Regional Training Course on the Regional Training Course on the Safe Transport of Radioactive Material in the Safe Transport of Radioactive Material in the
CaribbeanCaribbeanModule 2.4Module 2.4
Transport Package Types and Material Classification
Paul Gray
June 3 2014Panama
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OverviewOverview
2
1. The classification and selection of materials and package types
2. The main requirements for package types
3. Flow diagram for classification of radioactive material into appropriate UN number
4. Summary
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“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
RADIOACTIVECONTENTS
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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)
RAM classified as LSA-I or SCO-I
may also be transported unpackaged
- This presentation will focus on Type A packages
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GRADED APPROACH TO TRANSPORTGRADED 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
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Basic safety functions of packages for Basic safety functions of packages for radioactive materialradioactive material
Hazards of the radioactive Material
Safety functions of the Packaging
Radiotoxicity(Contamination,Incorporation)
Radiation(α, β, γ, n-Radiation)
Heat release
Criticality
Shielding
Containment
Heat transfer
Criticality Safety
6
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Concept of a Safe Package – Graded ApproachConcept of a Safe Package – Graded ApproachThe greater the hazard the stronger the packageThe greater the hazard the stronger the package
7(Paras of IAEA Regulations TS-R-1, 2009)
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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
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UN Numbers for Excepted PackageUN Numbers for Excepted Package
9
Excepted package
UN 2908 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
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Quantities of Radioactive Material in Excepted Packages (UN 2910 and 2911)
Solids:
special form 10-2A1 A1 10-3A1
other form 10-2A2 A2 10-3A2
Liquids 10-3A2 10-1A2 10-4A2
Gases
tritium 2 x 10-2A2 2 x 10-1A22 x 10-2A2
special form 10-3A1 10-1A1 10-3A1
other forms 10-3A2 10-2A2 10-3A2
Physical State Instrument or article Materialsof contents Item limits Package limits Package limits
ACTIVITY LIMITS UN 2911 UN 2910
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Quantities of Radioactive Material in Excepted Packages (UN 2909 and 2908)
UN 2909: Unlimited quantities of manufactured articles• natural uranium• depleted uranium• natural thoriumIf 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)
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• 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
General Design Requirements for Excepted Packages
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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
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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
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.
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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
Low Specific Activity (LSA) Material (cont.)
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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
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
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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
Surface Contaminated Object (SCO) (cont.)
SCO-II
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UN Numbers for LSA Material and SCOUN Numbers for LSA Material and SCO
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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
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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
Design Requirements for Industrial Packages Type IP-1, IP-2, IP-3
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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)
Design Requirements for Industrial Packages Type IP-1, IP-2, IP-3 (cont.)
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Radioactive contents
Industrial package type Exclusive use Not exclusive use
LSA-I
Solid
Liquid
Type IP-1
Type IP-1
Type IP-1
Type IP-2
LSA-II
Solid
Liquid and gas
Type IP-2
Type IP-2
Type IP-2
Type IP-3
LSA-III Type IP-2 Type IP-3
SCO-I Type IP-1 Type IP-1
SCO-II Type IP-2 Type IP-2
Requirements for Industrial Package Types and LSA/SCO contents
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LSA and SCO in Industrial Packages
Activity limit for
Conveyances Hold (inland waterway)
LSA-I No limit No limit
LSA-II and LSA-IIINon-combustible solids
No Limit 100 A2
LSA-II and LSA-III Combustible solids and all
liquids and gases
100A2 10A2
SCO 100A2 10A2
Conveyance Limits for LSA/SCO in Industrial Packages
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Type A and Type B Packages 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
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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
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- 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
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Layers of protection (Type A)Layers of protection (Type A)
Security tape Packing tape Cardboard box Styrofoam for impact and
penetration protection Lead pot for shielding Absorbent material Vial
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Basic Radionuclide Values for Transport of Radioactive Material
Radionuclide (atomic number)
A1 (TBq)
A2 (TBq)
Activity concentration
for exempt material
(Bq/g)
Activity limit for
an exempt consignment
(Bq)
Am-241 1 x 101 1 x 10-3 1 x 100 1 x 104
Co-60 4 x 10-1 4 x 10-1 1 x 101 1 x 105
I-129 Unlimited Unlimited 1 x 102 1 x 105
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
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UN Numbers for Materials in Type A UN Numbers for Materials in Type A packagespackages
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Type A package
UN 2915 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
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• 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
Design Requirements for Type A Package
Type A package (after 9m drop test)
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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
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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
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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, < 10 000 kg– 0.6 m if package > 10 000 kg, <15 000 kg– 0.3 m if package > 15 000 kg
Para. 722
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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
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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
Para. 724
Simulates objects falling onto package, impact from loading hooks or forklifts, without loss of contents
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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
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Type B Packages (F-458)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
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Transport PackagingTransport Packaging
Thermal and impact protection
some shielding
10”
7.25”2.75
4”
19.4”
15.8”
OverpackShielding
VesselLeak Proof
Insert
Radioactive shielding Containment of isotope
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Layers of protection (Type B)Layers of protection (Type B)
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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 - 5.25 year half-life
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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)
Special Form Requirements
Special form radioactive material shall mean either an indispersible solid radioactive material or a sealed capsule containing radioactive material
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Sea Freight Container Handling
Containers must be able to withstand worst-case potential accident conditions
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F-168: A Type B(U) Package
Large dimensions, weight and radioisotope holding capacityCobalt-60 to sterilization facilities: - ports for export to overseas destinations - road/ocean/rail shipments
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F-168 Package: Layers of Protection
54.0 in. (1372 m m )
39.88 in. (1013 m m )
57.3
1 in
. (14
56 m
m)
8.0
in.
(203
mm
) (203
mm
)
8.0
in.
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)
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F-168 Container Design – Shielding
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F-168 Container Design - Plug
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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)
Design Requirements for Type B Package
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• 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)
Design Requirements for Type B Package (cont.)
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Classification of Radioactive MaterialClassification of Radioactive Material
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Radioactive material should be classified andassigned 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.
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Flow Diagram for Classification of RAM (non-Flow Diagram for Classification of RAM (non-fissile) into appropriate UN Number (1)fissile) into appropriate UN Number (1)
StartActivity ≤ 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).
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
N
N
Y
Y
(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;
(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;
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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.
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.
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Flow Diagram for Classification of RAM (non-Flow Diagram for Classification of RAM (non-fissile) into appropriate UN Number (2)fissile) into appropriate UN Number (2)
50
UN 2911
UN 2909
Y
N
N
Y
N
YYEmpty
Packaging(425)
UN 2908
Manuf U/Th (426)(3)
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 Special form
Other form
Item limits 10-2A1 10-2A2 10-3A2 2x10-2A2 10-3A1 10-3A2
Package limits A1 A2 10-1A2 2x10-1A2 10-2A1 10-2A2
N
UN 2910
N
Y
(3) Manuf U/Th – articles manufactured from natural uranium or depleted uranium or natural thorium;
(3) Manuf U/Th – articles manufactured from natural uranium or depleted uranium or natural thorium;
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 Special form
Other form
Package limits 10-3A1 10-3A2 10-4A2 2x10-2A2 10-3A1 10-3A2
Excepted packageExcepted package
Package surface dose rate ≤ 5 µSv/h (515)
Package surface dose rate ≤ 5 µSv/h (515)
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Flow Diagram for Classification of RAM (non-Flow Diagram for Classification of RAM (non-fissile) into appropriate UN Number (3)fissile) into appropriate UN Number (3)
51
UN 2913Y
N
Y
N
SCO(413)
LSA-I(409a)
Y
LSA-II(409b)
LSA-III(409c)
UN 2912
UN 3321Y
UN 3322Y
N
N
N
Industrial Package Type IP-1, IP-2, IP-3Industrial 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)
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)
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Flow Diagram for Classification of RAM Flow Diagram for Classification of RAM (non-fissile) into appropriate UN Number (4)(non-fissile) into appropriate UN Number (4)
52
Type APackage
(427)UN 3332
NN
SpecialForm
NonSpecial Form
Y
Y
Type CPackage
(430, 434)
UN 2915
Y
N Y UN 3323Typ B
Package(430)
AirTransport Y
N
Activities not greater than the following (433)
(a) For LDRM — as authorized for the package design as specified in the certificate of approval,
(b) For special form radioactive material — 3000A1; or 100 000A2, whichever is the lower; or
(c) For all other radioactive material — 3000A2.
Activities not greater than the following (433)
(a) For LDRM — as authorized for the package design as specified in the certificate of approval,
(b) For special form radioactive material — 3000A1; or 100 000A2, whichever is the lower; or
(c) For all other radioactive material — 3000A2.
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Flow Diagram for Classification of RAM (non-Flow Diagram for Classification of RAM (non-fissile) into appropriate UN Number (5)fissile) into appropriate UN Number (5)
53
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.
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.
TypeB(U) PackageRequirements
(431)
UN 2916
N
Transportunder SpecialArrangement
UN 2917
Y
UN 2919
TypeB(M) PackageRequirements
(432)
Y
N
Transport prohibited but see Special Arrangement
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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
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Questions?Questions?
55
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Extra SlidesExtra Slides
56
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IAEA Transport Regulations – Basis for safe IAEA Transport Regulations – Basis for safe transport, reviewed / revised continuouslytransport, reviewed / revised continuously
Oct. 2
009
Jun.
201
0
Aug. 2
010
Dec. 2
010
Apr. 2
011
Jun.
201
1
6th
Mar
ch 2
012
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)
57
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Implementation of IAEA Regulations through Implementation of IAEA Regulations through Dangerous Goods Transport Regulations Class 7Dangerous Goods Transport Regulations Class 7
58
international Recommen-
dations
international modal
provisions
national modal
provisions
IAEO UN
class 7
GGVSEBGGVSEBLuftVZOLuftVZO GGVSeeGGVSee
OTIF UNECE
all 9 classes of dangerous goods
ICAO IMOCCNR/UNECE
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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 materialis 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
Scope of the Transport Regulations
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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
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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
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Basic safety concept
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
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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
Basic safety concept (cont.)
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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
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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 safetySubject to CA approval (package design approval certificate)
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Other PackageTypes (cont.)
Packages containing Uranium Hexafluoride (UF6)
In quantities of 0,1 kg or more additional structural and integrity requirements regarding containmentSubject to CA approval (package design approval certificate H(U) or H(M))
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Introduction to Testing
• Type A and belowtesting programmes can be performed at many establishments
• Type B tests require more specialized, sophisticated & expensive equipment and facilities
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Type B Tests - Accident Conditions of Transport
Tests for Type B Packagesare designed to simulate extremely severe accidentsin surface transport modes
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Mechanical Tests for Type B Packages
Drop from 9m onto unyielding target
Para. 727
Drop from 1m onto flat top face of steel bar of 150 mm diameter mounted on unyielding surface
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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
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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