1. Regional Training Course on the Safe Transport of Radioactive Material in the Caribbean Module Transport Package Types and Material Classification
June Panama
Paul Gray

2. Overview
The classification and selection of materials and package types
The main requirements for package types
Flow diagram for classification of radioactive material into appropriate UN number
4. Summary 2

3. “Packaging” and “Packages” are terms of vital importance in Transport Regulations
Package - The packaging with its radioactive contents as presented for transport
Packaging - The assembly of components necessary to enclose the radioactive contents completely + =
PACKAGING
PACKAGE
RADIOACTIVE
CONTENTS
Key Points:
IAEA definitions and any related requirements and testing procedures must not be confused with terminology developed for operational or other regulatory requirements such as storage or handling of radioactive materials or wastes.
A PACKAGE is defined (TS-R-1 §230 ) as a PACKAGING with its RADIOACTIVE CONTENTS as presented for transport.
There are 8 basic PACKAGE types defined in TS-R-1 §230 There are only simple requirements relating to the PACKAGING component of the PACKAGES in the transport regulations (§606 - §616 TS-R-1).
However, the transport regulations have a comprehensive graded series of requirements and tests for all PACKAGES (SECTIONS VI and VII of TS-R-1).
The Type B(U), B(M) and Type C packages are tested to withstand extremely severe accidents without loss of contents. They are Competent Authority approved and normally licensed to carry a large RADIOACTIVE CONTENT.
The other PACKAGE types listed in § 230 are only tested to withstand routine and normal conditions of transport (§106 TS-R-1).
Consequently their RADIOACTIVE CONTENTS are limited so that any losses under accident conditions will present no significant hazard to workers or the general public.

4. Package Type Options for Transporting Radioactive Material
Excepted packages
Industrial packages Types IP-1, IP-2, IP-3
Type A packages
Type B packages
Type C packages
Other (Fissile, UF6)
Key Points:
Explain that the package types, including unpackaged materials, addressed in this slide are discussed, in order, in this module.
Briefly state the following:
- Unpackaged materials are applicable to solids which qualify as LSA-I materials or SCO-I
- Excepted packages are limited to a very restrictive activity, usually associated with limited quantities
- Industrial packages are designed and tested to carry qualified, e.g., LSA materials and SCO, radioactive contents
- Type A packages are restricted to carry contents up to a maximum of A1 or A2.
- Type B(U) and B(M) packages are generally for contents with activities >A1 or >A2.
- Type C packages are for transport of high content activity by air
- UF6 packages are unique only to UF6 materials
- Fissile material packages are specifically designed for the fissile material content and may include IPs, Type A, Type B, Type C and UF6 packages.
Objective(s):
None
References:
Module 7
Exercises:
None at this point
RAM classified as LSA-I or SCO-I
may also be transported unpackaged
- This presentation will focus on Type A packages

5. GRADED APPROACH TO TRANSPORT
Package integrity is a function of the potential hazard of the contents and the response of a package under
routine conditions of transport (incident free) – represented by general design requirements for all package types,
normal conditions of transport (including minor mishaps) represented by Type A tests and
accident conditions of transport (severe accidents) represented by Type B tests
to assure the same level of safety for all types of packages
Excepted Package
Type A Package
Type B Package

6. Hazards of the radioactive Material Safety functions of the Packaging
Basic safety functions of packages for radioactive material
Hazards of the radioactive Material
Safety functions of the Packaging
Radiation
(α, β, γ, n-Radiation)
Shielding
Radiotoxicity
(Contamination,
Incorporation)
Containment
Heat release
Heat transfer
Criticality
Criticality Safety 6

7. Concept of a Safe Package – Graded Approach The greater the hazard the stronger the package
(Paras of IAEA Regulations TS-R-1, 2009)

8. Excepted Package
Radioactive material in limited quantity (fractions of A1/A2) representing low hazard
meets general design requirements to withstand routine conditions of transport
Surface dose rate ≤ 5 μSv/h
Only marking with UN number, consignor/consignee (mass > 50 kg)
No competent authority (CA) approval necessary but the consignor must , on request, make available for inspection by the relevant CA, documentary evidence of the compliance of the package design with all applicable requirements

9. UN Numbers for Excepted Package
RADIOACTIVE MATERIAL, EXCEPTED PACKAGE - EMPTY PACKAGING
UN 2909
RADIOACTIVE MATERIAL, EXCEPTED PACKAGE - ARTICLES MANUFACTURED FROM NATURAL URANIUM or DEPLETED URANIUM or NATURAL THORIUM
UN 2910
RADIOACTIVE MATERIAL, EXCEPTED PACKAGE - LIMITED QUANTITY OF MATERIAL
UN 2911
RADIOACTIVE MATERIAL, EXCEPTED PACKAGE - INSTRUMENTS or ARTICLES 9

10. Quantities of Radioactive Material in Excepted Packages (UN 2910 and 2911)
Solids:
special form 10-2A A A1
other form A A A2
Liquids A A A2
Gases
tritium 2 x 10-2A x 10-1A2 2 x 10-2A2
special form A A A1
other forms A A A2
Physical State Instrument or article Materials
of contents Item limits Package limits Package limits
ACTIVITY LIMITS UN UN 2910

11. Quantities of Radioactive Material in Excepted Packages (UN 2909 and 2908)
UN 2909: Unlimited quantities of manufactured articles
natural uranium
depleted uranium
natural thorium
If enclosed in an inactive sheat
UN 2908: Empty packaging, which had previously contained radioactive material and for which the internal non-fixed contamination does not exceed 400 Bq/cm² (beta-/ gamma emitters) and 40 Bq/cm² (alpha-emitters) (100 times the external surface contamination limits for all packages)

12. General Design Requirements for Excepted Packages
Designed in relation to its mass, volume and shape to be easily and safely transported and properly secured during transport
Only external features intended for lifting are available during handling
The external surfaces can be easily decontaminated
The external surfaces shall not retain water
Capable of withstanding the effects of acceleration, vibration and vibration resonance which may arise under routine conditions of transport
Materials of construction, components and structures shall be physically and chemically compatible
All valves should be protected against unauthorized operation
The design shall take into account ambient temperatures and pressures that are likely to be encountered in routine conditions of transport
Medical radioisotope
excepted package 12

13. Industrial Package Type IP-1, IP-2, IP-3
Mainly used for radioactive waste transport
Radioactive material must be classified as Low Specific Activity (LSA) material or Surface Contaminated Objects (SCO)
design requirements for excepted packages + parts of design requirements to withstand normal conditions of transport (Type A package)
Surface dose rate ≤ 2 mSv/h (dose rate at 2 m distance ≤ 0.1mSv/h)
Dose rate at 3 m distance from unshielded LSA/SCO contents ≤ 10 mSv/h
All marking and labelling requirements applicable
No competent authority (CA) approval necessary but the consignor must , on request, make available for inspection by the relevant CA, documentary evidence of the compliance of the package design with all applicable requirements

14. Low Specific Activity (LSA) Material
LSA material shall mean radioactive material which by its nature has a limited specific activity, or radioactive material for which limits of estimated average specific activity apply. External shielding materials surrounding the LSA material shall not be considered in determining the estimated average specific activity.
LSA-I
Uranium and thorium ores
Natural uranium, depleted uranium, natural thorium or their compounds, unirradiated in solid or liquid form
Radioactive material for which A2 value is unlimited (excluding fissile material)
Other radioactive material in which the activity is distributed throughout and the estimated average specific activity is  30 times the exempt activity concentrations listed in IAEA SSR-6, Table 2 14

15. Low Specific Activity (LSA) Material (cont.)
LSA-II
Water with a tritium concentration 0.8 TBq/L
Other material with average specific activity 10-4A2/g for solids and gases, and 10-5A2/g for liquids
LSA-III
Solids (eg consolidated wastes, activated materials) – not powders!
Radioactive material distributed throughout a solid (essentially uniformly distributed)
Relatively insoluble, under loss of packaging the loss of radioactive material by leaching in water would be 0.1A2 in 7 days
Estimated average specific activity of the solid (excluding shielding material) 2 x 10-3A2/g 15

16. Surface Contaminated Object (SCO)
Surface contaminated object (SCO) shal mean a solid object which is not itself radioactive but which has a radioactive material distributed on its surfaces
SCO-I
A solid object on which:
the non-fixed contamination on 300 cm2 accessible surface  4 Bq/cm2 for beta and gamma emitters and low toxicity alphas or 0.4 Bq/cm2 for all other alpha emitters
The fixed contamination on 300 cm2 accessible surface  4 x 104 Bq/cm2 for beta and gamma emitters and low toxicity alphas or  4 x 103 Bq/cm2 for all other alpha emitters
The non-fixed contamination plus the fixed contamination on 300 cm2 accessible surface  4 x 104 Bq/cm2 for beta and gamma emitters and low toxicity alphas or  4 x 103 Bq/cm2 for all other alpha emitters 16

17. Surface Contaminated Object (SCO) (cont.)
SCO-II
A solid object on which the non-fixed or fixed contamination on 300 cm2 accessible surface exceeds SCO-I limits, were;
The non-fixed contamination on 300 cm2 does not exceed 400 Bq/cm2 for beta and gamma emitters and low toxicity alphas or 40 Bq/cm2 for all other alpha emitters
The fixed contamination on 300 cm2 accessible surface  8 x 105 Bq/cm2 for beta and gamma emitters and low toxicity alphas or  8 x 104 Bq/cm2 for all other alpha emitters
The non-fixed contamination plus the fixed contamination on 300 cm2 accessible surface  8 x 105 Bq/cm2 for beta and gamma emitters and low toxicity alphas or  8 x 104 Bq/cm2 for all other alpha emitters 17

18. UN Numbers for LSA Material and SCO
Low specific activity radioactive material
UN 2912
RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY (LSA-I)
UN 3321
RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY (LSA-II)
UN 3322
RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY (LSA-III)
UN 3324
RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY (LSA-II), FISSILE
UN 3325
RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY (LSA-III), FISSILE
Surface contaminated objects
UN 2913
RADIOACTIVE MATERIAL, SURFACE CONTAMINATED OBJECTS (SCO-I or SCO-II)
UN 3326
RADIOACTIVE MATERIAL, SURFACE CONTAMINATED OBJECTS (SCO-I or SCO-II), FISSILE 18

19. Design Requirements for Industrial Packages Type IP-1, IP-2, IP-3
Type IP-1 package requirements
Excepted package requirements, plus
The smallest overall dimension shall not be less than 10 cm
Type IP-2 package requirements
Type IP-1, plus
Loss or dispersal of contents would be prevented and no more than 20% increase in the maximum surface dose rate at any external surface when subjected to:
A free drop from a height of 0.3m to 1.2m (depending on package mass)
Stacking test (24 hours), the greater of 5 times package mass or 13kPa x vertically projected area 19

20. Design Requirements for Industrial Packages Type IP-1, IP-2, IP-3 (cont.)
Type IP-3 package requirements
Type IP-1, plus
A security seal to indicate the package has been opened
Tie down attachments
Take account of component temperatures ranging from -40ºC to +70 ºC
Design and manufactured in accordance with national and international standards
Positive fastening device on containment system
Retain contents under a reduction of ambient pressure to 60 kPa
When subjected to water spray test, followed by free drop test, stacking test and penetration test (normal conditions of transport), loss or dispersal of contents would be prevented and no more than 20% increase in the maximum surface dose rate at any external surface (equivalent to Type A package for solids) 20

21. Industrial package type Exclusive use Not exclusive use
Requirements for Industrial Package Types and LSA/SCO contents
Radioactive contents
Industrial package type Exclusive use Not exclusive use
LSA-I
Solid
Liquid
Type IP-1
Type IP-2
LSA-II
Liquid and gas
Type IP-3
LSA-III
SCO-I
SCO-II 21

22. Conveyance Limits for LSA/SCO in Industrial Packages
LSA and SCO in Industrial Packages
Activity limit for
Conveyances Hold
(inland waterway)
LSA-I
No limit
LSA-II and LSA-III
Non-combustible solids
No Limit
100 A2
LSA-II and LSA-III Combustible solids and all liquids and gases
100A2
10A2
SCO 22

23. Type A and Type B Packages
Type A Package
small volume of radioisotope
small package dimension and weight
transported by air and locally by truck
Hospitals, clinics, health centers primary customers
Type B Package
larger dimensions, weight and radioisotope volume
Radiopharmaceuticals to radiopharmacies or intermediate processors who prepare unit doses
- air shipments primarily but also road

24. Type A Package Radioactive contents ≤ A1 or A2
meets Type A package design requirements to withstand normal conditions of transport
Surface dose rate ≤ 2 mSv/h (dose rate at 2 m distance ≤ 0.1mSv/h)
All marking and labelling requirements applicable
No competent authority (CA) approval necessary but the consignor must , on request, make available for inspection by the relevant CA, documentary evidence of the compliance of the package design with all applicable requirements

25. Type A packages for shipping smaller amounts of medical isotopes, such as individual formulations
~80% of all medical isotope shipments shipped in Type A packages

26. Layers of protection (Type A)
Security tape
Packing tape
Cardboard box
Styrofoam for impact and penetration protection
Lead pot for shielding
Absorbent material
Vial

27. Basic Radionuclide Values for Transport of Radioactive Material
The basic radionuclide values are to be found in Table 2 of SSR-6. For example:
A1 for special form radioactive material (Special Form Certificate)
A2 for all other forms

28. UN Numbers for Materials in Type A packages
RADIOACTIVE MATERIAL, TYPE A PACKAGE
UN 3327
RADIOACTIVE MATERIAL, TYPE A PACKAGE, FISSILE
UN 3332
RADIOACTIVE MATERIAL, TYPE A PACKAGE, SPECIAL FORM
UN 3333
RADIOACTIVE MATERIAL, TYPE A PACKAGE, SPECIAL FORM, FISSILE 28

29. Design Requirements for Type A Package
Type IP-3 for solids, plus
If designed to contain liquid radioactive material, the free drop test will be from a height of 9m onto an unyielding target followed by a penetration test from an increased height of 1.7m
The design shall include sufficient absorbent material to absorb twice the volume of liquid contents, or must have a containment system composed of a primary inner and secondary outer containment components designed to enclose and retain the liquid contents
For packages designed to contain gases, the package shall prevent loss or dispersal (tritium and noble gases are excepted)
When subjected to water spray test, followed by free drop test, stacking test and penetration test (normal conditions of transport), loss or dispersal of contents would be prevented and no more than 20% increase in the maximum surface dose rate at any external surface
Type A package
(after 9m drop test) 29

30. Type A Tests to Simulate Normal Conditions of Transport
Water spray test
Free drop test on unyielding target
Stacking test
Penetration test
Resulting in the most
damaging effect to the
package
Key Points:
Detailed discussion on design and testing of packages should be addressed in Module 8, “Package Requirements & Test Procedures.” At this time, simply recite the information on the slide and add minimal information as deemed appropriate.
Objective(s):
Obj. 3 and 4
References:
TS-R-1, ¶ 620
Exercises:
None

31. Water Spray Test for Type A packages
Simulates rainfall at rate of 50 mm/h
Applied for one hour
Package allowed to soak to maximum extent prior to next test
Intended for packages utilizing fiberboard
May be omitted (reasoned argument) if package materials are clearly not vulnerable to this test
Para. 721

32. Free Drop Test for Type A Packages
Simulates drops during normal transport
Specimen dropped so as
to cause maximum damage
Dropped onto flat,
unyielding target
Height of drop is graded
1.2 m if package <5000 kg
0.9 m if package > 5000 kg, < kg
0.6 m if package > kg, < kg
0.3 m if package > kg
Para. 722

33. Stacking Test for Type A Packages
Intended to ensure effectiveness of package in static compression loading
Specimen required to withstand for 24 h
5 times package weight stacked on top, or
13 kPa (0.13 kgf/cm2) multiplied by the vertically-projected area of the package
whichever is greater
Para. 723

34. Penetration Test for Type A Packages
Uses a 6 kg non-deformable bar with 32 mm diameter hemispherical head
Dropped onto package from height of 1 m
Direction/point of impact must assure maximum potential damage
Simulates objects falling onto package, impact from loading hooks or forklifts, without loss of contents
Para. 724

35. Type B Package
For large quantities of radioactive material as approved by the CA
meets Type B package design requirements to withstand accident conditions of transport
Surface dose rate ≤ 2 mSv/h (dose rate at 2 m distance ≤ 0.1mSv/h)
All marking and labelling requirements applicable
Subject to CA approval and package design approval certificate as Type B(U) or Type B(M) package issued by CA
Type B tests to simulate accident conditions of transport

36. Type B Packages (F-458) Type B(U) container can weigh 125 kg - 167 kg.
Shipping molybdenum-99, used ultimately in some 80% of all nuclear medicine or diagnostic scans. Also used for I-131

37. Thermal and impact protection
Transport Packaging
19.4”
10” 4”
2.75
7.25”
Shielding Vessel
15.8”
Leak Proof Insert
Overpack
Radioactive shielding
Containment of isotope
Thermal and impact protection
some shielding

38. Layers of protection (Type B)

39. Cobalt - 60
Cobalt-60 pencils emit gamma radiation - this energy is harnessed to eliminate pathogens and microbes
Cobalt-60:
- A solid metal
- Non-fissionable
- Non-soluble
- Non-dispersible
- Non-flammable
- Long half life
- Large quantities per container
- Sources and containers
licensed
year half-life

40. Special Form Requirements
Special form radioactive material shall mean either an indispersible solid radioactive material or a sealed capsule containing radioactive material
At least one dimension not less than 5mm
No break or shatter under
Impact test – free drop from a height of 9m
Percussion test – drop a 25mm diameter bar, 1.4 kg mass, from 1m height
Bend test – minimum length 10cm, rigidly clamped in horizontal position with half length exposed
No melting or dispersal in the heat test – 800 ºC for 10 minutes
Example: Special Form in a Type A package
A2 (0.6 TBq Cs137)
A1 (2 TBq Cs137 Special Form) 40

41. Sea Freight Container Handling
Containers must be able to withstand worst-case potential accident conditions

42. F-168: A Type B(U) Package
Large dimensions, weight and radioisotope holding capacity
Cobalt-60 to sterilization facilities:
- ports for export to overseas destinations
- road/ocean/rail shipments

43. F-168 Package: Layers of Protection
Steel-covered insulated fire shields for thermal protection
Steel fins dissipate heat during normal conditions of transport and provide impact protection
11 inches (270 mm) of lead shielding, encased in steel for radiation protection
Cage containing double-encapsulated sealed sources
Weight: 5,445 kg (12,000 lbs)

44. F-168 Container Design – Shielding

45. F-168 Container Design - Plug

46. Design Requirements for Type B Package
Type B content limits
The content limit is as defined in the package design safety case which is submitted to the competent authorities for assessment and approval
Type B package requirements
Type A, plus
Capable of operating in ambient temperatures of -40ºC to +38 ºC
Be capable of being left unattended for one week in an ambient of 38ºC plus insolation at equilibrium thermal conditions
with the heat generated by radioactive contents
package continues to meet its applicable requirements for
containment,
shielding, and
criticality control (fissile contents) 46

47. Design Requirements for Type B Package (cont.)
Restrict the loss of radioactive contents to 10-6A2 per hour when subjected to Type A tests
Restrict the loss of radioactive contents to A2 in a week when subjected to Type B tests:
A free drop test from 9m onto an unyielding target
A penetration test
A fully engulfing fire test of 800ºC for 30 minutes
A water immersion test of 15m for a minimum of 8 hours
A water immersion test of 200m for 1 hour ( >105 A2 )
A maximum normal operating pressure of 700 kPa (gauge) 47

48. Classification of Radioactive Material
Radioactive material should be classified and
assigned under the appropriate UN number and associated proper shipping name
The UN number assigned depends on
- the activity level of the radionuclides contained in the package,
- the fissile or non-fissile properties of these radionuclides,
- the type of package, and
the nature or form of the radioactive contents of the package, or
- on whether there are special arrangements governing
the transport operation. 48

49. Flow Diagram for Classification of RAM (non-fissile) into appropriate UN Number (1)
Activity ≤ AL or AC (236, Table 2)(1)(2) and; Non-radioactive solid objects contaminated on any surfaces ≤0.4 Bq/cm2 for beta and gamma and low toxicity alpha; or ≤0.04 Bq/cm2 for all other alpha emitters. (107f, 214).
Exempt
Start Y N
Radioactive Material (107)(2) (a) An integral part of the means of transport; (b) Moved within an establishment; (c) Implanted or incorporated into a person or live animal; (d) In consumer products; (e) Natural material and ores provided that the activity concentration does not exceed 10 times AC. Y N
(1) AL - activity limit for an exempt consignment in Table 2 of TS-R-1, 2009 Edition; AC - activity concentration for exempt material in Table 2 of TS-R-1, 2009 Edition;
(2) The number in ( ) – the paragraph number or table of TS-R-1, 2009 Edition; 49

50. Flow Diagram for Classification of RAM (non-fissile) into appropriate UN Number (2)
Excepted package
Package surface dose rate ≤ 5 µSv/h (515)
Empty Packaging (425)
UN 2908 Y Y N
UN 2909
Manuf U/ Th (426)(3) Y N
Instruments or articles containing no more activity than the values: (423, Table 5)
Physical state of contents
Solids
Liquids
Gases
Special form
Other form
Tritium
Item limits
10-2A1
10-2A2
10-3A2
2x10-2A2
10-3A1
Package limits A1 A2
10-1A2
2x10-1A2
UN 2911 N Y N
Material, other than instrument(s) or article(s), containing no more activity than the values: (424, Table 5)
Physical state of contents
Solids
Liquids
Gases
Special form
Other form
Tritium
Package limits
10-3A1
10-3A2
10-4A2
2x10-2A2
UN 2910 Y N
(3) Manuf U/Th – articles manufactured from natural uranium or depleted uranium or natural thorium; 50

51. Flow Diagram for Classification of RAM (non-fissile) into appropriate UN Number (3)
SCO (413) Y Y
Industrial Package Type IP-1, IP-2, IP-3
The external radiation level at 3 m from the unshielded material or collection of objects ≤ 10 mSv/h (516) and the total activity in a single hold or compartment of an inland watercraft, or in another conveyance does not exceed the limits (520,Table 7) N
UN 2912
LSA-I (409a) Y N
UN 3321
LSA-II (409b) Y N N
UN 3322
LSA-III (409c) N Y 51

52. Activities not greater than the following (433)
Flow Diagram for Classification of RAM (non-fissile) into appropriate UN Number (4)
Type A Package (427)
UN 3332
Special Form Y Y N N
Activities not greater than the following (433)
For LDRM — as authorized for the package design as specified in the certificate of approval,
For special form radioactive material — 3000A1; or A2, whichever is the lower; or
(c) For all other radioactive material — 3000A2.
UN 2915
Air Transport
Non Special Form Y N
Typ B Package
(430)
Type C Package (430, 434)
UN 3323 Y N Y 52

53. Flow Diagram for Classification of RAM (non-fissile) into appropriate UN Number (5)
Type B(U) Package Requirements (431)
UN 2916 Y N
Type B(M) Package Requirements (432)
UN 2917 Y N
Transport prohibited but see Special Arrangement
Special Arrangement (310)
Radioactive Material for which classification into one of the above UN Numbers is impractical, may be transported, subject to competent authority approval.
Transport under Special Arrangement
UN 2919 53

54. Summary
Based on the safety concept of the IAEA transport regulations safety in transport is mainly assured by the package itself together with some control measures during transport and approval needs by the competent authority, where necessary
Optimal characterization of radioactive contents is an essential pre-requisite for optimal package selection
Package selection should take into consideration not only material type, but also contents limits and shipment constraints
By using the flow diagram for classification of radioactive material into appropriate UN number proper package selection can be supported
Key Points:
Summarize the information covered in this module. Expand as necessary.
Objective(s):
All objectives
References:
Module 7 materials
Exercises:
Perform exercise targeted to the optimal selection of a package.

55. Questions?
Thank you 55

56. Extra Slides

57. IAEA Transport Regulations – Basis for safe transport, reviewed / revised continuously
Start of the revision process
(250 proposals from MS)
TRANSSC 19
TRANSSC 20
1st Draft of the new TS-R-1
(to MS for comments, 120-Day-Role)
TRANSSC 21
2nd Draft of the new TS-R-1
(send to MS)
TRANSSC 22
(Adoption)
Board of Governors
(Approval as SSR-6)
Oct. 2009
Jun. 2010
Aug. 2010
Dec. 2010
Apr. 2011
Jun. 2011
6th March 2012 57

58. Implementation of IAEA Regulations through Dangerous Goods Transport Regulations Class 7
IAEO UN
international Recommen-dations
class 7
all 9 classes of dangerous goods
CCNR/UNECE
ICAO
IMO
OTIF
UNECE
international modal provisions
national modal provisions
LuftVZO
GGVSee
GGVSEB 58

59. Scope of the Transport Regulations
The Regulations apply to transport of radioactive material by all modes of transport
on land (road, rail, inland waterway)
on sea (maritime)
In the air
Transport
comprises all operations and conditions associated with, and involved in, the movement of radioactive material; these include the design, manufacture, maintenance and repair of packaging, and the preparation, consigning, loading, carriage including in-transit storage, unloading and receipt at the final destination of loads of radioactive material and packages.
Radioactive material
is any material containing radionuclides where both the activity concentration (Bq/g) and the total activity in the consignment (Bq) exceed the values specified in Table 2 of SSR-6 59

60. Scope of the Transport Regulations (cont.)
SSR-6 does not apply to radioactive material:
that is an integral part of the means of transport
moved within an establishment not involving public roads or railways
implanted in or incorporated into a person or live animal
In or on a person who is to be transported for medical treatment
in consumer products having received regulatory approval, following sale to the end user
SSR-6 also does not apply to:
Natural material and ores containing natural radionuclides, provided the activity concentration that does not exceed 10 times the values listed in Table 2
Non radioactive solids objects with surface contamination levels ≤ levels defined in para 214
The regulations are not intended to apply to movements of radioactive material that form an integral part of the means of transport, such as depleted uranium counterweights or tritium exit signs used in aircraft.
However, vehicles carrying density measuring devices for example, where the carriage is incidental to the use of the radioactive material do fall under the scope of the Regulations.
Cardiac pacemakers are an example of implantation in persons. Another example is the case of people or animals treated with radioisotopes.
Smoke detectors or luminous dials are examples of consumer products containing small amounts of radioactivity that are on sale to the general public in many countries. Such consumer products are only outside the scope of the Regulations after sale to the end user. Any transport between manufacturer, distributor and retailer is within the scope of the Regulations.
The scope of the Regulations includes those natural materials and ores that form part of the nuclear fuel cycle or which will be processed in order to use their radioactive properties.
The Regulations do not however apply to other ores which may contain naturally occurring radionuclides, but whose usefulness does not lie in the fissile, or radioactive properties of those nuclides.

61. Objective and basic safety concept
The objective of these Regulations is to protect persons, property and the environment from the effects of radiation during the transport of radioactive material. This protection is achieved by requiring:
containment of the radioactive contents
control of external radiation levels
prevention of criticality
prevention of damage caused by heat

62. Basic safety concept applying a graded approach to
These requirements are satisfied by
applying a graded approach to
performance standards applied to package designs
contents limits for packages and conveyances
depending upon the hazard of the radioactive contents
imposing requirements on
design and operation of packages
maintenance of packagings
considering the nature of the radioactive contents
requiring administrative controls including, where appropriate, approval by a competent authority

63. Basic safety concept (cont.)
Regulatory approach (SSR-6 para 106)
A graded approach is applied in specifying the performance standards which are characterized in terms of three general severity levels:
(a) Routine conditions of transport (incident free);
(b) Normal conditions of transport (minor mishaps);
(c) Accident conditions of transport.
In summary safety is mainly assured by the package itself together with some control measures during transport and approval needs by the competent authority, where necessary 63

64. Type C package
Needed only for very large quantities of radioactive material ( > 3000 A2 ) as approved by the CA for air transport
Meets Type B(U) package design requirements + enhanced impact test (90 m/s on unyielding target), enhanced thermal test ( 800 °C for 1 h) and burial test to withstand air accident conditions of transport
Surface dose rate ≤ 2 mSv/h (dose rate at 2 m distance ≤ 0.1mSv/h)
All marking and labelling requirements applicable
Subject to CA approval and package design approval certificate as Type C package issued by CA

65. Other PackageTypes
Packages containing fissile material (U-233,-235, Pu-239,-241), Type IF, AF, B(U)F, B(M)F, CF
Additional requirements regarding criticality safety
Subject to CA approval (package design approval certificate)

66. Other PackageTypes (cont.)
Packages containing Uranium Hexafluoride (UF6)
In quantities of 0,1 kg or more additional structural and integrity requirements regarding containment
Subject to CA approval (package design approval certificate H(U) or H(M))

67. Introduction to Testing
Type A and below testing programmes can be performed at many establishments
Type B tests require more specialized, sophisticated & expensive equipment and facilities

68. Type B Tests - Accident Conditions of Transport
Tests for Type B Packages are designed to simulate extremely severe accidents in surface transport modes

69. Mechanical Tests for Type B Packages
Drop from 9m onto unyielding target
Drop from 1m onto flat top face of steel bar of 150 mm diameter mounted on unyielding surface
Para. 727

70. Thermal Test for Type B Packages
Package fully engulfed in thermal environment providing a heat flux equivalent to flames of at least 800°C from liquid hydrocarbon pool fire, for at least 30 minutes -
average flame emissivity > 0.9
surface absorptivity = 0.8
Para. 728

71. Immersion Test for Type B Packages
Package immersed under 15 m head of water for 8h in attitude leading to maximum structural damage (test may be conducted on separate specimen)
Enhanced water immersion test for packages containing more than 105 A2 under 200m head of water for not less than 1h
Paras. 729 and 730