Quality and Safety in Nuclear Medicine



Quality and Safety in Nuclear Medicine


Saima Muzahir





QUALITY CONTROL IN NUCLEAR MEDICINE

Quality control (QC) is important to ensure the dependable performance of equipment used in nuclear medicine. QC requires performing a routine series of tests on each device used in nuclear medicine. Routine QC testing starts after installation of the instrument, after acceptance testing, and continues on a regular basis throughout its lifetime.

The most common devices used in nuclear medicine include imaging and nonimaging devices. Nonimaging devices include dose calibrator, survey meters, and scintillation detectors. Imaging devices include planar gamma camera, single photon emission computed tomography (SPECT), and PET-CT.


NONIMAGING DEVICES


Dose Calibrator

Dose calibrator is an essential piece of instrument in any nuclear medicine department. It is a well-type ionization chamber capable of measuring quantities in the millicurie (mCi). Dose calibrators are checked for accuracy, constancy, linearity, and geometry (Fig. 9.1).


Accuracy

Accuracy should be checked at installation, annually, and after repair or when the instrument is moved to a new location within the clinic. Accuracy is a measure of the readings of the dose calibrator in comparison with the well-accepted standards. Long-lived radionuclides such as 57Co (half-life 270 days) and 137Cs (half-life 30 years) are measured repeatedly in the dose calibrator, and average readings are compared with the values issued by National institute of Standards and Technology (NIST). If the reading differs by more than 10% of standards, the instrument should not be used.1


Constancy

Constancy should be checked daily. For the constancy test, a reference source such as (57Co, 133Ba, 68Ge, or 137Cs) is placed in the dose calibrator, and the activity reading on each scale is recorded; day-to-day readings should agree within 10%. The readings at each predefined setting for different radionuclides used in the nuclear medicine department (99mTc, 131I, 123I, 111In, etc.) are recorded and compared with previous readings.






FIG. 9.1Dose calibrator. It is a gas-filled ionization chamber used to measure radioactivity. The sample to be measured is placed in the shielded ionization chamber.



Linearity

Linearity should be checked at the installation of the device, quarterly, when the instrument is moved from one place to another, and after repairs. For the quarterly check of linearity by the decay method, a high activity (˜37 GBq) of Tc-99m is independently calibrated and then the measurements are repeated at 12-hour intervals over three consecutive days. Over that time, which is equivalent to 12 half-lives of 99mTc, the activity decays to about 11 MBq. The measured activities are then plotted versus time on a semilogarithmic graph, and the best-fit straight line drawn through the data points is plotted. For each data point, the difference between the measured activity and the activity on the best-fit straight line at that point should be less than 10%. To save time, a more rapid technique known as the shield method is used. In this technique, lead sleeves of increasing thickness are placed in the dose calibrator with a 99mTc source (Fig. 9.2). The thickness of sleeves is such that when used both individually and in combination they effectively reproduce the decline in the activity of Tc-99m over 96 hours.


Geometry

The effect of sample geometry should be checked at installation and after repairs. The apparent activity of a dose will vary with the volume and shape of the container, as well as the position of the dose placed within the chamber of a dose calibrator. Dose measurements should not vary by more than 10% when the sample is measured in different types of containers such as vials, syringes, or bottles. The sample geometry can also be checked by placing a small amount of activity at the bottom of the container and then progressively adding a diluent such as water.


Survey Meters

Survey meters are an important component of any nuclear medicine department. They are portable, battery-operated, gas-filled ionization chambers or solid-state scintillation detectors used to measure exposure rates (e.g., in mR/h) or counting rates (e.g., in counts per minute [CPM]). The most familiar ones are Geiger counter and pocket dosimeters. Geiger counters are of high sensitivity and are well suited for low-level surveys, for example, for checking radioactive contamination (Fig. 9.3A, B). Cutie-pies are another type of survey meter that have relatively low-sensitivity ionization chambers and are designed for use where high fluxes of X- and γ-rays are encountered. Generally, cutie-pies are calibrated in exposure rates (mR/h) and Geiger counters in counting rates (cpm). QC of survey meters include a battery check, background check, constancy, and calibration.1,2






FIG. 9.2Lead sleeves. A set of lead-lined plastic sleeves for evaluation of dose-calibrator linearity by shield method.






FIG. 9.3Geiger-Mueller survey meter. A: This is used to measure low levels of radiation. A pancake detector is located at the end of the detector. A calibration sticker is attached. B: The dial reads in either counts per minute (CPM) or milliroentgens per hour (mR/hr).


Battery Check

The battery should be checked daily, with a display indicating whether the voltage supplied by the battery is within the acceptable operating range.


Background Check

Background check should be performed daily to ensure that the survey meter has not been contaminated, and the background exposure or counting rate is performed daily in an area well away from the radioactive sources within the department.



Constancy

A long-live radionuclide should be checked daily to ensure that the survey meter reading of the source remains constant, that is, within 10% of its original value. The survey meter should be recalibrated if the reading differs by more than 10% of original value.


Calibration

Calibration should be performed at installation, after repairs, and annually. All survey meters should be checked for accuracy using long-lived radionuclides. The readings are taken from two long-lived radionuclide sources at incremental distances from the sources (such as every 10th of a meter up to 1 m). The readings must be within 20% of their expected measurement. Many nuclear medicine facilities have their survey meters calibrated by the institutional radiation safety office or by a commercial calibration laboratory. The measurement procedure, the measured and expected exposure rates, and a dated sticker summarizing the calibration results are affixed to the meter itself.


Scintillation Detectors

Scintillation detectors include well counters and organ uptake probes. Well counters are of high sensitivity and are used for counting of radioactive specimens such as blood or urine samples or wipe tests for survey of removable contamination (Fig. 9.4). Counting results are expressed in activity (e.g., µCi), using the appropriate isotope-specific calibration factor (µCi/cpm). Routine QC includes energy peaking and background check, constancy, energy resolution, calibration, and efficiency.3


Energy Peaking and Background Check

Routine checks of the photopeak energy window (i.e., energy peaking) are performed if the counter is equipped with a multichannel analyzer (MCA) and a background check. Before counting samples containing a particular radionuclide, the energy spectrum is checked to verify that the counter is properly peaked so that the photopeak of the radionuclide coincides with the preset photopeak energy window. Isotope-specific radionuclide counting or imaging with a scintillation detector is commonly done using a 20% photopeak energy window, equivalent to an energy range of Eγ ± 10% (i.e., 0.9 to 1.1 Eγ), where Eγ is the X- or γ-ray energy of the radionuclide. This is performed daily.






FIG. 9.4Well counter. Well counters are high-sensitivity heavily shielded scintillation crystals used for counting of radioactive specimens such as blood or urine samples or wipe tests for survey of removable contamination.


Energy Resolution

Energy resolution (percentage full width at half-maximum) should be checked at least quarterly using a reference-source radionuclide such as 57Co. Energy resolution is the ability of a counter to discriminate between light pulses caused by gamma rays of different energies. The full width half-maximum (FWHM) of the photopeak should be less than 10% of the energy of the photopeak.


Calibration

Calibration is performed on a daily basis using a long-lived radionuclide source (such as 137Cs), which is placed in the well counter or in front of the probe.


Efficiency

Efficiency check is performed annually. Efficiency check is performed using reference standard sources with emission sources with similar energy emissions to the radionuclides measured routinely in the counter or in front of the thyroid/organ probe. The efficiency of the thyroid probe or well counter can be calculated using the following equation:


Efficiency= [(counts per minute of standard) – (counts per minute of background)] × [(activity of standard in microcurie)]-1.


Intraoperative Probes

Intraoperative probes are solid or semisolid state detectors. They are highly collimated handheld devices that are commonly used in surgical practice for sentinel node localization in different types of cancer (e.g., breast cancer, melanoma, etc.). The different QC tests include daily battery check, bias check, and background check. A daily bias check should be performed for both the primary and
any back-up battery to verify that bias voltage is within acceptable limits. Other tests include daily counting rate constancy using long-lived reference sources such as 157Co and 133Ba. A change of ±10% in the net counting rate from one day to the next indicates an inappropriate window setting.3






FIG. 9.5Organ uptake probe system. This includes a single crystal, thyroid/organ probe for measuring radionuclide uptake.








Table 9.1 SUMMARY OF QC TESTS FOR NONIMAGING DETECTORS.







































































Nonimaging Detectors


Quality Control Parameter


Frequency


Dose calibrator


Battery check


Daily



Constancy


Daily



Linearity


At installation, quarterly, and after repairs



Accuracy


At installation, annually, and after repairs



Geometry


At installation and after repairs


Survey meter


Battery check


Daily



Background check


Daily



Constancy


Daily



Calibration


Annually and after repairs


Well counter


Energy peaking and background check


Daily



Energy resolution


Quarterly



Calibration


Daily



Efficiency


Annually


Organ uptake probe


Battery check


Before each use



Background check


Before each use



Constancy


Before each use



Organ Uptake Probes

Organ uptake probes have been commonly used to measure thyroid uptake and are commonly known as thyroid uptake probes (Fig. 9.5). Most of the QC tests for uptake probes are similar to well counter, and these include checks of the photopeak energy window, background, constancy, and efficiency. Efficiency of uptake probe should be checked more frequently so that net counting rate can be reliably converted to thyroid uptake for each individual patient. Table 9.1 summarizes the commonly performed QC procedures for nonimaging detectors.

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Oct 14, 2018 | Posted by in GENERAL RADIOLOGY | Comments Off on Quality and Safety in Nuclear Medicine
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