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Файл:Ординатура / Хирургия / Библиотека им академика М.И. Перельмана / Книга_5545_Библиотеки_им_академика_М_И_Перельмана.pdf
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- •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

378
18 Radiation Protection andRegulations
Table 18.5
Record keeping of various activities related to radioactive materials
Type of operation Information needed
Written directives
Copy of written directives 3years
(10CFR35.2040)
Procedures requiring written
Copy of procedures Duration of
directive (10CFR35.2041)
Dosage of radiopharmaceuticals
dispensed (10CFR35.2063)
Name, lot number, expiration date,
patient’s name or identication number
prescribed dosage and dispensed dosage,
date and time of administration, name of
individual
Calibration of dose calibrator
(10CFR35.2060)
Model, serial number of dose calibrator,
date and results of test, and name of
individual doing the test
Calibration of survey meters
(10CFR35.2061)
Model and serial number of instrument,
date and results of calibration, and name of
individual
Semiannual leak tests and
inventory of sealed sources
(10CFR35.2067)
Model and serial number of each source
and its radionuclide, estimated activity,
measured activity in μCi (Bq), date of test,
location of source (inventory), name of
individual
Moly breakthrough
(10CFR35.2204)
μCi (kBq) of
99m
Tc, date and time of measurement, name
99
Mo per mCi (MBq) of
of individual
82
Sr and 85Sr breakthrough
(10CFR35.2204)
μCi (kBq) of 82Sr and 85Sr per mCi (MBq)
82
of
Rb, date and time of measurement,
name of individual
Thyroid bioassay and whole
body counting (10CFR20.2106)
Name of individual having bioassay, date
of reading, and the individual taking the
measurement
Personnel exposure monitoring
(10CFR20.2106)
Radioactive waste disposal by
decay-in-storage
(10CFR35.2092)
Planned special procedures
(10CFR20.2105)
Must be on NRC-5 form according to
items described on the form
Date of disposal, instrument used,
background reading, and surface reading of
waste container and name of the individual
Circumstances, name of authorizing
individual, doses expected
Surveys (10CFR35.2070) Date, area, trigger level (mR/h), survey
data, instrument used, and name of
individual
a
Time to
maintain records
license
3years
3years
3years
3years
3years
3years
Until the NRC
terminates the
license
Until the NRC
records
terminates the
license
3years
Until the NRC
terminates the
license
3years
(continued)

18.8 Recordkeeping
379
Table 18.5
Type of operation Information needed
Medical mobile service
(10CFR35.2080)
Release of patients with
unsealed by-product material
(10CFR35.2075)
Instructions given to breastfeeding (10CFR35.2075)
Actions taken by licensee in
radiation protection program
(10CFR35.2026)
Authority, duty and
responsibility of management,
RSO, and ARSO
(10CFR35.2024)
Changes in radiation program
(10CFR35.2026)
Disposal of byproduct material
(10CFR20.2108)
Transfer of byproduct material Date, amount, type of activity transferred.
Prior occupational dose
(10CFR20.2104)
Release of radioactive efuents
to environment (10CFR20.2013)
Dose to members of the public
(10CFR20.2107)
Receipt of byproduct material Date of receipt, type and quantity of
Adapted from NRC Guide NUREG 1556vol 9, Rev 3, 2019; 10CFR 35 and 10CFR30
a
NRC website
(continued)
2
Copies of agreement between clients and
the service provider
Basis of calculation to release the patient,
such as retained activity, occupancy factor
less than 0.25 at 1m, using T
considering shielding by tissue
Instructions given if dose to the infant
exceeds 0.5rem (5mSv)
Copy of actions taken and management’s
2
signature
Copy of these elements with signatures of
management, RSO and ARSO
Copy of old & new programs, date,
approval signature of management
Date and method of disposal, amount and
type of activity, person disposing of
Names of transferor and recipient
Prior doses from previous employers Duration of
Date, concentration of efuents Duration of
Date of record, dose values Duration of
activity, name of receiver
or Te, or
p
Time to
maintain records
3years
3years
3years
5years
5years
5years
Duration of
license
3years after
transfer
license
license
license
Duration of
possession
keeping in mind the principle of containment of radioactivity. Survey and wipe tests
must be performed after decontamination. The RSO will investigate the accident
and recommend corrective action if a major spill occurs.
18.8 Recordkeeping
Records must be maintained for the receipt, storage, and disposal of radioactive
materials, and also for various activities performed in the radiation laboratories.
According to the NRC regulations, these records must contain specic information
and be kept for a certain period of time. Table18.5 lists different records that are
required by the NRC and the period of time to be kept.

380
18 Radiation Protection andRegulations
18.9 Transportation ofRadioactive Materials
The transportation of radioactive materials is governed by the U.S.Department of
Transportation (DOT), which establishes the guidelines for packaging, types of
packaging material, limits of radioactivity in a package, and exposure limits. Title
49 of the Code of Federal Regulations (49CFR) and 10CFR71 contain all these
regulations related to packaging and transportation of radioactive materials. There
are two types of packaging:
Type A: This type of packaging is used primarily for most radiopharmaceuticals.
Such packaging is sufcient to prevent loss of radioactive material with proper
shielding to maintain the prescribed exposure during normal transportation. The
limits of radioactivities of various radionuclides under this category are specied
in 49CFR and 10CFR71.
Type B: When the radioactivity exceeds the limits specied in Type A, Type B pack-
aging must be used. Such packaging is considerably more accident resistant and
is required for very large quantities of radioactive material. The packages must
pass certain tests such as the drop test, corner drop test, compression test, and
30-min water spray test.
The radioactive packages must be labeled properly before transportation. There
are three types of labels (Fig.18.3) according to the exposure reading in mR/h at
1m from the surface of the package (transport index). The criteria for the three
labels are given in Table 18.6. The transport index (TI) must be indicated on the
label, and the sign “RADIOACTIVE” must be placed on the package. The maximum permissible TI value is 10, although it is limited to three for passenger- carrying
aircrafts. For liquids, the label “THIS SIDE UP” must be placed on the package.
Fig. 18.3 The three types
of U.S.Department of
Transportation labels
required for transportation
of radioactive material
Table 18.6 Labeling
categories for packages
containing radioactive
materials
Exposure (mR/h)
Type of label
White-I < 0.5 –
Yellow-II >0.5≤50 < 1
Yellow-III >50≤200 >1≤10
No package shall exceed 200 mR/h at the surface of the package or 10 mR/h at 1 m.
Transport index is the reading in mR/h at 1m
from the package surface (10CFR71)
At surface At 1m

18.9 Transportation ofRadioactive Materials
381
Table 18.7
Limited quantities of several radionuclides that are exempt from shipping and label-
ing requirements, according to 49CFR I73.425
Quantity
Radionuclides
57
Co (s) 270 10,000
67
Ga (l) 8.1 300
123
I (l) 8.1 300
125
I (l) 8.1 300
131
I (l) 1.9 70
89
Sr (l) 1.6 60
111
In (l) 8.1 300
32
P (l) 1.4 50
99m
Tc (l) 11 400
20l
Tl (l) 11 400
133
Xe (g) 270 10,000
18
F (l) 1.6 60
a
s solid; l liquid; g gas
a
(mCi) (MBq)
Each package must be labeled on opposite sides with the appropriate warning label
(one of the labels in Fig.18.3). The label must identify the content and amount of
radionuclide in curies or becquerels. The package must contain shipping documents
inside, bearing the identity, amount, and chemical form of the radioactive material
and the TI.
Placards are necessary on the transport vehicles carrying yellow-III–labeled
packages and must be put on four sides of the vehicle.
According to 49CFR173.421, radionuclides are exempted from the packaging
and labeling requirements if only a limited quantity of these radionuclides is
shipped. The surface exposure readings should not exceed 0.5 mR/h at all points of
the package surface, and the wipe test indicates no removable contamination in
excess of 6600dpm/300cm
2
. The outside of the inner packaging or, if there is no
inner packaging, the outside of the packaging itself bears the marking, “Radioactive”.
The outside of the package must be marked with UN2910. If the inner packaging
materials read less than 0.5 mR/h for exposure and 6600dpm/300cm2 for contamination, then the shipment is considered “Empty” and should be labeled “UN2908”
on the outside. No shipping paper is required for both limited quantity or empty
packages, if the material is not hazardous. The limited quantities for some important
radionuclides are given in Table18.7 based on 10−4 A2 for liquids and 10−3 A2 for
solids and gases, as stated in 49CFR173.425. The values of A2 are obtained from
49CFR173.435.
Employees who ship hazardous material including radioactive material must
have hazmat training to be able to recognize and identify hazardous material, to
conduct their specic function, and to enforce safety procedures to protect the public. The training must be given to a new employee within 90days of employment

382
and then repeated every three years. The training is provided by the hazmat employer
or other public or private sources, and a record of training must be made.
18 Radiation Protection andRegulations
18.10 Dirty Bombs
A dirty bomb, also called a Radiological Dispersal Device (RDD), is a mix of explosive, such as dynamite, with radioactive materials. After the explosion, in addition
to the immediate devastating effects of the explosive material causing injury and
property damage, radioactive dust and smoke spread the radioactive contamination
into the surrounding areas. Radioactive dust and smoke, if inhaled, can cause ill
health effects. The use of dirty bombs by perpetrators is to spread radioactive contamination and create fear and panic, more than anything else. Subsequent decontamination could involve considerable time and cost.
A dirty bomb is not an atomic bomb and is primarily used to disrupt and not
destroy the human life. A type of RDD may contain a high level of radioactive source
hidden in a bus, train, or subway station, where people passing close to the source
might get a signicant dose of radiation. Prompt detection of these devices (bomb or
radioactive source) is essential in order to take protective measures.
The sources of radioactive materials are the hospitals, research facilities, and
industrial and construction sites where radioactivity is used for various purposes
(diagnosis and treatment at hospitals, research work, sterilizing equipment, and
check of welding). Some of the highly hazardous radioactive sources are cobolt-60,
strontium-90, cesium-137, and iridium-192 used in industrial radiographic services.
These radionuclides have long half-lives. Many of these sources are mostly in
metallic capsule form and the likelihood of dispersion is minimal. However, they
can be available in liquid and powder forms and potentially be used in dirty bombs,
which can result in widespread contamination in the surrounding areas of explosion.
Because one cannot see, taste, or feel radiations, excessive exposure can be received
unknowingly by people in the vicinity of the area.
18.11 Types of Accidental R adiation Exposure
Radiation exposure from radiation accidents can be localized and/or whole-body
type. The localized exposure may be caused by direct handling of or close proximity
to highly radioactive sources. The local injury includes erythema, epilation, desquamation, ulceration, or blistering depending on the level of exposure. The treatment
of choice for localized injuries is the use of antibiotic for infection and control of
pain. In severe cases, amputation or plastic surgery is warranted.
The whole-body exposure causes various acute radiation syndromes that have
been discussed earlier in this chapter. These syndromes include hematopoietic, gastrointestinal, and cerebrovascular syndromes, depending on the absorbed doses.
Although cerebrovascular syndromes occur with 10,000rem (100Sv), and result in

18.12 Protective Measures in Case of Explosion of a Dirty Bomb
383
death, the hematopoietic and gastrointestinal syndromes may be managed by bone
marrow transplantation and other prophylactic treatment.
When a RDD explodes, radioactive material may be airborne and contaminate
food and water. Internal contamination can occur from the ingestion of contaminated food and water, inhalation of the contaminated air, and diffusion through the
skin or wounds. The principle of the treatment of internal contamination primarily
involves dilution, displacement by nonradioactive material, complex formation, and
blockage. In the case of internal contamination with radioiodine (e.g., incidences of
fallout from a nuclear explosion or a nuclear reactor accident), both the NRC and
FDA have approved the use of potassium iodide (KI) as a preventive measure. Such
use of KI is intended to block the thyroid from trapping
131
I and it should be taken
before the exposure or within several hours of exposure. The recommended daily
dose is 130 mg of KI for adults, 65mg for 3–18 year old, 32 mg for children
1month to 3year old, and 16mg for infants less than 1month old (Mettler and
Voelz 2002).
Outer garments such as clothing and shoes can be contaminated by radioactivity
from the explosion of a dirty bomb. Such contamination does not constitute a medical emergency and most of it can be removed by taking off these garments. Minor
skin contamination can be eliminated by thorough washing with water and detergent, and a shower, if appropriate. Skin should not be abraded by a heavy brush, as
this may facilitate internal absorption. If an individual has a life-threatening condition in addition to the external contamination, the patient must be rst managed for
the medical condition before decontamination is carried out. Burns and wounds that
are not contaminated should be rst covered and then decontamination of the other
affected areas carried out.
18.12 Protective Measures in Case of Explosion of a
Dirty Bomb
According to the advisory of the NRC and the Center for Disease Control (available
at www.nrc.gov and www.bt.cdc.gov), the following steps should be taken in case
of a dirty bomb explosion.
1. If you are outside and close to the explosion of a dirty bomb, cover the nose and
mouth with a mask or cloth to reduce the risk of breathing in radioactive dust or
smoke. If possible, immediately go inside the building that is not affected by the
explosion and remove the outer layer of clothing and shoes and seal them in a
plastic bag, if available. Store the plastic bag in a safe place for decay of the
radioactivity. Next, take a shower to remove any dust that remains on the body.
2. If you are inside and close to the incident that has occurred outside, close all the
doors and windows and do not leave the building. Turn off heat and air conditioner to stop air circulation from outside.
3. Listen to the local news for further appropriate instructions.

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18 Radiation Protection andRegulations
4. Food and water are unlikely to be contaminated. If contaminated, do not con-
sume these items. Local or federal authorities are likely to monitor the food and
water in the area of explosion and inform the public of their suitability for
consumption.
5. If it is denitely known that there is radioiodine contamination, KI should be
orally administered within a short time according to the regimen described
earlier.
6. Monitoring is essential and critical to estimate the level of contamination or
decontamination using a GM counter and is performed by hospital personnel,
police, and reghters who are specially trained for this purpose.
18.13 Verification Card for Radioactive Patients
After the September 11, 2001 attack on the World Trade Center in NewYork,
numerous security measures have been adopted by the US Federal Government.
The Department of Homeland Security was authorized to implement and monitor
different aspects of the security measures against radiation. Security checks of airline passengers, background checks of many visitors, and monitoring suspected terrorist groups are some of the examples. In view of the concerns over the use of dirty
bombs by miscreants, the Homeland Security has established checkpoints at various
strategic locations such as airports, tunnels, mass transit, bridges, border crossing
points, historical monuments, landmarks, and the like, to monitor the transport of
RDDs by using radiation detectors.
One pitfall of this measure is that patients who received radioactive materials for
diagnostic and therapeutic purposes may trigger the monitors while passing through
these checkpoints and undergo undue hassle with authorities to provide proof that
the radioactivity was really from medical uses. These incidents have been reported
all over the country. In 2003, the NRC issued a guidance “NRC Information Notice
2003–2022: Heightened Awareness for Patients Containing Detectable Amounts of
Radiation from Medical Administration” to address this situation. In essence,
according to this guidance, if a patient has detectable radioactivity due to a nuclear
medicine test or a therapeutic implant, the licensee is asked to explain to the patient
that during commuting, the internal activity may trigger the monitoring equipment
installed in specic areas required by US Homeland Security Administration. It
further recommends that the licensee considers providing a verication card with
licensee’s address, a contact phone number, and an assurance that the level of activity from the study poses no danger to the public and is allowed by NRC medical use
regulations. Based on this, a verication card is designed containing information
such as the name of the patient, type of radionuclide administered, date of study, and
a contact number. The patient is recommended to carry the card as a proof of radioactive examination for a period of time (discussed below) till the activity is low
enough not to trigger the monitoring equipment.
A question arises as to how long the patient who has undergone nuclear studies
should carry the card. It depends on the half-life of the radionuclide, types of

18.14 Radiation Phobia
385
radiations the radionuclide emits, and the biological elimination of the radiotracer
from the body. Zuckier etal. (2004) in a paper presented at The Radiological Society
of North America annual meeting in Chicago suggested the following periods for
different radionuclides for the patients to carry the card.
18
F 1day
99m
123
Tc,
I 3days
111
In 14–17days
67
201
Ga,
Tl 30days
131
I 95days
Since the above guidance is only a recommendation, many institutions offer verication cards only to patients administered with therapy dosages and undergoing
brachytherapy. In nuclear medicine, patients having diagnosticc tests are not given
verication cards. Also, the program varies state to state.
18.14 Radiation Phobia
The public in general is unduly fearful of radiation because of several factors. One
important factor is the graphic images of the devastating effects of the atomic bombs
detonated in Hiroshima and Nagasaki in 1945, and to a lesser extent, the images of
the Chernobyl reactor accident in 1986. The most noticeable effects of these incidents are death of living species and destruction of property at the site of the explosion and its immediate vicinity. Because of these images, many people associate
radiation exposure with adverse health effects and death. These images are rmly
embedded in the minds of the public causing perpetual fear of radiation. However,
these incidents are very uncommon.
Another ashpoint in creating radiation phobia in the public’s mind is the knowledge of assumption that any level of ionizing radiation is dangerous to health, alluding to the linear no-threshold (LNT) theory of the dose–response relationship.
Psychological warfare with anecdotal rhetoric among the rival countries possessing
nuclear weapons also creates fear of radiation among the public. Dreadening effects
of radiation on children and future offspring, and long-term damage to property are
major concerns of the public. Furthermore, the media often play a role in exacerbating the problem of fear from radiation exposure.
Is there a logical justication for this radiation phobia of the public? Denitely,
nuclear detonation causes an instantaneous, devastating effect on the population and
property, and so can be a reason for fear and panic. But the long-term effects of low
doses of radiation, even from the fallout of the atomic bombs in Japan and the
Chernobyl accident, have been shown to be relatively small. The average individual
lifetime dose from the Chernobyl fallout is estimated to be 0.6–6rem (6–60mSv)
(Jaworowski 1999). By comparison, the worldwide average annual dose an individual receives from natural radiation on earth is 220 mrem (2.2mSv) and the lifetime dose of about 15rem (150mSv). In the United States, an individual receives

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18 Radiation Protection andRegulations
an annual dose of about 311 mrem (3.1mSv) from natural sources, including radon,
and a lifetime dose of 21rem (210mSv). These values are even ten times higher in
some regions in India and Brazil, and yet the incidence of excess cancer is not
shown to be higher in these places.
People face risk of cancer, injuries, and even death from day-to-day living activities, such as driving, smoking cigarettes, drinking alcohol, eating food, and breathing air, in addition to hazardous job-related activities. Thirty-three percent of the
population will contract cancer just from these activities without any radiation
exposure, and 22% will die from natural causes (American Cancer Society, 2003).
If the population is exposed to 1rem (10 mSv) of radiation exposure, the risk of
cancer increases only by 0.1% and half of them (0.05%) will die, which is quite
negligible (BEIR VII, 2005). Based on these arguments, it can be said that although
nuclear explosions can be a cause for grave concern, low-dose radiation from medical facilities, natural background, and the like, are fairly safe relative to the hazards
of different living activities, and the risk from such radiation exposure is small.
To allay the fears of radiation in the public’s mind is essential and critical. It can
be achieved through education of the public. People knowledgeable in radiation
should talk to laymen explaining the relatively small risk of low-level radiations
compared to many other day-to-day living activities. The media should play an
important role in communicating this information to the public. Radiation experts
should hold regular public seminars to explain the minimal risk of low level radiation. Radiation-related professional organizations such as the Society of Nuclear
Medicine, The Radiological Society of North America, Health Physics Society, and
American Association of Physicists in Medicine should undertake appropriate
approaches of communication with the public to shed their concern and fear of
radiation.
18.15 European Regulations Governing Radiation
The European Union (EU) currently consists of 28 member countries in Europe,
which adopt various rules and regulations that are uniformly applicable to all member states. There are several countries that have applied to join the EU and others are
considering joining. Regulations governing the use of ionizing radiations varied
among member states until 1989, when the EU applied uniform regulations for
radiopharmaceuticals to be implemented by each member state. The European
Regulatory Organizations of the EU has three main instruments: Directives,
Guidelines, and Regulations. Directives are mandatory to be translated into national
legislation and implemented in each member country. Guidelines are recommendations (not mandatory) for the implementation of the Directives by each member
country. Regulations are mandatory for all member countries without adoption into
individual national legislation.
Use and control of radiation are regulated by Directives from the European
Atomic Energy Community (EURATOM). Initial Directives 84/466 EURATOM,
and 84/467 EURATOM were based on the recommendations of the ICRP, and

18.15 European Regulations Governing Radiation
387
mandate regulations for radiation protection for patients, radiation workers, and the
public. Because the ICRP revised the basic standards for radiation protection in
1996, Directive 84/467 EURATOM was repealed and substituted with Directive
96/29/EURATOM.Upon further revision of the basic standards by the ICRP, the
Directive 96/29/EURATOM had been amended by 97/43/EURATOM, and nally,
Directive 84/466/EURATOM was repealed.
In 2013, all previous directives were repealed and a consolidated Council
Directive 2013/59/Euroatom was introduced. These directives are similar to NRC
10CFR20 regulations in the USA and address all aspects of radiation protection to
individuals involved with radiation. They include exposure limits to exposed workers (article 9), minors (article 11), pregnant women and nursing mothers (article
10), and public members (article 12); monitoring of radiation areas (aticle 38) and
working personnel (article 41); designation of controlled (article 37) supervised
(article 38) areas; optimization of radiation exposure (article 560) (similar to
ALARA in the US); training and experience of the radiation workers and physicians
(article 15 and 18); monitoring in the case of accidental or emergency exposure
(article 42); record keeping and reporting of incidents (article 43); and so on. Radon
measurements shall be carried out in workplaces such as basements or underground
to monitor if the permissble limit is exceeded. Table18.8 shows the dose limits from
radiation exposure to radiation workers, minors and nursing motther and pregnant
women, and the public, which are somewhat different from those adopted by the US
NRC 10CFR20. The disposal, recycling, or reuse of radioactive substances is
required to have prior authorization (article 30), but may be exempted from these
requirements if the clearance levels of radioactivity established by the member state
comply with those of the EURATOM Directive. Interstate shipment of radioactive
materials between member states is governed by Directive 1493/93
EURATOM.Personnel monitoring is mandatory for all radiation workers by using
Table 18.8 Dose limits from Council Directive 2013/59/EURATOM (2013)
Apprentices and
Limits
Effective dose 20mSv (2rem); 50mSv
Equivalent
dose for eye
lens
Equivalent
dose for skin,
hands,
forearms, feet,
ankle
Exposed workers (aged over
18)
(5rem) allowed, provided
ave. dose over 5 consecutive
years. does not exceed 2mSv
(2rem)
20mSv (2rem) or 100mSv
(10rem) in consecutive
5years. subject to a max of
50mSv (5rem) in a single
year
500mSv(50rem) 150mSv
students
(16–18years) Public
6mSv (600
mrem)
15mSv
(1.5rem)
(15rem)
1mSv(100
mrem)
15mSv
(1.5rem)
50mSv
(5rem)
Pregnant and
breast feeding
workers
ALARA and
less than 1mSv
(100 mrem)
during
pregnancy
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