The international Working Forum on Regulatory Supervision of Legacy Sites (RSLS) Radiation Monitoring and Protection Services R. Cruz Suaréz and A. Capote-Cuellar Radiation Safety and Monitoring Section Radiation Protection of Workers and Monitoring Unit Division of Radiation, Transport and Waste Safety
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The international Working Forum
on
Regulatory Supervision of Legacy Sites (RSLS)
Radiation Monitoring and Protection
Services
R. Cruz Suaréz and A. Capote-Cuellar Radiation Safety and Monitoring Section Radiation Protection of Workers and Monitoring Unit Division of Radiation, Transport and Waste Safety
IAEA
Agenda
• IAEA Safety Regulations
• IAEA facilities for individual monitoring
• Visit to the laboratories.
IAEA
IAEA Overall Responsibility
• The International Atomic Energy Agency (IAEA) is responsible for the protection of members of staff, individuals under contract, expert consultants, trainees, visitors and any other persons from ionizing radiation arising from activities conducted by the Agency or under its supervision or control.
• In exercising this responsibility, the Agency has a statutory obligation to provide for the application of its safety standards to its own operations
IAEA
• IAEA Statute
• Safety Convention System
• Code of Conduct
• IAEA Standards
• Fundamentals
• Requirements
• Guidance
• Technical Documents
• Radiation Safety Regulation (IAEA RSR)
Organizational Structure and Responsibilities
Regulations
• Procedure and Guideline Manual
Regulatory Framework
http://www-ns.iaea.org/standards/
IAEA RADIATION SAFETY
REGULATION
INTERNATIONAL ATOMIC ENERGY AGENCY
VIENNA, AUSTRIA
AUGUST 2007
PROCEDURES AND GUIDELINES
FOR THE INTERNAL REGULATION
OF RADIATION SAFETY
MANUAL
INTERNATIONAL ATOMIC ENERGY AGENCY
VIENNA, AUSTRIA
AUGUST 2007
IAEA
Radiation Safety Regulations
(IAEA RSR)
• Are a consequence of the IAEA Statute, Article III.
• Are based on the Agency Radiation Safety Standards
• Has been approved by IAEA DG.
• Issued as IAEA Administrative Manual Part X.
• Are effective since October 2007
• Content
• General provisions
• Occupational Exposure
• Public Exposure
• Safety of Sources
• Radiation Emergency Response at Agency Premises
• Protection of Workers Undertaking Interventions
http://oasis.iaea.org/OASIS/OASIS/NS/Documents/RadiationSafetyRegulations.pdf
IAEA RADIATION SAFETY
REGULATION
INTERNATIONAL ATOMIC ENERGY AGENCY
VIENNA, AUSTRIA
AUGUST 2007
IAEA
RADIATION SAFETY AND MONITORING
SECTION (RSM)
RSM Incident and Emergency
Center
Radiation
Protection
Rad.Protection
of Workers
and Monitoring
Rad. Protection
of Patients
-Individual Monitoring
-Workplace Monitoring
- Emergency response
-Harmonization of quantities
-Preparation of Standards-ISOE
-Staff Training
-Health & safety measures
-Quality Management
IAEA
Individual Monitoring Service
Radiation Protection
of Workers
and Monitoring Unit
NATURAL
RADIATION
SOURCES
INDIVIDUAL
MONITORING
SERVICE GROUP
OPERATIONAL
SERVICE
GROUP
EXTERNAL
MONITORING
INTERNAL
MONITORING
WORKPLACE
MONITORING
IAEA
Measurements related to the assessment or
control of exposure to radiation and
radioactive material
Monitoring is more than simply measurement.
It involves interpretation and assessment
Definition of Monitoring
IAEA
Individual Monitoring
• Assessment of external exposure
• Assessment of internal radiation
exposure
• Individual dose assessment
IAEA
10 100 1000
0.0
0.2
0.4
0.6
0.8
1.0 All applications
Hospital
Testing
Isotope
Nuclear power
Sp
ec
tra
l d
istr
ibu
tio
n
(No
rma
lis
ed
to
ma
x=
1)
Photon energy (keV)
Averages
1E-9 1E-8 1E-7 1E-6 1E-5 1E-4 1E-3 0,01 0,1 1 10
0,00
0,05
0,10
0,15
0,20
0,25
0,30
0,35
0,40
E
E /
/
cm
-2E / MeV
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VENUS-F
VENUS-C
BN1
BN2A
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R4-A
Ringh-D
Ringh-N
EXPOSURE PATHWAYS
1E-9 1E-8 1E-7 1E-6 1E-5 1E-4 1E-3 0,01 0,1 1 10
0,00
0,05
0,10
0,15
0,20
0,25
0,30
0,35
0,40
E
E /
/
cm
-2
E / MeV
KKK-cask1
KKK-cask2
KKK-SAR
KKK-TOP
VENUS-F
VENUS-C
BN1
BN2A
BN2B
BN3
R4-L
R4-A
Ringh-D
Ringh-N
IAEA
Working conditions
Characteristics
of the workplace
Characteristics
of the activities
Characteristics
of 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 Budget
Quality
Management
System
Calibration
Organization of the monitoring programme
Monitoring
Assessment of the intakes and doses
THE PROCESS
IAEA
The occupational exposure of any worker shall be restricted so that the following limits be not exceeded:
• An effective dose of 20 mSv per year averaged over five consecutive years,
• An effective dose of 50 mSv in any single year,
• An equivalent dose to the lens of the eye of 150 mSv in a year,
• An equivalent dose to the extremities (hands and feet) or the skin of 500 mSv in a year.
Monitoring- Dose Limits
IAEA
Assessment of Occupational Exposure
The following equation is used for assessment of occupational
exposure and demonstration of compliance with dose limits:
Where,
HP(10) is the personal dose equivalent,
e(g)j, ing is the dose coefficient for ingestion,
Ij,ing is the intake from ingestion,
e(g)j,inh is the dose coefficient for inhalation, and
Ij,inh is the intake from inhalation
j
inh,jinh,jj
ing,jing,jPtI)g(eI)g(e)10(HE
IAEA
Measurement results will be recorded
and, when appropriate, reported in terms of:
Hp(d) - Personal Dose Equivalent (mSv)
A - Activity Measured (Bq) (recorded)
I - Intake (Bq) (recorded)
HE - Committed Effective Dose (mSv) (reported)
E - Effective Dose (mSv)
QUANTITIES
QUANTITIES
IAEA
Individual Monitoring
Services: Dosimeters for
assessment of external
exposure
IAEA
• An 8814 beta/gamma/neutron dosimeter holder with appropriate
filtration containing a 4 TLD-elements rigid aluminum card, to
comprise complete assemblies
• An 8806 neutron (albedo) dosimeter holder with appropriate
filtration containing a 4 TLD-elements rigid aluminum card, to
comprise complete assemblies
• Both card assemblies are labeled with the name of the individual
and sealed in a plastic bag
• TLD chips for extremity monitoring (Finger ring)
• Electronic personal dosimeters
External Dosimetry Laboratory- Dosimeters
IAEA
IAEA
IAEA
Disk dosimeter
with circular barcode
Extremity Dosimeter
dosimeters
dosimeters
IAEA
FACILITIES FOR
ASSESSMENT OF INTAKE
OF RADIONUCLIDES
IAEA
• Direct methods
• Whole Body
• Organs
• Indirect methods
• Biological samples
• Physical samples
Methods of Measurement
IAEA ICAS - BFSI
IAEA
IAEA
IAEA
Quantities and Data Management
Monitored Quantities.
Signal measured.
Operational Quantities.
Hp(d) or Intake
Protection Quantities.
Effective Dose
Related by calibration
and calculation
Related by calculation
All results
kept
in the IMSG
Results reported
to the DIRs, RPO
and staff
IAEA
• Monitoring does not measure directly the
committed effective dose. Biokinetic model
has to be applied
• Interference from other naturally occurring
or artificial radionuclides
• Administration of radiopharmaceuticals.
Interfering Factors
IAEA
Personnel Monitoring Results
• Mandatory Services for external and internal dosimetry
• 600 Safeguards and other 190 staff
• More than 1200 TC Experts and training participants
• 15,000 dosimeters issued yearly
• 1,200 Urine Analysis performed
• 800 Whole Body Counter measurements performed
IAEA
INCREASE OF INDIVIDUAL MONITORING
0
500
1000
1500
2000
2500
1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006
Years
Mo
nit
ore
d w
ork
ers
Total
SG
TC
IAEA
Quality Policy
• The management and the staff are fully committed to meeting and exceeding customers' expectations.
• The staff of the testing laboratory believes that quality consists of services provided on time, using good professional practice and in conformance with customer requirements. The service definition shall be done in close cooperation with our customers enabling the testing laboratory to efficiently serve their needs.
• The testing laboratory seeks recognition as being efficiently managed within the IAEA.
• The Quality Management System (QMS) has been developed so that it may also serve as a “model” for Member States. It is based on ISO/IEC17025. The requirements are applied to all monitoring services rendered by its testing laboratory.
IAEA
ACCREDITED METHODS:
Individual monitoring:
External Dosimetry-
•Active Personal Dosimeters,
•TLD (γ, β, n) and extremity (β)
Internal Dosimetry-
•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
Staffing
Miroslav Pinak
SH-RSM
Radiation Safety Technical
Services Officer
Jizeng Ma
UH-RPWM
Deputy Radiation Safety
Technical Services Officer
Ingeborg Pucher
Secretary
Rodolfo Cruz Suárez
IMSG Leader
Operational Radiation Protection
Specialist
Erika Gann
Dosimetry Technician
Gerhard Kolb
EDL-Laboratory Technician
Josef Heiss
WBC-Laboratory Technician
Antonio Capote-Cuellar
UAL-Laboratory Technician
Rosaida Alonso Vazquez
Clerk
IAEA
THANK YOU
http://www-ns.iaea.org/home/rtws.asp
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