Prompt Gamma-ray Neutron Activation Analysis Research Articles

Elemental analysis of concrete samples using an accelerator-based PGNAA setup

Elemental analysis of concrete samples was carried out using an accelerator-based prompt gamma ray neutron activation analysis (PGNAA) setup. The gamma rays were produced via the capture of thermal neutron in the concrete sample. The prompt gamma ray yield was measured for 12 cm long concrete samples as a function of sample radius over a range of 6–11.5 cm radii. The optimum yield of the prompt gamma rays from the concrete sample was measured from a sample with 11.5 cm radius. The gamma ray yield was also calculated for 12 cm long concrete samples with 6–11.5 cm radius using Monte Carlo simulations. The experimental results were in excellent agreement with the calculated yield of the prompt gamma rays from the samples. Result of this study has shown the useful application of an accelerator-based PGNAA setup in elemental analysis of concrete sample. The facility can be further used to determine the chloride and sulfate concentrations in concrete samples for corrosion studies of reinforcement steel in concrete structures.

Stabilization of prompt gamma-ray neutron activation analysis (PGNAA) spectra from NaI detectors

NaI detectors are still used frequently in industrial Prompt Gamma-Ray Neutron Activation Analysis applications such as in bulk material analysis. They have the advantages of being efficient for high-energy gamma rays, being relatively rugged, and being able to be used without cooling. When using NaI detectors, and consequently photomultiplier tubes, the quality of the data can drastically deteriorate through gain and zero shifts that result in spectral smearing due to temperature and/or counting rate changes. A new offline approach is presented to stabilize the NaI spectral drift. The approach is not sensitive to the cause of the drift and takes into account the NaI and ADC non-linearities. Peak resolution is improved substantially when this approach is used in the presence of spectral drift.

Determination of Hydrogen in Semiconductors and Related Materials by Cold Neutron Prompt Gamma-ray Activation Analysis

ABSTRACTAn instrument for prompt gamma-ray activation analysis (PGAA) at the NIST Center for Neutron Research has proven useful for the measurement of hydrogen and other elements in a variety of materials. The sample is irradiated by a beam of low energy neutrons. Gamma-rays emitted by atomic nuclei upon neutron capture are measured and elemental concentrations determined by comparison with appropriate standards. The detection limit for hydrogen is < 5 mg/kg in most materials, and 2 mg/kg for hydrogen measured in silicon. The instrument has been used to measure hydrogen mass fractions of < 100 mg/kg in high purity germanium, and < 10 mg/kg in quartz. More recently PGAA has been used to measure hydrogen in 1 μm thick porous thin films on a silicon substrate, and in crystals of silicon carbide and cerium aluminate.

Validity test of design calculations of a PGNAA setup

A rectangular moderator has been designed for the prompt gamma ray neutron activation analysis (PGNAA) setup at King Fahd University of Petroleum and Minerals (KFUPM) to analyze Portland cement samples. The design of the moderator assembly was obtained using Monte Carlo calculations. The design calculations of the new rectangular moderator of the KFUPM PGNAA setup have been verified experimentally through prompt gamma ray yield measurement as a function of the front moderator thickness. In this study the yield of the 3.54 and 4.94 MeV prompt gamma rays from silicon in a soil sample was measured as a function of thickness of the front moderator of the rectangular moderator. The experimental results were compared with the results of the Monte Carlo simulations. A good agreement has been achieved between the experimental results and the results of the calculations. The experimental results have provided useful information about the PGNAA setup performance, neutron moderation, and gamma ray attenuation in the PGNAA sample.

The analog linear interpolation approach for Monte Carlo simulation of PGNAA: The CEARPGA code

The analog linear interpolation approach (ALI) has been developed and implemented to eliminate the big weight problem in the Monte Carlo simulation code CEARPGA. The CEARPGA code was previously developed to generate elemental library spectra for using the Monte Carlo – library least-squares (MCLLS) approach in prompt gamma-ray neutron activation analysis (PGNAA). In addition, some other improvements to this code have been introduced, including (1) adopting the latest photon cross-section data, (2) using an improved detector response function, (3) adding the neutron activation backgrounds, (4) generating the individual natural background libraries, (5) adding the tracking of annihilation photons from pair production interactions outside of the detector and (6) adopting a general geometry package. The simulated result from the new CEARPGA code is compared with those calculated from the previous CEARPGA code and the MCNP code and experimental data. The new CEARPGA code is found to give the best result.

Neutron moderation in a bulk sample and its effects on PGNAA setup geometry

In a prompt gamma ray neutron activation analysis (PGNAA) setup, the neutron moderation in the bulk sample also plays a key role. This can even dominate the thermalization effects of the external moderator in some cases. In order to study the neutron moderation effect in the bulk sample, moderators with two different sizes of the sample were tested at the King Fahd University of Petroleum & Minerals (KFUPM) PGNAA facility. In these tests, the thermal neutron relative intensity and prompt gamma ray yield from the two moderators were measured using nuclear track detectors (NTDs) and NaI detector, respectively. As predicted by Monte Carlo simulations, the measured intensity of thermal neutron inside the large sample cavity due to the external moderator was smaller than that from the smaller sample cavity. Due to its larger size, additional thermalization of neutrons will take place in the larger sample. In spite of smaller thermal neutron yield from the external moderator at the large sample location, higher yield of the prompt gamma ray was observed as compared to that from the smaller sample. This confirms the significance of neutron moderation effects in the bulk sample and can thereby affect the PGNAA geometry size. This allows larger samples in conjunction with smaller moderators in the PGNAA setup.

Prompt gamma ray analysis of Portland cement sample using keV neutrons with a Maxwellian energy spectrum—a Monte Carlo study

Monte Carlo calculations have been carried out to determine the prompt gamma ray yield from a Portland cement sample using keV neutrons from a 3H(p,n) reaction with a Maxwellian energy distribution with kT=52 keV. This work is a part of wider Monte Carlo studies being conducted at the King Fahd University of Petroleum and Minerals (KFUPM) in search of a more efficient neutron source for its D(d,n) reaction based (2.8 MeV neutrons) Prompt Gamma Ray Neutron Activation Analysis (PGNAA) facility. In this study a 3H(p,n) reaction based prompt gamma ray PGNAA setup was simulated. For comparison purposes, the diameter of a cylindrical external moderator of the 3H(p,n) reaction based PGNAA setup was assumed to be similar to the one used in the KFUPM PGNAA setup. The results of this study revealed that the optimum geometry of the 3H(p,n) reaction based setup is different from that of the KFUPM PGNAA facility. The performance of the 3H(p,n) reaction based setup is also better than that of the 2.8 MeV neutrons based KFUPM facility and its prompt gamma ray yield is about 60–70% higher than that from the 2.8 MeV neutrons based facility. This study has provided a theoretical base for experimental test of a 3H(p,n) reaction based setup.

Performance tests of external moderators of a PGNAA setup

Performance tests of external cylindrical moderators of an accelerator-based prompt gamma ray neutron activation analysis (PGNAA) setup have been carried out through thermal neutrons and prompt γ-ray yield measurements. The PGNAA setup is to be used for analysis of cement samples. This study was conducted to investigate the effects of geometry of cylindrical moderator on yield of thermal neutrons and prompt γ-rays for two different types of moderator assemblies. One of the moderators was to be used with a small sample and the other to be used with a large sample. Fast and thermal neutron yield was measured inside the sample volume as a function of the front moderator thickness as well as sample length. Neutron yield measurement was carried out at the King Fahd University of Petroleum and Minerals 350 keV pulsed beam accelerator using nuclear track detectors. The pulsed 200 keV deuteron beam with 5 ns pulse width and 31.25 kHz frequency was used to produce 2.8 MeV neutrons via D(d,n) reaction. Neutron yield measurements showed that the large sample moderator has a smaller yield of thermal neutrons as compared to the small sample moderator, which is in complete agreement with the results of Monte Carlo yield calculations of the thermal and fast neutrons from both the moderators. Finally, the prompt γ-ray yield from a Portland cement sample was measured using the two moderators and was compared with each other. As predicted by Monte Carlo simulations, in spite of a smaller yield of thermal neutrons, the large sample moderator has a higher yield of prompt γ-rays.

Monte Carlo simulations for design of the KFUPM PGNAA facility

Monte Carlo simulations were carried out to design a 2.8 MeV neutron-based prompt gamma ray neutron activation analysis (PGNAA) setup for elemental analysis of cement samples. The elemental analysis was carried out using prompt gamma rays produced through capture of thermal neutrons in sample nuclei. The basic design of the PGNAA setup consists of a cylindrical cement sample enclosed in a cylindrical high-density polyethylene moderator placed between a neutron source and a gamma ray detector. In these simulations the predominant geometrical parameters of the PGNAA setup were optimized, including moderator size, sample size and shielding of the detector. Using the results of the simulations, an experimental PGNAA setup was then fabricated at the 350 kV Accelerator Laboratory of this University. The design calculations were checked experimentally through thermal neutron flux measurements inside the PGNAA moderator. A test prompt gamma ray spectrum of the PGNAA setup was also acquired from a Portland cement sample, using a pulsed beam of 2.8 MeV neutrons. Prompt gamma ray peaks due to the calcium, silicon and iron content of the Portland cement were detected.

Monte Carlo Calculations for Design of An Accelerator Based PGNAA Facility

Monte Carlo calculations were carried out for design of a set up for Prompt Gamma Ray Neutron Activation Analysis (PGNAA) by 14 MeV neutrons to analyze cement raw material samples. The calculations were carried out using code the MCNP4B2. Various geometry parameters of the PGNAA experimental setup such as sample thickness, moderator geometry and detector shielding etc were optimized by maximizing the prompt gamma ray yield of different elements of sample material. Finally calibration curve of the PGNAA setup were generated for various concentrations of calcium in the material sample. Results of this simulation are presented.

Fast and thermal neutron intensity measurements at the KFUPM PGNAA setup

Fast and thermal neutron intensity distributions have been measured at an accelerator based prompt gamma ray neutron activation analysis (PGNAA) setup. The setup is built at the 350 keV accelerator laboratory of King Fahd University of Petroleum and Minerals (KFUPM). The setup is mainly designed to carry out PGNAA elemental analysis via thermal neutron capture. In this study relative intensity of fast and thermal neutrons was measured as a function of the PGNAA moderator assembly parameters using nuclear track detectors (NTDs). The relative intensity of the neutrons was measured inside the sample region as a function of front moderator thickness as well as sample length. Measurements were carried out at the KFUPM 350 keV accelerator using 2.8 MeV pulsed neutron beam from D(d,n) reaction. The pulsed deuteron beam with 5 ns pulse width and 30 kHz frequency was used to produce neutrons. Experimental results were compared with results of Monte Carlo design calculations of the PGNAA setup. A good agreement has been found between the experimental results and the calculations.

On-Belt Analysis of Ash in Coal

A new neutron and gamma-ray analysis system has been developed for the direct on-conveyor belt analysis of ash in coal. This analysis system incorporates a method for ash measurements that is relatively independent of changes in segregation, belt loading, and ash composition. Consequently, the analysis system provides greater accuracy than on-belt dual energy gamma-ray transmission (DUET) gauges but at a much lower cost than by-line prompt gamma-ray neutron activation analysis (PGNAA) analyzers and samplers. The NITA (Neutron Inelastic scatter and Thermal capture Analysis) method simultaneously measures prompt neutron inelastic scatter and thermal neutron capture gamma rays from bulk coal samples using a 241 Am-Be fast neutron source and bismuth germanate (BGO) detectors in transmission and backscatter geometries. The NITA method has been tested in both laboratory feasibility studies and, more recently, under simulated industrial conditions using a prototype analyzer. Measurements have been carried out on coal samples of ash contents from 6.7 to 49.4 wt% (dry basis (d.b.)) with variable ash composition and at thicknesses between 100 and 300 mm. The results show that accuracies of ∼0.5 wt% ash are achievable over a wide range of ash values, compositions, and thicknesses.

Measurement of k0-Factors in Prompt Gamma-Ray Neutron Activation Analysis

The guided thermal neutron beam at 100 MW Dhruva research reactor facility of Bhabha Atomic Research Centre (BARC) was used to carry out prompt gamma-ray neutron activation analysis (PGNAA). The prompt k0-factors have been determined for the isotopes of the elements H, B, K, Co, Cu, Ca, Ti, Cr, Cd, Ba, Hg and Gd with respect to 1951 keV gamma-line of 36Cl. The prompt k0-factors for H, Cl and Cu were also measured with respect to the 1381 keV gamma-line of 49Ti. Different samples like NH4Cl, Ti metal, cobalt chloride and other stoichiometric compounds and pure metals were used for this purpose. Prompt gamma-rays were accumulated using a 22% HPGe detector connected to a PC based 8k MCA in single mode counting. The energy calibration in the range of 100–8500 keV was carried out using gamma-rays from 152Eu and 60Co, and the prompt gamma-rays from 36Cl whereas the absolute detection efficiency for this energy range was determined using 152Eu and prompt gamma-rays from 36Cl and 49Ti.

Calibration and Validation of a Monte Carlo Model for PGNAA of Chlorine in Soil

A prompt gamma-ray neutron activation analysis (PGNAA) system was used to calibrate and validate a Monte Carlo model as a proof of principle for the quantification of chlorine in soil. First, the response of an n-type HPGe detector to point sources of 60Co and 152Eu was determined experimentally and used to calibrate an MCNP4a model of the detector. The refined MCNP4a detector model can predict the absolute peak detection efficiency within 12% in the energy range of 120–1400 keV. Second, a PGNAA system consisting of a light-water moderated 252Cf (1.06 μg) neutron source, and the shielded and collimated HPGe detector was used to collect prompt gamma-ray spectra from Savannah River Site (SRS) soil spiked with chlorine. The spectra were used to calculate the minimum detectable concentration (MDC) of chlorine and the prompt gamma-ray detection probability. Using the 252Cf based PGNAA system, the MDC for Cl in the SRS soil is 4400 μg/g for an 1800-second irradiation based on the analysis of the 6110 keV prompt gamma-ray. MCNP4a was used to predict the PGNAA detection probability, which was accomplished by modeling the neutron and gamma-ray transport components separately. In the energy range of 788 to 6110 keV, the MCNP4a predictions of the prompt gamma-ray detection probability were generally within 60% of the experimental value, thus validating the Monte Carlo model.

Characterization of Hydrogen in Concrete by Cold Neutron Prompt Gamma-Ray Activation Analysis and Neutron Incoherent Scattering

ABSTRACTA combination of cold neutron prompt gamma-ray activation analysis (PGAA) and neutron incoherent scattering (NIS) has been used for nondestructive characterization of hydrogen as a function of position in slabs of wet concrete of different compositions. Hydrogen was determined by PGAA by scanning each sample across a 5 mm diameter neutron beam in 10 mm increments, and measuring the 2223 keV prompt gamma ray. NIS measurements were performed by scanning the sample across a 5 mm diameter neutron beam at 5 mm increments and detecting scattered neutrons. The measurements demonstrate the feasibility of the techniques for 2D compositional mapping of hydrogen and other elements in materials, and indicate the potential of these methods for monitoring the uniformity of drying concrete.

Determination of Hydrogen in Metals, Semiconductors, and Other Materials by Cold Neutron Prompt Gamma-Ray Activation Analysis

ABSTRACTCold neutron prompt gamma-ray activation analysis has proven useful for nondestructive measurement of trace hydrogen. The sample is irradiated in a beam of neutrons; the presence of hydrogen is confirmed by the emission of a 2223 keV gamma-ray. Detection limits for hydrogen are 3 mg/kg in quartz and 8 mg/kg in titanium. We have used the technique to measure hydrogen in titanium alloys, germanium, quartz, fullerenes and their derivatives, and other materials.

Feasibility of neutron activation methods for measurement of sodium and aluminium in green liquor

The feasibility of neutron activation methods including prompt gamma-ray neutron activation analysis (PGNAA), neutron activation analysis (NAA), and continuous neutron activation analysis (CNAA) has been investigated for both the off-line and on-line continuous measurement of sodium and aluminum in green liquor. It is found that in the measurement of sodium and aluminium dissolved in green liquor at the 11% and 5.5% levels, respectively, one must also know the chlorine content to determine the average neutron flux for any method involving neutron activation. Chlorine may be present in green liquor in amounts up to 0.5% which would significantly (as much as 10%) affect the average thermal neutron flux in a sample. It was found that PGNAA is quite sensitive to chlorine and somewhat to sodium, but very insensitive to aluminum. However, NAA and CNAA are quite sensitive to aluminum, then sodium, but very insensitive to chlorine. The final proposed approaches for discrete samples and continuous samples are to use NAA and CNAA, respectively, with time lags incorporated between activation and detection to reduce the effect of the otherwise overly intense aluminum spectrum on the less intense sodium spectrum and use of a 3He detector to monitor the average neutron flux (a function primarily of chlorine content) in the samples. Extensive experimental and benchmarked Monte Carlo simulations are used to evaluate the feasibility of this approach. It appears that the approach is viable and will allow accurate (1% relative standard deviation for both sodium and aluminum) discrete sample or on-line continuous analysis of both sodium and aluminum in green liquor in reasonable times (10–30 min) with a relatively small (15 μg) 252Cf source. Prototype devices are planned for future development.

A brief review of the determination of cadmium by prompt gamma-ray neutron activation analysis

An examination of the literature concerning the determination of cadmium by Prompt Gamma-Ray Neutron Activation Analysis (PGNAA) has been conducted. In-vivo activation analysis of the liver and kidney is the most common application reported and is briefly reviewed here. This review will concentrate on the determination of cadmium in in-vitro systems. These include a number of different complex matrices such as geological, environmental and biological materials, as well as water, sediments, foods and construction material. Nuclear reactors, accelerators, and radioisotopes have all been used as neutron sources with varying degrees of sensitivity.

Prompt gamma-ray neutron activation analysis by the absolute method

In this study an investigation into the applicability of the absolute method in Prompt Gamma-ray Neutron Activation Analysis (PGNAA) was undertaken. Although the system parameters are adequately characterized, the scatter in nuclear data for a number of elements is significant. For our particular experimental set up the K-factors were calculated for a number of elements using both Au and Fe as monostandards. A comparison was made between the calculated and experimentally determined K-factors and from this comparison the feasibility of the absolute method in neutron prompt gamma-rays can be realized for a number of elements.

Prompt gamma-ray neutron activation analysis for multi-element determination in sediment samples

A facility for the irradiation of internal targets has been installed at the research reactor FRG-of the GKSS Research Center. Thermal-neutron induced prompt gamma radiation was detected by pair spectrometer. With this experimental arrangement concentrations of the major and mino elements Na, Al, Si, K, Ca, Ti, Mn, Fe, Zn, Cl, and S, as well as of the trace constituents Cr Ni, Cu Cd, and Hg of samples from a sediment core of the Elbe River could be determined. The results indicate, that prompt gamma-ray neutron activation analysis (PGNAA) is a powerful instrumental tool for a complete characterization of the main sediment constituents and for the detection of the trace elements Cd and Hg which are of considerable ecological relevance.