A new microcomputer program for processing data in neutron activation analysis

A new utility program for processing data in neutron activation analysis (NAA) has been developed for use on MS-DOS microcomputers. Peak areas are read from ASCII data files of gamma-ray spectra which have been processed by a Gaussian peak fitting program, GAMANAL-PC. Elemental concentrations are then calculated by this new program, QUACANAL, via a semi-absolute algorithm that uses pre-determined activation constants. User-defined ASCII library files are employed to specify the elements of interest required for analysis, and (n, p) and (n, ) interferences are taken into account. The program has been written in turbo PASCAL, is menu driven and contains options for processing data from cyclic NAA. An interactive philosophy has been used in designing the program.Sabbatical address for 1991/1992.     

Data analyzer computer program for neutron activation analysis

In order to save time, manpower and minimize human error, a new computer program was designed, built and implemented using Visual Basic 6.0. The new program automatically reads and recognizes all the information in the “peak reports” from Gammaplus software, and is capable of automatically detecting the chemical isotopes within samples and calculating their concentrations and uncertainties. With minimum input from the user, the software has proven to be fast, reliable and user friendly.     

The SPECTRA program library: A PC based system for gamma-ray spectra analysis and INAA data reduction

A PC based system has been developed for the analysis of gamma-ray spectra and for the complete reduction of data from INAA experiments, including software to average the results from multiple lines and multiple countings and to produce a final report of analysis. Graphics algorithms may be called for the analysis of complex spectral features, to compare the data from alternate photopeaks and to evaluate detector performance during a given counting cycle. A database of results for control samples can be used to prepare quality control charts to evaluate long term precision and to search for systematic variations in data on reference samples as a function of time. The entire software library can be accessed through a user-friendly menu interface with internal help.     

CLP-type data validation guidelines for neutron activation analysis

Neutron activation analysis data quality must be validated to serve evidentiary purposes for environmental restoration and health protection projects. This paper gives a basis for determining the technical validity of neutron activation analysis data.     

Neutron activation analysis: A simple versatile program for automated gamma spectrometry with a personal computer

A set of interactive routines has been developed to use a personal computer for instrumental neutron activation analysis. The program operates a multichannel analyzer by remote control and output concentrations, standard deviation and/or detection limit for each requested element. The program is able to combine data from several spectra, so that computation is continuous and takes less than 4 minutes for 15 elements. Reliable results have been obtained for low peak/background ratios encountered in atmospheric and marine particulate matter analyses.     

Computer program for neutron activation analysis with the SLOWPOKE reactor

A FORTRAN computer program for automatic neutron activation analysis is presented. The program locates and identifies peaks in a gamma-ray spectrum, calculates peak areas and the concentrations of the elements of interest in the sample. This program was specifically designed for the SLOWPOKE reactor, it uses a semi-absolute method and does not need standards or flux monitors. The program was written so as to minimize the computation time, and a typical 4096-channel spectrum is processed in five seconds by an IBM 360/75 computer.     

Computer program for processing gamma spectra in neutron activation analysis

A program based on the method of least squares and written in the ALGOL-60 code was developed for data processing in the activation analysis of biological substances. The applicability of the program was checked on synthetic mixtures of the radioisotopes⁶⁴Cu,^69mZn and⁵⁶Mn measured with a scintillation γ-spectrometer.     

An algorithm for data processing in neutron activation analysis

An algorithm for processing NAA data is described. Input data are the output data from a multichannel pulse-height analyzer with a microprocessor. This algorithm permits to calculate the concentrations of the analyzed elements (using a standard or a standard curve), the error of concentrations in the analysis of one or several parallel samples and the sensitivity of the analysis according to Currie's criteria in counts, g and g/g. Some other intermediate data (e.g. corrected net area of the peaks, parameters of the standard curve) may have individual importance in differenct cases.     

CINA — A program for complete instrumental neutron activation analysis with a PC-type minicomputer

A program has been developed to use a PC-type minicomputer for instrumental neutron activation analysis. The program has the capacity for photopeak search, peak area computation, and element concentration determination using the single comparator method. Analysis time for a 4096-channel spectrum containing 20 photopeaks is about 4 minutes.     

Total body calcium by neutron activation analysis: Reference data for children

There is a paucity of data on the chemical composition of the humanbody during growth. Total body calcium (TBCa) has been reported for only onemale child, aged 41/2 yr. We have obtained TBCa values for 25 children and27 young women using in vivo neutron activation analysis. Our TBCa resultswere lower than those reported for the one male cadaver, as well as the estimatesderived for the Reference Man model. We conclude that the referencevalues for TBCa may need to be adjusted to appropriately describe skeletalmineralization of contemporary children.     

A computer program for activation analysis

A computer program for calculating activation analysis results is described. The program comprises two gamma spectrum analysis programs, STOAV and SAMPO and one program for calculating elemental concentrations, KVANT. STOAV is based on a simple summation of channels and SAMPO is based on fitting of mathematical functions. The programs are tested by analyzing the IAEA G-1 test spectra. In the determination of peak location SAMPO is somewhat better than STOAV and in the determination of peak area SAMPO is more than twice as accurate as STOAV. On the other hand, SAMPO is three times as expensive to use with a Cyber 170 computer as STOAV.     

A multi-element serum standard for neutron activation analysis

An annular ²²⁷AcBe isotopic neutron source, containing 6.6-Ci ²²⁷Ac, is described for application in fast and thermal neutron activation analysis, with high accuracy, for major constituents in ores, alloys and industrial concentrates. The characteristics of the neutron output and of the fast, epithermal and thermal flux and flux gradients is described in detail. The determination of manganese in pyrolusite ores and ferro-manganese is compared to results obtained previously with a cylindrical 1-Ci ²²⁶RaBe source. Two new sources of systematic errors have been discovered.     

A simple program for weighted linear regression applied to activation analysis data processing

A simple ALGOL program for activation analysis data handling is presented The program, although designed in principle for processing single-channel spectrometry data, may also be used for multichannel spectrometry, on condition that the peak area is computed separately. The calculations of instrumental error and standard deviation are carried out. The outliers are tested, and the regression line diagram with the related observations are plotted by the program.     

Precise timing in program-controlled data acquisition for 14 MeV neutron activation analysis

A solution for the automation of a fast pneumatic transport system and its application is given.     

Nuclear data measurements for zirconium isotopes used for activation analysis and neutron metrology

In order to establish more accurate nuclear data for the zirconium isotopes⁹⁴Zr and⁹⁶Zr, joint experimental work has been conducted in three different reactor types. After carefully calibrating the neutron spectra in the irradiation channels used, nuclear constants k₀ and Q₀ were remeasured and found to be The relevant effective resonance energies have been recalculated using the latest BNL neutron resonance parameters yielding . The epithermal neutron shielding factor G_e has been experimentally determined as a function of foil thickness. The results gave G_e(⁹⁴Zr)=0.983 (±0.3%) and G_e(⁹⁶Zr)=0.973 (±0.4%) for the most frequently used 0.125 mm foil thickness. Finally the half life of the⁹⁷Zr isotope has also been remeasured to give T_1/2(⁹⁷Zr)=16.744±0.011 h with 1 limit.     

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.     

Multivariate calibration for neutron activation analysis

The application of target factor analysis to the analysis of gamma-ray spectra collected for activation analysis is proposed. Satisfactory analysis of a trial set of samples was carried out using measured spectra as targets. Single-isotope spectra were obtained from mixture spectra by free-floating and performed satisfactorily as target spectra. The factor analysis method requires less resolution than peak-based methods.     

Delayed neutron activation analysis for safeguards

Delayed neutron activation analysis (DNAA) presents a fast, accurate, and reliable method for quantification of fissile material. The method has relatively few sources of error and may be accomplished nondestructively. The need for a fast, accurate screening of materials stems from the necessity to protect cleanroom facilities from widely varying fissile quantities in samples and from desired gains in efficiency of mass spectrometric analysis by assisting in spike level selection and by removing from the sample set those materials that are not of interest. During the last several years, many different materials have been screened or analyzed in support of international safeguards, internal process control for actinide separations, and in uranium contamination assessments. Swipes from a variety of sources have been analyzed, either before or after dissolution, and comparison of the DNAA results to mass spectrometry results is generally favorable. A facility characterization of the High Flux Isotope Reactor was performed using filter paper swipes to demonstrate the utility of the DNAA technique.     

Reactor neutron activation analysis based on characteristic X-ray spectrometry

The possibility of using characteristic X-ray from radioactive products of reactor activation was investigated with particular emphasis on /n,/, /n,n/, /n,2n/, /n,p/ and /n,/ products with long half lives. The characteristic X-rays emitted are a result of electron capture or internal conversion processes during isomeric transition. First of all the sensitivity and detection limits were investigated.