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Positron Emission
Tomography,
an insight (part 1)
By Etienne Grech
1: Introduction
Positron emission tomography (PET) may be defined as ‘‘a
computerised radiographic technique that uses radioactive substances to examine
the metabolic activity of various body structures. The patient either inhales or
is injected with a metabolically important substance such as glucose, carrying a
radioactive element that emits positively charged particles, or positrons. When
the positrons combine with electrons normally found in the cells of the body,
gamma rays are emitted. The electronic circuitry and computers of the PET
scanner detect the gamma rays and construct colour-coded images that indicate
the intensity of the metabolic activity throughout the organ involved’’
(Anderson 2002)
2: Historical
overview
The concepts behind PET have been around since the 1950’s,
however the first PET scanner was developed in 1970. Until recently, its
clinical applications were limited due to the lack of advanced hardware and
software. Also the cyclotrons, which are used to produce the radionuclides, were
quite bulky. Although very expensive, PET scanners have found their way out of
research labs and are being used by large healthcare institutions.
3: Principles
of PET
The positron is a positively charged beta particle that is
emitted from neutron poor radionuclides. As this particle is emitted, it travels
several millimetres in tissue depositing its kinetic energy. During this
process, the positron interacts with a free electron in tissue and a mutual
annihilation occurs. The unique aspect of this conversion is that the resultant
conversion is not one gamma ray of 1.02MeV, but two gamma rays each equal to
exactly one half that energy i.e. 150 keV. Furthermore, these rays are emitted
at 180 degrees to each other. The patient is surrounded with a ring of detectors
and electronically coupled opposing detectors to simultaneously identify the
pair of photons.
4: The PET
camera
The camera used in PET looks like no ordinary nuclear
medicine camera. It physically resembles a CT scanner. The camera uses rings of
detectors that are either arranged in a circle around the patient, or in a
hexagonal array where the detectors are grouped into cassettes. The content of
each cassette varies according to the manufacturer, but usually these consist of
256 crystals being viewed by 16 photomultiplier tubes (four blocks composed of
64 crystals and four photomultiplier tubes) with as many as three rings of 16
buckets in a circle (12,288 crystals with 768 photomultiplier tubes). An
alternative design to the bucket, is one that uses rings of detectors with 11
crystals in a staggered array being exposed to 6 photomultiplier tubes.
4.1 PET detectors
As in the common gamma camera, PET detectors are composed of
crystals and photomultiplier tubes. However positron detectors are usually made
of denser material than that used for lower energy single photon detectors. Such
materials include bismuth germanate, barium fluoride, sodium iodide and caesium
fluoride with bismuth germanate and barium fluoride being used mostly. A common
characteristic of these crystals is their ability to emit light when interacting
with photons. The light is then directed towards photomultiplier tubes where it
is converted to an electrical signal. Unlike other nuclear medicine equipment
where one crystal is viewed by one or more photomultiplier tubes, PET detectors
are composed of multiple crystals being exposed by one photomultiplier tube.
Crystal selection depends upon whether the equipment is to be used in situations
requiring a high-count rate or in situations where a high signal to noise ratio
(or high image quality) is required. Such a decision should be based upon four
basic crystal characteristics. As bismuth germanate and barium fluoride are most
commonly used their characteristics will be discussed.
4.1.1 Detector sensitivity
In theory, all PET camera should keep untrue interactions as
low as possible so as to be able to process more true interactions. This is a
function of detector sensitivity. Sensitivity varies with multiple coincidence
detection capability, density discrimination threshold level and detector size.
If the density discrimination threshold level is considered to be the same in
both detectors, bismuth germanate has an excellent coincidence detection
capability (41%) when compared to that of barium fluoride (4%). Such data shows
that bismuth germanate has a higher sensitivity when compared to barium fluoride
or other detector material.
4.1.2
Random count rate
Random events may be described as photon pairs that reach the
detectors at the same time by sheer chance. These may be annihilation photons
from two unassociated annihilation events or they may be completely unrelated to
the pair of annihilation gamma rays therefore being considered undesirable as
spatial resolution is worsened. The higher the threshold discrimination and the
narrower the coincidence time window, the fewer random events are detected. Due
to its scintillation pulse profile, barium fluoride has excellent
characteristic, which reduce the random count rate.
4.1.3 Scatter count rate
If a 511 keV energy spectrum had to be inspected with bismuth
germanate and barium fluoride, one would notice that there are more scattered
photons due to Compton interaction in barium fluoride than with bismuth
germanate. This suggests that the time that is spent rejecting scattered photons
would result in rejecting true coincidence counts because of the dead time
considerations. With bismuth germanate, there is a lower number of scattered
photons to reject and therefore there is more time to accept true coincidence
counts.
4.1.4 Light yield
Another important feature in the consideration of the
appropriate crystal for the detection of positrons is the amount of light
produced per photon interaction. The crystal material with the best light yield
is sodium iodide and it had been used in PET for quite sometime for this reason.
However, its hydroscopicity and decay times might contraindicate its use.
4.1.5 Scintillation decay time
Scintillation output is usually seen as a rapid rise in the
output of light followed by a slower release (decay time). As shown in table 1
bismuth germanate has a very high decay time (300 nsec) when compared to that of
barium fluoride (0.8 nsec). This difference in decay time is the main reason why
barium fluoride is preferred to bismuth germanate in high-count rate studies.
|
|
Density g/cm |
Decay time (nsec) |
Light yield
|
Hydroscopic |
|
|
Bismuth germanate |
7.13 |
300 |
12 |
No |
|
Barium fluoride |
4.89 |
0.8 |
5 |
No |
|
Caesium fluoride |
4.64 |
3 |
8 |
No |
|
Sodium iodide |
3.67 |
100 |
100 |
yes |
Table 1 showing the properties of various PET detectors
4.2: PET vs. SPECT
PET has shown to have various advantages over SPECT (single
photon emission computed tomography). Both the sensitivity and spatial
resolution of PET are superior to that of SPECT. Furthermore, PET offers the
flexibility of labelling biochemical molecules. However PET scanners and
cyclotrons are very expensive and when compared to a normal gamma camera and
generator, they are considerably large.
5:
Radionuclides used in PET
5.1 Production of radionuclides
Production of positron radionuclides requires a cyclotron.
This is a device, which accelerates charged particles in a spiral fashion to
high energies by means of an alternating electric field placed between
electrodes in a magnetic field.
5.2 Radionuclides
The analysis of metabolic function is essential for diagnosis
and therapy. This can be achieved with PET, as the short-lived radionuclides
used are attached to substrates so that a biochemical process can be
investigated.
Amongst the isotopes of organic elements, only a few
radionuclides exist which have suitable properties for in-vivo use. These
include oxygen 15 (half-life =2 min.), nitrogen 13 (half-life = 10 min.) and
carbon 11 (half-life = 20 min).
If metabolic substrates are to be labelled indirectly, other
radionuclides are used. These include: Bromine 75 and 76, Iodine 124 or Rubidium
82, Gallium 68 and Copper 62. One should note that the choice of nuclide depends
upon the problem being investigated.
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