DOSIMETRY FOR MEDICAL APPLICATION OF IONIZING RADIATIONS: Calibration requirements and clinical applications
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Olivera Ciraj-Bjelac, Milojko Kovacevic, Danijela Arandjic, Djordje Lazarevic Vinca Institute of Nuclear Sciences Radiation and Environmental Protection Department Laboratory for Radiation Measurements Belgrade, Serbia
[email protected]
Content
Metrology and calibration requirements Clinical application
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Global trends in medical exposures Dosimetric quantities and units Dosimetry in diagnostic radiology
Medical exposure to ionizing radiation
Medical exposure contributes 99% of man-made radiation exposure to humans The concept of risk is used to quantify possible detrimental effects
0.005 0.002
0.002
0.005
mSv Medical
Nuclear weapons Occupational Chernobyl 0.61
Atmospheric nuclear tests
Total dose from man-made sources of radiation> 0.61 mSv
Medical: 0.6 mSv (> 99.97%)
Source: United Nations Scientific Committee for Effect of Atomic Radiation (UNSCEAR), 2010
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Medical exposure to ionizing radiation
The role of dosimetry is to determine the amount of radiation received by a person from the radiological examination
Dose?
Patient dose assessment Establishment of Diagnostic Reference Levels (DRL), optimisation of protection Assessment of x-ray equipment performance Standards of good practice Assessment of radiation detriment
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Dosimetry in diagnostic radiology
Global trend 3,6 billion radiological examinations in the period 1997-2007 Significant increase of CT practice: Examination frequency Dose per examination
Interventional procedures
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Increase of 50% compared to previous decade
Dose to patient
0.02- 0.05 mSv
2 mSv 100CxR
5-20 mSv 400- 1000 CxR
50 chest radiographies= annual natural background radiation dose
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Depends on the examination type Variations for the same type of procedure
Dose for the same examination type varies up to 2 orders of magnitude Increased utilization of high-dose procedures CT Interventional procedures
Effects Increase of probability for stochastic effects, in particular in the case of the repeated examinations Possible radiation injuries in high-dose procedures
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Problems
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Radiation injuries
ICRP 85 10
International Measurements System (IMS) Framework for dosimetry in diagnostic radiology Consistency in radiation dosimetry
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Basic metrology elements
Bureau International des Poids et Mesures (BIPM) National Primary Standard Dosimetry Laboratories (PSDL) Secondary Standards Dosimetry Laboratories (SSDL) Users performing measurements
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International Measurements System (IMS)
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Traceability chain
Dosimeters used to determine doses received by individuals Measurements need to be traceable though an unbroken chain of comparisons to national and international standards Traceability is needed to ensure accuracy and reliability Legal and economic implications
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Metrology and traceability
The prime function: to provide a service in metrology Designated by the competent national authorities SSDL-Secondary standards, calibrated against the primary standards of laboratories participating in the IMS
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Role of the SSDL
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Journal of the ICRU Vol 5 No 2 (2005) Report 74
Dosimetric quantities in units in diagnostic radiology Basic dosimetric quantity: Air kerma Easy to measure
Calibration: Clinical application: Quantities derived from air kerma for different imaging modalities
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Dosimeters calibrated in terms of air kerma
Dosimetric quantities
Quantities for risk assessment Conversion coefficient for tissue and organ dose assessment
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Basic dosimetric quantities Application specific dosimetric quantities
Energy fluence Unit:J/m2
dR da
Kerma Unit:J/kg, Gy
tr dEtr K dm
Absorbed dose Unit:J/kg, Gy
en d D dm
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Basic dosimetric quantities
Basic dosimetric quantities
en tr K D
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Charged-particle equilibrium Absence of bremsstrahlung losses
Application specific dosimetric quantities Symbol
Unit
Equation
Incident air kerma
Ki
Gy
Entrance -surface air kerma
Ke
Gy
Ke Ki B
Air-kerma area product
PKA
Gym2
PKA K (x , y)dxdy A
Air-kerma length product
PKL
X-ray tube output
Y(d)
Gym
PKL Kair (z)dz L
Gy/As
Y (d) Ka (d) / PIt
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Quantity
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Application specific dosimetric quantities: computed tomography
Application specific dosimetric quantities: computed tomography Symbol
Unit
CT air-kerma index Ca,100 (free in air)
Gy
CT air-kerma index (in standard CPMMA, 100 phantom)
Gy
Weighted CT air kerma index Normalized weighted CT air kerma index Air-kerma length product
Cw
Gy
Equation C a ,100
1 T
50
50
1 CW C PMMA,100,c 2C PMMA,100,p 3 CVOL CW
nCw
Gy/As n CVOL
PKL
Gym
K (z)dz
NT C W I p
CVOL PIt
PKL n CVOLj l j PItj j
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Quantity
Quantities describing risk Dose-conversion coefficients for assessment of organ and tissue doses c
dosimetric quantity normalisat ion quantity
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Organ and tissue dose Equivalent dose Effective dose
The Use of Effective Dose (E) E is a risk-related quantity and should only be used in the low-dose range Primary use: Not for: detailed retrospective dose and risk assessments after exposure of individuals epidemiological studies, neither in accidents. In the last cases: organ doses are needed !
ICRP 103, ICRP 105
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to demonstrate compliance with dose limits in regulation, for prospective planning of radioprotection
Effective Dose in Medical Exposure The relevant quantity for planning the exposure of patients and risk-benefit assessments is the equivalent dose or the absorbed dose to irradiated tissues.
E can be of value for comparing doses from different diagnostic procedures similar procedures in different hospitals and countries different technologies for the same medical examination.
ICRP 103, ICRP 105
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The assessment and interpretation of E is very problematic when organs and tissues receive only partial exposure or a very heterogeneous exposure (x-ray diagnostics)
Dosimeters in diagnostic radiology
Ionization chambers
Semiconductor dosimeters Others
Accurate
Compact
TLD
Good energy dependence
Energy dependant
OSL
Design for different application (cylindrical, parallel-plate, different volumes..)
PSDL/SSDL
Film (radiochromic) Scintillation (kVp meters)
user
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Tube voltage 20-150 keV, various A/F combinations, various modalities
IEC 61674: Dosimeters with ionization chambers and/or semi-conductor detectors as used in X-ray diagnostic imaging Diagnostic dosimeter: detector and measuring assembly IEC 60580: Dose area product meters
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Dosimetry standards in diagnostic radiology
User IEC 61674 Ionization chambers Semiconductor detectors SSDL Ionization chamber of reference class
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Requirements for dosemeters
Air kerma: Radiography and mammography Kerma-length product Dosimeters in CT Kerma-area product Radiography and fluoroscopy PPV: kVp meters Frequency: according to national regulations
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Calibrations in diagnostic radiology
Calibration in diagnostic radiology
Calibrated Quality control Traceability for all beam qualities
Auxiliary equipment: electrometers, thermometers, barometers… Environmental conditions
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SSDL with relevant measurement capabilities General requirements: beam qualities, tube voltage and filtration measurements Dosimeter of reference class (with electrometer)
Dosimetry
Radiation source
Ionization chambers Position system HV supply for monitor and reference class ionization chamber Electrometer
X-ray generator, 50-150 kVp, 20-40 kVp Ripple less than 10% for radiography and less than 4% for mammography Beam qualities according IEC 61267 “Shutter” mechanism Filters and attenuators Tube voltage meter (ppv, ±1.5%)
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Equipment
Reference class dosemeter Range tube voltage (kV)
Intrinsic uncertainty (k=2)
Maximum variation of response (%)
Unattenuated beam
General radiography
cylindrical or plane parallel
60-150
3.2
±2.6
Fluoroscopy
cylindrical or plane parallel
50-100
3.2
±2.6
Mammography
plane parallel
22-40
3.2
±2.6
10 μGy/s10 mGy/s
CT
cylindrical
100-150
3.2
±2.6
0.1 mGy/s50 mGy/s
Dental radiography
cylindrical or plane parallel
50-90
3.2
±2.6
1 μGy/s10 mGy/s
1 mGy/s500 mGy/s
Attenuated beam
10 μGy/s5 mGy/s
0.1 μGy/s100 μGy/s
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Application
Type of chamber
Range of air kerma rate
Spectrum X-ray beam quality: First half-value layer (HVL1) Second half-value layer (HVL2) Homogeneity coefficient: h
Tube voltage Total filtration
HVL1 HVL2
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Specification of the x-ray beam
Radiation quality
RQR
Radiation origin Unfiltered beam emerging from x-ray assembly
Phantom material
No phantom
Application General radiography, fluoroscopy, dental radiology Measurements behind the patient (on the image intensifier)
RQA
Radiation beam from Aluminium an added filter
RQT
Radiation beam from Copper an added filter
CT applications (free in air)
RQR-M
Unfiltered beam emerging from x-ray assembly
Mammography (free in air)
RQA-M
Radiation beam from Aluminium an added filter
No phantom
Measurements behind the patient
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Radiation beam qualities (IEC 61267)
Typical calibration set up Apertures
Focal spot
Test point
Shutter
Additional filtration
Monitor chamber
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X-ray tube window
Procedures before calibration (acclimatization, positioning, stabilization…) Calibration procedures (methods, number of measurements, interval between measurements…corrections… Procedures following calibration (uncertainty budget, certificate…)
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Calibration procedures
Dosimetry formalism Air kerma:
K M Q M 0 N K ,Q0
Reference conditions: set of influencing quantities K M Q M 0 N K ,Q0 ki
Influencing condition: quantities that are not subject of mesusremst but have an impact on the result P 273.15 T Air density correction: kTP 0 P 273.15 T0 Beam quality correction: K Q M Q N K ,Q0 kQ ,Qo
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i
Calibrations of dosemeters for CT
Information on chamber response only Size on active volume only assumed Far from real situation
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Traditionally, irradiation of the whole volume Contras:
Calibration for CT: air kerma length product Cylindrical chamber, 100 mm Non-uniform irradiation Uniform response RQT 9 (120 kVp, HVL: 8.5 mm Al)
Focal spot
Aperture
Monitor chamber
Ionization chamber
w da dr
N PKL ,Q K w / M
dr da
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Calibration for fluoroscopy: air kerma area product N PKA ,Q
M KAP
Ref. chamber
Film
10 cm
Cekerevac at al, Poster B3
10 cm
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In laboratory (SSDL) Field calibration
M ref N Kref,Qo kQ Anom
Calibration in terms of practical peak voltage X-ray tube voltage measurements Practical Peak Voltage (ppv):
Invasive or non-invasive measurements Voltage divider
Uˆ
pU U wW i 1 n
i
i
i
pU wU i 1
i
i
Property of the whole exposure cycle Related to image contrast
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n
Uncertainty budget Uncertainty of the reference standard Uncertainty of user’s instrument Uncertainty due to calibration set up Uncertainty of the evaluation procedure Vinca Institute of Nuclear Sciences Radiation and Environmental Protection Laboratory www.vinca.rs
Air kerma: ± 2.7 % Air kerma length product: ± 3.0 % Air kerma area product: ± 15 % Non-invasive tube voltage measuring devices: 2.5 %
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Uncertainty budget
Goal: minimal uncertainty Assurance and control of traceability Quality manual: technical details, methods, traceability, uncertainty budget, QC, safety…. Continuous improvements and reviews External peer review/audit
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Quality Management System
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Patient dose assessment
Clinical dosimetry
Output of the X-ray tube, scaled for exposure and geometry
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Direct measurement on patients or phantoms Indirect measurements on patients or phantoms
Quantities a) incident air kerma, entrance surface air kerma and kermaarea product (radiography); b) kerma-area product and entrance surface air kerma rate (fluoroscopy); c) incident and entrance surface air kerma (mammography); and d) kerma-length product (computed tomography)
KAP
BSF
Ke
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Dosimetric quantites
Patient Real situation
Phantoms Objects that simulate real patients in terms of interaction of radiation with matter Easy to perform Standardized
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Patients and phantoms
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Radiography
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Fluoroscopy
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Mammography
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Computed tomography
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Patient dose levels
Uncertainty of clinical dose assessment Use of k=2 for expression of uncertainty of dose assessment Typically >10% and close to 25%*
*if correction for beam quality and for individual patient is not applied
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Radiographers taking the x-ray images Determining tube output Calculation of individual patient doses Determining dose to an average patient
Form measurements towards risk assessment Conversion of measured quantity into organ doses and effective dose Ratio of the dose to a specified tissue or effective dose divided by the normalization quantity Measured using phantoms or calculated using computer models Voxel phantoms based on images of human anatomy
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Conversion coefficients
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Organ dose assesment
ICRU 74 Vinca Institute of Nuclear Sciences Radiation and Environmental Protection Laboratory www.vinca.rs
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Optimization of protection
Application of DRLs
DRLs will be intended for use as a convenient test for identifying situations where the levels of patient dose are unusually high. Quantities that are easily measured!
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Values of measured quantities above which some specified action or decision should be taken Values must be specified Action must be specified
Doses to patients from radiographic and fluoroscopic X-ray imaging procedures in the UK—2005 review. HPA RPD-029, HPA; 2007.
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Diagnostic Reference Levels
Diagnostic radiology is major contribution to total dose from man-made sources of radiation Dose measurements: population dose assessment, optimization of practice Application-specific dosimetric quantities (patients, phantoms) Calibration of dosimeters in the conditions that are similar to the clinical environment, in terms of air kerma kerma-area product kerma-length product
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Re-cap
Olivera Ciraj-Bjelac, PhD, research associate, dosimetry and radiation physics Milojko Kovacevic, MSc, Head of MDL, radiation physicist Danijela Arandjic, MSc, PhD student, dosimetry and radiation physics Djordje Lazarevic, MSc, PhD student, dosimetry and radiation physics Dragana Divnic, technician Milos Jovanovic, technician Nikola Blagojevic , technician
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