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Side Effects & Adverse Reactions
Xenon Xe 133 Gas delivery systems, i.e., respirators or spirometers, and associated tubing assemblies must be leakproof to avoid loss of radioactivity into the environs not specifically protected by exhaust systems.
Xenon Xe 133 adheres to some plastics and rubber and should not be allowed to stand in tubing or respirator containers. The unrecognized loss of radioactivity from the dose for administration may render the study non-diagnostic.
The vial stopper contains dry natural rubber latex and may cause allergic reactions in providers or patients who are sensitive to latex.
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Uses
Inhalation of Xenon Xe 133 Gas has proved valuable for the evaluation of pulmonary function and for imaging the lungs. It may also be applied to assessment of cerebral flow.
History
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Other Information
XENON Xe 133 Gas is supplied in a mixture of xenon gas (5%) in carbon dioxide (95%). It is contained within septum sealed glass vials and is suitable for inhalation in the diagnostic evaluation of pulmonary function and imaging, as well as assessment of cerebral blood flow. Xenon Xe 133 Gas is reactor-produced as a by-product of Uranium U235 fission. Each vial contains the labeled amount of Xenon Xe 133 radioactivity at the time of calibration. The contents of the vial are in gaseous form, contain no preservatives, and are ready for use.
Xenon Xe 133 is chemically and physiologically related to elemental Xenon, a non-radioactive monoatomic gas which is physiologically inert except for anesthetic properties at high doses.
Xenon Xe 133 decays by beta and gamma emissions with a half-life of 5.245 days.1 Significant radiations which are emitted by the nuclide are listed in Table 1.
Mean | Mean % per | |
---|---|---|
Radiation | Energy (KeV) | Disintegration |
Beta-2 | 100.6 | 99.3 |
Ce-K-2 | 45.0 | 53.3 |
Ce-L-2 | 75.3 | 8.1 |
Ce-M-2 | 79.8 | 1.7 |
Gamma-2 | 81.0 | 36.5 |
Kα2X-ray | 30.6 | 13.6 |
Kα1X-ray | 31.0 | 25.3 |
KβX-ray | 35.0 | 9.1 |
- 1
- Kocher, David C., "Radioactive Decay Data Tables," DOE/TIC-11026, p. 138,1981.
The specific gamma ray constant for Xenon Xe 133 is 3.6 microcoulombs/Kg-MBq-hr (0.51R/hr-mCi) at 1 cm. The first half value thickness of lead is 0.0035 cm. A range of values for the relative attenuation of the radiation emitted by this radionuclide that results from the interposition of various thicknesses of Pb is shown in Table 2. For example, the use of 0.20 cm of Pb will decrease the external radiation exposure by a factor of 1,000.
cm of Pb | Radiation Attenuation Factor |
---|---|
0.0035 | 0.5 |
0.037 | 10-1 |
0.12 | 10-2 |
0.20 | 10-3 |
0.29 | 10-4 |
To correct for physical decay of this radionuclide, the fractions that remain at selected time intervals after the time of calibration are shown in Table 3.
Fraction | Fraction | ||
---|---|---|---|
Day | Remaining | Day | Remaining |
|
|||
0* | 1.000 | 8 | .349 |
1 | .877 | 9 | .302 |
2 | .768 | 10 | .268 |
3 | .674 | 11 | .235 |
4 | .591 | 12 | .206 |
5 | .518 | 13 | .181 |
6 | .452 | 14 | .157 |
7 | .398 |
Sources
Xenon Manufacturers
-
Lantheus Medical Imaging, Inc.
Xenon | Lantheus Medical Imaging, Inc.
Xenon Xe 133 gas is administered by inhalation from closed respirator systems or spirometers.
The suggested activity range employed for inhalation by the average adult patient (70 kg) is:
Pulmonary function including imaging: 74-1110MBq (2-30mCi) in 3 liters of air.
Cerebral blood flow: 370-1110MBq (10-30mCi) in 3 liters of air.
The patient dose should be measured by a suitable radioactivity calibration system immediately prior to administration.
RADIATION DOSIMETRYThe estimated absorbed radiation doses2 to an average patient (70 kg) for pulmonary perfusion and cerebral blood flow studies from a maximum dose of 1110 MBq (30mCi) of Xenon Xe 133 in 3 liters of air are shown in Table 4.
Table 4. Radiation Doses Effective Whole Half-Time Lungs* Brain Body * 99% of activity is in lungs. mGy/1110MBq (rads/30mCi) Pulmonary
Perfusion
2 min.
2.5(0.25)
0.014(0.0014)
0.027(0.0027) Cerebral
Flow
5 min.
6.3(0.63)
0.035(0.0035)
0.068(0.0068) 2 Method of Calculation: A Schema for Absorbed-Dose Calculation for Biologically Distributed Radionuclides, Supplement No. 1, MIRD pamphlet No. 1, J. Nucl. Med., p.7 (1968).
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