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Experiment 3
Gamma-Ray Spectroscopy Using NaI(Tl)
o SPA38 Integral Assembly consisting of a 38 mm x 38 mm NaI(Tl) Scintillator, Photomultiplier Tube, and PMT Base with Stand o 4001A/4002D NIM Bin and Power Supply o 556 High Voltage Bias Supply o 113 Scintillation Preamplifier o 575A Spectroscopy Amplifier o Easy-MCA-2k including USB cable and MAESTRO-32 software (other ORTEC MCAs may be substituted) o Personal Computer with a USB port and a recent, supportable version of the Windows operating system. o Oscilloscope with a bandwidth ≥150 MHz, e.g., Tektronix Model TDS 3032C or equivalent.
o C-34-12 RG-59A/U 75-Ω Cable with one SHV female plug and one MHV male plug, 3.7-m (12-ft) length. o Five C-24-1 RG-62A/U 93-Ω Coaxial Cables with BNC plugs, 30-cm (1-ft.) length. o C-24-12 RG-62A/U 93-Ω Coaxial Cable with BNC plugs, 3.7-m (12-ft.) length. o Three C-24-4 RG-62A/U 93-Ω Coaxial Cables with BNC plugs, 1.2-m (4-ft.) length o C-29 BNC Tee Connector o C-27 100 Ω Terminator (BNC male plug)
o RSS8 Gamma Source Set. Includes ~1 μCi each of: 60 Co, 137 Cs, 22 Na, 54 Mn, 133 Ba, 109 Cd, 57 Co, and a mixed Cs/Zn source (~0. μCi 137 Cs, ~1 μCi 65 Zn). The first three are required in this experiment. An unknown for Experiment 3.2 can be selected from the remaining sources. o GF-137-M-5 5 μCi ±5% 137 Cs Gamma Source. (Used as a reference standard for activity in Experiment 3.5) o GF-057-M-20 20 μCi 57 Co Source (for Experiment 3.9)
o One each of pure metal foil absorber sets: FOIL-AL-30, FOIL-FE-5, FOIL-CU-10, FOIL-MO-3, FOIL-SN-4, and FOIL-TA-5. Each set contains 10 identical foils of the designated pure element and thickness in thousandths of an inch (Foil-Element-Thickness). o RAS20 Absorber Foil Kit containing 5 lead absorbers from 1100 to 7400 mg/cm^2. The 10 aluminum absorbers from 140 to 840 mg/cm^2 also included in this kit are not used in this experiment.
o 427A Delay Amplifier o 551 Timing Single-Channel Analyzer o 426 Linear Gate o 416A Gate and Delay Generator
The purpose of this experiment is to acquaint the student with some of the basic techniques used for measuring gamma rays. It is based on the use of a thallium-activated sodium iodide detector. The written name of this type of detector is usually shortened to NaI(Tl). In verbal conversations, it is typically simply called a sodium iodide detector.
Most isotopes used for gamma-ray measurements also have beta-emissions in their decay schemes. The decay scheme for the isotope typically includes beta decay to a particular level, followed by gamma emission to the ground state of the final isotope. The
beta particles will usually be absorbed in the surrounding material and not enter the scintillation detector. This absorption can be assured with aluminum absorbers (ref. 10). For this experiment, the beta emissions cause negligible interference, so absorbers are not specified. There is always some beta absorption by the light shield encapsulating the detector. The gammas, however, are quite penetrating, and will easily pass through the aluminum light shield.
Generally there are two unknowns that we would like to investigate about a gamma source. One is measuring the energies of the gamma rays from the source. The other is counting the number of gamma-ray photons that leave the source per unit of time. In this experiment the student will become familiar with some of the basic NaI(Tl) measurements associated with identifying a gamma- emitting radioisotope. A total time of ~6 hours is required to complete all the parts of Experiment 3 (3.1 through 3.10). Since each part is written to be fairly independent of the others, the complete series can be done in two 3-hour lab periods.
The structure of the NaI(Tl) detector is illustrated in Figure 3.1. It consists of a single crystal of thallium activated sodium iodide optically coupled to the photocathode of a photomultiplier tube. When a gamma ray enters the detector, it interacts by causing ionization of the sodium iodide. This creates excited states in the crystal that decay by emitting visible light photons. This emission is called a scintillation, which is why this type of sensor is known as a scintillation detector. The thallium doping of the crystal is critical for shifting the wavelength of the light photons into the sensitive range of the photocathode. Fortunately, the number of visible-light photons is proportional to the energy deposited in the crystal by the gamma ray. After the onset of the flash of light, the intensity of the scintillation decays approximately exponentially in time, with a decay time constant of 250 ns. Surrounding the scintillation crystal is a thin aluminum enclosure, with a glass window at the interface with the photocathode, to provide a hermetic seal that protects the hygroscopic NaI against moisture absorption. The inside of the aluminum is lined with a coating that reflects light to improve the fraction of the light that reaches the photocathode.
At the photocathode, the scintillation photons release electrons via the photoelectric effect. The number of photoelectrons produced is proportional to the number of scintillation photons, which, in turn, is proportional to the energy deposited in the crystal by the gamma ray.
The remainder of the photomultiplier tube consists of a series of dynodes enclosed in the evacuated glass tube. Each dynode is biased to a higher voltage than the preceding dynode by a high voltage supply and resistive biasing ladder in the photomultiplier tube base. Because the first dynode is biased at a considerably more positive voltage than the photocathode, the photoelectrons are accelerated to the first dynode. As each electron strikes the first dynode the electron has acquired sufficient kinetic energy to knock out 2 to 5 secondary electrons. Thus, the dynode multiplies the number of electrons in the pulse of charge. The secondary electrons from each dynode are attracted to the next dynode by the more positive voltage on the next dynode. This multiplication process is repeated at each dynode, until the output of the last dynode is collected at the anode. By the time the avalanche of charge arrives at the anode, the number of electrons has been multiplied by a factor ranging from 10^4 to 10^6 , with higher applied voltages yielding larger multiplication factors. For the selected bias voltage, the charge arriving at the anode is proportional to the energy deposited by the gamma ray in the scintillator.
Gamma-Ray Spectroscopy Using NaI(Tl)
Fig. 3.1. The Structure of the NaI(Tl) Detector and Various Types of Gamma-Ray Interactions that Occur in the Typical Source-Detector-Shield Configuration.
The MCA listed in the Equipment Required for this experiment uses software in a supporting personal computer to operate the instrument and display the spectrum. The MCA connects to the computer via a USB cable. It is important to become familiar with the controls that are accessible via the MAESTRO-32 software. The most efficient approach may be to have the laboratory instructor provide a quick demonstration. You will need to know how to start/stop data acquisition, clear the contents of the memory, select the digital resolution, adjust the upper and lower discriminator thresholds, set the preset live time, monitor the percent dead time, read the peak positions with the mouse pointer, set regions of interest, and calibrate the horizontal scale to read in keV (energy).
One of the benefits of the MCA is the incorporation of a live time clock. This feature automatically corrects for dead time losses by measuring elapsed time only when the spectrometer is not busy processing a pulse. See references 1, 11, 13 and 14 for more information.
EXPERIMENT 3.1. Energy Calibration
Set up the electronics as shown in Fig. 3.2.
There are two parameters that ultimately determine the overall gain of the system: the high voltage furnished to the phototube and the gain of the spectroscopy amplifier. The gain of the photomultiplier tube is quite dependent upon its high voltage. A rule of thumb for most phototubes is that, near the desired operating voltage, a 10% change in the high voltage will change the gain by a factor of 2. The desired high voltage value depends on the phototube being used. Consult your instruction manual for the phototube and select a value in the middle of its normal operating range. Sometimes, the detector will have a stick-on label that lists the percent resolution and the voltage at which that resolution was measured. In that case, use the high voltage value on that label. Lacking those sources to specify the operating voltage, check with the laboratory instructor for the recommended value. The operating voltage will likely fall in the range of +800 to +1300 Volts.
Gamma-Ray Spectroscopy Using NaI(Tl)
Gamma-Ray Spectroscopy Using NaI(Tl)
The NaI(Tl) detector produces a pulse of charge that lasts for about 1 μs at the anode output of the photomultiplier tube. The preamplifier collects that charge on the input capacitance and turns it into a voltage pulse at the preamplifier output. Because the anode pulse has a negative polarity, and the 113 Preamplifier is non-inverting, the voltage pulse at the preamplifier output has a negative polarity. The decay time of the scintillation controls the shape of the leading-edge response of the preamplifier output pulse. For the 250-ns decay time constant of the NaI(Tl) scintillator, the fall time (10% to 90% of the pulse height) on the leading edge of the voltage pulse will be approximately 0.55 μs. Within about 1 μs, the absolute value of the pulse amplitude reaches its maximum excursion. Subsequently, the voltage pulse decays back towards zero Volts with an exponential decay that is characterized by a 50 μs time constant. That decay time constant is nominal, and could lie anywhere in the range of 30 to 80 μs.
In the amplifier, the long exponential decay of the preamplifier must be replaced by the shorter exponential decay selected by the shaping time constant switches on the amplifier. This is the function of the Pole-Zero Cancellation circuit near the input of the amplifier. The adjustment of the Pole-Zero Cancellation to achieve exact replacement will be implemented in the next series of steps. For more information on pole-zero cancellation, consult references 1, 11 and 12.
CAUTION: On some oscilloscopes, the 10-V pulse amplitude may cause an overload of the oscilloscope amplifiers on the more sensitive vertical scales. When this happens the recovery of the trailing edge of the pulse will appear distorted, making it impossible to make a valid PZ adjustment. If this problem is suspected, start with the 5 V per major division scale and increase the vertical scale sensitivity one step at a time. For each increase in vertical sensitivity verify that the shape of the trailing edge differs from the shape on the previous scale setting in proportion to the change in the scale factor. When abrupt distortion is encountered on the more sensitive vertical scale, return to the previous, less sensitive scale to make the PZ adjustment.
It may be useful to try different horizontal scales ranging from 10 μs to 100 μs per major division while making the pole-zero cancellation adjustment.
Fig. 3.3. Oscilloscope Signal.
Gamma-Ray Spectroscopy Using NaI(Tl)
Note that 100 counts in a channel corresponds to a 10% standard deviation, 10,000 counts yield a 1% standard deviation, and 1 million counts are needed to achieve a 0.1% standard deviation. Consequently, the vertical scatter in the spectrum will begin to appear acceptable when the rather flat continuum at energies below the Compton edge has more than a few hundred counts per channel.
EXERCISES
a. From the 137 Cs and 60 Co spectra determine the photopeak positions and fill in items 1, 2, and 3 in Table 3.1. These peak positions are most conveniently determined with the mouse pointer in the spectra displayed on the computer screen.
b. From items 1, 2, and 3 in Table 3.1, make a plot of energy of the photopeaks vs. channel number. Fig. 3.6 shows this calibration for the data taken from Figs. 3.4 and 3.5. If other calibration sources are available, additional data points can be added to Fig. 3.6. The other entries in Table 3.1 will be filled out in Experiment 3.3.
c. Use the energy calibration feature of the MCA and compare the results with those found in Exercise b.
d. Does the straight line for the energy calibration intercept channel zero at zero energy? If there is a finite zero intercept, what could cause the offset?
Item Energy (MeV) Channel No.
(^60) Co 1.33-MeV gamma ray
(^60) Co for 1.33-MeV gamma ray
(^60) CO for 1.17-MeV gamma ray
Fig. 3.5. NaI(Tl) Spectrum for 60 Co.
Fig. 3.6. Energy Calibration Curve for NaI(Tl) Detector.
EXPERIMENT 3.2. Energy Analysis of an Unknown Gamma Source
This experiment uses the calibrated system of Experiment 3.1 to measure the photopeak energies of an unknown gamma-ray emitter and to identify the unknown isotope.
EXERCISE
Use refs. 7 and 8 to identify the unknown isotope.
EXPERIMENT 3.3. Spectrum Analysis of 60 Co and 137 Cs
The purpose of this experiment is to explain some of the features, other than the photopeaks, usually present in a pulse-height spectrum. These are the Compton edge, the Compton continuum and the backscatter peak.
The photopeak is created when the gamma-ray photon interacts in the scintillator via the photoelectric effect. The photon encounters an orbital electron that is tightly bound to a nucleus. The entire energy of the photon is transferred to the electron, causing the electron to escape from the atom. The gamma-ray photon disappears in the process. As the photoelectron travels through the scintillator, it loses its energy by causing additional ionization. At the end of the process, the number of ionized atoms is proportional to the original energy of the photon. As the electrons re-fill the vacancies in the ionized atoms, visible light photons are generated. This is the source of the scintillation, wherein the number of visible photons is proportional to the original energy of the gamma-ray. Consequently, the event populates the photopeak in the spectrum. This peak is often called the full-energy peak, because a two-step interaction, a Compton scattering followed by a photoelectric interaction, also contributes a small number of events to the full-energy peak.
The Compton interaction is a pure, kinematic collision between a gamma-ray photon and what might be termed a free electron in the NaI(Tl) crystal. By this process, the incident gamma-ray photon gives up only part of its energy to the electron as it bounces off the free electron. The recoiling electron loses energy by causing ionization as it travels through the crystal. Thus the number of visible photons in the resulting scintillation is proportional to the recoil energy of the Compton electron. The amount of energy transferred from the gamma-ray photon to the recoiling electron depends on whether the collision is head-on or glancing. For a head-on collision, the gamma ray transfers the maximum allowable energy for the Compton interaction. Although it involves a photon and an electron, the interaction is similar to a billiard-ball collision. The reduced energy of the scattered gamma ray can be determined by solving the energy and momentum conservation equations for the collision. The solution for these equations in terms of the scattered gamma-ray energy can be written as
where
Eγ' is the reduced energy of the scattered gamma-ray, γ', in MeV,
θ is the scattering angle for the direction of γ' relative to the direction of the incident gamma-ray, γ,
Eγ is the energy of the incident gamma-ray, γ, in MeV,
Gamma-Ray Spectroscopy Using NaI(Tl)
EXPERIMENT 3.4. Energy Resolution
The purpose of this experiment is to measure the resolution of the NaI(Tl) detector.
The resolution of a spectrometer is a measure of its ability to resolve (i.e., separate) two peaks that are fairly close together in energy. Fig. 3.4 shows the gamma spectrum that was plotted for the 137 Cs source. The resolution of the photopeak is calculated from the following equation:
Where δE is the Full Width of the peak at Half of the Maximum count level (FWHM) measured in number of channels, and E is the channel number at the centroid of the photopeak.
In Fig. 3.4 the photopeak is in channel 280 and its FWHM = 32 channels. From Eq. (7), the resolution is calculated to be 11.5%. It is standard practice to specify the quality of the NaI(Tl) detector by stating its measured percent resolution on the 662-keV photopeak from a 137 Cs radioactive source.
EXERCISE
Calculate the resolution of the system from your 137 Cs spectrum. Record this value for later reference.
EXPERIMENT 3.5. Activity of a Gamma Emitter (Relative Method)
In Experiments 3.1 and 3.3, procedures were given for determining the energy of an unknown gamma-ray source. Another unknown associated with the gamma-ray source is the activity of the source, which is usually measured in Curies (Ci); 1 Ci = 3.7 x 10 10 disintegrations/second. Most of the sources used in nuclear experiments have activities of the order of microcuries (μCi). The purpose of this experiment is to outline one procedure, called the relative method, by which the activity of a source can be determined.
In using the relative method, it is assumed that the unknown source has already been identified from its gamma-ray energies. For this example, assume that the source has been found to be 137 Cs. Then all that is necessary is to compare the activity of the unknown source to the activity of a standard 137 Cs source that will be supplied by the laboratory instructor. For convenience, call the standard source S1 and the unknown source U1.
Gamma-Ray Spectroscopy Using NaI(Tl)
Gamma-Ray Spectroscopy Using NaI(Tl)
EXERCISE
a. Solve for the activity of U1 by using the following ratio:
Where AS1 is the activity of the standard source, S1, and A (^) U1 is the calculated activity of the unknown source, U1. NOTE: Since the efficiency of the detector is only energy dependent, the standard and unknown sources do not have to be the same isotope. It is necessary only that their gamma energies be approximately the same (±10%) in order to get a fairly good estimate of the absolute gamma activity of the unknown. However, this relaxation of the comparison requirements may be invalid if one of the sources has a more complicated decay scheme, or if the gamma-ray decay fraction is different for the two isotopes.
b. Check the nominal activity listed on the label attached to the unknown source. How closely does your calculated value match that number?
c. Increasing the detector-to-source distance results in longer counting times to achieve adequate precision in the counting statistics, as a result of the Inverse Square Law (see Expt. 2.5). What is the other way that the source-to-detector distance significantly affects the accuracy of the relative activity measurement?
EXPERIMENT 3.6. Activity of a Gamma Emitter (Absolute Method)
The activity of the radioactive source used in Experiment 3.5 can be determined by the absolute method. The purpose of this experiment is to outline the procedure for this method. Here, the source to be measured will be called U1.
Where
tL is the live time in seconds,
εp is the intrinsic peak efficiency for the gamma-ray energy and detector size used (Fig. 3.7 and ref. 10),
f is the decay fraction of the unknown activity, which is the fraction of the total disintegrations in which the measured gamma ray is emitted (refs. 7 and 8 and Table 3.2)
G = [area of the detector (cm^2 )] / [4πs 2 ], and
s is the source-to-detector distance in cm.
Gamma-Ray Spectroscopy Using NaI(Tl)
I 0 is the intensity before the absorber,
μ is the total mass absorption coefficient in cm 2 /g, and
x is the density thickness in g/cm 2.
In this experiment, the intensity will be measured as the net counts in the photopeak divided by the elapsed live time. Net counts means the background contribution has been subtracted from the total counts in the region of interest (ROI) set across the photopeak. The density thickness is the product of the density in g/cm 3 times the thickness in cm.
The half-value layer (HVL) is defined as the density thickness of the absorbing material that will reduce the intensity to one half of its original value. From Eq. (10):
If I/I 0 = 0.5, and x = HVL, then In(0.5) = –μ(HVL) and hence
In this experiment we will measure μ for lead at 662 keV using the gamma rays from 137 Cs. The accepted value for μ at that energy is 0.105 cm^2 /g. Values for other materials can be found in references 8 and 15.
Background Subtraction : Two different methods can be used for background subtraction. In Experiments 3.5 and 3.6, the background contribution was determined by measuring the counts when the radioactive source was absent. This is a useful scheme if there is some risk that a natural background is producing a peak that overlaps the photopeak of the radioisotope that is the primary subject of the measurement. There is an alternative method that is productive when it is not feasible to remove the source under investigation, or when other gamma-rays from the source generate a Compton continuum under the peak of interest. In this latter scheme, the counts in background regions on either side of the peak are measured, and an interpolation is employed to estimate the background under the peak. The MAESTRO-32 software can perform this latter calculation of the Net Counts in the region of interest. It generally uses the first three channels and the last three channels of the region of interest to calculate the interpolated background and subtract it. Thus, the ROI should be set up so that the first three and the last three channels are in the flat background regions to either side of the peak. Use the Gross Area readout from the ROI when a separate background spectrum will be acquired for background subtraction. Employ the Net Area when it is desirable to subtract the local background interpolated from both sides of the peak in the spectrum. In Experiment 3.7, use the Net Area to subtract the background.
Table 3.3. Data for Mass Absorption Coefficient.
Absorber Absorber Thickness (mg/cm^2 ) ΣCs – Σb 1 0 2 3 4 5 6 7 8
a. Using semilog graph paper, plot I vs. absorber thickness in mg/cm 2 , where I = (ΣCs – Σb)/(live time). Determine the HVL from this curve, and calculate μ from Eq. (12). How does your value compare with the accepted value of 0.105 cm 2 /g?
b. The μ for aluminum at 662 keV is 0.074 cm^2 /g, and the density of aluminum is 2.70 g/cm^3. What is the half-thickness of aluminum in mg/cm^2 and in cm? Why is the half-thickness of aluminum so much larger than the half-thickness for lead? How does the mass absorption coefficient depend on atomic number?
EXPERIMENT 3.8. Sum Peak Analysis
Fig. 3.5 shows the two pronounced peaks from a 60 Co radioisotope. Their origin is documented by the 60 Co decay scheme illustrated in Fig. 3.8. Most of the time (>99%), the decay occurs by β–^ emission to the 2.507 MeV excited state of 60 Ni. Subsequent decay to the ground state always occurs by a 1.174 MeV gamma-ray emission to the 1.3325 MeV level, followed almost simultaneously by the 1.3325 MeV gamma emission to the ground state. Experiment 19 will demonstrate that these two events are in coincidence, and have an angular correlation that deviates from an isotopic distribution by only 16%. For the purposes of this experiment we can assume that each of these gamma rays are isotropically distributed. In other words, if γ 1 departs in a particular direction, γ 2 can go in any direction that it wishes. The range of available angles (directions) for each of the two gamma-rays covers the 4π steradians of a sphere centered on the point source. There is a certain probability that γ 2 will go in the same direction as γ 1. If this occurs within the resolving time of the detector, the energies of γ 1 and γ 2 will be summed in the scintillator. Hence a sum peak will show up in the spectrum. Adopting the definitions in Experiment 3.6, the number of counts, Σ 1 , under the γ 1 peak is given by:
where A is the activity of the sample, t (^) L is the live time for the measurement, ε 1 is the intrinsic photopeak efficiency at the γ 1 energy, and f 1 is the fraction of the total decays in which γ 1 is emitted. Similarly, the sum Σ 2 for γ 2 is given by:
Using the basic concepts behind equations (13) and (14), the number of counts in the sum peak, Σs, can be expressed as:
where W(0°) is a term that accounts for the angular correlation function (ref. 16 & 17). For the case of 60 Co, W(0°) ≈ 1.0, f 1 ≈ f 2 ≈ 1.0, and Eq. (15) can be approximately expressed as:
This experiment, will confirm that the sum peak for 60 Co has an energy of 2.507 MeV, and that the number of counts in the sum peak is given by Eq. (16).
Gamma-Ray Spectroscopy Using NaI(Tl)
Fig. 3.8. The Decay Scheme of 60 Co.
where Eγ = hv is the original energy of the gamma-ray photon, h is Planck's constant, v is the oscillatory frequency of the photon, and E (^) B is the binding energy of the electron in its host atom. The probability of a photoelectric interaction occurring is dependent on the atomic number of the absorbing material and the energy of the gamma-ray or x-ray photon. Although it is difficult to write an exact analytical expression for this probability, it can be shown that, for low-energy photons
where k is a proportionality constant, Z is the atomic number, and n is usually a number between 4 and 5.
Taking the logarithm of both sides of the equations yields
For this experiment, the gamma-ray energy will be held constant at Eγ = 122 keV, while the atomic number of the absorber is varied. Consequently, the terms within the square brackets in equation (20) will be constant. Thus, plotting the mass absorption coefficient versus the atomic number on log-log graph paper should produce a straight line with a slope equal to n.
The setup for this experiment is the same as for Experiment 3.7.
Gamma-Ray Spectroscopy Using NaI(Tl)
Table 3.4. Elemental Foil Parameters
Foil Element
Individual Foil Thickness (^) Density (g/cm 3 )
μ @ 122 keV in cm 2 /g
Half Value Inches cm g/cm 2 Layer in g/cm 2 Al 0.030 0.0762 0.206 2.70 0.154 4. Fe 0.005 0.0127 0.099 7.80 0.272 2. Cu 0.010 0.0254 0.226 8.89 0.321 2. Mo 0.003 0.0076 0.069 9.00 0.685 1. Sn 0.004 0.0102 0.074 7.30 1.020 0. Ta 0.005 0.0127 0.211 16.60 2.592 0. Pb 0.039 0.0986 1.119 11.35 3.376 0.
Gamma-Ray Spectroscopy Using NaI(Tl)
a. On log-log graph paper, make a plot of μ vs. Z from your experimental data. (Alternatively, plot the ln(μ) versus the ln(Z) in an Excel spreadsheet). Draw a straight line through the data points and calculate the value of “n” in equations (19) and (20) from the slope of that straight line. How do your results compare to the theory?
b. How does the inability to match the half-value layer thickness affect the accuracy of the measurement?
EXPERIMENT 3.10. The Linear Gate in Gamma-Ray Spectroscopy
The purpose of this experiment is to learn how to set up the analog and logic signal alignment when employing a linear gate to restrict the categories of nuclear events that are analyzed. The demonstration will involve limiting the analyzed events to only those appearing in the photopeak.
Fig. 3.9. Block Diagram of the Electronics for Gamma-Ray Spectrometry with a Linear Gate Interposed.
Gamma-Ray Spectroscopy Using NaI(Tl)
EXERCISE
a. With the additional modules inserted, there are at least two factors that may have changed the energy calibration of the spectrum in this experiment compared to the previous experiments. What are those factors? It will not be necessary to re-calibrate the horizontal (energy) scale, as long as the features of the spectrum are readily identifiable for the purposes of Experiment 3.10.
Currently, external linear gates are rarely used in nuclear measurements, because virtually all commercially-available MCAs incorporate a linear gate. It turns out that it is much easier, and more convenient, to design a high-quality linear gate into the MCA. The previous set of measurements demonstrated what is happening in the linear gate. The next set of measurements shows how to meet the needs of the linear gate imbedded in the MCA.
Because the goal of the MCA is to measure the maximum height of the analog pulse, it automatically closes its linear gate after the peak amplitude of the pulse has been captured. Consequently, the linear gate logic pulse does not need to last more than a few tenths of a microsecond past the peak amplitude of the analog pulse. Different MCAs have diverse requirements for when the linear gate logic pulse must begin relative to start of the analog pulse. Some designs require that the logic pulse arrive slightly before the start of the analog pulse. Others simply require that the logic pulse be present at the time the peak amplitude of the analog pulse is captured.
In the following set of measurements, the alignment requirements of the Easy-MCA gating function will be investigated.
EXERCISE
b. Make a sketch of the analog and logic pulses showing their time relationship.
If the timing requirements of the MCA linear gate are not well known, the above procedure can be employed to determine those requirements. Alternatively, it is usually safe to adjust the gating logic pulse to span the entire analog pulse.
References
Gamma-Ray Spectroscopy Using NaI(Tl)
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