Radiation protection is the science whose aim is to minimize the risks generated by the use of ionizing radiation. Briefly discusses The ICRP System of Radiological Protection, STRUCTURAL SHIELDING OF
IMAGING FACILITIES, APPLICATION OF INDIVIDUAL DOSE LIMTS, RADIATION EXPOSURE IN PREGNANCY, Diagnostic reference level, Personnel Protection in
Medical X-ray Imaging, Dose Optimization in CT, Radiation Protection in Nuclear Medicine.
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Principle of Radiation Protection- Avinesh Shrestha
1.
2. INTRODUCTION
Radiation protection is the science whose aim is to minimize the risks (for people and environment)
generated by the use of ionizing radiation.
Radiation Protection aims to reduce Stochastic effects and eliminate Deterministic effects of radiation
The first sign that there was a limit to how much radiation exposure an individual could sustain without ill
effects was known in the 1900s.
It was not until the death of Clarence Dally (1865–1904), Thomas Edison’s assistant in the manufacture of
X-ray apparatus, and the documentation of his struggle with burns, serial amputations, and extensive lymph
node involvement, that medical observers took seriously the notion that the rays could prove fatal
He died in 1904 from mediastinal cancer. Following this, Thomas Edison abandoned his research on X-
rays.
In 1928, the formal radiation protection standards were introduced with the formation of International
Commission on Radiological Protection (ICRP)
4. 5.3. Categories of exposure
The Commission distinguishes between three categories of exposures:
Occupational exposures; defined by the Commission as all radiation exposure of workers incurred
as a result of their work.
Public exposures; encompasses all exposures of the public other than occupational exposures and
medical exposures of patients. Public is defined by the Commission as any individual who receives
an exposure that is neither occupational nor medical
Medical exposures of patients; Radiation exposures of patients occur in diagnostic, interventional,
and therapeutic procedures.
A given individual may be exposed as a worker, and/or as a member of the public, and/or as a patient.
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5. Fundamental Principles and Methods of Exposure Control
International Commission on Radiological Protection (ICRP) has formulated a set of principles (“System of
Radiation Protection”) that apply to the practice of radiation protection (ICRP, 2007):
Justification of practice
Optimization of protection
Application of individual Dose Limits
6. JUSTIFICATION OF PRACTICE
Any decision that alters the radiation exposure situation, for example, by introducing a new radiation source or
by reducing existing exposure, should do more good than harm, that is, yield an individual or societal
benefit that is higher than the detriment it causes.
No practice involving exposure to radiation should be adopted unless it produces at least sufficient benefit to
the exposed individuals or to society to offset the radiation detriment it causes.
If the exposure has no benefit it is not justified.
7. OPTIMIZATION OF PROTECTION
Optimization of protection should ensure the selection of the best protection option under the
prevailing circumstances, that is, maximizing the margin of good over harm.
Thus, optimization involves keeping exposures as low as reasonably achievable (ALARA), taking
into account economic and societal factors.
It means adjusting the quality and quantity of the radiation to the body habitus of the patient to
use only the dose necessary for producing a study from which a diagnosis can be made with
confidence.
8. OPTIMIZATION OF PROTECTION
ALARA (As Low As Reasonably Achievable) concept
Refers to the continual application of the optimization principle in the day-to-day practice
Because of some risk, however small, exists from any radiation dose, all doses should be
kept ALARA.
9. OPTIMIZATION OF PROTECTION
ALARA vs ALADA
The term ALADA (As Low As Diagnostically Acceptable) has been cited in the literature;
concern that the dose rather than the diagnostic utility of the image may become the overriding metric of
quality.
This is not the intent of ALARA and it certainly can be applied to medicine if correctly interpreted, some see
the distinction useful to keep the right balance on the elements that most affect patient care.
10. OPTIMIZATION OF PROTECTION
ALARA vs ALADA
Both the ALARA and the ICRP optimization principles imply using the lowest dose necessary to produce an
examination result of appropriate diagnostic quality or, in the case of an image-guided intervention, to
achieve the goals of the intervention.
Therefore, reducing the examination dose to the point where important diagnostic information is lost or that
results in the exam needing to be repeated is counterproductive and increases rather than decreases the
overall risk to the patient.
This is, in essence, the ALADA concept.
In the United Kingdom (UK), ALARP-As Low As Reasonably Practicable (ALARP)
11. Methods of Exposure Control
There are four principal methods by which radiation exposure to persons can be minimized:
reducing the time (period) of exposure,
increasing distance from the radiation source,
shielding the source of the radiation, and
controlling contamination of radioactive material.
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Cardinal Principle
14. DISTANCE
Effective & Easy
Inverse Square Law (ISL)
Doubling distance from source, decreases dose by factor of
four
Tripling it decreases dose nine-fold
More Distance = Less Radiation Exposure
15. DISTANCE
Scattered radiation for diagnostic energy x-rays, a good rule of
thumb is that at 1 m from a patient at 90° to the incident beam,
the radiation intensity is approximately 0.1% to 0.15% of the
intensity of the beam to the patient for a 400 cm2 x-ray field
area on the patient (typical field area for fluoroscopy).
All personnel should stand as far away from the patient as
practicable during x-ray imaging procedures and behind a
shielded barrier or out of the room, whenever possible.
The NCRP recommends that personnel should stand at least 2
m from the x-ray tube and the patient during radiography with
mobile equipment (NCRP, 1989b).
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16. SHIELDING
Materials “absorb” radiation
Proper shielding = Less Radiation Exposure
Shielding used where appropriate
Significantly reduces radiation effects
Lead, conventional gypsum board ,concrete block or brick
17. SHIELDING
Due to the higher photon energies emitted from most of the radionuclides used in nuclear medicine, it is
often not practical to shield the technologist from the radiation emitted from the patient
Distance is the primary dose reduction technique.
Imaging rooms should be designed to allow a large distance between the imaging table and the computer
terminal where
The use of a high atomic number material for shielding such as lead enhance photoelectric absorption
thus reducing the thickness of the shielding compared to lower density materials.
Placing shielding closer to a source of radiation does not reduce the thickness needed, but does reduce
the mass of shielding necessary by reducing the area requiring shielding.
18. • Lead apron, lead glasses, lead
gloves
• Gonadal shielding
• Thyroid shielding
Personnel shielding
X-ray tube shielding
• Primary protective barrier (1.6
mm LE)
• Secondary protective barrier
(0.8 mm LE)
• Viewing window – Lead glass
(1.5 mm LE)
Room shielding
(Structural shielding)
• Protective housing
• Total filtration-2.5mm Al when
operated above 70Kvp
•Proper light localized collimator
19. SHIELDING
Lead free Aprons
Metals like Tungsten, Tin, Antimony, Barium or Bismuth which have a
smaller atomic weight as lead.
When used together, Bismuth and Antimony provide similar qualities
to lead.
Lead-Free aprons have similar attenuation properties to the traditional
lead but can weigh up to 15 - 40% less. (From 7kg reduced to 4kg)
The real advantage in using lead free material is that it is not
hazardous to the environment such as lead.
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20. Sources of Exposure
The sources of exposure that must be
shielded in a diagnostic or interventional x-
ray room
Scatter and leakage radiation are together
called secondary or stray radiation.
Primary radiation, also called the useful
beam
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21. Sources of Exposure
For radiation protection purposes scatter is considered as a separate radiation source with essentially
the same photon energy spectrum (and penetrability) as the primary beam.
The exposure due to leakage radiation is limited by FDA regulations
0.88 mGy/h (100 mR/h) at 1 m from the tube housing when the x-ray tube
operated at the maximum allowable continuous tube current (usually 3 to 5 mA)
at the maximum rated tube potential, typically 150 kV.
10/4/2023 21
22. Sources of Exposure
The primary and secondary radiation exposure of an individual in an adjacent area to be protected
depends primarily on the:
1. amount of radiation produced by the source;
2. distance between the patient and the radiation source;
3. amount of time a given individual spends in an adjacent area;
4. amount of protective shielding between the source of radiation and the individual; and
5. distance between the source of radiation and the individual.
10/4/2023 22
23. Computation of X-ray Imaging Shielding
Requirements
the point of closest approach to the barrier is
assumed to be
0.3 m for a wall,
1.7 m above the floor below, and,
for transmission through the ceiling, at least
0.5m above the floor of the room above
10/4/2023 23
24. STRUCTURAL SHIELDING OF
IMAGING FACILITIES
Areas to be protected by shielding are designated as controlled and
uncontrolled areas
Shielding design goals, P, are amounts of air kerma delivered over a
specified time at a stated reference point
NCRP Report No. 147 recommends that the shielding design goal P for
controlled areas be 5 mGy per year and that for uncontrolled areas be 1
mGy per year.
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25. STRUCTURAL SHIELDING OF
IMAGING FACILITIES
Shielding designed by these methods will keep the effective doses or
effective dose equivalents received by workers in these areas
much less than a tenth of the current occupational dose limits in the
United States,
will keep the dose to an embryo or fetus of a pregnant worker much
less than 5 mGy over the duration of gestation, and
will keep the effective doses to members of the public and employees,
who are not considered radiation workers, less than 1 mSv per year.
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26. Computation of X-ray Imaging Shielding Requirements
Terminologies
Factors that must be considered for calculation of
thickness of barrier
Workload(W):it is the quantity of x rays generated
per week
Workload=mAs/patient X patient/hr X
hr/week=mAs/week
kVP: measure of the penetrability. Constant
operation assumed; 100 for general and 30 for
mammography
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27. Computation of X-ray Imaging Shielding
Requirements
Use factor( U) :It is the fraction of time that the beam is directed at a particular barrier.
floor and ceiling:1 and wall :1/4
Occupancy factor(T): Amount of time that the area will be occupied .
T=1 means that the area will be occupied by the same individuals throughout the full workday.
Distance (d)
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29. Example Shielding Calculation
Shielding thickness charts found in NCRP Report No. 147, which display the required shielding
thicknesses for the various barriers as a function of N × T/(P × d2),
where,
N is the number of patients per week,
T is the occupancy factor
P is the shielding design goal in mGy/wk, and
d is the distance in meters from the radiation source to the point to be protected.
In abbreviated notation, this is NT/Pd2.
Charts, which assume specific normalized workloads per patient (Wnorm)
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32. Example Shielding Calculation
For the chest bucky
wall primary
radiation barrier
with T = 0.2, P =
0.02 mGy/wk,
and d = 2.4 m,
NT/Pd2 = 120 ×
0.2/(0.02 × 2.42) =
208 and,
the lead thickness
required is about
1.3 mm to achieve
the shielding
design goal
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33. Example Shielding Calculation
Example Barrier Calculation for a CT Scanner
For a CT scanner, all walls in the room are secondary barriers, because the detector array within the
gantry is the primary radiation barrier.
Three methods can be used to determine the shielding requirements
based upon CTDIvol,
based upon typical dose length product (DLP) values per acquisition, and
based on the measured scatter distribution isodose maps provided by the manufacturer.
10/4/2023 33
34. Example Shielding Calculation
Example Barrier Calculation for a CT Scanner
produces a scatter air kerma of 63.8 mGy/wk at 1 m from
the gantry isocenter.
barrier that is 3.3 m from the gantry isocenter
to an uncontrolled corridor with P = 0.02 mGy/wk
occupancy factor T = 0.2
reduce the radiation to a level less than P/T = 0.02/0.2 =
0.1 mGy/wk.
At 3.3 m, the unshielded air kerma is 63.8/3.32 = 5.86
mGy/wk, and
transmission factor,B through the lead must therefore
be less than 0.1/5.86 = 0.017
Consulting Figure 21-15, this transmission factor
requires a minimum of 1.0 mm lead. 10/4/2023 34
35. 10/4/2023 35
Secondary (scatter and leakage) radiation distributions for a 32-cm-diameter PMMA phantom, 40-
mm collimation, 64-channel MDCT, 140 kV, 100 mA, 1 s scan. Actual secondary radiation levels must
be scaled to the techniques used for the acquisition. A.Horizontal isodose scatter distribution at the
height of the isocenter. B.Elevational isodose scatter distribution; the distribution is vertically
symmetric above and below the level of the table.
36. APPLICATION OF INDIVIDUAL DOSE LIMTS
A limit should be applied to the dose (other than from medical exposure and background radiation)
received by an individual as the result of all practices to which he/she is exposed.
Doses should not exceed specific values called “individual dose limits”.
These dose limits are established in order to keep away from the “maximum risk level” so that no
individual is exposed to a radiation that is judged to be unacceptable in any normal circumstance.
The ICRP recommends that the last principle, limitation of maximal doses, not apply to medical exposure
of patients or emergency situations.
However, the other two principles do apply to medical exposure of patients and emergency situations.
37. 10/4/2023 37
Diagnostic Radiology Physics: a Handbook for Teachers and Students – chapter 24, 37
Recommended dose limits in planned exposure situationsa (ICRP 103, 2007)
Type of limit Occupational Public
Effective dose 20 mSv per year, averaged over
defined periods of 5 yearse
1 mSv in a yearf
Annual equivalent dose in:
Lens of the eyeb 20 mSv 15 mSv
Skinc,d 500 mSv 50 mSv
Hands and feet 500 mSv –
b this limit is a 2011 ICRP recommendation
c The limitation on effective dose provides sufficient protection for the skin against stochastic effects
d Averaged over 1 cm2 area of skin regardless of the area exposed
e With the further provision that the effective dose should not exceed 50 mSv in any single year Additional restrictions apply to
the occupational exposure of pregnant women
f In special circumstances, a higher value of effective dose could be allowed in a single year, provided that the average over 5
years does not exceed 1 mSv per year
•The BSS also adds stronger restrictions on occupational doses for “apprentices” and “students” aged 16 to 18 –
namely dose limits of an: effective dose of 6 mSv in a year
equivalent dose to the lens of the eye of 20 mSv in a year
equivalent dose to the extremities or the skin of 150 mSv in a year
These stronger dose limits would apply, for example, to any 16-18 year old
student radiographers
38. RADIATION EXPOSURE IN PREGNANCY
MEDICAL EXPOSURES
Special consideration should be given to pregnant women because different types of biological effects
are associated with irradiation of the unborn child
As a basic rule it is recommended that radiological procedures of the woman likely to be pregnant should
be avoided unless there are strong clinical indications
There should be signs in the waiting area, cubicles and other appropriate places requesting a woman to
notify the staff if she is or thinks she is pregnant
For radiological procedures which could lead to a significant dose to an embryo or foetus, there should be
systems in place to ascertain pregnancy status
39. FETAL RADIATION RISK
There are radiation-related risks throughout pregnancy which are related to the
stage of pregnancy
absorbed dose
Radiation risks are most significant during organogenesis and in the early fetal period somewhat
less in the 2nd trimester and least in the third trimester
40
Less Least
Most
risk
40. RADIATION EXPOSURE IN PREGNANCY
If, after consultation between the referring medical practitioner and the radiologist, it is not possible to substitute a
lower dose or non-radiation examination, or to postpone the examination, then the examination should be
performed
Even then, the process of optimization of protection needs to also consider protection of the embryo/foetus
Foetal doses from radiological procedures vary enormously, but clearly are higher when the examination includes
the pelvic region
At the higher end, for example, routine diagnostic CT- examinations of the pelvic region with and without contrast
injection can lead to a foetal absorbed dose of about 50 mGy
The use of a low-dose CT protocol and reducing the scanning area to a minimum would lower the foetal dose
41. RADIATION EXPOSURE IN PREGNANCY
If a foetal dose is suspected to be high (e.g. >10 mGy) it should be carefully determined by a medical physicist and
the pregnant woman should be informed about the possible risks
It is, however, generally considered that for a foetal dose <100 mGy, as in most diagnostic procedures, termination
of pregnancy is not justified from the point of radiation risks
A fetal dose of 100 mGy has a small individual risk of radiation-induced cancer. There is over a 99% chance that the
exposed fetus will NOT develop childhood cancer or leukaemia
At fetal doses in excess of 100 mGy, there can be fetal damage, the magnitude and type of which is a function of
dose and stage of pregnancy
High fetal doses (100-1000 mGy) during late pregnancy are not likely to result in malformations or birth defects
since all the organs have been formed.
42. OCCUPATIONAL EXPOSURE IN PREGNANCY
A female worker should, on becoming aware that she is pregnant, notify the employer in order that
her working conditions may be modified if necessary
The employer shall adapt the working conditions in respect of occupational exposure so as to ensure
that the embryo or foetus is afforded the same broad level of protection as required for members of
the public, that is, the dose to the embryo or foetus should not normally exceed 1 mSv
In general, in diagnostic radiology it will be safe to assume that provided the dose to the employee’s
abdomen is less than 2 mSv, then the doses to the foetus will be lower than 1 mSv
43. Diagnostic reference level
A Diagnostic Reference Level (DRL), is defined by the (ICRP) as: a form of investigation level, applied to an
easily measured quantity, usually the absorbed dose in air, or tissue-equivalent material at the surface of a
simple phantom or a representative patient.
The ICRP recommends the establishment of diagnostic reference levels as a tool for optimizing the radiation
dose delivered to patients in the course of diagnostic and/or therapeutic procedures.
Used for optimisation of medical exposure, not for public and occupational exposure, Not to individual, a
level set for standard procédure , standard sized patient, or phantom.
Does not demarcate between good and bad practice, established for frequent and dose intensive procedures
44. Diagnostic reference level
Main aim to avoid unnecessary dose not contributing clinical task by comparing Established levels with
observed values.
The purpose is advisory (not for regulatory or commercial purposes, and not linked to limits or
constraints)
a form of investigation level ( quality assurance) to identify unusually high levels, which calls for local
review if consistently exceeded.
Values BELOW DRLs may need optimization if the image quality is inadequate for clinical purposes.
Values ABOVE DRLs require an investigation and optimization of X Ray system or protocols.
47. X-ray Image Receptors
Screen-film radiographic image receptors, now obsolete, had an inherent safety feature, but DR
international exposure index standard for digital radiography is implemented
This standard requires the imaging device vendor to estimate the radiation dose incident on the detector for a
given exam (e.g., chest, abdomen, extremity) as an Exposure Index, EI, and to compare it to an accepted
target Exposure Index, EIT, for that same exam.
For immediate feedback to the technologist, a Deviation Index, DI, is generated as: DI = 10 log[EI/EIT]
Acceptable DI values should be within –3.0 (underexposure of 50%) to +3.0 (overexposure of 100%).
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48. The following is a list of measures to be taken during a procedure to protect the patient:
Increase SOD
Select the lowest acceptable dose mode and fluoro pulse rate.
Select the lowest acceptable digital magnification setting
Remove the anti-scatter grid for small patients, for small body parts, and when the image receptor is far from the
patient.
Decrease OID.
Collimate the x-ray beam aggressively. Use “virtual collimation,” which requires no radiation, to adjust the
collimator.
Minimize beam-on time. The operator should only activate fluoroscopy to see motion. Use last-image-hold
feature.
Minimize image recording. In cine and DSA, limit the number of imaging acquisition runs, duration of runs, and
frame rate. Use fluoro-store as a low dose alternative when you can tolerate the increased random noise.
10/4/2023 49
Fluoroscopy and Intervention
49. The following is a list of measures to be taken during a procedure to protect the patient:
Be aware that steeper beam angles increase the dose, due to the greater thickness of the body along the
x-ray beam axis. Implement precautions to ensure, in steep oblique and lateral projections, that the
patient's arm is not accidentally in the x-ray beam. Having an arm in the beam has been a contributing
factor for some terrible tissue injuries
Use more than one beam angle (“dose spreading”) if the dose to an area on the skin is approaching an
amount that may cause injury.
Assign a staff member to notify the operator when specified dose metric thresholds are reached. For the
metric reference point air kerma (Ka,r), recommended notification values are 3 Gy and every Gy
thereafter (NCRP, 2010a)
If the procedure uses a biplane fluoroscopy system (two x-ray tubes and two image receptors), the
notifications should be performed for both systems.
10/4/2023 50
Fluoroscopy and Intervention
50. The following is a list of actions to be taken by staff to protect themselves:
Wear appropriate radiation protective apparel.
scatter intensity is much higher on the x-ray tube side of the patient.
Increase distance from where the x-ray beam intercepts the patient
Support staff in the room should stand well back from the patient whenever they can.
Use appropriate shielding
Staff should keep their hands out of the primary x-ray beam, unless absolutely necessary.
Wear dosimeters correctly.
10/4/2023 51
Fluoroscopy and Intervention
64. 10/4/2023 65
Summary of Operational Factors That Affect Image
Quality and Radiation Dose to the Patient and Staff
65. Dose Optimization in CT
Reduce unnecessary phases.
Thin slice, dose and resolution
Tissues with inherently high tissue contrast may be
acquired at low dose without loss of diagnostic value.
These include lung and bone, CT-KUB Calculi, Lung
nodule F/U.
A kV of 140 could be selected for the most obese
patients. Create separate abdominal protocols for obese
patients.
Reduced kV can also be employed, (80, 100 kvp)
Scan only the z-axis length you need.
When possible, avoid radiation directly to the eyes.
Vary tube current according to contrast phase. You may
be able to use a lower mA for non-contrast phases.
Use iterative reconstruction, if available.
Use automatic tube current modulation, if available.
Create low-dose protocols
Compare these dose indices from individual scan
protocols with DRLs and achievable doses.
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66. Dose Optimization in CT
For cardiac CT protocols, substantial dose reduction can be achieved by the following strategies:
Minimize the scan range.
Use heart rate reduction.
Prospective triggering results in lower dose than does retrospective gating.
If using retrospective gating, employ ECG-gated mA modulation.
Reduce tube voltage whenever possible to 100 kV or even 80 kV.
10/4/2023 67
67. Dose Optimization in CT
The AAPM has recommended that the notification level be set higher than the relevant diagnostic
reference level so that notifications are issued only for doses that are “higher than usual,” thereby
warning the technologist that an acquisition parameter may be set incorrectly.
The notification values recommended by AAPM are shown below (AAPM, 2011b).
10/4/2023 68
68. Radiation Protection in Nuclear Medicine
The most effective method for reducing dose in nuclear medicine diagnostic procedures is to use
radionuclides with short half-lives.
A spectacular success in this area was the replacement of 131 I with its half-life of 8.1 days by
123I with a half-life of 13 hrs or 99mTc with half-life 6hrs.
131I was the only radionuclide used for thyroid function studies prior to 1960.
In 1989 only 8% thyroid scans use 131I, the remainder being divided equally betweenn the 2 short
lived radionuclides.
The thyroid dose 650mSv from 2Mbq of 131 I was reduced to 39 mSv with the use of 10 MBq of
123 I and 2.6mSv with the us of 75MBq of 99m TC .
Handling the radionuclide with care and without direct handling with hand.
73. Patient protection
Cardinal principles
Technique selection
Filtration
Projection
Image receptor
Collimation
Shielding
Immobilization
Equipment
Public protection
Information boards
Restricted entry inside radiation area
Regular radiation survey
X-ray room design
Radiation warning lamps and signs
Professional Protection
Patient protection
Cardinal principles
Use protective apparels
Minimum fluoroscopy time
Never hold patients
Personnel monitoring
ALARA
74. Conclusion
As a radiology technologist we should;
Always justify benefit to risk ratio while performing study
Optimize the facilities and factors to reduce dose
Apply ALARA principle i.e. time , distance and shielding.
We should provide ;
Shielding materials like lead apron
Provide protection to attender
Always try to take in one attempt
Use proper technical factor.
76. References
Bushberg J. The essential physics of medical imaging. 3rd ed. Philadelphia, PA: Wolters Kluwer / Lippincott Williams &
Wilkins; 2012.
Bushong S. Radiologic science for technologists : physics, biology, and protection. 11th ed. Elsevier Health Sciences;
2016.
Kelsey C. Radiation biology of medical imaging. Hoboken, NJ: Wiley Blackwell; 2014.
Hall. Radiobiology for the Radiologist. 8th ed Wolters Kluwer; 2019.
Forshier S. Essentials of radiation biology and protection. 2nd ed Clifton Park, NY: Delmar; 2009.
ICRP 73. Radiological Protection and Safety in Medicine. Annals of the ICRP, 26(2), 1996.
Radiation Protection 118. Referral Guidelines for Imaging, European Commission, 2008.
ACR Practice guideline for imaging pregnant or potentially pregnant adolescents and women with ionizing radiation.
ACR Practice guideline for Diagnostic Reference Levels and achievable doses in medical x-ray imaging.
Radiation shielding for diagnostic X Rays. BIR report (2000) Ed. D.G. Sutton & J.R. Williams
NCRP Measurements, Report No. 147, “Structural Shielding Design for Medical X-Ray Imaging Facilities” Bethesda,
MD 2004 10/4/2023 77
The
Commission’s dose limits and dose constraints are not recommended for individual
patients because they may reduce the effectiveness of the patient’s diagnosis or treatment,
thereby doing more harm than good. The emphasis is therefore on the justification
of the medical procedures and on the optimisation of protection and, for
diagnostic procedures, the use of diagnostic reference levels (see Chapter 7).
Exposures of comforters and carers, and exposures of volunteers in research, are discussed in Chapter 7.
Optimization means that minimum risk and maximum benefit should be achieved.
Optimization means that doses should be ‘As Low As Reasonably Achievable’ (ALARA).
ALARA is the responsibility of all employees.
(Fernandes et al., 2016)
(Fernandes et al., 2016)
Exposure=exposure rate x exposure time
The majority of nuclear medicine technologist's annual wholebody radiation dose is received during patient imaging
The maximum energy of x-rays from machines used for diagnostic and interventional imaging typically does not exceed ~140 keV and the average energy of the x-ray spectrum is much less. The annihilation photons used in PET have energies of 511 keV and require
Shielding design goals are stated in terms of K (mGy) at a reference point beyond a protective barrier (e.g., 0.3 m for a wall, a conservative assumption of the distance of closest approach).
0.3 m
0.3 m
Weekly exposure at a point can be calculated as
E = E’ WUT/d2
a Limits on effective dose are for the sum of the relevant effective doses from external exposure in the
specified time period and the committed effective dose from intakes of radionuclides in the same period
For adults, the committed effective dose is computed for a 50-year period after intake, whereas
for children it is computed for the period up to age 70 years
In terms of quantum mottle and noise digital flat-panel detectors have higher detection efficiencies, equivalent to 400- to 600-speed screen film receptors
while CR (PSP) detectors are equivalent to a 200-speed receptor due to lower detective quantum efficiency.
For compensation and equivalent image noise, technique factors for CR receptors are typically two times higher than corresponding TFT flat-panel detectors.