements in 140 samples, with 14 SRM’s, can reduce the time required by over 80 %. The adoption of open standards in the nuclear industry has been very successful over the years in promoting interchangeability and maximising the lifetime and output of nuclear measurement systems. OpenNAA will provide similar benefits within the NAA application space, safeguarding user investments in their current system, while providing a solid path for development into the future.

Cylindrical IEC Fusion Neutron Source for Broad Area NAA

The development of a unique long cylindrical neutron source for broad area neutron activation analysis (NAA) is presented. This source uses inertial electrostatic confinement (IEC) to produce 2.54 MeV D-D or 14.1 MeV D-T fusion neutrons. The IEC offers a variety of applications ranging from security inspection stations to driven-subcritical research assemblies. This IEC design uses a biased grid to initial in a unique “star” mode plasma discharge creating beam-background gas (target) fusion reactions. They routinely produce ∼108 2.54 MeV D-D neutrons/s at steady state. Pulsed operation has achieved upto 109n/s. (∼1011n/s if a deuterium mixture is used). Indeed, a version of the IEC has been commercially produced as a portable neutron source for industrial NAA applications. While that IEC source used spherical geometry, the present work uses a cylindrical version which provides a unique long “linelike” neutron source for use in the present broad area NAA system.

Comparison of IUPAC k 0 values and neutron cross sections to determine a self-consistent set of data for neutron activation analysis

Abstract Independent databases of nuclear constants for Neutron Activation Analysis (NAA) have been independently maintained by the physics and chemistry communities for many year. They contain thermal neturon cross sections σ 0, standardization values k 0, and transition probabilities P γ . Chemistry databases tend to rely upon direct measurements of the nuclear constants k 0 and P γ which are often published in chemistry journals while the physics databases typically include evaluated σ 0 and P γ data from a variety of experiments published mainly in physics journals. The IAEA/LBNL Evaluated Gamma-ray Activation File (EGAF) also contains prompt and delayed γ-ray cross sections σ γ from Prompt Gamma-ray Activation Analysis (PGAA) measurements that can also be used to determine k 0 and σ 0 values. As a result several independent databases of fundamental constants for NAA have evolved containing slightly different and sometimes discrepant results. An IAEA CRP for a Reference Database for Neutron Activation Analysis was established to compare these databases and investigate the possibilitiy of producing a self-consistent set of σ 0, k 0, σ γ , and P γ values for NAA and other applications. Preliminary results of this IAEA CRP comparison are given in this paper.