Radioactive material transportation

1. TRANSPORT OF
RADIOACTIVE MATERIAL
P SABARI KUMAR
M.Sc. RADIATION PHYSICS

2. The wide use of ionizing radiation in medicine, industry,
agriculture, research etc. has made the necessity of voluminous
transport of the radioactive material from one place to another.
There are national & international regulations for the safe
transport of radioactive material by various modes such as road,
rail, air, sea, inland waterway and post
INTERNATIONAL ATOMIC ENERGY AGENCY,
Regulations for the Safe Transport of Radioactive Material, 2012
Edition, Specific Safety Requirements No. 6, SSR-6, IAEA, Vienna
AERB Safety Code No. AERB/NRF-TS/SC-1 (Rev.1),
Safe Transport of Radioactive Material
(2016)
INTRODUCTION

3. PRINCIPLE
Doses received by persons in connection with activities relating
to transport of radioactive material, the number of persons
exposed are kept
As
Low
As
Reasonably
Achievable
economic and social factors being taken into account

4. Needful Definitions
A1:
The max. amount of radioactivity in Type A package for a special
form of radionuclide that is allowed
Special Form: Hazards purely related to external gamma
radiation when material releases from packing
Ex: Encapsulated Co-60 source
A2:
The max. amount of radioactivity in Type A package for normal
form of radionuclide that is allowed
Normal Form: Hazards relates to external gamma & beta
radiation, Inhalation, Ingestion and gamma radiation from gaseous
cloud of radioactive material
Ex: Radioactive waste in plastic bags

5. Radionuclide A1 (TBq) A2 (TBq)
Activity limit
for exempted
consignment
(Bq)
Activity
concentration limit
for Exempted
material (Bq/g)
Co -60 0.4 0.4 1 x 105 1 x 101
Cs-137 2 0.6 1 x 104 1 x 101
Ir-192 1 0.6 1 x 104 1 x 101
P-32 0.5 0.5 1 x 105 1 x 103
I-125 20 3 1 x 106 1 x 103
Tc -99m 10 4 1 x 107 1 x 102
Usually A1 and A2 values can’t exceed 37 TBq or 1000Ci
 A2 values refers to normal form of radioactive materials. So
these values are less than A1 values
A1 and A2 values determines that the amount of radioactive
material to be packed and shipped

6. Single Radionuclide:
In a radioactive decay chain, in which no daughter nuclide has a
half-life either longer than 10 days or longer than that of the parent
nuclide, shall be considered as a single radionuclide.
the activity to be taken into account and the A1 or A2 value to be
applied shall be that corresponding to the parent nuclide of that
chain

7. Mixture of Radionuclide:
In a radioactive decay chain in which any daughter nuclide has a
half-life either longer than 10 days or longer than that of the parent
nuclide, the parent and such daughter nuclides, shall be
considered as mixtures of Radionuclides
For mixtures of radio nuclides, the basic radionuclide values
may be determined as follows:
Xm= 1 / Σi (f(i) / X(i))
where
f(i) – Fraction of activity or activity concentration of radionuclide ‘I’
X(i) - Appropriate value of A1 or A2, for the radionuclide “ I ”
Xm - Derived value of A1 or A2, in the case of a mixture

8. Surface Contaminated Object (SCO)
A solid object itself is not a radioactive but has radioactive
material distributed on its surfaces.
SCO shall be in one of two groups:
SCO – I:
Material For Beta and Gamma emitters For alpha emitters
Non fixed 4 Bq/cm2 0.4 Bq/cm2
Fixed 4 x 104 Bq/cm2 4 x 103/cm2
Non fixed + fixed 4 x 104 Bq/cm2 4 x 103/cm2
SCO – II :
Material For Beta and Gamma emitters For alpha emitters
Non fixed 400 Bq/cm2 40 Bq/cm2
Fixed 8 x 105 Bq/cm2 8 x 104/cm2
Non fixed + fixed 8 x 105 Bq/cm2 8 x 104/cm2
(on the accessible surface of which averaged over 300 cm2)

9. Limited Specific Activity
Radioactive material which by its nature has a limited specific
activity.
External shielding materials surrounding the LSA material shall
not be considered in determining the estimated average specific
activity.
LSA-I:
Ores containing naturally occurring radionuclides which are
intended to be processed for the use of these radionuclides
(Uranium, Thorium etc.,)
Radioactive material for which the A2 value is unlimited.
Radioactive material in which the activity is distributed
throughout and the estimated average specific activity does not
exceed 30 times the values for activity concentration specified

10. LSA-II:
 water with tritium concentration up to 0.8 TBq/lt; or other
material in which the activity is distributed throughout and the
estimated average specific activity does not exceed 10-4 A2/g
for solids and gases, and 10-5 A2/g for liquids.
LSA-III:
 The radioactive material is distributed throughout a solid or a
collection of solid objects
 The radioactive material is relatively insoluble, the loss of
radioactive material per package by leaching when placed in
water for seven days would not exceed 0.1 A2
 The estimated average specific activity of the solid, excluding
any shielding material, does not exceed 2 × 10-3 A2/g

11. Low Dispersible Radioactive Material
Low dispersible radioactive material shall mean either a
solid radioactive material or a solid radioactive material
in a sealed capsule, that has limited dispersability and is
not in powder form.

12. Transport of radioactive materials takes places in situations:
 Delivery of sources
 Disposal of sources
 Transport between hospitals
 Within the hospitals
The protection while source transport can be achieved by :
 Containment of the source
 Control of external radiation levels
 Prevention of criticality
 Prevention of damage caused by heat

13. Factors need to consider, while designing the transport system:
 Quantity & physical/chemical form of the radioactive material
 Mode(s) of transport
 Package(s) being used
 Transport schedules and route of shipment

14. Features should incorporate while design of security measures:
 Avoid predictable movement schedules
 Plan routes to avoid areas, which are, affected by a natural
disaster or a disruption of the local law and order situation
 Keep total transport duration and the number of modal
transfers to the minimum
 Disseminate information regarding the transport and related
security measures on a ‘need-to-know’ basis
 Do not leave packages or conveyances containing radioactive
material unattended

15. Security Levels Envisaged during Transport :
Three levels of security are envisaged during the transport of
radioactive material.
Level 1 - Prudent Management Practices
This is the minimum level of security
applicable for ‘Exempted Packages’ and ‘Industrial Packages
Level 2 - Basic Security
This is the basic security level nuclear medicine, LDR Brachy
sources, etc.
applicable for all radioactive material, except fissile material,
transported in Type A packages
Level 3 - Enhanced Security
This would be the security level sources used in Teletherapy,
irradiator, HDR sources, industrial radiography sources, etc.
Applicable for all radioactive material (except irradiated nuclear
fuel and fissile material) transported in Type B (U)/(M) packages.

16. Categorization of Radioactive Material Packages for Transport :
The first method:
 Based on the IAEA method
 Sorts all sealed radioactive sources in five categories
 Category1 are treated to be the most ‘dangerous’ (high risk)
 Category 5 are the least dangerous;
 Does not cover unsealed sources and radioactive sources,
which are not defined as sources, (Ex: spent nuclear fuel)
The second method:
 Covers all types of Radioactive materials, including sealed
sources, unsealed sources and irradiated nuclear fuel
 the categorization should be such that the user (consignor or
consignee) is able to identify the level of security applicable
to the specific consignment being transported

17. PACKAGE
The assembly of components necessary to enclose the
radioactive contents completely.
It may consist of one or more receptacles, absorbent materials,
spacing structures, radiation shielding, providing handling and tie-
down capability, thermal insulation.
The packaging may be a box, or drum, or receptacle, or a freight
container, or tank or intermediate bulk container.
Types of packages defined by IAEA :
 Exempted Packages
 Industrial Packages ( IP-I, IP-II and IP-III)
 Type A Packages
 Type B (U/M) Packages
 Type C Packages

18. Exempted Packages:
Extremely low activity with very low hazard
 The radiation level at 10cm from any point on the external
surface of any unpackaged material is not greater than 0.1mSv/hr
Dose rate less than 0.005mSv/hr on surface of packaged
material
Excluded from special packing, labeling and shipping paper
requirements. However package must be strong and tight enough
to avoid leak or release during transportation
Marking should be required as “ Radioactive – Exempted ”
Ex: consumer goods as smoke detectors
Physical state of content Limit
Solids: Special form 10-3A1
Solids: Normal Form 10-3A2
Liquids 10-4A2
Gases: Special form 10-3A1
Gases: Normal form 10-3A2

19. Industrial Packages:
IP s are used to transport LSA & SCO materials
Both types are inherently safe either because of low activity and
material not in form easily dispersible
Three categories of industrial packages: IP-1, IP-2 & IP-3, which
differ regarding the degree to which they are required to withstand
routine and normal conditions of transport
IP-1 package should withstand on normal transport conditions
and also temperature & pressure tests while transporting by air
IP-2 packages have to satisfies IP-1 and also if it were subjected
to free drop test (0.3m to 1.2m height depends on mass of
package) and stacking test
IP-3 packages should satisfies IP-2 tests, penetration test (6Kg
bar drops from 1m) and also Type A package tests
More than 20% increase in the max. radiation level at any
external surface of package

20. Type A Package:
 To transport small quantity of radioactive material with higher
concentrations of radioactivity
 Constructed with steel, wood or fiberboard and have inner
containment of glass/plastic/metal
 The package retains its containment integrity and shielding
under transport condition.
 Type A package is possible only when radioactive inside the
package dose not exceed A1 or A2 values
Ex: Nuclear Medicine, Radioactive waste and
sources used in industrial applications

21. Type A Package tests:
The tests are the water spray test, the free drop test, the
stacking test and the penetration test. Specimens of the package
shall be subjected to the free drop test, the stacking test and the
penetration test, preceded in each case by the water spray test.
Water Spray Test: The specimen shall be subjected to a water spray
test that simulates exposure to rainfall of approximately 5 cm per hour
for at least 1 h.
Free Drop Test: The specimen shall drop onto the target so as to suffer
maximum damage in respect of the safety features
Stacking test: The specimen shall be subjected, for a period of 24 h, to
a compressive load equal to the greater
Penetration Test: The specimen shall be placed on a rigid, flat,
horizontal surface. A bar 3.2 cm in diameter with a hemispherical end &
a mass of 6 kg shall be dropped and directed to fall from 1 m height.
Tolerance Limit: 10-6A2/hr in all above tests

22. Type B (U/M):
 Designed to transport materials with highest levels of
radioactivity (Life endangering amounts)
 Designed to survive severe accidents conditions
 When radioactivity level exceeds the values of A1 & A2, then
this package is used
 Generally, 3000A1 or 105A2 whichever is lower preferred limit
for Type B(U/M) package
Ex: High level radioactive waste, Cesium & cobalt sources,
spent nuclear fuel etc.,

23. Type B Package tests:
 The specimen shall be subjected to Type A tests as well
cumulative effects of the mechanical test & thermal tests
Thermal Test: subject to the solar isolation conditions and subject to
the design maximum rate of internal heat generation within the
package from the radioactive contents.
Water Immersion Test: The specimen shall be immersed under a
head of water of at least 15 m for a period of not less than 8 h in
the attitude that will lead to maximum damage
Puncture–tearing Test: The specimen shall be subjected to the
damaging effects of a vertical solid probe made of mild steel
Impact Test: The specimen shall be subjected to an impact on a
target at a velocity of not less than 90 m/s, at such an
orientation as to suffer maximum damage.
Enhanced Water Immersion Test: The specimen shall be
immersed under a head of water of at least 200 m for a period
of not less than 1 h.
The loss of radioactive contents should not more than 10–6A2/hr

24. Type C Package:
 The 1996 Edition of the IAEA Transport Regulations
introduced a requirement for a more robustly designed package –
the Type C Package – to transport the more highly radioactive
material by air.
 Type C packages must satisfy all the additional requirements
of Type A packages and most of the additional requirements of
Type B packages.
 Type C packages are submitted to a series of tests to prove
their ability to withstand transport incidents and accidents
 Especially used for radioactive materials which have equal or
above the value of 3000A1 or 105A2 for Type C package
 It would retain sufficient shielding to ensure that the radiation
level 1m from the surface of the package would not exceed
10 mSv/h

25. Common Tests for all packages of Type A, Type B and Type C

26. Package Markings
All shipments of radioactive material,
will have markings on the outside of
the package that give key information
about the package.
Package markings are designed to
inform transportation workers and
emergency response personnel about
the package’s radioactive contents.
Markings may be printed directly on a
cardboard container or attached via
printed shipment specific label to more
robust containers.
Ex: “Radioactive LSA”
“Radioactive SCO1”

27. Transport Index
It is the maximum radiation level (mSv/hr) at a distance of 1m
from the external surface of the package, multiplied by 100
Ex: A TI of 0.2 would indicate that, at 1 meter from the labeled
package, the radiation dose rate should be not more than
0.002 mSv/hr
When assessing a package’s integrity at an accident scene, this
information can be used as a baseline for determining if damage
has occurred to the package

28. Transport Index
The categories of packages are determined by the TI
the TI and the surface radiation level conditions shall be taken
into account in determining which category is appropriate.
When the TI satisfies the condition for one category but the
surface radiation level satisfies the condition for a different
category, the package shall be assigned to the higher category
The no. of radioactive Yellow II & Yellow III stored in any one
storage area must be limited so that sum of individual TI doesn’t
exceed 50
Transport
Index
Max dose (mSv/hr) on outer
surface
Category
0 <5μSv/hr (or) 500μR/hr White I
0 <TI<1 5μSv/hr to 0.5mSv/hr (or) 5mR/hr Yellow II
1<TI<10 0.5mSv/hr to 2mSv/hr (or) 0.23R/hr Yellow III
>10 2mSv/hr to 10mSv/hr (or) 1.14R/hr Yellow III

29. Labeling
Each package, over-pack and freight container shall bear the
labels
The standard labels are placed on opposite sides of the
package
the basic trefoil symbol with proportions based on
a central circle of radius R

30. Label
Labels include the following information:
 Radioactivity trefoil
 category of package
 Contents
 Activity
 Transport index (TI)
 Class number

31. Label
Yellow II : Dose rate on surface of
package is in the range of 5μSv/hr
to 0.5mSv/hr
Content: Cs-137 source
Activity : 0.37GBq (10mCi)
TI - 0.8 : Exposure level at 1m is
0.008mSv/hr
Hazard 7: content is Radioactive
material (UN identification Number)

32. Placards
Placards are larger, more durable (not paper) versions of hazard
labels that are usually placed on bulk packages or transport
vehicles to communicate the hazards of “hazardous material”
inside.
They inform the public
They inform emergency responders
Placards must be in plain view and displayed on all four sides of
the transport vehicle as shown above

33. Transport Vehicle Considerations:
If the vehicle is not exclusive for radio nuclides transport:
Dose rate should not be exceeds 2.0mSv/hr at surface of
package
0.1mSv/hr at 1m distance from package
If the vehicle is specially meant for radio nuclide transport, then:
10mSv/hr at 1m from surface of package
2mSv/hr at external surface of the vehicle
0.1mSv/hr at 2m distance from vehicle surface
0.02mSv/hr at any normal occupied position in the vehicle

34. Few General Considerations in Radioactive Material Transport:
the consignee of a radioactive consignment is duly authorized
by the Competent Authority
the carrier and cargo personnel are adequately instructed,
through appropriate and effective about their responsibilities as:
to safe handling of package,
accumulation of packages
segregation of packages
emergency response actions during transport
Persons engaged in the transport of radioactive material should
receive training, concerning about handling of radioactive
materials, radiation protection, including the precautions in
emergency conditions
A structured and systematic approach has to be developed and
adopted by all organizations connected with transport of
radioactive material

35. THANK YOU