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Файл:Ординатура / Хирургия / Библиотека им академика М.И. Перельмана / Книга_5545_Библиотеки_им_академика_М_И_Перельмана.pdf
X
- •Preface
- •Contents
- •1: Structure of Matter
- •2: Radioactive Decay
- •2.1 Spontaneous Fission
- •1.1.1 Radiation
- •1.2 The Atom
- •1.2.3 Nuclear Binding Energy
- •1.3 Nuclear Nomenclature
- •1.5 Questions
- •Suggested Readings
- •2.2 Isomeric Transition
- •2.2.1 Gamma (γ)-Ray Emission
- •2.2.2 Internal Conversion
- •2.2.2.1 Problem 2.1
- •2.2.2.2 Answer
- •2.3 Alpha (α)-Decay
- •2.4 Beta (β−)-Decay
- •2.5 Positron (β+)-Decay
- •2.6 Electron Capture
- •2.7 Questions
- •Suggested Readings
- •3.1 Radioactive Decay Equation
- •3.1.1 General Equation
- •3.1.2 Half-Life
- •3.1.3 Mean Life
- •3.1.4 Effective Half-Life
- •3.2 Units of Radioactivity
- •3.3 Specific Activity
- •3.4 Calculation
- •3.5 Successive Decay Equations
- •3.5.1 General Equation
- •3.5.2 Transient Equilibrium
- •3.5.3 Secular Equilibrium
- •3.6 Questions
- •Suggested Readings
- •4.5 Poisson Distribution
- •4.6 Gaussian Distribution
- •4.7 Chi-Square Test
- •4.8 Minimum Detectable Activity
- •4.10 Questions
- •Suggested Readings
- •5.1 Cyclotron-Produced Radionuclides
- •5.2 Reactor-Produced Radionuclides
- •5.2.1 Fission or (n, f) Reaction
- •5.2.2 Neutron Capture or (n, γ) Reaction
- •5.6 Radionuclide Generators
- •5.8 Questions
- •Suggested Readings
- •6.1.1 Specific Ionization
- •6.1.2 Linear Energy Transfer
- •6.1.3 Range
- •6.1.4 Bremsstrahlung
- •6.1.5 Positron Annihilation
- •6.2.1.1 Photoelectric Effect
- •6.2.1.2 Compton Scattering
- •6.2.1.3 Pair Production
- •6.2.1.4 Raleigh Scattering
- •6.2.1.5 Photodisintegration
- •6.3.2 Half-Value Layer
- •6.5 Questions
- •Suggested Readings
- •7: Gas-Filled Detector
- •7.1 Principles of Gas-Filled Detector
- •7.2 Ionization Chamber
- •7.2.1 Ion Chamber Survey Meter
- •7.2.2 Dose Calibrator
- •7.2.2.1 Constancy
- •7.2.2.2 Accuracy
- •7.2.2.3 Linearity
- •7.2.2.4 Geometry
- •7.2.3 Pocket Dosimeter
- •7.3 Proportional Counter
- •7.4 Geiger–Müller Counter
- •7.5 Questions
- •Suggested Readings
- •8.1 Scintillation Counter
- •8.4.3 Characteristic X-Ray Peak
- •8.4.4 Backscatter Peak
- •8.4.5 Iodine Escape Peak
- •8.2 Solid Scintillation Detector
- •8.2.1 NaI (Tl) Detector
- •8.2.2 Bismuth Germanate Detector
- •8.2.3 Barium Fluoride Detector
- •8.2.4 Lutetium Oxyorthosilicate Detector
- •8.2.5 Gadolinium Oxyorthosilicate Detector
- •8.2.6 Yttrium Oxyorthosilicate Detector
- •8.2.7 Yttrium Aluminum Perovskite Detector
- •8.2.8 Lutetium Yttrium Oxyorthosilicate Detector
- •8.2.9 Lanthanum Bromide Detector
- •8.3 Solid-State Detector
- •8.3.2 Cadmium–Zinc–Tellurium Detector
- •8.3.3 Cesium Iodide (CsI(Tl)) Detector
- •8.3.4 Solid Scintillation Counter
- •8.3.4.1 NaI(Tl) Detector
- •8.3.4.2 Photomultiplier Tube
- •8.3.4.3 Preamplifier
- •8.3.4.4 Linear Amplifier
- •8.3.4.5 Pulse-Height Analyzer
- •8.3.4.6 Display or Storage
- •8.4 Gamma-Ray Spectrometry
- •8.4.1 Photopeak
- •8.4.6 Positron Annihilation Peak
- •8.4.7 Coincidence Peak
- •8.5 Liquid Scintillation Counter
- •8.5.1 Quenching
- •8.6.1 Energy Resolution
- •8.6.2 Detection Efficiency
- •8.6.2.1 Intrinsic Efficiency
- •8.6.2.2 Photopeak Efficiency or Photofraction
- •8.6.2.3 Geometric Efficiency
- •8.6.3 Dead Time
- •8.7 Gamma Well Counter
- •8.8 Thyroid Probe
- •8.8.1 Thyroid Uptake Measurement
- •8.9 Questions
- •Suggested Readings
- •9: Gamma Camera
- •9.1 Gamma Camera
- •9.1.2 Detector
- •9.1.3 Collimator
- •9.1.4 Photomultiplier Tube
- •9.1.5 X-, Y-Positioning Circuit
- •9.1.6 Pulse-Height Analyzer
- •9.2 Digital Camera
- •9.2.1 Solid State Digital Camera
- •9.3 Questions
- •Suggested Readings
- •10.1.1 Spatial Resolution
- •10.1.1.1 Intrinsic Resolution
- •10.1.1.2 Collimator Resolution
- •10.1.1.3 Scatter Resolution
- •10.1.2.1 Bar Phantom
- •10.1.2.2 Line-Spread Function
- •10.1.2.3 Modulation Transfer Function
- •10.1.3 Sensitivity
- •10.1.3.1 Collimator Efficiency
- •10.1.4 Uniformity
- •10.1.5 Pulse-Height Variation
- •10.1.6 Nonlinearity
- •10.1.7 Edge Packing
- •10.2 Gamma Camera Tuning
- •10.4 Contrast
- •10.4.1 Count Density
- •10.4.2 Image Noise
- •10.4.4 High Count Rate
- •10.4.6 Patient Motion
- •10.5.1 Daily Checks
- •10.5.1.2 Uniformity
- •10.5.2 Weekly Checks
- •10.5.3 Monthly Checks
- •10.5.3.1 High-Count Uniformity Calibration
- •10.5.3.2 Collimator Integrity
- •10.5.4 Annual, Semiannual, or As-Needed Checks
- •10.6 Questions
- •References and Suggested Readings
- •11.1.1 Central Processing Unit
- •11.1.2 Computer Memory
- •11.1.3 External Storage Device
- •11.1.4 Input/Output Device
- •11.1.7 Digital-to-Analog Conversion
- •11.1.8 Digital Image
- •11.2.1 Digital Data Acquisition
- •11.2.2 Static Study
- •11.2.3 Dynamic Study
- •11.2.4 Gated Study
- •11.2.7 Display
- •11.3.1 PACS
- •11.4 Questions
- •Suggested Readings
- •12: Single Photon Emission Computed Tomography
- •12.1 Tomographic Imaging
- •12.2 Single Photon Emission Computed Tomography
- •12.2.1 Data Acquisition
- •12.2.2 Image Reconstruction
- •12.2.2.1 Simple Backprojection
- •12.2.2.2 Filtered Backprojection
- •12.2.2.3 The Convolution Method
- •12.2.2.4 The Fourier Method
- •12.2.2.6 Iterative Reconstruction
- •12.3 SPECT/CT Scanner
- •12.4 Factors Affecting SPECT
- •12.4.1 Photon Attenuation
- •12.4.2 Attenuation Correction Methods
- •12.5 Partial-Volume Effect
- •12.5.2 Sampling
- •12.5.3 Scattering
- •12.6.1 Spatial Resolution
- •12.6.2 Sensitivity
- •12.6.3 Other Parameters
- •12.7.1 Daily Tests
- •12.7.2 Weekly Tests
- •12.7.2.1 Spatial Resolution
- •12.9 Questions
- •References and Suggested Readings
- •13: Positron Emission Tomography
- •13.1 Introduction
- •13.2 PET Radiopharmaceuticals
- •13.3.2 Block Detector
- •13.5 Coincidence Timing Window
- •13.6 PET/CT Scanner
- •13.7 PET/MR Scanner
- •13.7.2 MR Scanner
- •13.7.3 Commercial PET/MR Scanner
- •13.8 Mobile PET or PET/CT Scanner
- •13.9 Micro-PET Scanner
- •13.11 Data Acquisition
- •13.12 Image Reconstruction
- •13.13 Factors Affecting PET
- •13.13.1 Normalization
- •13.13.2 Photon Attenuation Correction
- •13.13.4 Random Coincidences
- •13.13.5 Scatter Coincidences
- •13.13.6 Dead Time
- •13.13.7 Radial Elongation
- •13.14.1 Spatial Resolution
- •13.14.2 Sensitivity
- •13.14.2.1 Noise Equivalent Count Rate
- •13.15.1 Daily Tests
- •13.15.1.1 Sinogram Check
- •13.15.2 Weekly Tests
- •13.15.2.1 Normalization
- •13.18 Questions
- •References and Suggested Reading
- •14.1 Background
- •14.5 Artificial Neural Network
- •14.7 Machine Learning
- •14.7.1 Decision Tree
- •14.7.2 Random Forest
- •14.7.3 Support Vector Machine
- •14.7.4 Computer Vision
- •14.8 Deep Learning
- •14.8.1 Convolutional Network
- •14.8.2 Recurrent Neural Network
- •14.8.3 Generative Adversarial Network
- •14.8.4 Transfer Learning
- •14.9 Radiomics
- •14.10 Natural Language Processing
- •14.11 Large Language Model
- •14.12 Generative Artificial Intelligence
- •14.13.1 Prompt
- •14.13.2 Token
- •14.13.3 Hallucination
- •14.13.4 Deepfake
- •14.13.5 Overfitting
- •14.15 Chatbot
- •14.18 Legal Implication
- •14.20 Questions
- •References
- •15.1 Introduction
- •15.2.1 Scheduling
- •15.2.2 Image Acquisition
- •15.2.3 Image Processing
- •15.2.4 Interpretation
- •15.2.5 Reporting
- •15.3.1 Oncology
- •15.3.2 Cardiovascular Disease
- •15.3.3 Bone Scintigraphy
- •15.3.4 Thyroid Imaging
- •15.5 Drug Development
- •15.6 Questions
- •References and Suggested Reading
- •16: Internal Radiation Dosimetry
- •16.1 Radiation Unit
- •16.1.1 Roentgen
- •16.1.2 Rad
- •16.1.3 Gray
- •16.1.4 Rem
- •16.1.5 Radiation Weighting Factor
- •16.1.6 Quality Factor
- •16.1.7 Sievert
- •16.2 Dose Calculation
- •16.2.1 Radiation Dose Rate
- •16.2.2 Cumulative Radiation Dose
- •16.2.3 Factors Affecting Ã
- •16.2.4 The S Values
- •16.4 Pediatric Dosage
- •16.5 Questions
- •References and Suggested Readings
- •17: Radiation Biology
- •17.1 The Cell
- •17.2.1 DNA Molecule
- •17.2.2 Chromosome
- •17.5 Cell Survival Curves
- •17.6 Factors Affecting Radiosensitivity
- •17.6.1 Dose Rate
- •17.6.2 Linear Energy Transfer
- •17.6.4 Chemicals
- •17.7 Radiosensitizer
- •17.7.1 Oxygen
- •17.7.2 Pyrimidine
- •17.7.3 Others
- •17.8 Radioprotector
- •17.9 Apoptosis
- •17.13.1 Hematopoietic Syndrome
- •17.13.2 Gastrointestinal Syndrome
- •17.13.3 Cerebrovascular Syndrome
- •17.14.1 Somatic Effects
- •17.14.1.1 Carcinogenesis
- •17.14.1.3 Dose–Response Relationship
- •17.14.1.5 Leukemia
- •17.14.1.6 Breast Cancer
- •17.14.1.7 Other Cancers
- •17.14.1.10 Nonspecific Life-Shortening
- •17.14.1.11 Cataractogenesis
- •17.14.2 Genetic Effects
- •17.14.2.1 Spontaneous Mutation
- •17.14.2.2 Doubling Dose
- •17.14.2.3 Genetically Significant Dose
- •17.17 Questions
- •References and Suggested Readings
- •18.1 Introduction
- •18.2 Radiation Protection
- •18.2.3 Occupational Dose Limits
- •18.2.4 ALARA Program
- •18.2.5.1 Time
- •18.2.5.2 Distance
- •18.2.5.3 Shielding
- •18.2.5.4 Activity
- •18.2.6 Personnel Monitoring
- •18.2.6.1 Film Badge
- •18.2.6.2 Thermoluminescent Dosimeter
- •18.2.6.3 Optically Stimulated Luminescence Dosimeter
- •18.3 Radiation Regulations
- •18.3.1 License
- •18.3.1.1 General License
- •18.3.1.2 Specific License of Limited Scope
- •18.3.1.3 Specific Licenses of Broad Scope
- •18.3.2 Radiation Safety Committee
- •18.3.3 Radiation Safety Officer
- •18.3.4.3 Supervision
- •18.3.4.4 Mobile Nuclear Medicine Service
- •18.3.4.5 Written Directives
- •18.4 Bioassay
- •18.6 Radioactive Waste Disposal
- •18.6.2 Release into Sewerage Systems
- •18.6.4 Other Disposal Methods
- •18.7 Radioactive Spill
- •18.8 Recordkeeping
- •18.10 Dirty Bombs
- •18.11 Types of Accidental Radiation Exposure
- •18.12 Protective Measures in Case of Explosion of a Dirty Bomb
- •18.13 Verification Card for Radioactive Patients
- •18.14 Radiation Phobia
- •18.15 European Regulations Governing Radiation
- •18.16 Questions
- •References and Suggested Readings
- •Index

62
5 Production ofRadionuclides
two, 6-h bombardments (Scholten etal. 1999). Considering a 10-h decay and 15%
loss during processing and an average patient dosage of 25 mCi (0.93 GBq), almost
800 dosages of
99m
Tc products can be prepared—sufcient enough to serve a large
metropolitan of ~5–7million people. Because of the lack of generator possibility,
many cyclotrons have to be installed throughout individual countries for
99m
Tc pro-
duction by this method.
5.8 Questions
1. Describe the different methods of production of radionuclides. Which method
gives relatively more proton-rich and neutron-rich radionuclides?
2. What are the differences between a positive ion and a negative ion cyclotron?
3. What is the average number of neutrons emitted in ssion?
4. What is the difference between carrier-free and no-carrier-added radionuclides?
5. Why are cadmium rods and graphite placed in the reactor?
6. If 68Zn is bombarded with protons in a cyclotron and three neutrons are emitted
from the nucleus, what is the product of the nuclear reaction? Write the nuclear
reaction.
7. (a) What are the primary requirements for making a radionuclide generator?
(b) How long does it take to reach transient equilibrium in a 99Mo–
generator?
(c) What is the permissible limit of 99Mo breakthrough in the
(d) A 20-mCi (740-MBq)
99
Mo. Can this preparation be injected into a patient?
(e) Why is Al3+ undesirable in the
Al3+ in the
99m
Tc eluate?
8. A 2-Ci (74-GBq) 99Mo–
at 10 a.m. on the following Monday. Calculate the
yield and 87% of
99
9. Calculate the activity in millicuries (MBq) of
g of pure
111
Cd for 3h with 12-MeV protons having a beam intensity of 1013
particles/(cm2s). The cross section for formation of
millibarns (1millibarn=10
99m
Tc eluate is found to contain 10μCi (0.37 MBq) of
99m
Tc eluate? What is the permissible limit of
99m
Tc generator calibrated for Thursday noon was eluted
−27cm2
99m
Tc.
).
Mo decays to
99m
Tc activity assuming 80%
111
In produced by irradiation of 1
111
In(t
99m
Tc eluate?
=2.8days) is 200
1/2
99m
Tc
Suggested Readings
Colombetti LG. Radionuclide generators. In: Rayudu GVS, ed. Radiotracers for Medical
Applications. Boca Raton, Fla: CRC Press; 1983; II: 133–168.
Friedlander G, Kennedy JW, Macias ES, Miller JM. Nuclear and Radiochemistry. 3rd ed.
NewYork: Wiley; 1981.
McCarter JL, Brennan HM, Burns S et al. Accelerator production of Mo-99 using Mo-100.
12th Int. Particle Accel. Conf., JACow Publishing, 2021. https://doi.org/10.18429/
JACoW-IPAC2021-MOPAB412

Suggested Readings
63
Mirzadeh S, Mausner LF, Garland MA.Reactor-produced medical radionuclides. In: Vértes A,
Nagy S, Klencsár Z, eds. Handbook of Nuclear Chemistry. Vol 4, Dordrecht: Kluwer; 2003.
Noronha OPD, Sewatkar AB, Ganatra RD, etal. Fission-produced
99
99m
Mo–
Tc generator system
for medical use. J Nucl Med Biol. 1976;20:32–36.
NorthStar Medical Radioisotopes, LLC RadioGenix® Molybdenum-99/Technetium-99m
Generator System Licensing: Guidance for Medical Use Licensees
Quaim SM.Cyclotron production of medical radionuclides. In: Vértes A, Nagy S, Klencsár Z, eds.
Handbook of Nuclear Chemistry. Vol 4, Dordrecht: Kluwer; 2003.
Saha GB. Miscellaneous tracers for imaging. In: Rayudu GVS, ed. Radiotracers for Medical
Applications. Boca Raton, Fla: CRC Press; 1983; II: 119–132.
Saha GB. Fundamentals of Nuclear Pharmacy. 7th ed. NewYork: Springer; 2018.
Saha GB. Basics of PET Imaging. 3rd ed. NewYork: Springer; 2016.
Saha GB, MacIntyre WJ, Go RT.Cyclotron and positron emission tomography radiopharmaceuti-
cals for clinical imaging. Semin Nucl Med. 1992; 22:150–161.
Scholten B, Lambrecht RM, Cogneau etal. Excitation functions for the cyclotron production of
99m
Tc and 99Mo. Appl Radiat Isotopes 1999; 51:69.

Interaction ofRadiation
withMatter
All particulate and electromagnetic radiations can interact with the atoms of an
absorber during their passage through it, producing ionization and excitation of the
absorber atoms. These radiations are called ionizing radiations. Because particulate
radiations have mass and electromagnetic radiations do not, the latter travel a longer
distance through matter before losing all energy than the former of the same energy.
Electromagnetic radiations are therefore called penetrating radiations and particulate radiations nonpenetrating radiations. The mechanisms of interaction with matter, however, differ for the two types of radiations, and therefore they are discussed
separately.
6.1 Interaction ofCharged Particles withMatter
6
The energetic charged particles such as α-particles, protons, deuterons, and
β-particles (electrons) interact with the absorber atoms, while passing through it.
The interaction occurs primarily with the orbital electrons of the atoms and rarely
with the nucleus. During the interaction, both ionization and excitation as well as
the breakdown of the molecule may occur. In excitation, the charged particle transfers all or part of its energy to the orbital electrons, raising them to higher energy
shells. In ionization, the energy transfer may be sufcient to overcome the binding
energy of the orbital electrons, ultimately ejecting them from the atom. Electrons
ejected from the atoms by the incident charged particles are called primary elec-
trons, which may have sufcient kinetic energy to produce further excitation or
ionization in the absorber. The high-energy secondary electrons from secondary
ionizations are referred to as delta (δ-) rays. The process of excitation and ionization
will continue until the incident particle and all electrons come to rest. Both these
processes may rupture chemical bonds in the molecules of the absorber, forming
various chemical entities.
© The Author(s), under exclusive license to Springer Science+Business Media, LLC,
part of Springer Nature 2025
G. B. Saha, Physics and Radiobiology of Nuclear Medicine,
https://doi.org/10.1007/978-1-0716-4816-2_6
65

66
LET SI W .
6 Interaction ofRadiation withMatter
When charged particles travel through a dialectic medium at a speed greater than
the speed of light, they polarize the molecules of the medium, which then turn back
rapidly to their ground state, emitting radiation in the process. The emitted radiation
is bluish in color, which is called Cerenkov radiation. The charged particles travel-
ing at more than the speed of light creates a photonic shock wave in the medium,
similar to a situation when a supersonic body traveling at more than the speed of
sound creates sound shock wave. This effect can be observed with electrons of a few
hundred keV energy, whereas α- particles and protons require several thousands of
MeV to exceed the velocity of light and to produce Cerenkov Effect. Since its probability is low, it is of no practical importance in nuclear medicine.
In ionization, an average energy of W is required to produce an ion pair in the
absorber and varies somewhat with the type of absorber. The value of W is about 35
eV in air and less in oxygen and xenon gases, but falls in the range of 25–45 eV for
most gases. The process of ionization, that is, the formation of ion pairs, is often
used as a means of the detection of charged particles in ion chambers and Geiger–
Müller counters described in Chap. 7.
Three important quantities associated with the passage of charged particles
through matter are specic ionization, linear energy transfer, and range of the particle in the absorber, and these are described next.
6.1.1 Specific Ionization
Specic ionization (SI) is the total number of ion pairs produced per unit length of
the path of the incident radiation. The SI values of α-particles are slightly greater
than those of protons and deuterons, which in turn are larger than those of electrons
because of the greater charge and much slower velocity of the former. Typically, the
SI values of α-particles are 100 times greater than those of electrons with the
same energy.
Specic ionization increases with decreasing energy of the charged particle
because of the increased probability of interaction at low energies. Therefore,
toward the end of the travel, the charged particle shows a sharp increase in ionization (Fig.6.1). This peak ionization is called Bragg ionization. This phenomenon is
predominant for heavy charged particles and is negligible for electrons. Bragg ionization is taken advantage of in radiation therapy of tumors with protons.
6.1.2 Linear Energy Transfer
The linear energy transfer (LET) is the amount of energy deposited per unit length
of the path by the radiation. From the preceding, it is clear that
(6.1)

Distance (cm)
Specific Ionization
LET SI
W
./
6.1 Interaction ofCharged Particles withMatter
Fig. 6.1 Illustration of
Bragg ionization showing a
peak near the end of the
travel of the charged
particle
1.0
0.8
0.6
0.4
0.2
1234 5678 91011
67
Table 6.1
some radiations in tissue
LET values of
Radiation LET (keV/μm)
3 MV x-rays 0.5
250 KV x-rays 3.0
5-MeV α-particles 100.0
1-MeV electrons 0.25
14-MeV neutrons 20.0
The LET is expressed in units of keV/μm and is very useful in concepts of radiation protection. Electromagnetic radiations and β-particles interact with matter, losing only little energy per interaction and therefore have low LETs. In contrast,
heavy particles (α-particles, neutrons, and protons) lose energy very rapidly, producing many ionizations in a short distance, and thus have high LETs. Some comparative approximate LET values in keV/mm in tissue are given in Table6.1.
Problem 6.1
If a particulate radiation produces 45,000 ion pairs per centimeter in air, cal-
culate the LET of the radiation.
Answer
W = 35 eV per ion pair
Using Eq. (6.1),
45 000 35
,
eV
keV
eV cm
m
m
.
1 575 000
,, /
157 5
./
0 1575

68
Electron
a
b
6 Interaction ofRadiation withMatter
6.1.3 Range
The range (R) of a charged particle in an absorber is the straight-line distance traversed by the particle in the direction of motion. The range of a particle depends on
the mass, charge, and kinetic energy of the particle and also on the density of the
absorber. The heavier and more highly charged particles have shorter ranges than
lighter and lower charged particles. The range of charged particles increases with
the energy of the particle. Thus, a 10-MeV particle will have a longer range than a
1-MeV particle. Also, the denser the absorber, the shorter the range. The unit of
range is given in mg/cm2 of the absorber.
Depending on the type of the charged particle, the entire path of travel may be
unidirectional along the initial direction of motion, or tortuous (Fig.6.2). Because
the α-particle loses only a small fraction of energy in a single collision with an electron because of its heavier mass and is not appreciably deected in the collision, the
α-particle path is nearly a straight line along its initial direction (Fig.6.2a). Many
collisions in a short distance create many ion pairs in a small volume. In contrast,
β-particles or electrons interact with extra nuclear orbital electrons of the same mass
and are deected considerably. This leads to tortuous paths of these particles
(Fig.6.2b). In this situation, the true range is less than the total path traveled by the
particle.
It is seen that the ranges of all identical particles in a given absorber are not
exactly the same, but show a spread of 3–4% near the end of their path (Fig.6.3).
This phenomenon, referred to as the straggling of the ranges, results from the statistical uctuations in the number of collisions and in the energy loss per collision. The
range straggling is less prominent with α-particles but is severe with electrons
because it is mostly related to the mass of the particle. The light mass electrons are
considerably deected during collisions and hence exhibit more straggling. If the
transmission of a beam of charged particles through absorbers of different thicknesses is measured, the beam intensity will remain constant until the region of range
Fig. 6.2 Concept of
passage of α particles and
electrons through an
absorber: (a) heavy α
particles move in almost a
straight line, (b) light
electrons move in zigzag
paths
α
‐
parcle
-
e
Absorber
-
e
-
e
-
e
-
e
-
e
-
e
-
e
-
e

STRAGGLING
ABSORBER THICKNESS
RELATIVE BEAM
6.1 Interaction ofCharged Particles withMatter
69
Fig. 6.3 Mean range and
straggling of charged
particles in an absorber
100
50
INTENSITY (%)
MEAN RANGE
RANGE
straggling is encountered, where the beam intensity falls sharply from its initial
value to zero. The absorber thickness that reduces the beam intensity by one half is
called the mean range. The mean range of heavier particles such as α-particles is
better dened than that of electrons. Because β−-particles are emitted with a continuous energy spectrum, their absorption, and hence their ranges, become quite
complicated.
6.1.4 Bremsstrahlung
When energetic charged particles, particularly electrons, pass through matter and
come close to the nucleus of the atom, they lose energy as a result of deceleration in
the Coulomb eld of atomic nuclei. The loss in energy appears as x-ray that is called
bremsstrahlung (German for “braking” or “slowing down” radiation). These bremsstrahlung radiations are commonly used in radiographic procedures and are generated by striking a tungsten target in X-ray tubes with a highly accelerated
electron beam.
Bremsstrahlung production increases with the kinetic energy of the particle and
the atomic number (Z) of the absorber. For example, a 10-MeV electron loses about
50% of its energy by bremsstrahlung, whereas a 90-MeV electron loses almost 90%
of its energy by this process. The bremsstrahlung production is proportional to Z2 of
the absorber atom. Therefore, bremsstrahlung is unimportant in lighter materials
such as air, aluminum, and so forth, whereas it is very signicant in heavy metals
such as lead and tungsten. High-energy β−-particles (1.7 MeV) from radionuclides
such as 32P can produce bremsstrahlung in heavy metals such as lead and tungsten.
For this reason, these radionuclides are stored in low-Z materials such as plastic
containers rather than in lead containers.
Bremsstrahlung is inversely proportional to the mass of the charged particles and
therefore is insignicant for heavy particles, namely α-particles and protons,
because the probability of penetrating close to the nuclei is relatively low due to
their heavier masses.

70
6 Interaction ofRadiation withMatter
6.1.5 Positron Annihilation
When energetic β+-particles pass through an absorber, they lose energy via interaction with orbital electrons of the atoms of the absorber. When the β+-particle comes
to almost rest after losing all energy, it combines with an orbital electron of the
absorber atom and produces two 511-keV annihilation radiations that are emitted in
opposite directions (180°). These annihilation radiations are the basis of positron
emission tomography (PET) in which two photons are detected in coincidence,
which is discussed in Chap. 13.
6.2 Interaction ofγ-Radiations withMatter
6.2.1 Mechanism ofInteraction ofγ-Radiations
When penetrating γ-rays pass through matter, they lose energy by interaction with
the orbital electrons or the nucleus of the absorber atom. The γ-ray photons may lose
all of their energy, or a fraction of it, in a single encounter. The specic ionization
of γ-rays is one-tenth to one-hundredth of that caused by a nonpenetrating electron
of the same energy. There is no quantity equivalent to a range of particles for γ-rays,
but they travel a long path in the absorber before losing all its energy. The average
energy loss per ion pair produced by the photons is the same as for electrons, that is,
35 keV in air.
There are several mechanisms by which γ-rays interact with absorber atoms during their passage through matter, and they are described below.
6.2.1.1 Photoelectric Effect
In the photoelectric effect, the incident γ-ray transfers all its energy to an orbital
electron of the absorber atom whereby the electron, called the photoelectron, is
ejected with kinetic energy equal to E
−EB, where Eγ and EB are the energy of the
γ
γ-ray and the binding energy of the electron, respectively (Fig.6.4). The photoelec-
tron loses its energy by ionization and excitation in the absorber, as discussed previously. The photoelectric effect occurs primarily in the low-energy range and
decreases sharply with increasing photon energy. It also increases very rapidly with
increasing atomic number Z of the absorber atom. Roughly, the phooelectric effect
is proportional to z3/E
3
. The photoelectric contribution from the 0.15-MeV γ-rays in
γ
aluminum (Z = 13) is about the same (~5%) as that from the 4.7-MeV γ-rays in lead
(Z = 82).
The photoelectric effect occurs primarily with the K-shell electrons, with about
20% contribution from the L-shell electrons and even less from higher shells. There
are sharp increases (discontinuities) in photoelectric effects at energies exactly
equal to binding energies of K-, L- (etc.) shell electrons. These are called K-, L-, etc.,
absorption edges. The vacancy created by the ejection of an orbital electron is lled

E
.c
E
//..10
6.2 Interaction ofγ-Radiations withMatter
Fig. 6.4 The photoelectric
effect in which a γ-ray with
energy E
energy to a K-shell
electron, and the electron
is ejected with E
where E
energy of the K-shell
electron
transfers all its
γ
−EB,
γ
is the binding
B
71
in by the transition of an electron from the upper energy shell. It is then followed by
emission of a characteristic x-ray or Auger electron, analogous to the situations in
internal conversion or electron capture decay.
6.2.1.2 Compton Scattering
In Compton scattering, the γ-ray photon transfers only a part of its energy to an
electron in the outer shell of the absorber atom, and the electron is ejected. The
photon, itself with reduced energy, is deected from its original direction (Fig.6.5).
This process is called the Compton scattering. The scattered photon of lower energy
may then undergo further photoelectric or Compton interaction, and the Compton
electron may cause ionization or excitation, as discussed previously.
At low energies, only a small fraction of the photon energy is transferred to the
Compton electron, and the photon and the Compton electron are scattered at an
angle θ. Using the law of conservation of momentum and energy, the scattered photon energy is given by
EE
//
sc
os10511 1
(6.2)
where Eγ and Esc are the energies in MeV of the initial and scattered photons. The
scattered photon energy varies from a maximum in a collision at 0° (forward) to a
minimum at θ=180° in a backscattering collision. Conversely, the Compton electron carries a minimum energy in the forward collision to a maximum energy in the
backscattering collision. At higher energies, both the scattered photon and the
Compton electron are predominantly scattered in the forward direction.
If the photon is backscattered, that is, scattered at 180°, then the backscattered
photon has the energy E
given by the expression (cos180°=−1):
sc
EE
sc
256 (6.3)

72
Fig. 6.5 The Compton
scattering, in which a γ-ray
interacts with an outer
orbital electron of an
absorber atom. Only a part
of the photon energy is
transferred to the electron,
and the photon itself is
scattered at an angle. The
scattered photon may
undergo subsequent
photoelectric effect or
Compton scattering in the
absorber or may escape the
absorber
6 Interaction ofRadiation withMatter
In backscattering of a 140-keV photon, the scattered photon and the Compton
electron would have 91 and 49 keV, respectively, whereas for a 1330-keV photon,
these values are 215 and 1115 keV, respectively. It can be seen that as the photon
energy increases, the scattered photon energy approaches the minimum limit of 256
keV, and the Compton electron receives the maximum energy.
Compton scattering is almost independent of the atomic number Z of the absorber.
Compton scattering contributes primarily in the energy range of 0.1–10 MeV,
depending on the type of absorber.
6.2.1.3 Pair Production
When the γ-ray photon energy is greater than 1.02 MeV, the photon can interact
with the nucleus of the absorber atom during its passage through it, and a positive
electron and a negative electron are produced at the expense of the photon (Fig.6.6).
The energy in excess of 1.02MeV appears as the kinetic energy of the two particles.
This process is called pair production. It varies almost linearly with Z2 of the
absorber and increases slowly with the energy of the photon. In soft tissue, pair
production is insignicant at energies up to 10MeV above 1.02MeV.Positive electrons created by pair production are annihilated to produce two 0.511-MeV photons
identical to those produced by positrons from radioactive decay.
The relative importance of photoelectric, Compton, and pair production interactions with absorbers of different atomic numbers is shown in Fig.6.7, as a function
of the energy of the incident photons. It is seen that the photoelectric effect is predominant in high-Z absorbers at lower energies (<0.1MeV), whereas the Compton
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