Multichannel Analyzers (MCA)

Gamma Spectroscopy / Isotope Indentification

ICS-PCI MCA-based Spectroscopy System for PC
	The ICS-PCI system utilizes a PCI card for the multichannel analyzer and is available as 1024, 2048 and 4096 channel versions for Windows 98 and higher.
UCS-30 MCA-based Spectroscopy System for PC and MAC
	The UCS-30 is an external MCA interfacing through the computer USB port. This is designed for newer computers supporting USB and lacking an available ISA or PCI slot for a plug-in card. It is also for people who do not want to open their computer to install a plug-in card. System Software is provided for Windows and Macintosh.
ICS-4000 Isotope Indentifier
	The Model ICS-4000 isotope identifier is an easy to use field-portable gamma ray spectrometer, suitable for a variety of field survey and analysis applications. A sensitive cadmium zinc telluride (CZT) detector, 4000 channel multichannel analyzer and powerful microprocessor are combined to allow sophisticated laboratory-grade analysis in the field.
URSA II Multichannel Analyzer
	The URSA II is a 4096 channel MCA, software is included. Just add your own computer and the detector of your choice. Sophisticated multiple alarm functions can be based on the overall count rate or individual ROIs, and can be based on exceeding a specific rate or an increase in rate over a specific time interval.
Model 7010 Rainbow Multichannel Analyzer
	The Model 7010 "Rainbow" Multi-Channel Analyzer is a low cost, portable, self-contained MCA. The Model 710 can be used in the field or the lab for routine and emergency measurements. It includes1024 channels, dead time correction, digital gain, expanded scales, and built-in memory storage. The 7010 Rainbow MCA is recommended for experienced physcists who are able to recognize the isotope by observing the energy peaks.

notes:

Gamma spectroscopy involves the spectroscopy of radionuclides by means of a multi channel analyzer (MCA). While a Geiger counter determines only the count rate (i.e. the number of gamma rays hitting the detector in one second) , a gamma spectrometer (MCA) determines the energy of gamma rays emitted by radioactive substances.

Most radioactive sources produce gamma rays of various energies and intensities. When these emissions are collected and analyzed with a gamma spectroscopy system (MCA), a gamma energy spectrum can be produced. A detailed analysis of this spectrum is typically used to determine the identity and quantity of gamma emitters present in the source. The gamma spectrum is characteristic of the gamma-emitting nuclides contained in the source.

The equipment used in gamma spectroscopy includes an energy-sensitive radiation detector, a pulse sorter (i.e., multichannel analyzer), and associated amplifiers and data readout devices. The most common detectors include sodium iodide (NaI) scintillation counters and high-purity germanium detectors. A gamma spectroscopy system (MCA) consists of a detector, electronics to collect and process the signals produced by the detector, and a computer with processing software to generate, display, and store the spectrum. Other components, such as rate meters and peak position stabilizers, may also be included.

Gamma spectroscopy detectors are passive materials that wait for a gamma interaction to occur in the detector volume. The most important interaction mechanisms are the photoelectric effect, the Compton effect, and pair production. The photoelectric effect is preferred, as it absorbs all of the energy of the incident gamma ray. Full energy absorption is also possible when a series of these interaction mechanisms take place within the detector volume. When a gamma ray undergoes a Compton interaction or pair production, and a portion of the energy escapes from the detector volume without being absorbed, the background rate in the spectrum is increased by one count. This count will appear in a channel below the channel that corresponds to the full energy of the gamma ray. Larger detector volumes reduce this effect.

The voltage pulse produced by the detector (or by the photomultiplier in a scintillation detector) is shaped by a multichannel analyzer (MCA). The multichannel analyzer takes the very small voltage signal produced by the detector, reshapes it into a Gaussian or trapezoidal shape, and converts that signal into a digital signal. In some systems, the analog-to-digital conversion is performed before the peak is reshaped. The analog-to-digital converter (ADC) also sorts the pulses by their height. ADCs have specific numbers of "bins" into which the pulses can be sorted; these bins represent the channels in the spectrum. The number of channels can be changed in most modern gamma spectroscopy systems by modifying software or hardware settings. The number of channels is typically a power of two; common values include 512, 1024, 2048, 4096, 8192, or 16384 channels. The choice of number of channels depends on the resolution of the system and the energy range being studied.
The multichannel analyzer output is sent to a computer, which stores, displays, and analyzes the data. A variety of software packages are available from several manufacturers, and generally include spectrum analysis tools such as energy calibration, peak area and net area calculation, and resolution calculation.

Gamma spectroscopy - Multichannel Analyzer (MCA) systems are selected to take advantage of several performance characteristics. Two of the most important include detector resolution and detector efficiency. Gamma rays detected in a spectroscopic system produce peaks in the spectrum. The width of the peaks is determined by the resolution of the detector, a very important characteristic of gamma spectroscopic detectors. High resolution enables the spectroscopist to separate two gamma lines that are close to each other. Gamma spectroscopy (MCA) systems are designed and adjusted to produce symmetrical peaks of the best possible resolution. The peak shape is usually a Gaussian distribution. In most spectra the horizontal position of the peak is determined by the gamma ray's energy, and the area of the peak is determined by the intensity of the gamma ray and the efficiency of the detector.

The most common figure used to express detector resolution in a gamma spectroscopy system (MCA) is full width at half maximum (FWHM). This is the width of the gamma ray peak at half of the highest point on the peak distribution. Resolution figures are given with reference to specified gamma ray energies. Resolution can be expressed in absolute or relative terms. For example, a sodium iodide (NaI) detector may have a FWHM of 9.15 keV at 122 keV, and 82.75 keV at 662 keV. These resolution values expressed in absolute terms. To express the resolution in relative terms, the FWHM in eV or MeV is divided by the energy of the gamma ray and multiplied by 100. Using the preceding example, the resolution of the detector is 7.5% at 122 keV, and 12.5% at 662 keV. A germanium detector may give resolution of 560 eV at 122 keV, yielding a relative resolution of 0.46%.

Not all gamma rays emitted by the source and pass through the detector will produce a count in the system. The probability that an emitted gamma ray will interact with the detector and produce a count is the efficiency of the detector. High-efficiency detectors produce spectra in less time than low-efficiency detectors. In general, larger detectors have higher efficiency than smaller detectors, although the shielding properties of the detector material are also important factors. Detector efficiency is measured by comparing a spectrum from a source of known activity to the count rates in each peak to the count rates expected from the known intensities of each gamma ray.

Efficiency, like resolution, can be expressed in absolute or relative terms. The same units are used (i.e., percentages); therefore, the spectroscopist must take care to determine which kind of efficiency is being given for the detector. Absolute efficiency values represent the probability that a gamma ray of a specified energy passing through the detector will interact and be detected. Relative efficiency values are often used for germanium detectors, and compare the efficiency of the detector at 1332 keV to that of a 3 in × 3 in NaI detector (i.e., 1.2×10-3 cps/Bq). Relative efficiency values greater than one hundred percent can therefore be encountered when working with very large germanium detectors.

The energy of the gamma rays being detected is an important factor in the efficiency of the detector. An efficiency curve can be obtained by plotting the efficiency at various energies. This curve can then be used to determine the efficiency of the detector at energies different from those used to obtain the curve. High-purity germanium (HPGe) detectors typically have higher sensitivity.

Scintillation detectors use crystals that emit light when gamma rays interact with the atoms in the crystals. The intensity of the light produced is proportional to the energy deposited in the crystal by the gamma ray. The mechanism is similar to that of a thermoluminescent dosimeter. The detectors are joined to photomultipliers that convert the light into electrons and then amplify the electrical signal provided by those electrons. Common scintillators include thallium-doped sodium iodide (NaI(Tl)), often simplified to sodium iodide (NaI) detectors and bismuth germanate (BGO). Because photomultipliers are sensitive to ambient light, scintillators are encased in light-tight coverings.

Thallium-doped sodium iodide (NaI(Tl)) has two principal advantages: It can be produced in large crystals, yielding high efficiency, and
it produces intense bursts of light compared to other spectroscopic scintillators. NaI(Tl) is also convenient to use, making it popular for field applications such as the identification of unknown materials for law enforcement purposes.

Sodium iodide systems, as with all scintillator systems, are sensitive to changes in temperature. Changes in the operating temperature caused by changes in environmental temperature will shift the spectrum on the horizontal axis. Peak shifts of tens of channels or more are commonly observed. Such shifts can be prevented by using spectrum stabilizers. Because of the poor resolution of NaI-based detectors, they are not suitable for the identification of complicated mixtures of gamma ray-producing materials. Scenarios requiring such analyses require detectors with higher resolution.

Semiconductor detectors, also called solid-state detectors, are fundamentally different from scintillation detectors. In semiconductor detectors, an electric field is applied to the detector volume. An electron in the semiconductor is fixed in its valence band in the crystal until a gamma ray interaction provides the electron enough energy to move to the conduction band. Electrons in the conduction band can respond to the electric field in the detector, and therefore move to the positive contact that is creating the electrical field. The gap created by the moving electron is called a "hole," and is filled by an adjacent electron. This shuffling of holes effectively moves a positive charge to the negative contact. The arrival of the electron at the positive contact and the hole at the negative contact produces the electrical signal that is sent to the preamplifier, the MCA, and on through the system for analysis. The movement of electrons and holes in a solid-state detector is very similar to the movement of ions within the sensitive volume of gas-filled detectors such as ionization chambers.

Common semiconductor-based detectors include germanium, cadmium telluride, and cadmium zinc telluride. Germanium detectors provide significantly improved energy resolution in comparison to sodium iodide detectors, as explained in the preceding discussion of resolution. Germanium detectors produce the highest resolution commonly available today. Cryogenic temperatures are vital to the operation of germanium detectors.

If a gamma spectrometer is used for identifying samples of unknown composition, its energy scale must be calibrated first. Calibration is performed by using the peaks of a known source, such as cesium-137 or cobalt-60. Because the channel number is proportional to energy, the channel scale can then be converted to an energy scale. Because of background radiation, the spectrum should be analyzed when no source is present. The background radiation must then be subtracted from the actual measurement. Lead absorbers can be placed around the measurement apparatus to reduce background radiation.