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.     

Preconcentration techniques for trace analysis via neutron activation

A review is given of the methods that have been proposed for enrichment of trace elements in samples that are to be analysed by neutron-activation methods. The emphasis is on classification of methods, with full illustrations by means of practical examples.     

Updating analytical techniques for fast neutron activation analysis

Two improvements in the analytical techniques used for fast neutron activation analysis have been developed and put into routine use. The first is neutron shielding of a NaI (TL) counting system, which reduces the counting noise encountered during neutron generation. The second is a modification of batch type irradiation for long lived nuclides so they can be done simultaneously with other test.     

Practical applications of neutron activation and radioisotope techniques in optical waveguide research and development

Gamma-ray spectrometric survey analyses were used to screen raw materials available during the infancy of the optical waveguide research program. Examinations of γ-ray spectra and semiquantitative survey analyses showed most samples to be insufficiently pure for waveguide applications. Highly pure samples have been prepared successfully under carefully controlled conditions when the purification process is adequately monitored by analyses. Radioisotope techniques and neutron activation analyses were vital in the development of successful procedures for purifying various reagents from which glass could be subsequently fabricated by melting techniques. Contamination sources during fiber production have also been detected by neutron activation analyses.     

A software counting loss correction method for neutron activation analysis with short-lived radionuclides

A method has been developed for the correction of counting losses in NAA for the case of a mixture of short-lived radionuclides. It is applicable to systems with Ge detectors and Wilkinson or successive approximation ADC's and will correct losses from pulse pileup and ADC dead time up to 90%. The losses are modeled as a constant plus time-dependent terms expressed as a fourth order polynomial function of the count rates of the short-lived radionuclides. The correction factors are calculated iteratively using the peak areas of the short-lived radionuclides in the spectrum and the average losses as given by the difference between the live time and true time clocks of the MCA. To calibrate the system a measurement is performed for each short-lived nuclide. In a test where the dead time varied from 70% at the start of the measurement to 13% at the end, the measured activities were corrected with an accuracy of 1%.     

Some considerations for future instrumentation and software developments in neutron activation analysis

After 25 years of rapid development, neutron activation analysis is now in a period of maturing. In this period, the attention has to be focussed on improvement of sensitivity, precision and accuracy without an appreciate increase of analysis costs, and on decrease of the costs per analysis without affecting sensitivity, precision and accuracy. The present paper indicates how already well known technical and physical possibilities can be used to reach this aim.     

The role of neutron activation analysis in VLSI manufacturing and development

Very large scale integrated (VLSI) semiconductor manufacturing and development require trace analyses for materials inspections, process characterization, contamination control, and failure analysis. Improvement in alternate analytical techniques has reduced the relative importance of neutron activation analysis (NAA) in these activities, but, for certain types of problems, NAA can still play a significant role.     

An automated neutron activation system for short-lived nuclides

The present paper describes an attempt to create a reliable and easy to use system for neutron activation with short-lived nuclides, suitable to be used with several irradiation and counting procedures in instrumental neutron activation analysis (INAA) at the Portuguese Research Reactor. This system can become very useful for a large community within LNETI, as well as other national institutes and universities, particularly for those involved in studies where the analysis of a large number of samples is required. Selenium determination has been performed, through the short-lived nuclide^77mSe, as an example of the reliability of the system.     

Multielement content of coal by neutron activation analysis techniques

Due to the interaction with components present in natural waters, radionuclides may be present in different physico-chemical forms, varying in size, charge and density. The distribution pattern will influence the transport, mobility and biological uptake of the radionuclides. Size fractionation based on hollow fiber is useful for the determination of the size distribution pattern of radionuclides in natural waters. Furthermore, a continuous mixing and separation system has been developed for the investigation of the association of radionuclides with naturally occurring colloids. Results based on radionuclides in waste water from the Forsmark nuclear power plant, Sweden, will illustrate the potential usefulness of the technique.     

Improvements of neutron activation techniques for the determination of fissile material concentrations

Certain experimental improvements, as variable sample size and irradiation position, automation and flexibility in radiation detection, broaden the measurable concentration range, increase the possible rate and accuracy of analysis and enlarge the application range of the home-made nuclear analyzer for fissile material analysis by delayed fission neutron counting and for short-lived multielement analysis by neutron activation gamma-ray spectrometry. Intercomparisons of results by various methods and laboratories show the need for regular checks of techniques to ensure reliable measurements.     

Development of an automatic system for neutron activation analysis

An automatic measurement system for activation analysis has been developed at the La Reina Nuclear Center of the Chilean Nuclear Energy Commission. A gamma-ray spectrometer equipped with an automatic sample changer is linked to an IBM-compatible PC/AT. The peripheral devices are interconnected and suitable software for routine operation have been prepared. The computer handles solenoid valves and microswitch sensors. The gamma-spectra are stored in the hard disk and later transferred to a main frame computer where all the information is processed to obtain final results. The system is in full operation and the operation manuals that have been prepared allow it to be used by people who are not trained in activation analysis.     

月球样品的中子活化分析技术研究

月球的起源是月球研究的核心问题。月球探测任务返回的数据和样品极大地提高了人类对地月系统的认知,同时也发现了更多未解之谜,亟待未来的探测任务和科学研究来解答。嫦娥五号月壤是我国首次地外天体采集返回的样品,也是继美国和苏联探月采样任务45年后人类再次获得的月球样品。鉴于月球样品的珍贵性和特殊性,利用先进技术开展其全元素含量的非破坏精准分析对于认识月球演化和月球资源就地开发利用具有重要的意义。依托大型核反应研究堆和加速器中子注量率优势,利用中子活化分析技术可实现月球样品中的全元素非破坏分析：1)仪器中子活化分析技术(INAA)可测量Na—U元素之间的60余种元素;2)瞬发γ中子活化分析技术(PGNAA)可补充测量INAA不适合测量的元素如H、B、C、N等;3)中子深度剖面分析技术(NDP)可测量样品近表面(微米级)聚变能源³He的浓度深度分布;4)缓发中子测量技术(DNC)可定量样品中痕量裂变核素如²³⁵U和²³⁹Pu,并结合INAA可测量²³⁸U/²³⁵U同位素比值;5)14 Me...     

Comparison of instrumental neutron activation analysis of geological materials with other multielement techniques

Results obtained for 12 elements in approximately 1600 rocks by instrumental neutron activation analysis (INAA) are compared with those obtained by ICP emission spectrometry (ICP-ES), XRF, and atomic-absorption spectrometry (AAS). Sample duplicates and two controls are used to evaluate the precison of the methods investigated. Application of a method (Maximum Likelihood Functional Relationship) to determine and quantify rotational and translational bias is demonstrated. The elements Na, Fe, Ba, Co, Cr, La, Ni and Rb can be determined in rocks by INAA with sufficient sensitivity and precision, whereas the determination of Ag, Yb, Zn and Zr suffers from inadequate sensitivity. Good agreement is seen in the results for Na (by INAA, ICP-ES and XRF) and AG (INAA and AAS). A significant positive bias (13% or less) is evident in the comparison of results by INAA and ICP-ES or XRF for Cr, Ba, Ni and Fe over a wide range of concentration. A similar trend, though less significant, is observed for the elements Yb, Rb, La and Co; the upper limit of concentration for satisfactory determination is within a decade of the highest detection limit for these elements. Rotational and translational bias is evident for Zn in the comparison of data obtained by INAA and ICP-ES, the results by INAA being appreciably lower above about 400 ppm Zn.     

Characterization of protein-bound metal species by bioanalytical and neutron activation techniques

Several bioanalytical techniques have been employed in conjunction with instrumental neutron activation analysis (INAA) to study metalloproteins and protein-bound trace elements in bovine kidneys. The accuracy of the INAA method developed has been evaluated by analyzing certified reference materials. Up to 29 elements can be reliably determined in biological tissue samples by INAA. Dialysis of the bovine kidney homogenate shows that more than 90% of Ca, Cd, Cu, Fe, Mg, Mn, Mo, Se, V and Zn, and about 20% of Br are bound to macromolecules, mainly proteins. A combination of gel filtration and ion exchange chromatography, chromatofocusing, electrofocusing, ammonium sulphate precipitation and INAA of the bovine kidney microsomecytosol subcellular fraction further indicates that much of the copper is associated with a single protein of an isoelectric point around 5 and a molecular weight of about 30 000 daltons. Some results on manganese proteins are also reported.     

CAMAC-based instrumentation for a non-destructive neutron activation analysis system

The measuring system described in this paper, developed for non-destructive neutron activation analysis, consists of a semiconductor detector gamma-ray spectrometer and a sample changer coupled to a PDP-9 computer via a CAMAC interface system. CAMAC modules implemented in this system are an ADC interface, a sample changer control, display unit, a timer and a time-of-the-year clock. The spectra are accumulated in a section of the computer memory. The computer is further used for experiment control and for the analysis and interpretation of the measured gamma-ray spectra.     

Validation of a loss-free counting system for neutron activation analysis with short-lived indicators

The use of loss-free counting systems makes possible the exact correction for pile-up and dead-time losses during counting of a mixture of short-lived radionuclides even at very high count rates. However, counting statistics cannot be calculated by taking into account only the Poisson distribution of the incoming -quanta, such as is done in existing computer programs for -spectrometry. At moderate count rates Müller statistic was found to account for the observed variability between duplicate countings; however, at higher count rates the variability of weighing factors was found to be significant in comparison with the Müller statistic. While counting statistics could not be correctly estimated for short-lived species, experiments showed excellent accuracy for initial dead times up to 90%.     

The development of a thermal neutron activation (TNA) system as a confirmatory non-metallic land mine detector

In order to detect and locate buried landmines for peacekeeping, the Canadian Department of National Defence (DND), under the Improved Landmine Detection Project, is developing a vehicle-mounted, two-phase mine detection system. The first phase constitutes a suite of detectors used to indicate the possibility of a mine at a particular location (to ±30 cm in accuracy). In the second phase a Thermal Neutron Activation (TNA) system is used to confirm the presence of explosives via detection of the 10.83 MeV gamma-ray associated with nitrogen decay. The TNA system developed for this uses a 100 μg²⁵²Cf neutron source surrounded by four 3″×3″ NaI(Tl) detectors. Combining the use of state-of-the art radiation transport codes for design, judicious choice of specialized shielding materials and development of high-rate, fast-pulse processing electronics, has led to a system which can; (i) confirm the presence of all surface- or lightly-buried anti-tank mines in a few seconds to a minute (depending on mass of explosive), (ii) confirm the presence of anti-tank mines down to 20 cm depth in less than 5 minutes, (iii) confirm the presence of large (>100 g nitrogen) anti-personnel mines in less than five minutes, (iv) operate in adverse climatic conditions. These results have been verified in field trials and the system is due to be fielded in 1999.