non-imaging devices in nuclear medicine
TRANSCRIPT
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Non-imaging Non-imaging devices devices in Nuclear Medicinein Nuclear Medicine
Pawitra Masa-at4937092 SIRS/MMarch 23, 2007
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2Nuclear Medicine
Type of non-imaging Type of non-imaging devicedevice Gas-filled detectors
Radionuclide dose calibrators
Scintillation detectorScintillation detector Gamma well counter The thyroid uptake probe Liquid scintillation detector
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Radionuclide dose Radionuclide dose calibratorscalibrators
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4Nuclear Medicine
Gas-Filled DetectorsGas-Filled Detectors
I ; Ionization chamber regionP ; Proportional regionGM ; Geigur-Mueller region
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5Nuclear Medicine
In the ionization chamber region The number of ion pairs collected by the
electrodes is equal to the number of ion pair produced by the radiation in the detector.
There is no change in the number of ion pairs collected as the voltage increase.
Ionization Chamber
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6Nuclear Medicine
Ionization Chamber
HV
+
-
Negative ion
Positive ion
1234
Electrometer
The response is proportional toionization rate (activity, exposure rate)
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7Nuclear Medicine
Dose calibrators (Activity meter) A radionuclide calibrator is in essence a well-type gas
ionization chamber into the well of which a radioactive material is introduced for measurement.
The activity of the material is measured in terms of the ionization current produced by the emitted radiations which interact in the gas.
The chamber is sealed, usually under pressure, and has two co-axial cylindrical electrodes maintained at a voltage difference derived from a suitable supply, the axial space constituting the well.
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8Nuclear Medicine
Dose calibrators
In the associated electrometer, the ionization current is converted to a voltage signal, which is amplified, processed and finally displayed, commonly in digital form in units of activity - becquerels (Bq) or curies (Ci).
This is possible since for a given radionuclide, assuming a fixed geometry and a linear response, ionization current is directly proportional to activity.
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9Nuclear Medicine
Dose calibrators
SC97
Proportionality between the number of photons emitted and the ionization current
Well-shaped ionization chamberfilled with a gas of high atomicnumber (e.g. Xenon) and keptunder pressure
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10Nuclear Medicine
Dose calibrators
The response of the detector will depend on:
• Radionuclide (energy and abundance of photons).• Geometry of the detector.• Geometry of the source.• The condition of the instrument (QC).
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11Nuclear Medicine
ACTIVITY MEASUREMENT
Setting Measured activityTc-99m 1.00Co-57 1.19In-111 2.35Tl-201 1.76Ga-67 1.12I-123 2.19I-131 1.43
Measured activity/True activity of Tc.99m if the indicated settings are used
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12Nuclear Medicine
Geometric efficiencyThe quotient: number of photons reaching the detector overthe number of photons emitted from the sample
Increasing geometric efficiency
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13Nuclear Medicine
SAMPLE HOLDER(reproducible geometry)
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14Nuclear Medicine
Quality control of the dose calibrator.should include:
Test of precision and accuracy Test of linearity of activity response Test of reproducibility (Constancy test) Check of background
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15Nuclear Medicine
Sealed sources for calibration of activity meters
• Long half-life• Range of photon energies• Range of activities• Calibrated within 5%
Co-57, Ba-133, Cs-137, Co-60
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16Nuclear Medicine
Sealed sources for calibration of activity meters
Radionuclide Photon energy (keV)
Half-life Activity
(MBq)
Co-57 122 271 d 185
Ba-133 81, 356 10.7 y 9.3
Cs-137 662 30 y 7.4
Co-60 1173, 1332 5.27 y 1.9
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17Nuclear Medicine
Source (sealed): Cs-137 or Co-57
Procedure: Select settings for the radionuclideand adjust background. Insert source in holderand make 10 measurements.
Data analysis: To assess precision, calculate foreach source (i) the percentage difference between themeasured activity Ai and their mean Amv. (+/-5%)To assess accuracy, calculate the percentage differencebetween the mean activity and the certified activity.(+/- 10%).
Measurement of precision and accuracy
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18Nuclear Medicine
Mv: 9.834SD: 0.125
0
5
10
15
20
0 20 40 60
Measurement no
Act
ivit
y
Measure the activity of a sealed referencesource e.g. every morning. Use Tc-99m settings.
Measurement of reproducibility
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19Nuclear Medicine
Measurement of reproducibility
•Check of Reproducibility. Part of control chart. The Cs-137 Source used had amean measured activity of 4.55 MBq (123 uCi) on 1 April.
•The limits of accepability indicated correspond to +/- 5% of the expected activity.
•The initial discrepant result on 17 May arose from failure to allow sufficient time for the reading to stabilize
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20Nuclear Medicine
Use a radionuclide with short half-life e.g. Tc-99mMake repeated measurements during several half-lives.
Slope = -0.11471, R2=0.9999T=6.04 h
1
10
100
1000
10000
100000
0 20 40 60
Time (h)
Acti
vit
y (
MB
q)
Measurement of linearity
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21Nuclear Medicine
Type of non-imaging Type of non-imaging devicedevice Gas-filled detectors
Radionuclide dose calibrators
Scintillation detectorScintillation detector Gamma well counter The thyroid uptake probe Liquid scintillation detector
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Gamma well counterGamma well counter The thyroid uptake The thyroid uptake probeprobe
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23Nuclear Medicine
Scintillation detectors can be used as a part of both non-imaging and imaging devices.
From the non-imaging devices, scintillation well counters and thyroid probes are used.
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24Nuclear Medicine
The gamma well counter The gamma well counter
The gamma well counter consists of a scintillation detector with a hole in the center, for a sample to be placed inside for increasing the geometric efficiency and hence the counting efficiency of the counter, and other associated electronics.
Well counters are used namely for in vitro measurements of different samples. They are usually available with automatic sample changers and are mostly programmable with computers.
Their major advantage is high detection efficiency which is from 50% to 70% for 140 keV gamma photons.
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25Nuclear Medicine
RIA 125I
Kidney clearance 51Cr
Vitamin B12 deficiency 57Co,58Co
Ferrokinetic studies 59Fe
Total body water 3H
Blood volume 125I, 51Cr, 99mTc
Biomedical research 3H, 14C
Examples of use of sample counters
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26Nuclear Medicine
HV
Ampl. PHA
Timer
Scaler
Rate-meterGain Base Window
Voltage
Detector Sample
Lead shield PM-tube
Gamma counter
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27Nuclear Medicine
Scintillation detector
Detector
PhotocathodecathoddDynodes
Anode
Amplifier
PHA
ScalerProportionality between thesignal and the energy absor-bed in the detector
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28Nuclear Medicine
Pulse height analyzer
UL
LL
Time
Pulse height (V)
The pulse height analyzer allows only pulses of a certain height(energy) to be counted.
counted not counted
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29Nuclear Medicine
Pulse-height distributionNaI(Tl)
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30Nuclear Medicine
The The TT hyroid hyroid PProberobe
The thyroid probe is a scintillation counter used for measuring radioacitivity above the thyroid gland to assess the uptake of 131I after its oral administration.
In contrast to well counter the thyroid probe must be equipped with collimator, which limits the field of view.
This is a cylindrical barrel made of lead and it covers all the detector including PM tube. It prevents the gamma radiations from other organs to reach the detector.
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31Nuclear Medicine
HV
Ampl. PHA
Timer
Scaler
Rate-meterGain Base Window
Voltage
Recorder
Collimator
PM
D
Probe system
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32Nuclear Medicine
Quality control of any scintillation detector systemshould include tests such as: Energy calibration Energy resolution and energy response Sensitivity Counting precision Background count rate Linearity of activity response
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33Nuclear Medicine
Energy window setting depends on the energy resolution of the detector and the photon energies
Window settingWindow setting
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34Nuclear Medicine
Gamma counterGamma counterDifferent design of the detector
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35Nuclear Medicine
COUNT LOSSES(LINEARITY OF ACTIVITY RESPONSE)
•Decaying source method•Graded source method
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Liquid scintillation Liquid scintillation countercounter
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37Nuclear Medicine
Liquid scintillation Liquid scintillation countercounter In the beta-counter or liquid scintillation counter, the sample is
dissolved in an organic scintillation solution. Due to the resulting 100% counting geometry and the absence of any detector window,this means that the counter has excellent properties in detecting radionuclides of low activity emitting low energy beta-particles, such as H3 and C14.
The light photons from the sample are collected by two photomultipliers in coincidence.
This arrangement will reduce the background due to thermal noise and only true scintillation events will be analysed and counted.
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38Nuclear Medicine
Liquid scintillation Liquid scintillation countercounter The main problem in liquid scintillation counting is the varying
counting efficiency due to quenching of scintillation events. This process is caused by chemical contamination of the sample
and/or a coloured sample. This means that the counting efficiency has to be determined for every sample.
Therefore a quality control of the instrument must include a control of the correction methods. Otherwise the QC methods will be the same as for any scintillation counter.
The sources needed for QC of a liquid scintillation counter include calibrated sources of H3 and C14 with different counting efficiencies as well as a background sample.
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39Nuclear Medicine
PM PM
Coinc
Ampl PHA ScalerTimer
No window100% geometricefficiency
Liquid scintillation counter
Sample mixed with scintillation solution
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40Nuclear Medicine
•Counting efficiency•Quenching•Sample preparation•Window setting•Reproducibility•Background
•Counting efficiency•Quenching•Sample preparation•Window setting•Reproducibility•Background
Operational considerations
Liquid scintillation counter
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Thank you Thank you Pawitra Masa-atPawitra Masa-at 4937092 SIRS/M4937092 SIRS/MMarch 23, 2007March 23, 2007