Performance Measurement Methodology Dr. Mohammed Alahmed [email protected] Dr. Mohammed Alahmed 1.
Dr. Mohammed Alnafea [email protected] RADIATION PROTECTION IN NUCLEAR MEDICINE.
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Transcript of Dr. Mohammed Alnafea [email protected] RADIATION PROTECTION IN NUCLEAR MEDICINE.
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Dr. Mohammed AlnafeaDr. Mohammed [email protected]@ksu.edu.sa
RADIATION PROTECTION IN NUCLEAR MEDICINE
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Outline Outline Introduction to Radiation SafetySocietal Benefits of RadiationSources of RadiationOccupational Risks Protection MethodsPersonal Dosimetry Instrumentation Demonstration
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A Typical Radiation A Typical Radiation SituationSituation
Firstly there is a source of radiation, secondly a radiation beam and thirdly some material which absorbs the radiation. So the quantities which can be measured are associated with the source, the radiation beam and the absorber.
6th lecture RAD 3113
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4
Radiation Exposure, Dose and Quantity
Exposure is an index of the ability of a radiation field to ionize air.
Dose is a measure of the energy imparted to matter, per unit mass, when an ionizing radiation field interacts with matter.
Quantity of radioactive material is expressed as “activity”, the number of nuclear disintegrations that occur in a sample per second.
6th lecture RAD 311
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The Inverse Square LawThe Inverse Square Law
what happens as we move our absorber away from the radiation source. In other words think about the influence of distance on the intensity of the radiation beam. You will find that a useful result emerges from this that has a very important impact on radiation safety.
The radiation produced in a radioactive source is emitted in all directions. We can consider that spheres of equal radiation intensity exist around the source with the number of photons/particles spreading out as we move away from the source.
6th lecture RAD 3115
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The Inverse Square LawThe Inverse Square Law
Consider an area on the surface of one of these spheres and assume that there are a certain number of photons/particles passing though it. If we now consider a sphere at a greater distance from the source the same number of photons/particles will now be spread out over a bigger area.
Following this line of thought it is easy to appreciate that the radiation intensity, I will decrease with the square of the distance, r from the source, i.e.
I I 1/r 1/r22
6th lecture RAD 3116
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Types of Ionizing Radiation
Alpha (heavy ion, damaging, not penetrating).
Beta (electron, medium damage, little penetration)
Gamma (photon, less damage, penetrating)
X-ray (photon, less damage, penetrating)
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Ionizing Radiation’s Interaction With Human
Tissue May cause free radicals - Indirect Effects
(self-repair mechanism)
May cause DNA damage - Direct Effects (self-repair mechanism)
Hence, a threshold effect??
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Sources of Ionizing Radiationto General Public
Natural (82%)Radon ( 55 %)Cosmic ( 8 %)Terrestrial ( 8 %)Internal ( 11 %)
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Sources of Radiation Artificial (18%)
x-ray ( 11 %)nuclear medicine ( 4 %)consumer products ( 3 %)nuclear power ( <1 %)fallout ( <1 %)
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Occupational Exposure Limits(Whole Body)
“Trained” Radiation Worker 5 rem Pregnant Radiation Worker 0.5 rem
General Public 0.1 rem
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What is a rem ???
A rem is a unit of measurement A rem is a unit of measurement for radiation delivered to human for radiation delivered to human
tissuetissue
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What level of radiation is safe ??
Consensus of Scientific Opinion:5 rem annual exposure to an adult
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Acute Radiation Dose Effects 450 rem LD 50/60 200 rem Hemopoietic Syndrome 100 rem Acute Radiation Syndrome 50 rem 1st identifiable sign of
effects 5 rem Yearly dose limit for
Radiation Worker. 0.5 rem Gestation dose limit
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However, the concept of ALARA must also be
implemented
What is ALARA?
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ALARA As Low As Reasonable Achievable
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ALARA for External Radiation
ProtectionMinimize Time in Radiation Field
Maximize Distance from Radiation Source
Use of Shielding
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Examples of External Radiation
Diagnostic X-rayDiagnostic Nuclear MedicineTherapeutic Nuclear Medicine Radiotracer uses in Research
(e.g., C-14, H-3, P-32, S-35, P-33, I-125)
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ALARA for Internal Radiation
Protection
Use of protective clothing Spill preventionUse of fume hoodsRespiratory protection if neededEngineering controls if neededMonitor for loose contaminationNo eating, drinking, smoking in laboratory
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Early Protective Suit•Lead glasses
•Filters
•Tube shielding
•Early personal “dosemeters”
•etc.
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Examples of Internal Radiation
ResearchAccidental Intake (Ingestion, Inhalation)
Nuclear MedicineAccidental intake Misadministration
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Spill ResponseSpill Response
6th lecture RAD 31122
On Skin—flush completely.
On Clothing—remove.
If Injury—administer first aid.
Radioactive Gas Release—vacate area, shut off fans, post warning.
Monitor all persons and define the area of Monitor all persons and define the area of contaminationcontamination
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Basic Principals of Radiation Basic Principals of Radiation ProtectionProtection
JustificationBenefit > risk
OptimisationDoses as low as reasonably achievable
LimitationAbsolute legal limits for staff and publicReference levels as guidance for patients.
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ALARAALARA
As Low As Reasonably Achievablemeans making every reasonable effort to
maintain exposures to radiation as far below the dose limits as is practicable.
How?How?Time, Distance and Shielding
Reduce time exposedIncrease distance from sourceUse shielding between you and the source
Minimize internal contaminationPlan work
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RadiationRadiation ProtectionProtection
6th lecture RAD 31125
Decrease Decrease TimeTime
Increase Increase DistanceDistance
Increase Increase ShieldingShielding
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6th lecture RAD 31126
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Basic Principles
Time
Distance
Shielding
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6th lecture RAD 31128
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Distance
•Double distance = 1/4 dose
•Triple distance = 1/9th dose.
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6th lecture RAD 31130
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6th lecture RAD 31131
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6th lecture RAD 31132
2
20
0 r
rII
2
20
0 r
rDD
The radiated energy can be considered to be spread over a sphere of area 4r2 at any distance r from the source. Since the radiation intensity is equal to the energy per unit area :
If the radiation intensity is I0 at a distance r0 from the source, the intensity I at any other distance r will be given by :
Since the radiation dose is proportional to the intensity, the dose D can be calculated by the same type of relationship :
24Energy
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6th lecture RAD 31133
Radiation ProtectionRadiation ProtectionReducing Radiation ExposureReducing Radiation Exposure
DistanceMaintain maximal practical distance from radiation source
To Limit Care giver Dose to 5 rem
Distance Rate Stay time
1 ft 12.5 R/hr 24 min
2 ft 3.1 R/hr 1.6 hr
5 ft 0.5 R/hr 10 hr
8 ft 0.2 R/hr 25 hr
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Shielding
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Shielding
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Lead Apron StorageLead Apron Storage
Always return to hangerDo not
folddump on floor and run
trolleys over the top of them!!!
X-ray will check annuallyBut if visibly damaged,
ask X-ray to check them.
366th lecture RAD 311
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6th lecture RAD 31137
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6th lecture RAD 31138
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Detecting and Measuring Detecting and Measuring RadiationRadiation
6th lecture RAD 31139
InstrumentsInstrumentsLocate contamination - GM Survey Meter Locate contamination - GM Survey Meter
(Geiger counter)(Geiger counter)Measure exposure rate - Ion ChamberMeasure exposure rate - Ion Chamber
Personal Dosimeters - measure doses to staffPersonal Dosimeters - measure doses to staffRadiation Badge - Film/TLDRadiation Badge - Film/TLDSelf reading dosimeter (analog & digital)Self reading dosimeter (analog & digital)
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6th lecture RAD 31140
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6th lecture RAD 31141
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6th lecture RAD 31142
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Measurement of Radiation Exposure ReceivedPersonnel Monitoring Device - External
Sources of RadiationBioassay - Internal Radiation)
blood sampleurine samplethyroid monitoring
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My time is up!
Any questions ??
446th lecture RAD 311