Radiation Protection in Nuclear Medicine

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IAEA Training Material on Radiation Protection in Nuclear Medicine
Part 2
Radiation Physics
Objective
To become familiar with the basic knowledge in
radiation physics, dosimetric quantities and units to
perform related calculations, different types of
radiation detectors and their characteristics, their
operating principles, and limitations.
Nuclear Medicine
Part 2: Radiation Physics
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Content

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
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Atomic structure
Radioactive decay
Production of radionuclides
Interaction of ionizing radiation with matter
Radiation quantities and units
Radiation detectors
Note: Radiation units & quantities are in the process of
undergoing consensus through ICRU and IAEA. There may
be changes necessitating incorporation in this CD.
Nuclear Medicine
Part 2: Radiation Physics
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IAEA Training Material on Radiation Protection in Nuclear Medicine
Part 2. Radiation Physics
Module 2.1. Atomic structure
THE ATOM

The nucleus structure


protons and neutrons = nucleons
Z protons with a positive electric charge
(1.6 10-19 C)



neutrons with no charge (neutral)
number of nucleons = mass number A
The extranucleus structure

Z electrons (light particles with electric charge)

equal to proton charge but negative
Particle Symbol Mass
Energy Charge
(kg)
(MeV)
---------------------------------------------------------Proton
p 1.672*10-27 938.2
+
Neutron n 1.675*10 -27 939.2
0
Electron e 0.911*10 -30 0.511
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Identification of an Isotope
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Part 2: Radiation Physics
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Ernest Rutherford (1871-1937)
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Electron Binding Energy


Electrons can have only discrete energy levels
To remove an electron from its shell
 E  electron binding energy




Discrete shells around the nucleus : K, L, M, …
K shell has maximum energy (i.e. stability)
Binding energy decreasing when Z increases
Maximum number of electrons in each shell : 2 in K,
8 in L shell, …
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Part 2: Radiation Physics
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Ionization-Excitation
Energy
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De-excitation
Augerelectron
characteristic
radiation
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The Nucleus
Energy Levels
ENERGY
Excitation
Deexcitation
Particle emission
0 MeV
~8 MeV
Gamma ray
Occupied levels
The nucleons can occupy different energy levels and the nucleus can be present in a
ground state or in an excited state. An excited state can be reached by adding energy to
the nucleus. At deexcitation the nucleus will emit the excess of energy by particle
emission or by electromagnetic radiation. In this case the electromagnetic radiation is
called a gamma ray. The energy of the gamma ray will be the difference in energies
between the different energy levels in the nucleus.
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Isomeric Transition
Normally the excited nucleus will undergo de-excitation within
picoseconds. In some cases, however, a mean residence time for
the excited level can be measured. The de-excitation of such a
level is then called isomeric transition (IT). This property of a
nucleus is noted in the label of a nuclide by adding the letter m in
the following way: technetium-99m, Tc-99m or 99mTc
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Nuclear Excitation
Energy
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particles
photons
Part 2: Radiation Physics
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Nuclear De-excitation
alpha-particle
beta-particle
Gamma radiation
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Part 2: Radiation Physics
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Internal Conversion
characteristic
radiation
conversion
electron
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Gamma Ray Spectrum
(characteristic of the nucleus)
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Photons are part of the
electromagnetic spectrum
IR: infrared, UV: ultraviolet
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IAEA Training Material on Radiation Protection in Nuclear Medicine
Part 2. Radiation Physics
Module 2.2. Radioactive decay
Stable Nuclides
long ranged
electrostatic
forces
p
Line of stability
p
n
short ranged
nuclear forces
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Stable and Unstable Nuclides
Too many
neutrons
for stability
Too many
protons
for stability
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Radioactive Decay
Fission
The nucleus is divided into two parts, fission fragments. and
3-4 neutrons. Examples: Cf-252 (spontaneous), U-235 (induced)
a-decay
The nucleus emits an a-particle (He-4). Examples: Ra-226, Rn-222
b-decay
226
86
4
Ra 222
84 Rn+ 2 a
Too many neutrons results in b- -decay. n=>p++e-+n. Example:H-3,
C-14, I-131.
Too many protons results in b+ -decay
p+=>n+ e++n
Examples: O-16, F-18
or electron capture (EC).
p+ + e-=>n+n
Examples: I-125, Tl-201
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Radioactive Decay
It is impossible to know at what time a certain radioactive nucleus
will decay. It is, however possible to determine the probability l
of decay in a certain time. In a sample of N nuclei the number of
decays per unit time is then:
dN
 -N  
dt
N(t) = N 0  e - t
T1/ 2
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ln 2


Part 2: Radiation Physics
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Activity
The number of decaying nuclei per unit of time
1 Bq (becquerel)=1 per second
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1 Bq is a small quantity
3000 Bq in the body from natural
sources
 20 000 000-1000 000 000 Bq in nuclear
medicine examinations

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Multiple & Prefixes (Activity)
Multiple
1
1 000 000
1 000 000 000
1 000 000 000 000
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Prefix
Abbreviation
Bq
Mega (M)
MBq
Giga (G)
GBq
Tera (T)
TBq
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Henri Becquerel 1852-1908
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Maria Curie 1867-1934
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Parent-Daughter Decay
A
λ1
B
A(t) = A 0  e
λ2
C
- 1t
A 0  2 -1 t -2 t
B(t) 
(e - e )
2 - 1
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Parent-Daughter Decay
Secular equilibrium
TB<<TA ≈ ∞
Transient equilibrium
TA ≈ 10 TB
No equilibrium
TA ≈ 1/10 TB
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99Mo-99mTc
87.6%
99Mo
12.4%
ß- 442 keV
 739 keV
T½ = 2.75 d
99mTc
 140 keV
T½ = 6.02 h
99Tc
ß- 292 keV
T½ = 2*105 y
99Ru
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Part 2: Radiation Physics
stable
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Irene Curie (1897-1956)
&
Frederic Joliot (1900-1958)
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IAEA Training Material on Radiation Protection in Nuclear Medicine
Part 2. Radiation Physics
Module 2.4. Interaction of Ionizing
Radiation with Matter
Ionizing Radiation
Charged particles
•
alpha-particles
•
beta-particles
•
protons
Uncharged particles
•
photons (gamma- and X rays)
•
neutrons
Each single particle can cause ionization,
directly or indirectly
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Charged Particles Interaction
with Matter
heavy
light
Macroscopic
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Microscopic
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Transmission
Charged Particles
Alpha particles
Beta particles
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Mean Range of b-particles
Energy (MeV)
10
1
0,1
0,01
0,16
1
5
10
50
100
500
1000 5000
Mean range (m g/cm 2)
Radionuclide Max energy
Range (cm) in
(keV)
air
water
aluminium
------------------------------------------------------------------------------------H-3
18.6
4.6
0.0005
0.00022
C-14
156
22.4
0.029
0.011
P-32
1700
610
0.79
0.29
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Bremsstrahlung
Photon
Electron
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Bremsstrahlung Production
The higher the atomic number of the Xray target, the higher the yield
 The higher the incident electron energy,
the higher the probability of X-ray
production
 At any electron energy, the probability
of generating X-rays decreases with
increasing X-ray energy

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X-ray Production

High energy electrons hit a (metallic)
target where part of their energy is
converted into radiation
electrons
Low to
medium
energy
(10-400keV)
target
High
> 1MeV
energy
X-rays
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X-Ray Tube for low and
medium X-ray production
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Megavoltage X-ray Linac
electrons
target
X-rays
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Issues with X-ray Production
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
Angular distribution: high energy X-rays are
mainly forward directed, while low energy Xrays are primarily emitted perpendicular to
the incident electron beam
Efficiency of production: In general, the
higher the energy, the more efficient is X-ray
production - this means that at low energies
most of the energy of the electron (>98%) is
converted into heat - target cooling is
essential
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The Resulting X-Ray Spectrum
INTENSITY
Unfiltered radiation (in vacuum)
Characteristic
X-rays
Bremsstrahlung
Spectrum after
filtration
20
40
60
80
100
120
PHOTON ENERGY (keV)
Maximum electron energy
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Photons Interaction with Matter
absorption
scattering
transmission
energy deposition
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Photoelectric Effect
photon
electron
characteristic
radiation
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Compton Process
scattered
photon
photon
electron
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Pair Production
positron
photon
electron
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Annihilation
(511 keV)
b+ + eb+
(511 keV)
(1-3 mm)
Radionuclide
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Photon Interaction
Atomic number (Z)
100
90
80
70
60
Pair
production
Photoelectric
effect
50
40
Compton
process
30
20
10
0
0,01
0,1
1
10
100
Photon energy (MeV)
Photon energy (MeV)
The dominating photon absorption process in different materials of different atomic numbers
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Transmission-Photons
N  N0  e
-  d
d: absorber thickness
:attenuation coefficient
HVL: half value layer
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TVL: tenth value layer
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HVL
Thickness of an absorber necessary to reduce the transmission of radiation to 50 percent
(HVL).
Radiation quality
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HVL (mm)
Concrete
Lead
50 kV
4.3
0.06
100 kV
10.6
0.27
200 kV
25
0.52
500 kV
36
3.6
1 MV
44
7.9
2 MV
64
12.5
5 MV
96
16.5
10 MV
119
16.6
20 MV
137
16.3
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IAEA Training Material on Radiation Protection in Nuclear Medicine
Part 2. Radiation Physics
Module 2.5. Radiation Quantities and
Units
Energy Absorption
High absorbed energy per unit mass
Many ionizations per unit mass
Increased risk of biological damage
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Absorbed Dose
Absorbed energy per mass unit
1 Gy (gray)=1 J/kg
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Harold Gray 1905-1965
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1 Gy is a relatively large Quantity
Radiotherapy doses > 1Gy
 Dose from nuclear medicine
examination typically 0.05-0.001Gy
 Annual background radiation due to
natural radiation (terrestic, cosmic, due
to internal radioactivity, Radon,…) about
0.002-0.004 Gy

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Fractions & Prefixes (Dose)
Fraction
Prefix
1
1/1000
1/1,000,000
milli (m)
micro ()
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Part 2: Radiation Physics
Abbreviation
Sv
mSv
Sv
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A note of caution:
Energy deposition in
matter is a random
event and the
definition of dose
breaks down for
small volumes (e.g.
a single cell). The
discipline of Microdosimetry aims to
address this issue.
Adapted from Zaider 2000
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Equivalent Dose/
Effective Dose
He = wr * D
D: absorbed dose (Gy), wr : radiation weighting factor (1-20)
Heff=wT*He
He: equivalent dose (Sv), wT: tissue weighting factor (0.05-0.20)
Unit: 1 Sv (sievert)
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Effective Dose
E  w H
T
T
T
Tissue or organ
Weighting factor
Gonads
0.20
Bone marrow (red)
0.12
Colon
0.12
Lung
0.12
Stomach
0.12
Bladder
0.05
Breast
0.05
Liver
0.05
Oesophagus
0.05
Thyroid
0.01
Bone surface
0.01
Remainder (adrenals, kidney, muscle, 0.05
upper large intestine, small intestine,
pancreas, spleen, thymus, uterus, brain)
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Diagnostic Effective Dose (mSv)
X-ray
cardioangiography
CT pelvis
large intestine
CT abdomen
urography
lumbar spine
chest
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10
1
0.1
thyroid
myocard
I-131
Tl-201
CBF
thyroid
bone
thyroid
liver
lung
renography
Tc-99m
I-123
Tc-99m
Tc-99m
Tc-99m
Tc-99m
I-131
blood volume
clearance
I-125
Cr-51
extremities
dental
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0.01
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Rolf Sievert (1896-1966)
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Collective Dose
The total equivalent dose or effective dose to a certain
population, such as all patients in a nuclear medicine
department, all staff in the department, the whole
population in a country etc.
The unit is 1 manSv
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Collective effective doses in Sweden
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IAEA Training Material on Radiation Protection in Nuclear Medicine
Part 2. Radiation Physics
Module 2.6. Radiation Detectors
The detector is a fundamental base
in all practice with ionizing radiation
Knowledge of instrumentation
potential as well as their limitation
is essential for proper interpretation
of the measurements
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Detector Material
Any material that exhibits measurable radiation related
changes can be used as detector for ionising radiation.
•Change of colours
•Chemical changes
•Emission of visible light
•Electric charge
•…..
•…..
Active detectors: immediate measurement of the change.
Passive detectors: processing before reading
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Detector Principles

Gas filled detectors





Other detectors
ionisation chambers
proportional counters
Geiger Müller (GM) tubes



Semi conductor detectors
Film
Thermoluminescence
detectors (TLD)
Scintillation detectors


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solid
liquid
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Detector Types
1) Counters
Gas filled detectors
Scintillation detectors
2) Spectrometers
Scintillation detectors
Solid state detectors
3) Dosimeters
Gas filled detectors
Solid state detectors
Scintillation detectors
Thermoluminescent detectors
Films
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Gas-filled Detectors
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Ionization Chamber
Electrometer
+
1234
HV
Negative ion
The response is proportional to
ionization rate (activity, exposure rate)
Positive ion
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Ionization Chambers
Applications in Nuclear Medicine
• Activity Meter
• Monitoring Instruments/
Survey Meters
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General Properties of
Ionization Chambers
• High accuracy
• Stable
• Relatively low
sensitivity
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Regions of Operation for Gasfilled Detectors
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Proportional Counter
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Proportional Counters
Applications in Nuclear Medicine
• Monitoring Instruments
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Properties of Proportional
Counters as Monitor
• A little higher sensitivity than the
ionization chamber
• Used for particles and low energy
photons
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Geiger Müller-Tube Principle
-
+
-
A single incident particle cause full ionization
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Geiger Müller - Tube
Applications in Nuclear Medicine
• Contamination Monitor
• Dosemeter (if calibrated)
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General Properties of
Geiger Müller - Tubes
• High Sensitivity
• Lower Accuracy
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Scintillation Detectors
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Scintillation Detector
Detector
Amplifier
Photocathode
cathodd
Dynodes
PHA
Anode
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Scaler
82
Pulse Height Analyzer
Pulse height (V)
UL
LL
Time
The pulse height analyzer allows only pulses of a certain height
(energy) to be counted.
counted
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not counted
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Pulse-Height Distribution
NaI(Tl)
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Liquid Scintillation Detector
Sample mixed
with scintillation
solution
PM
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PM
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Scintillation Detectors
Applications in Nuclear Medicine
• Sample counters
• Single- and multi-probe systems
• Monitoring instruments
• Gamma camera
• PET Scanners
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Other Detectors
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Semi-conductor Detector as
Spectrometer
Solid Germanium or Ge(Li) detectors
 Principle: electron - hole pairs
(analogous to ion-pairs in gas-filled
detectors)
 Excellent energy resolution

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Comparison of spectrum
from a Na(I) scintillation
detector and a Ge(Li)
semi-conductor detector
Knoll
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Semi-conductor Detectors
Applications in Nuclear Medicine
• Identification of nuclides
• Control of radionuclide purity
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Film
Principle: As normal photographic film
Silver halide grains, via changes due to
irradiation and development to metallic
silver
Application in Nuclear Medicine: Personal
dosemeter
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Film
Requires processing ---> problems with
reproducibility
 Two dimensional dosimeter
 High spatial resolution
 High atomic number ---> variations of
response with radiation quality

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Thermoluminescence
TLD principle
thermoluminescent
photomultiplier
material
heating filament
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emitted light
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Simplified Scheme of the TLD
Process
1
ionising radiation
2
visible light
electron
trap
HEATING
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Thermoluminescence
Dosimetry (TLD)
Small crystals
 Tissue equivalent
 Passive dosimeter - no cables required
 Wide dosimetric range (Gy to 100s of
Gy)
 Many different applications

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Thermoluminescence
Dosimetry (TLD)
Applications in Nuclear medicine
• Personal Dosemeters (body, fingers…)
• Special Measurements
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Thermoluminescence
Dosimetry (TLD)
Disadvantages:
• Time consuming
• No permanent record
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Questions?
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Discussion
A Mo/Tc generator contains 15 GBq
Mo-99 at a certain time. What activity
concentration of Tc-99m will we get 15h
later if the elution volume is 3 ml?
Assume an elution efficiency of 75%.
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Discussion
A treatment is performed using iodine131. Which are the dominating modes
of interaction between the emitted types
of radiation and human soft tissue?
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Discussion
A laboratory is performing work with H-3.
Discuss the type of detector suitable to
detect contamination of equipment and
work areas.
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Where to Get More Information

Further readings:


Nuclear Medicine
WHO Manual on Radiation Protection in Hospital
and General Practice. Volume 1 Basic
Requirements
Cherry SR, Sorensen JA & Phelps ME. Physics in
Nuclear Medicine. 2003
Part 2: Radiation Physics
102
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