Download University of Victoria Radiation Safety Refresher Course

Document related concepts

Nuclear and radiation accidents and incidents wikipedia , lookup

John Gofman wikipedia , lookup

Gamma ray wikipedia , lookup

Fallout shelter wikipedia , lookup

Sievert wikipedia , lookup

Radiation therapy wikipedia , lookup

Iodine-131 wikipedia , lookup

Technetium-99m wikipedia , lookup

Ionizing radiation wikipedia , lookup

Background radiation wikipedia , lookup

Transcript
University of Victoria
Radiation Safety Refresher Course
Catherine Franz
Radiation Safety Officer
Occupational Health, Safety &
Environment
Telephone: 721-8876
[email protected]
Overview
•  Welcome to the online Radiation Refresher Course.
•  The course is intended as a refresher training only. If you
have not completed in-class radiation safety training you must
do so prior to working with radiation.
•  The intent of this course is to ensure that all persons handling
and responsible for radioactive materials are properly trained,
informed of the hazards and are familiar with the regulations
and policies of possessing and handling radioactive sources.
This is to ensure there is no undue risk to health, safety,
security and the environment.
•  In order to successfully complete and receive credit for the
course, a score of 80% must be achieved on the quiz.
Course Outline
I. BASIC THEORY
II. TYPES OF RADIATION
III. RADIATION UNITS
IV. ROLES AND RESPONSIBILITIES
V. RADIATION PROTECTION
VI. INSTRUMENTATION
VII. EMERGENCY PROCEDURES
I. BASIC THEORY
•  Radiation
▫ 
Energy in the form of waves or particles
•  Ionizing Radiation
▫ 
Radiation that can produce ions in the material it passes
through by stripping electrons
▫ 
Non-ionizing radiation does not have sufficient energy to ionize or to break
chemical bonds.
Non-ionizing
Ionizing
V
Radio
109
i
s
i
b
l
e
Infrared
106
103
X-Rays
Ultra-Violet
Light
Cosmic Rays
Gamma
Rays
102
10
Wavelength (nm)
Electromagnetic
10-6
Definitions
• 
Isotopes: atoms of the same element with the same
number of protons but different number of neutrons.
• 
Nuclide: general term referring to any known isotope,
whether stable or unstable, of any chemical element.
• 
Radionuclide: an unstable (radioactive) nuclide.
Nuclear Stability
• 
Stable nuclides have an ideal ratio of protons to neutrons
• 
If the ratio differs from the ideal, the nucleus becomes
unstable and will undergo radioactive decay to achieve
stability.
• 
Radioactive Decay: the spontaneous rearrangement of
an unstable atom to a more stable form. The excess
energy is emitted in the form of electromagnetic or
particle radiation.
Nuclear Stability
•  1H (Hydrogen): 1 proton
STABLE!
•  2H (Deuterium): 1 proton, 1 neutron
STABLE!
•  3H (Tritium): 1 proton, 2 neutrons
UNSTABLE!
8
Radioactive Decay
• 
Each radionuclide decays at a specific rate per unit time
which is not affected by physical or chemical processes
• 
Radioactive Half-Life (T1/2): Time required for half the
original number of radioactive atoms to decay into atoms
of a different chemical element
• 
Effective Half-Life: Time required for any isotope in the
body to be diminished by 50% as a result of radioactive
decay and biological elimination
II. TYPES OF RADIATION
•  ALPHA PARTICLES
•  BETA PARTICLES
•  GAMMA RADIATION
•  X-RAYS
Alpha Particles
• 
Large charged particle identical in mass to a helium atom.
• 
Originates in the nucleus
• 
Range in air is short (few centimeters)
• 
Stopped by a piece of paper and the outer dead layer of skin.
• 
Example of alpha decay:
Beta Particles
• 
Small charged particle identical in mass to an electron. Can be
either negatrons or positrons (similar to electrons but with a +ve
charge)
• 
Originate in the nucleus
• 
Emit continuous spectrum of energies to a maximum value
 
“low energy beta”: <250 keV (max)
 
“high energy beta”: >250 keV (max)
• 
Range in air can be several meters.
• 
A thick layer of plastic is an effective shield.
• 
Example of beta decay:
32
P
15
32
S
16
+
β-
Gamma Radiation
•  Electromagnetic photons emitted from the nuclei of
radioactive atoms.
•  Very high-energy ionizing radiation.
•  Have no mass and no electrical charge.
•  Occurs when the nucleus of a radioactive atom has too much
energy. Often follows the emission of a beta particle.
•  Highly penetrating – requires lead or concrete shielding.
•  Causes severe damage to internal organs.
X-Rays
•  X-rays are emitted when high speed electrons
are slowed down or change direction due to the
atoms in a target material. (Bremsstrahlung)
•  X-rays originate in the electron fields
surrounding the nucleus or are machineproduced.
Bremsstrahlung Radiation
•  “Braking Radiation”
•  When beta particles pass
through matter, X-rays can be
produced.
•  As the beta particle
approaches the nucleus, the
strong attractive forces cause a
rapid change in direction,
producing photon energy.
Bremsstrahlung
• 
As the atomic number of the absorbing material increases,
more secondary radiation is produced
• 
Bremsstrahlung may be more of an exposure problem than
the beta particles which were originally being shielded
against
• 
This is why low density material (e.g. plexiglass) is a more
effective shield for beta emitters
16
III. RADIATION UNITS
•  ACTIVITY
Activity
• 
ACTIVITY: a quantity for describing the amount of radioactivity,
based on the number of transformations per unit time.
• 
Units:
▫  Becquerel (Bq) – S.I. Unit
▫ 
 
is the quantity of radioactive material in which one atom is
transformed per second. Therefore:
 
1 Bq = 1 dps (disintegration per second)
Curie (Ci) – conventional unit
▫ 
Is the quantity of radioactive material in which 3.7 x 1010
atoms disintegrate per second
Activity
• 
The curie is a large unit of activity. The terms millicurie (mCi)
or microcurie (µCi) are more commonly used.
• 
The conversions between Ci and Bq are shown below:
  1 Ci = 3.7 x 1010 Bq or 37 GBq
  1 mCi = 3.7 x 107 Bq or 37 MBq
  1 µCi = 3.7 x 104 Bq or 37 kBq
• 
Please note that the units cpm (counts per minute) and dpm (disintegrations per minute)
are not equivalent. CPM is often used in liquid scintillation counting and portable radiation
detection instruments, but must be converted to obtain the actual activity. !
IV. ROLES AND RESPONSIBILITIES
•  REGULATORY AND STANDARDS AGENCIES
•  UNIVERSITY OF VICTORIA, RADIATION
PROTECTION PROGRAM: STRUCTURE AND
RESPONSIBILITES
Regulatory and Standards Agencies
•  Canadian Nuclear Safety Commission (CNSC)
•  WorkSafe BC
•  Radiation Protection Services of BCCDC
•  Radiation Protection Bureau of Canada
Canadian Nuclear Safety Commission (CNSC)
•  Is an independent federal organization which regulates
nuclear energy and the use of nuclear materials in
Canada.
•  Enforces compliance with the Nuclear Safety and
Control Act, regulations, and any licence conditions
imposed by the commission.
•  CNSC website: www.nuclearsafety.gc.ca
WorkSafe BC
•  Occupational Health & Safety Regulation
▫  Part 7: Noise, Vibration, Radiation and
Temperature
•  Outlines:
  Exposure limits
  Requirement for an exposure control plan
  Requirements for protecting an unborn child
  Monitoring exposure requirements
  Requirement for radiation surveys
http://www2.worksafebc.com
Radiation Protection Services of BCCDC
•  Key Functions:
  Hazard identification and evaluation
  Risk assessment and communication
  Monitoring programs and audits
  Radiation health protection & harm prevention
  Expert advice and primary consultation
  Technical training; field & laboratory services
  Policy and legislation advocacy and support
  Emergency preparedness and response support
•  BCCDC website: www.bccdc.org/
Radiation Protection Bureau of Canada
•  The Radiation Protection Bureau of Canada is a
part of Health Canada.
  RPB website: www.hc-sc.gc.ca/hecs-sesc/rpb/
•  RPB is a federal organization which enforces the
Radiation Emitting Devices Act and provides
information, conducts research and provides
services in radiation protection (National Dose
Registry).
University of Victoria
Radiation Protection
Program: Structure and
Responsibilities
ADMINISTRATION
Consolidated License!
CNSC !
(Canadian Nuclear !
Safety Commission)
Legislation, Federal Inspectors!
UVIC !
Permits!
!
R!
S!
O!
Radiation Safety !
Committee
Policies and Procedures!
Radioisotope !
Permit Holder!
UVIC Faculty!
Authorized User!
UVIC Staff, Students!
!
CNSC Consolidated Radioisotope
Licensing Agreement
•  The University of Victoria has a consolidated radioisotope
licensing agreement with the CNSC. Some of the activities
covered in the agreement include:
▫ 
▫ 
▫ 
▫ 
▫ 
▫ 
▫ 
Maximum quantities allowed in possession
Project approval
Area classification and storage
Bioassay and dosimetry
Lab decommissioning
Contamination and survey meter requirements
Report requirements
UVic Radiation Safety Policies & Procedures
•  The success of any Radiation Safety Program is vitally
dependent on the cooperation of the individuals involved in
all aspects of radioisotope use. It is therefore essential that all
users be thoroughly familiar with the policies and procedures
outlined in UVic’s Radiation Safety Manual.
•  The Radiation Safety Policies & Procedures manual is
available online at: http://ohs.uvic.ca/radsafety/radpolicy.pdf
In addition, in each lab where radiation is stored/used, a hard
copy should be made available.
•  The next few slides highlight some of the responsibilities of
Permit Holders and Radiation Users.
Provide Adequate Facilities,
Equipment and Instruments
Provide designated
radiation work areas
Provide an annually
calibrated survey meter
Permit
Holder
Provide adequate
shielding
Conduct regular lab
inspections
Personnel Management
Ensure personnel are
properly instructed and
supervised
Inform RSO, by memo,
of any new users
Permit
Holder
Ensure experiments
after hours will be
properly attended
Laboratories are
secured against
unauthorized access
Inventory & Waste Management
Maintain inventory
database
Follow UVic procedures
for waste disposal
Permit
Holder
Ensure proper labeling
and storage of sources
Do not exceed permitted
possession limits
Working Safely
Be familiar with and comply
with UVic’s Radiation Safety
Regulations – Policies and
Procedures
Successfully complete UVic’s
Radiation Safety Course
Radiation User
Ensure that use of sources of
radiation does not endanger
others
Report any incident or
accident
V. RADIATION PROTECTION
•  BIOLOGICAL EFFECTS
•  PRINCIPLES OF RADIATION PROTECTION
•  CONTAMINATION CONTROL
Biological Effects
•  DETERMINISTIC: Severity increases with
radiation dose
▫  Examples: hair loss, skin reddening, cataract
induction
•  STOCHASTIC: Probability of occurrence
increases with radiation dose
▫  Examples: cancer induction, genetic mutations
Radiation Damage
•  4 STAGES:
▫  Energy deposited in cells causing ionization of
atoms
▫  Ions interact with other molecules
▫  Interactions with important organic molecules
causing chemical changes
▫  Biological changes
Radiation Damage
•  POTENTIAL FOR DAMAGE AFFECTED BY:
▫  Type of radioactive decay
▫  Energy of radioactive decay
▫  Half-life of the radioisotope
▫  Rate at which radioisotope is excreted from the
body
▫  Radiosensitivity of the critical organ
Principles of Radiation Protection
•  TIME
•  DISTANCE
•  SHIELDING
•  CONTAMINATION CONTROL
Time
•  The shorter the time spent working with radioactive
material, the smaller the exposure
•  Reducing the time by 1/2 will reduce the dose by 1/2
•  Shorter times can be achieved by pre-planning:
▫  mark out the work area and assemble all equipment
▫  ensure all equipment is working
▫  do a “dry-run”
▫  consult someone more experienced with the experiment
Distance
•  The greater the distance between the radioactive
material and the user, the smaller the radiation
exposure.
•  For gamma radiation, the intensity varies inversely
with the square of the distance from the source.
•  Doubling the distance will reduce the dose rate by a
factor of 4.
Distance
•  Increasing the distance can be achieved by:
  Working at arms length
  Using remote manipulations devices when working
with stock solutions
  Returning the stock vial to storage immediately after
use
  Avoid ordering multi-millicurie quantities
Shielding
•  By choosing the correct absorber material to place
between the user and the radiation source, exposure can
be reduced or eliminated.
•  Examples:
  Shielding composed of low molecular weight atoms for
beta emitters (32P)  plexiglass, wood, glass, water.
  Shielding composed of high molecular weight atoms for
gamma or x-ray emitters (125I)  lead.
Contamination Control
•  Internal Contamination
  Entry of radioactive material into the body by
ingestion, inhalation, absorption or injection.
•  Laboratory Contamination
  The spread of radioactive material through improper
experimental and housekeeping techniques.
Preventing Internal Contamination
•  Ingestion:
  No eating or drinking in the lab
  Wash hands before leaving the lab
•  Inhalation:
  When working with volatile radioactive material, work only in
an approved fumehood (consult with RSO)
•  Absorption:
 
 
 
 
Use gloves and wear a lab coat
Wait for cuts to heal before working with radioactive materials
Take extra care when working with syringes or other sharps
Wash hands before leaving the lab
Preventing Lab Contamination
•  Prepare work area:
  Cover bench with absorbent liner and mark area with radiation tape
  Label equipment, fridges/freezers and waste containers where
radioactive sources are used and stored
  Work in a tray if handling large volumes of liquids
•  After completing work:
  Monitor area, equipment and yourself (hands, lab coat, shoes)
  Decontaminate if necessary
  Remove all wastes – do not let wastes accumulate
  Change absorbent liner on bench if necessary
VI. INSTRUMENTATION
•  DOSIMETERS
•  SURVEY METERS
•  LIQUID SCINTILLATION COUNTERS
Dosimetry
•  People who work with
radiation sources or in the
vicinity of radiation sources
may routinely be exposed to
radiation.
•  The amount of radiation
received is called radiation
dose.
•  The measurement of such
doses is known as radiation
dosimetry.
2008 Radiation Safety Institute of Canada
Radiation Doses
•  Radiation doses fall into two categories:
  External radiation dose
  Internal radiation dose
•  Internal radiation doses are measured using:
  Bioassays
  Specialized dosimeters
•  External radiation doses are measured using
dosimeters.
Dosimeters
•  DO NOT provide protection from radiation exposure
•  Required ONLY when there is a possibility of
exceeding 1 mSv per year
•  Used for personnel monitoring, including whole body badges
or extremity rings
•  Compact, sensitive and environmentally insensitive
•  Measures accumulated dose over a long period of time
•  Automated system allows for dose tracking
Maximum Permissible Doses
Person
Nuclear
Energy
Worker
(NEW)
Public
(Includes
all
UVic
radiaDon
users)
Period
Effec-ve
Dose
(mSv)
(a)  One‐year
dosimetry
period
(a)  50
(b)  Five‐year
dosimetry
period
(b)  100
One
calendar
year
1
Survey Meters
•  Designed to measure the rate of radiation
events.
•  Count rate (cpm)
•  Radiation dose rate (µSv/h)
•  Exposure rate (mR/h)
•  Usually hand-held
•  Battery operated
•  Multi-purpose
•  Detector probes available for measuring all types of
radiation.
Survey Meters
•  Geiger-Mueller (G-M) tube
▫  Gas-filled detector (He, Ne, Ar)
▫  Particle radiation ionizes gas
molecules
▫  Not efficient for x-rays or
gamma rays
▫  Suitable for 14C, 35S and 32P
•  Solid Scintillation Detector
▫  Large crystal detector (NaI)
▫  Crystals emit light photons
due to particle/wave energy
▫  Recommended for gamma
and x-rays
Indirect Monitoring
•  Liquid Scintillation Counters
▫  Highly sensitive detection
technology
▫  Large, immobile and expensive
▫  Programmable
▫  The energy of radioactive decay
is converted into visible light
which is detected by the
counter
Wipe Testing
•  Used to detect low levels of
removable contamination for
both alpha and beta emitters
•  Only effective method for
detecting low energy betas
(3H, 14C, 35S)
•  Effective in detecting
contamination where room
background is high
Wipe Test - Procedures
•  Wipe the work bench, floor, storage areas, lab coat,
equipment
•  With gloves on, wipe an area of approx 100 cm2 with a
moistened cotton swab or filter paper
•  Place swab into a vial and add scintillation cocktail
•  Count samples in a LSC, including a blank
•  Record and keep results
Wipe Test Results
•  Contamination checks must be done at least weekly
in areas where radionuclides are regularly used or
stored
•  If any measurements are above background, the area
must be decontaminated and re-wiped
•  Contamination monitoring records must be kept for
3 years
VII. EMERGENCY PROCEDURES
•  SPILLS
•  PERSONAL CONTAMINATION
•  EMERGENCY CONTACTS
Accidents & Incidents
•  Accident: defined as any unintended situation
or event, which causes injury to personnel or
property damage.
•  Incident: defined as minor occurrences that do
not cause injury or damage.
– The most likely type of radiation incident
occurring in a laboratory is a Spill.
Spills
•  Radiation spill kits and spill procedures should
be available in each lab where radiation is used.
•  In the event of a spill or personal contamination,
the Radiation Safety Officer shall be
notified IMMEDIATELY at 250-721-8971.
Emergency Contacts
•  If further assistance is required (ambulance/
fire), or assistance is required after hours use the
following numbers:
•  Campus Security
  local 7599 (24 hour emergency number)
•  Emergency Services
  911 or 9-911
Further Information
•  Information regarding purchasing, inventory
control, pregnant personnel, waste handling,
transportation and packaging, and receipt of
radioactive materials can all be found in UVic’s
Radiation Safety Policies and Procedures
manual.
Radiation Refresher Quiz
A reminder that this course is not a substitute for the inclass radiation safety training.
If you are ready to take the quiz, click the button below.
PROCEED TO QUIZ
The quiz is a ‘PDF’ document.
Send your completed quiz by fax to Local 6359 or by
Campus mail to: Occupational Health, Safety &
Environment, Sedgewick B130.