IAEA International Atomic Energy Agency Assessment of External and Internal Exposures Michael Hajek...

IAEAInternational Atomic Energy Agency

Assessment of External and Internal Exposures

Michael HajekRadiation Safety and Monitoring Section

Division of Radiation, Transport and Waste Safety

Department of Nuclear Safety and Security

IAEA

Radiation Safety Technical Services Mandate

• Apply safety standards to own operations and operations under IAEA control or supervision

IAEA Statute as amended up to 23 February 1989, Art. III.A.6.

• Responsible for radiation protection and safety of staff members, experts, trainees, visitors and other persons, who may be exposed to ionizing radiation during these operations (Articles III.A.6; XI.F.2 and XII.2)

IAEA Statute as amended up to 23 February 1989, Arts XI.F.2 and XII.A.2.

• Assess occupational exposure from external sources of radiation and due to intakes of radionuclides

Radiation Safety Technical Services 2

IAEA

Process of Individual Monitoring

Working conditions

Characteristicsof the workplace

Characteristics of the activities

Characteristicsof the source

Selection of the workers to be monitored

Selection of the monitoring techniques

Selection of the monitoring frequency

Management approval

Established conditions

Facilities Equipment Staff BudgetQuality

Management System

Calibration

Organization of the monitoring programme

Monitoring

Assessment of the intakes and doses


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Data Management Procedures

Monitored quantitiesSignal measured

Operational quantitiesHp(d) or intake

Protection quantitiesEffective dose

Results reported to DiCh, RPOs and staff members

Related by calibrationand calculation

Related by calculation

All results kept in the Individual Monitoring

Services Group (IMSG)


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Quantities Used for Reporting

• Measurement results will be recorded and, if appropriate, reported in terms of

Hp(d) … Personal dose equivalent [mSv]

A … Activity [Bq]

I … Intake [Bq]

HE … Committed effective dose [mSv]

E … Effective dose [mSv]


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External Dosimetry

• Whole-body thermoluminescence dosimeters (TLDs)− Labelled with wearer’s name and sealed in plastic bag− 8814 beta/gamma/neutron (BGN) dosimeter holder with appropriate filtration,

containing 4 LiF:Mg,Ti TLDs encapsulated between Teflon sheets on durable aluminium card substrate

− 8806 albedo gamma/neutron (GN) dosimeter holder with appropriate filtration, containing 4 LiF:Mg,Ti TLDs encapsulated between Teflon sheets on durable aluminium card substrate

• Extremity thermoluminescence dosimeters (DXT-RAD)− Adjustable finger ring carrying TLD pellet bonded to Kapton® film

• Whole-body electronic personal dosimeters (EPDs)


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Whole-Body TLD Configuration

BGN type GN type


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Whole-Body TLD Specifications

• Detector: LiF:Mg,Ti

• Measurement quantities: Hp(10) and Hp(0.07)

• Energy range:− Photons: 33 keV to 1,250 keV and 6.6 MeV− Beta: 230 keV (Pm) to 2.2 MeV (Sr)− Neutrons: Thermal to 5 MeV

• Dose range: 0.05 mSv to 10 Sv


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Extremity TLD Configuration

Disk dosimeterwith circular barcode

TLD pellets

TLD pellets


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TLD Readers

Harshaw 6600plus Harshaw 5500


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Whole-Body EPD Specifications

• Detector: 3 silicon diodes

• Measurement quantities: Hp(10) and Hp(0.07)

• Energy range:− Photons: 33 keV (N-40) to 1,250 keV (S-Co) and 6.6 MeV (R-F)− Beta: 230 keV (Pm) to 2.2 MeV (Sr)

• Dose range: 0.001 mSv to 10 Sv

• Neutron EPDs available upon request


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Internal Dosimetry

• Direct monitoring (in vivo)− Whole body− Organs (lungs, liver, thyroid, …)

• Indirect monitoring (in vitro)− Biological samples (urine, faeces, nails, …)− Physical samples


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Whole-Body Counting Laboratory

• Equipment:− Broad-energy Germanium detectors− Canberra DSA 1000 multichannel analyser

• Low energy range: 5 keV to 300 keV

• High energy range: 15 keV to 2 MeV


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Urine Analysis Laboratory

• Gamma spectrometry for photon emitters− Equipment: High-purity and broad-energy Germanium detectors− Energy range: 10 keV to 2 MeV

• Alpha spectrometry for alpha emitters− Equipment: Alpha Analyst with PIPS detectors− Energy range: 2 to 8 MeV

• Liquid scintillation counting for beta emitters− Equipment: Tri-Carb 3170 TR/SL− Energy range: 0 to 18.6 keV


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Accredited Methods

• Individual monitoring− External dosimetry by means of active personal

dosimeters, TLD (γ, β, n) and extremity (β)− Internal Dosimetry by means of WBC for torso

and lungs (trans-U), UAL for α, β and γ emitters

• Workplace monitoring− Dose rate, surface contamination, Pu in air and

waste, leakage test of sources


IAEA International Atomic Energy Agency Assessment of External and Internal Exposures Michael Hajek...

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