[Genie 2000 Basic Spectroscopy Software Download
Tilo Chopin
The Genie 2000 Programming Library is a software development tool used in nuclear spectroscopy applications. It provides a set of functions and libraries that allow for the customization and automation of Genie 2000 spectroscopy systems.
The Genie 2000 Programming Library works by allowing users to write code in a programming language such as C++ or Visual Basic, which can then be compiled and linked with the Genie 2000 software. This allows for the creation of custom applications and analysis routines.
The Genie 2000 Programming Library offers several benefits, including the ability to customize and automate data acquisition and analysis, increased efficiency and accuracy in data processing, and the ability to integrate with other software and hardware systems.
While some programming experience is required to use the Genie 2000 Programming Library, it does come with a comprehensive user manual and examples to help guide users through the process. Additionally, there are online resources and support available for users who may need assistance.
The Genie 2000 Programming Library is specifically designed to work with Genie 2000 spectroscopy systems. However, it may also be compatible with other spectroscopy systems that support the required programming languages and interfaces.
The DSA-LX analyzer is a full featured 16K channel integrated Multichannel Analyzer based on advanced digital signal processing techniques (DSP). When paired with a computer running Genie 2000 software the DSA-LX unit becomes a complete spectroscopy workstation, capable of the highest quality acquisition and analysis. The instrument interfaces to existing detector technologies such as HPGe, NaI, Si(Li), CdTe or Cd(Zn)Te.
The NRL gamma spectroscopy lab has three high-resolution gamma spectroscopy detectors. All of them are high purity germanium detectors (HPGe) housed in copper-lined lead caves to reduce background, and are used to identify and quantify radioisotopes in samples. A typical GRSS detector channel consists of a high-purity germanium (HPGe) semiconductor detector, a pre-amplifier, an amplifier, a high-voltage power supply, a multi-channel analyzer (MCA), and a computer-based acquisition and analysis system. In modern systems, many of these components are combined into integrated units. At the NRL, the Canberra Lynx system is employed, which integrates the power supply, digital amplifier, and MCA into a single box. The Lynx units are networked, allowing one computer to control multiple Lynxes.
Gamma rays emitted from a radioactive source that are absorbed in the HPGe detector produce electrical pulses, and the pulse amplitude is proportional to the energy deposited in the detector, which allows for measurement of gamma ray energies. The MCA sorts these pulses by amplitude, and computer software displays a plot of the number of pulses received at each pulse amplitude. Such a plot is called a spectrum because it shows the spectrum of energies emitted by the source. Comparison of the peaks found in a spectrum against a library of known radionuclide energies and abundances allows identification of the radioactive components of a sample. If the system efficiency is calibrated using a source with traceable activity, the activity of those radionuclides can be quantified.
Data acquisition and control, as well as quantitative analysis of identified radionuclide activity, is performed by the software package Genie 2000 from Canberra Industries. The software provides for spectrum acquisition, storage, isotope identification, and activity quantification, as well as detector system energy and efficiency calibration.
The figure below shows a picture of a GRSS system at the NRL. On the desk are the computer used for analysis and display as well as the Lynx MCA (seen behind the keyboard), and to the right is the detector shield that minimizes counts from background radiation and a vacuum dewar filled with liquid nitrogen for keeping the HPGe detector at its operating temperature.
GRSS CalibrationCalibration of a gamma-ray spectrometer involves placing a traceable source, often with emissions at multiple gamma-ray energies, in a repeatable position relative to the detector and acquiring a spectrum. Using the measured spectrum in conjunction with the source activity and date from the source calibration certificate, the analysis software computes the efficiency of the detector at each of the source energies for the source in that position. A polynomial curve fit provides an efficiency curve as a function of energy.
The HPGe detectors of the GRSS at the NRL are calibrated using a NIST-traceable mixed-nuclide point source. The first detector is a Canberra GC5019 HPGe, which has an efficiency of 50% relative to a standard 3 inch x 3 inch NaI detector at 1332 keV, and has full width at half max (FWHM) of 1.9 keV for peaks measured at 1332 keV. The second detector is a Canberra GC1419 HPGe, which has an efficiency of 14% relative to a standard 3 inch x 3 inch NaI detector at 1332 keV, and has full width at half max (FWHM) of 1.9 keV for peaks measured at 1332 keV. The third detector is a Canberra GC1420 HPGe, which has an efficiency of 14% relative to a standard 3 inch x 3 inch NaI detector at 1332 keV, and has full width at half max (FWHM) of 2.0 keV for peaks measured at 1332 keV. The calibration source contains nine radionuclides, with gamma emissions ranging from 88 keV to 1836 keV. This provides a calibration curve that covers all the major emissions from 22Na and 154Eu (123 keV - 1596 keV). For each peak in the source, the stated 3-sigma uncertainty (99% confidence) in the emission rate is 3%.
Calculations of sample activity take into account the efficiency of the detector system as a function of energy, the gamma-ray emission probability for the nuclide/energy, and correction for radioactive decay during the count. The figure below shows a sample spectrum from the calibration measurement. The nine nuclides result in eleven full-energy peaks.
In order to determine the natural radioactivity in ground water, twenty water samples were collected from most frequently used wells spread in different locations of Al-Baha region. It is located in the south-east of Saudi Arabia (200'0"N, 4130'0"E), as shown in Figure 1. The sampling locations were chosen mostly based on population density and accessibility. Al-Baha region is an agricultural area, the main agro products, are wheat, vegetables and fruits. This region was chosen based on the active usage of ground water for drinking and for irrigation purposes made by locals of the area which can also be a source of radionuclides in foods.
The collected water samples were acidified with nitric acid to avoid the collection of organic materials, then each sample was filled into 500 ml capacity polyethylene Marinelli beakers ( IAEA, 1989 ). Before use the containers were washed
with dilute HCl and rinsed with distilled water. The Marinelli beakers were sealed and stored for more than 4 weeks before counting to reach the secular equilibrium between 226Ra nuclides and 232Th nuclides and their daughters for gamma ray measurements ( Abbady, 2004 ). Detection and measurements of the sample concentrations were carried out using a coaxial high-purity germanium (HPGe) detector with relative efficiency of 25% and FWHM 2.0 keV at 1332 keV, of 60Co. The detector was housed inside a thick lead shield to reduce the background of the system. Genie 2000 basic spectroscopic software was installed in the computer for data acquisition and analysis. The system was calibrated for energy and efficiency on a regular basis in ( IAEA, 1989 ). Each sample after equilibrium was kept on the top of the HPGe detector and counted for 36,000 s. The background was measured every week under the same conditions of sample measurement.
where: Ca is the net gamma counting rate (counts per second), ε the detector efficiency of the specific γ-ray, Pγ the absolute transition probability of Gamma-decay and m the mass of the sample (kg).
The calculated total annual effective doses for adults ingested radionuclides 226Ra, 232Th and 40K from the ground water samples were tabulated in Table 1. The highest value (0.237 mSv/y) of effective dose was calculated in sample w6 due to the radium high concentration. The range of effective doses due to intake of 226Ra, 232Th, and 40K were from 0.004 to 0.237 mSv/y, with an average value of 0.058 mSv/y which is below the average limit (0.1 mSv/y) reported by WHO ( WHO, 2006 ). Consequently, we recommended that, the investigated waters are acceptable as drinking water for life-long human without any treatment to reduce the concentrations of radioactive contaminants. Figure 3, shows the effective dose for the ingestion of 226Ra, 232Th and 40K by adults.
the natural radioactivity concentrations of these nuclides were below the WHO guidance levels and were within the values reported by the other researchers. The risk assessment data show that the investigated radionuclides in water were below limit values and pose no detrimental health effect.
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