Prompt gamma neutron activation analysis of boron with a 241Am-Be neutron source

A prompt gamma neutron activation analysis (PGAA) setup installed at ANRTC has been used to analyze boron. It consists of a 22.6% REGe detector and a 740 GBq ²⁴¹Am-Be neutron source moderated with water and paraffin. At the sample irradiation position, the thermal neutron fluence rate measured was 2.36·10⁴ n·m^–2· s^–1 and the corresponding Cd-ratio was 22 for gold monitor. The absolute detection efficiency in the range of 120–1500 keV was determined using ¹⁵²Eu standard solution. The sensitivity and detection limit for standard boric acid samples has been determined. The boron content in boric acid prepared from Turkish borate ores is measured to be 15.91±0.46% wt.     

Prompt gamma activation analysis using a chopped neutron beam

A beam chopper has been developed at the cold neutron PGAA facility of the Budapest Research Reactor. In the open phase of the chopper the usual prompt gamma-spectrum is recorded, while in the decay phase short-lived decay lines can be collected with good counting statistics on an extremely low baseline. A series of elements has been measured with the chopped beam technique to assess the capabilities of the new technique. An archaeological sample was also examined, to demonstrate how spectral interferences can be resolved.     

Prompt gamma cold neutron activation analysis applied to biological materials

Summary Cold neutrons at the external neutron guide laboratory (ELLA) of the KFA Jülich are used to demonstrate their profitable application for multielement characterization of biological materials. The set-up and experimental conditions of the Prompt Gamma Cold Neutron Activation Analysis (PGCNAA) device is described in detail. Results for C, H, N, S, K, B, and Cd using synthetic standards and the “ratio” technique for calculation are reported for several reference materials and prove the method to be reliable and complementary with respect to the elements being determined by INAA. IAEA fellow at the KFA from 6. 3. 91 to 2. 9. 91 on contract No. VIE/9016R.     

Prompt gamma neutron activation analysis (PGAA): recent developments and applications

Journal of Radioanalytical and Nuclear Chemistry - Prompt gamma neutron activation analysis has become an important part of the analytical toolkit, practiced at several research reactors worldwide....     

Prompt gamma-ray neutron activation analysis methodology for determination of boron from trace to major contents

Prompt gamma ray neutron activation analysis methodologies were standardized using a reflected neutron beam and Compton suppressed γ-ray spectrometer to quantify boron from trace to major concentrations. Neutron self-shielding correction factors for higher boron contents (0.2–10 mg) in samples were obtained from the sensitivity of chlorine by irradiating KCl with and without boron. This method was validated by determining boron concentrations in six boron compounds and applied to three borosilicate glass samples with boron contents in the range of 1–10 mg. Low concentrations of boron (10–58 mg kg⁻¹) were also determined in two samples and five reference materials from NIST and IAEA.     

Determination of boron in water samples by chemical prompt gamma neutron activation analysis

Boron concentration has been determined in groundwater samples, collected from Khuchch, Gujarat, India, by prompt gamma neutron activation analysis (PGNAA) after selective separation and pre-concentration by solvent extraction with 10% 2-ethyl hexane 1,3-diol in CHCl₃. Solvent extraction separation helped to eliminate the interfering elements in PGNAA determination of boron. The sensitivity of PGNAA is found to be 18.83 cps/mg B based on the slope of a calibration plot obtained by carrying out measurements on synthetic boric acid samples containing boron in the range of 30–150 μg. Detection limit of the method is 0.2 μg/g counted for 35,000 seconds at a sample size of 15 gram. The precision (relative standard deviation at 1σ level) and accuracy of the method is 5%. The analytical results of the present method agreed well with well-established spectrophotometric determination of boron as boron-curcumin complex and inductively coupled plasma atomic emission spectroscopy (ICP-AES).     

Thermal neutron activation analysis of Cu in its ores by using an241Am−Be neutron source

A thermal neutron activation method has been developed for the determination of Cu in Cu–Pb–Zn ores and chalcopyrite ore concentrates using the reaction⁶³Cu(N, )⁶⁴Cu. The samples were irradiated with thermal neutrons from an²⁴¹Am–Be neutron source and the annihilation -radiations of 0.511 MeV were counted on 3×3 NaI(T1) detector coupled with single channel pulse height analyzer. The method is nondestructive, economical and ideal for bulk analysis of ores with 1–16% Cu.     

Performance comparison of an 241Am-Be neutron source-based PGNAA setup with the KFUPM PGNAA setup

Monte Carlo calculations have been carried out to compare the performance of an ²⁴¹Am-Be neutron source-based prompt gamma neutron activation analysis (PGNAA) setup with that of the 2.8 MeV neutron-based PGNAA setup at King Fahd University of Petroleum and Minerals (KFUPM) to analyze Portland cement samples. This work is a part of a wide Monte Carlo studies being conducted at KFUPM in search of a more efficient neutron source for its 2.8 MeV neutrons, from the D(d,n) reaction, based PGNAA facility. In this study an ²⁴¹Am-Be neutron source-based PGNAA setup was simulated. For comparison, the diameter of a cylindrical external moderator of the ²⁴¹Am-Be neutron source, based PGNAA setup, was assumed to be similar to that used in the KFUPM PGNAA setup. The results of this study revealed that although the optimum geometry of the ²⁴¹Am-Be neutron source-based setup is similar to that of the KFUPM PGNAA facility, the performance of the ²⁴¹Am-Be neutron source-based setup is slightly poorer than that of the 2.8 MeV neutron-based setup. This revised version was published online in July 2006 with corrections to the Cover Date.     

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 activation analysis of samples in thick containers

Two methods are presented for the prompt gamma activation analysis (PGAA) of samples in relatively thick containers. In the “Invisible container” method, the prompt gamma-radiation from the activated parts of the container can be suppressed in the spectrum. The target can be analyzed simultaneously with the shielding material, when the target signal in the spectrum is stronger. Uranium containing compounds were analyzed in lead capsules.     

Prompt gamma activation analysis (PGAA) and short-lived neutron activation analysis (NAA) applied to the characterization of legacy materials

The ⁹⁰YCl₃ radionuclide precursor (solution of ⁹⁰Y³⁺ in diluted HCl) of high purity and high specific activity is already commercially produced and successfully used in nuclear medicine. At the Nuclear Physics Institute ASCR, the ⁹⁰YCl₃ radionuclide precursor is prepared using extraction ⁹⁰Sr/⁹⁰Y generator (technology of centrifuge extractors with di-2-ethylhexylphosphoric acid, D2EHPA).¹ Its radionuclidic, radiochemical, and chemical purity were examined and specified. The procedure developed for labeling of DOTA-Tyr³-octreotide (DOTATOC) with carrier-free ^86/90Y by Rösch ² at the Institute of Nuclear Chemistry of the University Mainz was optimized and modified in our Department of Radiopharmaceuticals at NPI ASCR as standard labeling test (SLT) for analytical purposes. The SLT as a method for ⁹⁰YCl₃ radionuclide precursor quality control determining its labeling efficiency using ITLC SG chromatography is described and proposed thereinafter. The labeling-efficiency of the tested batches of our product reached more than 95%.     

Epithermal neutron activation analysis using a boron carbide irradiation filter

The use of boron carbide as a thermal neutron filter in epithermal neutron activation (ENAA) analysis has been investigated. As compared to the use of a cadmium filter, boron provides a greater reduction of activities from elements relatively abundant in terrestrial rocks and fossil fuels, such as Na, La, Sc and Fe. These elements have excitation functions which follow the 1/v law in the 1 to 10 eV lower epithermal region. This enhances the sensitivity of ENAA for elements such as U, Th, Ba and etc. which have strong resonances in the higher epithermal region above 10 eV. In addition, a boron carbide filter has the advantages over cadmium of acquiring a relatively low level of induced activity which poses minimal radiation safety problems, when used for ENAA.     

基于可移动中子源的瞬发γ活化成像研究进展

瞬发γ活化成像技术基于瞬发γ射线中子活化分析,结合准直测量或者伴随粒子测量手段,以实现对样品内部中元素位置分布的测量。当前大多数相关研究都是基于大型中子源开展的,这限制了该技术的应用场景,可移动小型化中子源是该技术现场应用的必然要求。基于可移动中子源的瞬发伽马活化成像技术按照准直方式可分为基于单孔准直、编码孔准直及伴随粒子测量三类,本文对其技术原理、研究进展及仍存在的问题进行介绍与讨论。目前的技术在空间分辨率上还需要进一步提升,未来将进一步结合图像处理算法提高成像质量并降低测量时间。     

Prompt-gamma neutron activation analysis using an isotopic neutron source

This paper describes an experimental set up using an isotopic neutron source with graphite, preferably to a hydrogen-rich compound, as moderator. This low thermal flux source has been employed in PGNAA experiments. Only those elements having a high cross section can be quantitatively analyzed at low concentration levels, mainly, Gd, Cd, Sm, B and Hg; the other elements can only be probed at macroscopic levels. An application to the determination of boron content in collyria examplifies the possibilities of the technique.     

Prompt gamma as a fluence rate monitor in neutron beam experiments

An accurate measurement of the neutron lifetime requires a determination of neutron fluence rate to an accuracy of a few tenths of a percent. The¹⁰B(n,)⁷ Li reaction offers the possibility of achieving this uncertainty. The thermal cross section is large and its departure from 1/v behavior is about 3 parts in 10000. The principal alpha branch is to the first excited state of⁷Li which then decays by emission of a 478 keV gamma ray. The measurement of the gamma branch can be made with boron samples that totally absorb thermal neutrons, allowing greater sensitivity and eliminating the uncertainty of target thickness. The absolute efficiency of the gamma detector can be determined by an alpha-gamma coincidence technique. Preliminary investigations of this method are presented with a discussion of the problems that must be overcome to achieve the desired uncertainty.Work supported in part by the Department of Energy     

Optimization of Linac-based neutron source for thermal neutron activation analysis

Journal of Radioanalytical and Nuclear Chemistry - A 20 MeV electron Linac based neutron beam has been shaped for neutron activation analysis (NAA) technique. A beam shaping assembly (BSA)...     

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.     

Multi-geometry241AmBe neutron irradiator: Design and calibration for total-body neutron activation analysis

Neutron activation analysis provides an accurate elemental assessment of body compositional compartments; the analytical technique identifies skeletal, muscle, protein, and fat masses. Our irradiator system uses 56²⁴¹AmBe sources (4.4·10⁷ n/s each) which can be arranged in four basic geometries to examine body sizes from a preterm infant (500 g, 30 cm) to a very large adult (120 kg, 2m). Both in vivo and human cadaver studies have been performed. Precisions of 1 to 2% for total body Ca, P, Na, and Cl have been obtained.     

Flux anisitropy around a241Am-9Be neutron source

The angular variation of an irradiating flux around the cylindrical axis of a 3 Ci /11.1x10¹⁰ Bq/²⁴¹Am–⁹Be neutron source has been investigated. Measurements using the²⁷Al/n,p/²⁷Mg reaction indicated a flux variation of up to 12% from the mean following a 2 rotation about the cylindrical axis.