1 / 54

Transport of Radioactive Material A Detailed Overview

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

josephcharles
Télécharger la présentation

Transport of Radioactive Material A Detailed Overview

An Image/Link below is provided (as is) to download presentation Download Policy: Content on the Website is provided to you AS IS for your information and personal use and may not be sold / licensed / shared on other websites without getting consent from its author. Content is provided to you AS IS for your information and personal use only. Download presentation by click this link. While downloading, if for some reason you are not able to download a presentation, the publisher may have deleted the file from their server. During download, if you can't get a presentation, the file might be deleted by the publisher.

E N D

Presentation Transcript

  1. Transport of Radioactive MaterialA 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

  2. Overview • Introduction • Overview of transport of radioactive material • The international regulatory framework • IAEA SSR-6 Transport Regulations

  3. 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

  4. 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

  5. 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

  6. Safety Fundamentals Safety Requirements Safety Guides Regulations – IAEA Safety Standards Hierarchy (2)

  7. The IAEA Safety Standards Regulations – IAEA Safety Standards (2) SSG 26 Advisory Material IAEA TS-G-1.2 Emergency Response Radiation Protection Programmes IAEA TS-G-1.3 IAEA TS-G-1.4 Management System GSR Part 1 IAEA TS-G-1.5 Compliance Assurance SSG 33 Schedules SSR 6 (2012) Guidance Documents GSR Part 3

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

  9. Overview of regulatory framework – SSR-6 Regulations – IAEA SSR-6 (2) • Prescriptive requirements - revised on biennial basis • 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 • 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 • Few UN national delegations include Class 7 experts

  10. 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

  11. 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

  12. 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’

  13. Regulations – UN Model Regulations (2) • Makes decisions by simple majority voting - not by consensus • Currently 27 voting countries, increasing geographical representation but European dominated • 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 20th - revised edition (19th) taking effect from 1 January 2016 • Works on 2 year revision cycle • Meets in Palais des Nations in Geneva each June and December • Ad hoc Working Groups meet (inter-session) if required

  14. Regulations – International framework (2) National Regulations Modal Regulations UN Model Regulations IAEA SSR6 (2012) State variations

  15. 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

  16. 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.

  17. 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 thedesign, manufacture, maintenance and repair of packaging, and the preparation, consigning, loading, carriage including in-transit storage, unloading and receipt at the final destination of loadsof 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

  18. 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

  19. Regulations – SSR-6 Definitions (2) Consignor shall mean any person, organization or government which prepares a consignment for transport (SSR-6 para 212) Carriershall 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) Consigneeshall mean any person, organization or government which is entitled to take delivery of a consignment (SSR-6 para 210)

  20. Regulations – SSR-6 Definitions (2) Unilateral approvalshall 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 approvalshall 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)

  21. 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

  22. SSR-6 Activity limits and classification (2) Activity Limits Packaging Type Accumulation of Packages and Classification and Consignment Limits Activity Content (Bq) Package Type Limits TI / CSI Activity Concentration (Bq/g) Package Requirements Dose rates Solid, Liquid or gas Package Certification - unshielded (3m) Radionuclide(s) Special Form - surface Activity Content (A1, A2) Radiometric survey - 1 m / 2m Temperature Contamination I-White, II & III Yellow

  23. SSR-6 Activity limits and material restrictions (2) A1 and A2 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 mSv • 0.5 Sv for individual organs or 0.15 Sv to the lens of the eye • Assumed a person will remain at 1m from a damaged package for < 30 minutes

  24. SSR-6 Activity limits and material restrictions (2) Examples of A1 and A2

  25. SSR-6 Package types (2) Activity Limits Packaging Type Accumulation of Packages and Classification and Consignment Limits Activity Content (Bq) Package Type Limits TI / CSI Activity Concentration (Bq/g) Package Requirements Dose rates Solid, Liquid or gas Package Certification - unshielded (3m) Radionuclide(s) Special Form - surface Activity Content (A1, A2) Radiometric survey - 1 m / 2m Temperature Contamination I-White, II & III Yellow

  26. SSR-6 Graded approach (2) The performance criterion of a package type depends upon its permitted contents (A1 and A2) In IAEA SSR6 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)

  27. SSR-6 Graded approach, UN numbers (2)

  28. SSR-6 Graded approach, UN numbers (2)

  29. SSR-6 Graded approach, UN numbers (2)

  30. SSR-6 Graded approach, UN numbers (2)

  31. SSR-6 Graded approach, UN numbers (2)

  32. SSR-6 Excepted package (2) Permitted package contents and release following an accident

  33. SSR-6 Excepted package requirements (2) Medical radioisotope excepted package

  34. 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 0.3m to 1.2m (depending on package mass) • Stacking test (24 hours), the greater of 5 times package mass or 13kPa x vertically projected area

  35. 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 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

  36. SSR-6 Activity limits and material restrictions (2) Examples of A1 and A2

  37. At least one dimension not less than 5mm 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 Heat test – 800 ºC for 10 minutes Special Form in a Type A package A2 (0.6 TBq Cs137) A1 (2 TBq Cs137 Special Form) SSR-6 Special Form (2)

  38. SSR-6 Type A package (2) Type A content limits • B(i) is the activity of radionuclide i as special formradioactive material • A1(i) is the A1 value for radionuclide i • C(j) is the activity of radionuclide j as other than special formradioactive material • A2(j) is the A2 value for radionuclide j

  39. SSR-6 Type A package (2) Type A content limits • The content limit is A2 or A1 (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 9m onto an unyielding target • Followed by a penetration test from an increased height of 1.7m • 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

  40. SSR-6 Type A package (2) Type A package (after 9m drop test)

  41. 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)

  42. SSR-6 Type B package (2) • Restrict the loss of radioactive contents to 10-6A2 per hour when subjected to normal conditions of transport tests • Restrict the loss of radioactive contents to A2 in a week when subjected to: • A free drop from 9m onto an unyielding target • A penetration test • An enveloping fire 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) – Type B(U) • Additional requirements for fissile material

  43. SSR-6 Type B package (2)

  44. SSR-6 Permitted package dose rates (2) * unshielded radioactive contents ** 10 mSv/h for packages under exclusive use (except by air which is limited to 2 mSv/h)

  45. SSR-6 Consignment limits(2) Activity Limits Packaging Type Accumulation of Packages and Classification and Consignment Limits Activity Content (Bq) Package Type Limits TI / CSI Activity Concentration (Bq/g) Package Requirements Dose rates Solid, Liquid or gas Package Certification - unshielded (3m) Radionuclide(s) Special Form- surface Activity Content (A1, A2) Radiometric survey - 1 m / 2m Temperature Contamination I-White, II & III Yellow

  46. 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 1m from surface of package (mSv/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

  47. SSR-6 Consignment TI limits(2) Transport Index (TI) limits for conveyances not under Exclusive Use

  48. SSR-6 Consignment CSI limits(2) CSI limits for conveyances containing fissile material

  49. 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) SSR-6 Temperatures (2)

  50. Non-fixed contamination on the external surfaces of a package under routine conditions of transport shall not exceed: (IAEA SSR-6 para 508) 4 Bq/cm2 for beta and gamma emitters and low toxicity alpha emitters 0.4 Bq/cm2 for all other alpha emitters These limits apply when averaged over 300 cm2 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) SSR-6 Contamination (2)

More Related