International Atomic Energy Agency Transport of Radioactive Material

International Atomic Energy Agency Transport of Radioactive Material A Detailed Overview Stephen Whittingham Head of Transport Safety Unit Division of Radiation, Transport & Waste Safety Department of Nuclear Safety and Security email: s. whittingham@iaea. org

Overview • Introduction • Overview of transport of radioactive material • The international regulatory framework • IAEA SSR-6 Transport Regulations International Atomic Energy Agency

Overview of transport of radioactive material (1) • In industry - non-destructive testing and measurement • In our homes and work places, smoke detectors and energy saving lights • In the environment - control of disease carrying insects, removal of pests in food and other goods • Mobile phones – computers and mobile phones contain electronic components made of tantalum metal (extracted from a radioactive ore) • Civil nuclear power generation programmes International Atomic Energy Agency

Overview of transport of radioactive material (1) In health care Diagnosis and treatment of cancer, heart disease and organ failure 80% of surgical gloves and nearly 50% of disposable medical devices are sterilized using radioactive materials Each Year Over 4 billion diagnostic medical radiation procedures 50 million nuclear medicine procedures 5. 5 million patients treated with radiotherapy In over 50 countries International Atomic Energy Agency

Overview of transport of radioactive material (1) • ~20 million shipments of radioactive material occur each year, much less than 5% by the nuclear industry • Commercial shipping (for larger sources, bulk material Uranium ores, etc) • Transport by air (short half-life material – Radiopharmaceuticals) • Almost, if not all, by road • Small percentage by rail International Atomic Energy Agency

Regulations – IAEA Safety Standards Hierarchy (2) Safety Fundamentals Safety Requirements Safety Guides International Atomic Energy Agency

Regulations – IAEA Safety Standards (2) The IAEA Safety Standards SSG 26 Advisory Material IAEA TS-G-1. 2 Emergency Response IAEA TS-G-1. 3 Radiation Protection Programmes IAEA TS-G-1. 4 Management System IAEA TS-G-1. 5 Compliance Assurance GSR Part 1 SSG 33 SSR 6 (2012) GSR Part 3 Schedules Guidance Documents International Atomic Energy Agency

Regulations – The international regulatory framework (2) Mainly Package design approval Regulators / some Transport Regulators Some countries UN MODEL REGULATIONS All 9 Dangerous Goods Classes - All modes SSR 6 (2012) Class 7 - All modes MODAL REGULATIONS AIR, LAND & SEA All 9 Dangerous Goods Classes Road, Rail and Inland Waterway (Europe) Sea Air International Atomic Energy Agency

Regulations – IAEA SSR-6 – Overview of regulatory framework(2) SSR-6 • • • Prescriptive requirements - revised on biennial basis • No guidance for UN or modal provisions, so legal texts need to address everything • • Modes take Class 7 provisions from UN, not from SSR 6 Supported by Advisory Material – aids consistent interpretation Global, multi-modal but not mandatory All 168 IAEA Member States can participate Transposed into UN Model Regulations Text does not look like UN or modal texts Few UN national delegations include Class 7 experts International Atomic Energy Agency

Regulations – UN Model Regulations (2) • UNITED NATIONS SUB-COMMITTEE OF EXPERTS on the transport of dangerous goods • A body established by ECOSOC (UN Economic and Social Council) in 1957 International Atomic Energy Agency

Regulations – UN Model Regulations (2) • Was originally the UN Committee of Experts on the Transport of Dangerous Goods • Now a sub-committee of UN Committee of Experts on the Transport of Dangerous Goods and on the Globally Harmonized System of Classification and Labelling of Chemicals • Originally consisted of ‘experts’ drawn from countries with demonstrable expertise and interest in the transport of dangerous goods International Atomic Energy Agency

Regulations – UN Model Regulations (2) • Draws up non-mandatory ‘Recommendations on the Transport of Dangerous Goods’ for all modes of transport throughout the world • Written in the form of ‘Model Regulations’ for international and national legislation • Known as the ‘Orange Book’ International Atomic Energy Agency

Regulations – UN Model Regulations (2) • • Makes decisions by simple majority voting - not by consensus • Non-voting countries and inter-governmental organisations can attend as ‘observers’ • International trade associations in UN consultative status may also attend • Currently working on the 20 th - revised edition (19 th) taking effect from 1 January 2016 • • • Works on 2 year revision cycle Currently 27 voting countries, increasing geographical representation but European dominated Meets in Palais des Nations in Geneva each June and December Ad hoc Working Groups meet (inter-session) if required International Atomic Energy Agency

Regulations – International framework (2) National State variations Regulations Modal Regulations UN Model Regulations IAEA SSR 6 (2012) International Atomic Energy Agency

Regulations – SSR-6 (2) Objective of SSR-6 (para 104) … is to establish requirements that must be satisfied to ensure safety and to protect persons, property and the environment from the effects of radiation in 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. No routeing or physical protection controls are specified - these may be implemented for reasons other than radiological safety International Atomic Energy Agency

Regulations – SSR-6 (2) 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. International Atomic Energy Agency

Regulations – SSR-6 Definitions (2) ‘Transport’ (SSR-6 para 106) … 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 (SSR-6 para 236) …. . any material containing radionuclides where both the activity concentration (Bq/g) and the total activity in the consignment (Bq) exceed the values specified in paras 402 - 407 International Atomic Energy Agency

Regulations – SSR-6 Definitions (2) Packaging (SSR-6 para 232) Packaging shall mean one or more receptacles and any other components or materials necessary for the receptacles to perform the containment and other safety functions Package (SSR-6 para 231) …. . shall mean the packaging with its radioactive contents as presented for transport International Atomic Energy Agency

Regulations – SSR-6 Definitions (2) Consignor shall mean any person, organization or government which prepares a consignment for transport (SSR-6 para 212) Carrier shall mean any person, organization or government undertaking the carriage of radioactive material by any means of transport. The term includes both carriers for hire or reward (known as common or contract carriers in some countries) and carriers on own account (known as private carriers in some countries (SSR-6 para 206) Consignee shall mean any person, organization or government which is entitled to take delivery of a consignment (SSR-6 para 210) International Atomic Energy Agency

Regulations – SSR-6 Definitions (2) Unilateral approval shall mean an approval of a design which is required to be given by the competent authority of the country of origin of the design only (SSR-6 para 205) Multilateral approval shall mean approval by the relevant competent authority of the country of origin of the design or shipment, as applicable, and also, where the consignment is to be transported through or into any other country, approval by the competent authority of that country (SSR-6 para 204) International Atomic Energy Agency

Regulations – SSR-6 General Provisions (2) • Radiation protection shall be optimised using ALARA, social and economic factors being taken into account • Emergency response provisions, established at national and/or international levels shall be observed • Management systems shall be established to standards acceptable to the competent authority • Training – the provision of appropriate radiation protection training for workers and general awareness/familiarisation training for others and the need for training records International Atomic Energy Agency

SSR-6 Activity limits and classification (2) Activity Limits Packaging Type and Classification Activity Content (Bq) Package Type Limits Activity Concentration (Bq/g) Package Requirements Solid, Liquid or gas Package Certification Radionuclide(s) Special Form Activity Content (A 1, A 2) Radiometric survey Accumulation of Packages and Consignment Limits TI / CSI Dose rates - unshielded (3 m) - surface - 1 m / 2 m Temperature Contamination I-White, II & III Yellow International Atomic Energy Agency

SSR-6 Activity limits and material restrictions (2) A 1 and A 2 values • A series of exposure routes are considered, each of which might lead to radiation exposure (internal or external) to persons in the vicinity of a Type A package involved in a severe transport accident: • External photon dose • External beta dose • Inhalation dose • Skin and ingestion due to contamination transfer • Submersion dose (gaseous isotopes) • Effective or committed dose to a person in the vicinity 50 m. Sv • 0. 5 Sv for individual organs or 0. 15 Sv to the lens of the eye • Assumed a person will remain at 1 m from a damaged package for < 30 minutes International Atomic Energy Agency

SSR-6 Activity limits and material restrictions (2) Examples of A 1 and A 2 Radionuclide A 1 Mass (g) A 2 Mass (g) (TBq) Specific activity (TBq/g) Co-60 0. 4 0. 00095 420 Ir-192 1 0. 0029 0. 6 0. 0017 340 Mo-99 1 5. 6 E-5 0. 6 3. 3 E-5 18 000 International Atomic Energy Agency

SSR-6 Package types (2) Activity Limits Packaging Type and Classification Activity Content (Bq) Package Type Limits Activity Concentration (Bq/g) Package Requirements Solid, Liquid or gas Package Certification Radionuclide(s) Special Form Activity Content (A 1, A 2) Radiometric survey Accumulation of Packages and Consignment Limits TI / CSI Dose rates - unshielded (3 m) - surface - 1 m / 2 m Temperature Contamination I-White, II & III Yellow International Atomic Energy Agency

SSR-6 Graded approach (2) The performance criterion of a package type depends upon its permitted contents (A 1 and A 2) In IAEA SSR 6 the following categories are defined [CA approved]: • • • • Excepted packages Industrial packages Type (IP-1, IP-2, IP-3) [ IF for fissile material] Type A package [ AF for fissile material] Type B(M), Type B(U) package [ B(U)F and B(M)F for fissile material] Type C package [ CF for fissile material] Type H(U) [ H(U)F for fissile material] Type H(M) [ H(M)F for fissile material] Shipment approval (T) Special arrangement (X) Low specific activity (LSA-I, LSA-II and LSA-III) Surface contaminated objects (SCO-I, SCO-II) Special Form (S) Low Dispersible Radioactive Material (LDRM) International Atomic Energy Agency

SSR-6 Graded approach, UN numbers (2) UN number Proper shipping name Excepted package UN 2908 RADIOACTIVE MATERIAL, EXCEPTED PACKAGE – EMPTY PACKAGE 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 UN 3507 URANIUM HEXAFLUORIDE, RADIOACTIVE MATERIAL, EXCEPTED PACKAGE - less than 0. 1 kg per package, non-fissile or fissile excepted International Atomic Energy Agency

SSR-6 Graded approach, UN numbers (2) UN number Proper shipping name Low specific activity material (LSA-I, LSA-III) UN 2912 RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY (LSA-I), nonfissile or fissile excepted UN 3321 RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY (LSA-II), non -fissile or fissile excepted UN 3322 RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY (LSA-III), non-fissile or fissile excepted UN 3324 RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY (LSA-II), FISSILE UN 3325 RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY (LSA-III), FISSILE Surface contaminated objects (SCO-I, SCO-II) UN 2913 RADIOACTIVE MATERIAL, SURFACE CONTAMINATED OBJECTS (SCO-I or SCO-II), non-fissile or fissile excepted UN 3326 RADIOACTIVE MATERIAL, SURFACE CONTAMINATED OBJECTS (SCO-I or SCO-II), FISSILE International Atomic Energy Agency

SSR-6 Graded approach, UN numbers (2) UN number Proper shipping name Type A package UN 2915 RADIOACTIVE MATERIAL, TYPE A PACKAGE, non-special form, non-fissile or fissile excepted UN 3327 RADIOACTIVE MATERIAL, TYPE A PACKAGE, FISSILE, nonspecial form UN 3332 RADIOACTIVE MATERIAL, TYPE A PACKAGE, SPECIAL FORM, non-fissile or fissile excepted UN 3333 RADIOACTIVE MATERIAL, TYPE A PACKAGE, SPECIAL FORM, FISSILE Type B(U) package UN 2916 RADIOACTIVE MATERIAL, TYPE B(U) PACKAGE , non-fissile or fissile excepted UN 3328 RADIOACTIVE MATERIAL, TYPE B(U) PACKAGE, FISSILE International Atomic Energy Agency

SSR-6 Graded approach, UN numbers (2) UN number Proper shipping name Type B(M) package UN 2917 RADIOACTIVE MATERIAL, TYPE B(M) PACKAGE , non-fissile or fissile excepted UN 3329 RADIOACTIVE MATERIAL, TYPE B(M) PACKAGE, FISSILE Type C package UN 3323 RADIOACTIVE MATERIAL, TYPE C PACKAGE, non-fissile or fissile excepted UN 3329 RADIOACTIVE MATERIAL, TYPE C PACKAGE, FISSILE Uranium hexafluoride UN 2977 RADIOACTIVE MATERIAL, URANIUM HEXAFLUORIDE, FISSILE UN 2978 RADIOACTIVE MATERIAL, URANIUM HEXAFLUORIDE, non-fissile or fissile excepted International Atomic Energy Agency

SSR-6 Graded approach, UN numbers (2) UN number Proper shipping name Special arrangement UN 2919 RADIOACTIVE MATERIAL, TRANSPORTED UNDER SPECIAL ARRANGEMENT, non-fissile or fissile excepted UN 3331 RADIOACTIVE MATERIAL, TRANSPORTED UNDER SPECIAL ARRANGEMENT, FISSILE International Atomic Energy Agency

SSR-6 Excepted package (2) Permitted package contents and release following an accident Package type Excepted Permitted contents (package) 10 -3 A 1 (solid) 10 -3 A 2 (solid) 10 -4 A 2 (liquid) 2 x 10 -2 A 1 (tritium) 10 -3 A 1 (SF) 10 -3 A 1 (Gas) Permitted release following accident Entire contents International Atomic Energy Agency

SSR-6 Excepted package requirements (2) Medical radioisotope excepted package International Atomic Energy Agency

SSR-6 Type IP-1 and Type IP-2 (2) 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. 3 m to 1. 2 m (depending on package mass) • Stacking test (24 hours), the greater of 5 times package mass or 13 k. Pa x vertically projected area International Atomic Energy Agency

SSR-6 Type IP-3 (2) 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 -40°C to +70°C • 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 k. Pa • 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 International Atomic Energy Agency

SSR-6 Activity limits and material restrictions (2) Examples of A 1 and A 2 Radionuclide A 1 Mass (g) A 2 Mass (g) (TBq) Specific activity (TBq/g) Co-60 0. 4 0. 00095 420 Ir-192 1 0. 0029 0. 6 0. 0017 340 Mo-99 1 5. 6 E-5 0. 6 3. 3 E-5 18 000 International Atomic Energy Agency

SSR-6 Special Form (2) • At least one dimension not less than 5 mm • Impact test – free drop from a height of 9 m • Percussion test – drop a 25 mm diameter bar, 1. 4 kg mass, from 1 m height • Bend test – minimum length 10 cm, rigidly clamped in horizontal position with half length exposed • Heat test – 800 ºC for 10 minutes Special Form in a Type A package • • A 2 (0. 6 TBq Cs 137) A 1 (2 TBq Cs 137 Special Form) International Atomic Energy Agency

SSR-6 Type A package (2) Type A content limits • B(i) is the activity of radionuclide i as special form radioactive material • A 1(i) is the A 1 value for radionuclide i • C(j) is the activity of radionuclide j as other than special form radioactive material • A 2(j) is the A 2 value for radionuclide j International Atomic Energy Agency

SSR-6 Type A package (2) Type A content limits • The content limit is A 2 or A 1 (Special Form) Type A package – requirements include • Type IP-3, plus • If designed to contain liquid radioactive material, the free drop test will be from a height of 9 m onto an unyielding target • Followed by a penetration test from an increased height of 1. 7 m • The design should include shall include sufficient absorbent material to absorb twice the volume of liquid contents, or • 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) • Additional requirements for fissile material International Atomic Energy Agency

SSR-6 Type A package (2) Type A package (after 9 m drop test) International Atomic Energy Agency

SSR-6 Type B package (2) 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) International Atomic Energy Agency

SSR-6 Type B package (2) • • Restrict the loss of radioactive contents to 10 -6 A 2 per hour when subjected to normal conditions of transport tests Restrict the loss of radioactive contents to A 2 in a week when subjected to: • A free drop from 9 m onto an unyielding target • A penetration test • An enveloping fire of 800ºC for 30 minutes • A water immersion test of 15 m for a minimum of 8 hours • A water immersion test of 200 m for 1 hour ( >105 A 2 ) A maximum normal operating pressure of 700 k. Pa (gauge) – Type B(U) Additional requirements for fissile material International Atomic Energy Agency

SSR-6 Type B package (2) International Atomic Energy Agency

SSR-6 Permitted package dose rates (2) Dose rates Package type Surface** Excepted 5μSv/h 2 m 3 m* 0. 1 m. Sv/h 10 m. Sv/h IP-I, II Type A 2 m. Sv/h 0. 1 m. Sv/h Type B 2 m. Sv/h 0. 1 m. Sv/h Type C 2 m. Sv/h 0. 1 m. Sv/h * unshielded radioactive contents ** 10 m. Sv/h for packages under exclusive use (except by air which is limited to 2 m. Sv/h) International Atomic Energy Agency

SSR-6 Consignment limits (2) Activity Limits and Classification Activity Content (Bq) Activity Concentration (Bq/g) Solid, Liquid or gas Radionuclide(s) Activity Content (A 1, A 2) Packaging Type Package Type Limits Package Requirements Package Certification Special Form Radiometric survey Accumulation of Packages and Consignment Limits TI / CSI Dose rates - unshielded (3 m) - surface - 1 m / 2 m Temperature Contamination I-White, II & III Yellow International Atomic Energy Agency

SSR-6 Definitions (2) Transport Index (SSR-6 para 244 and 523(a)) TI is a number used to provide control over radiation exposure. TI is assigned to a package, overpack or freight container, or to unpackaged LSA-I or SCO-1 TI =Radiation level at 1 m from surface of package (m. Sv/h) x 100 Criticality Safety Index (SSR-6 para 218) CSI is a number used to provide control over the accumulation of packages, overpacks or freight containers containing fissile material CSI assigned to a package, overpack or freight container containing fissile material International Atomic Energy Agency

SSR-6 Consignment TI limits (2) Transport Index (TI) limits for conveyances not under Exclusive Use Type of conveyance Limit on sum of TIs Freight container (small, large) 50 Vehicle 50 Aircraft Passenger Cargo Seagoing vessel Hold, compartment or defined deck area: Packages, overpacks, small freight containers Large freight containers Total vessel Packages, overpacks, small freight containers Large freight containers 50 200 200 No limit International Atomic Energy Agency

SSR-6 Consignment CSI limits (2) CSI limits for conveyances containing fissile material Type of conveyance Limit on sum of CSIs Not Exclusive Use Vehicle Aircraft Passenger Cargo Seagoing vessel Hold, compartment or defined deck area: Packages, overpacks, small freight containers Large freight containers Total vessel Packages, overpacks, small freight containers Large freight containers 50 / 50 na / 100 50 Freight container (small / large) Exclusive Use 100 50 50 na 100 50 50 100 200 No limit International Atomic Energy Agency

SSR-6 Temperatures (2) • The design of the package shall take into account ambient temperatures and pressures that are likely to be encountered during routine conditions of transport (SSR-6 para 616) • When transported by air, in an ambient of +38 ºC, and in the absence on insolation, accessible surface temperature of package ≤ +50 ºC (SSR-6 para 619) • When transported by air, integrity of containment of packages not affected by ambient temperatures -40 ºC to +55 ºC (SSR-6 para 620) • Components of the packaging -40 ºC to +70 ºC (SSR-6 para 639) • Unless transported by air, in an ambient of +38 ºC, and in the absence on insolation, accessible surface temperature of package ≤ +85 ºC, when transported under exclusive use (SSR-6, para 655) International Atomic Energy Agency

SSR-6 Contamination (2) Non-fixed contamination on the external surfaces of a package under routine conditions of transport shall not exceed: (IAEA SSR-6 para 508) (a)4 Bq/cm 2 for beta and gamma emitters and low toxicity alpha emitters (b) 0. 4 Bq/cm 2 for all other alpha emitters These limits apply when averaged over 300 cm 2 of any part of the surface Fixed contamination (c) Radiation level shall not exceed 5 µSv/h at the surface Non-fixed contamination on the external and internal surfaces of overpacks, freight containers, tanks, IBCs and conveyances shall not exceed (a) and (b) except: If equipment is dedicated to the transport of unpackaged radioactive material under exclusive use – (a), (b) and (c) do not apply to the internal surfaces (IAEA SSR-5 para 514) International Atomic Energy Agency

SSR-6 Package Labels (2) International Atomic Energy Agency

SSR-6 Package labels (2) Transport index (TI) Maximum radiation level on external surface m. Sv/h Category 0 ≤ 0. 005 I - WHITE >0≤ 1 >0. 005 ≤ 0. 5 II - YELLOW > 1 ≤ 10 > 0. 5 ≤ 2 III - YELLOW > 10 > 2 ≤ 10 III – YELLOW * Radiation level at 1 m from surface of package (m. Sv/h) x 100 * Under exclusive use II-YELLOW and III-YELLOW shall not be carried in compartments occupied by passengers (IAEA SSR-6 para 563) International Atomic Energy Agency

SSR-6 Package Labels (2) International Atomic Energy Agency

Stephen Whittingham Head of Transport Safety Unit Division of Radiation, Transport & Waste Safety Department of Nuclear Safety and Security Thank you email: s. whittingham@iaea. org International Atomic Energy Agency