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Safety Regulations for
Radioactive Material Transport
SAFE TRANSPORT OF RADIOACTIVE
MATERIAL
This document outlines the safety code approved by the Atomic Energy Regulatory Board (AERB) in November 2015 and published in March 2016, concerning the safe transport of radioactive material in India.
Foreword
The AERB is responsible for establishing safety standards and regulations for activities involving nuclear facilities and radiation sources, as per the Atomic Energy Act, 1962. This includes developing safety codes, standards, guides, and manuals. These are based on nationally and internationally accepted safety criteria. This revised safety code builds upon the earlier AERB/SC/TR-1; 1986, incorporating design and test requirements for low dispersible radioactive material, Type C packages, fissile-excepted material, and management systems, aligning with international standards.
Definitions
Carrier: Any entity (person, organization, or government) involved in transporting radioactive material via any mode of transport. Consignment: Any package or packages, or load of radioactive material, presented by a consignor for transport. Containment System: The assembly of packaging components designed to retain the radioactive material during transport. Criticality Safety Index (CSI): A number assigned to a package, overpack, or freight container containing fissile material to control accumulation. Design: The description of fissile material excepted under para. 4.6.1.1(f), special form radioactive material, low dispersible radioactive material, package or packaging that enables such an item to be fully identified. Deck Area: The area of a vessel's weather deck or a roll-on/roll-off ship's vehicle deck allocated for radioactive material stowage. Freight Container: A portable packaging with a capacity of no more than 3 m3, designed for mechanical handling, and resistant to stresses during handling and transport. Maximum Normal Operating Pressure: The maximum pressure above atmospheric pressure at mean sea level that would develop in the containment system in a period of one year under the conditions of temperature and solar radiation corresponding to environmental conditions in the absence of venting, external cooling by an ancillary system, or operational controls during transport.
Types of Packages: Packages covered by this safety code are subject to activity limits and material restrictions. These include Excepted packages, Industrial packages (Type IP-1, IP-2, and IP-3), Type B(M) packages and Type C packages. Packages containing fissile material or uranium hexafluoride are subject to additional requirements. Packaging: It may consist of one or more receptacles, absorbent materials, spacing structures, radiation shielding, service equipment for filling, emptying, venting and pressure relief devices for cooling, absorbing mechanical shocks, providing handling and tie-down capability, thermal insulation; and service devices integral to the package. Special Form Radioactive Material: An indispersible solid radioactive material or a sealed capsule containing radioactive material, conforming to specified requirements and approved by the Competent Authority. A1: The activity value of special form radioactive material listed in Table-I or derived in Section 3, used to determine activity limits. A2: The activity value of radioactive material (other than special form) listed in Table-I or derived in Section 3, used to determine activity limits. Fissile-Excepted: A consignment of radioactive material containing small quantities of fissile material that do not warrant specific additional requirements for criticality safety. Large Freight Container: A transport equipment article of permanent character, strong enough for repeated use, designed to facilitate goods transport without intermediate reloading, and designed to be secured and/or readily handled. Low Specific Activity (LSA) Material: Radioactive material with a limited specific activity or for which limits of estimated average specific activity apply. External shielding materials surrounding the LSA material should not be considered in determining the estimated average specific activity. Surface Contaminated Object (SCO): A solid object that is not itself radioactive but has radioactive material distributed on its surface.
Classification, Design and Test Requirements for
Packagings, Packages and Corresponding Activity Limits
This section covers:
Demonstration of Compliance with the Performance Standards for Packagings and Preparation of Specimen for Testing Target for Drop Tests General Requirements for all Packagings and Packages Additional Requirements for Packages Transported by Air Excepted Package Industrial Packages Packages Containing Uranium Hexafluoride Type A Package Type B(U), Type B(M) or Type C Package Packages Containing Fissile Material
Annexures
ANNEXURE-I: SUMMARY OF APPROVAL AND PRIOR NOTIFICATION
REQUIREMENTS (PART 1 to PART 4) ANNEXURE-II: SUMMARY OF CONSIGNMENTS REQUIRING EXCLUSIVE USE
References and Committees
The document includes a list of references, contributors, and committees involved in the development and review of the safety code. These include the Committee on Safe Transport of Radioactive Material (COSTRAM), the Standing Committee for Review and Revision of AERB Radiation Safety Documents (SCRRRSD), and the Advisory Committee on Radiological Safety (ACRS). It also lists safety codes and guides for regulation of transport of radioactive material.
Introduction
The safe transport of radioactive material is essential for various activities, including nuclear power production, and movement from supplier to user and to disposal facilities. This safety code incorporates UN recommendations and aligns with international instruments for the safe transport of dangerous goods. Compliance with this code, issued under rule 16 of the Atomic Energy (Radiation Protection) Rules, 2004, is mandatory for licensed individuals and institutions handling radioactive material.
Objective
The primary objective is to establish requirements that ensure safety and protect individuals, property, and the environment from radiation during the transport of radioactive material.
Scope
This safety code applies to the transport of radioactive material by all modes (land, water, air), including transport incidental to the use of the material. "Transport" encompasses all operations, including design, manufacture, maintenance, repair of packaging, preparation, consigning, loading, carriage (including in-transit storage), unloading, and receipt. The requirements aim to meet performance standards under routine, normal, and accident conditions.
Exclusions
The code does not apply to:
Radioactive material that is an integral part of the means of transport. Radioactive material in or on a person being transported for medical treatment due to accidental or deliberate intake or contamination.
Non-radioactive solid objects with surface contamination below specified limits (0.4 Bq/cm² for beta/gamma and low toxicity alpha emitters, 0.04 Bq/cm² for other alpha emitters).
Security
Measures must be implemented to secure radioactive material during transport to prevent theft, damage, and inappropriate relinquishment of control.
Subsidiary Risks
For radioactive material with subsidiary risks or transported with other dangerous goods, relevant transport regulations for dangerous goods apply in addition to this safety code.
Structure
The safety code is structured as follows:
Section 2: General provisions. Section 3: Basic radionuclide values (A1 and A2) and methods for calculating these values for mixtures. Section 4: Classification of radioactive material and design requirements for LSA-III, special form, and low dispersible form radioactive material, including test requirements. Section 5: Classification of packages, design requirements for packagings and packages, including test requirements. Section 6: Controls for transport of radioactive material. Section 7: Requirements for approvals and administration.
GENERAL PROVISIONS FOR RADIOLOGICAL
SAFETY
Radiation Protection
Doses received during the transport of radioactive material must remain below established dose limits. Organizations involved in the transport must implement a structured approach, considering the interactions between transport and other activities.
A radiation protection program (RPP) is required for the transport of radioactive material. This program must include dose limitation, emergency procedures, a training program, and segregation protocols. Segregation involves keeping packages, overpacks, freight containers with radioactive material, and unpackaged radioactive material away from workers, the public, photographic films, and other dangerous goods during transport and storage.
BASIC RADIONUCLIDE VALUES
General Provisions
Radioactive material must be classified according to the provisions outlined in this section and assigned to a UN number specified in Table-II.
Basic Radionuclide Values
Table-I provides the following basic values for individual radionuclides:
(a) A1 and A2 in TBq.
(b) Activity concentration limits for exempt material in Bq.g-1.
(c) Activity limits for exempt consignments in Bq.
Determination of Basic Radionuclide Values
For radionuclides not listed in Table-I, determining A1 and A2 values, activity concentration limits for exempt material, and activity limits for exempt consignments requires multilateral approval. An A2 value calculated using a dose coefficient for the appropriate lung absorption type, as recommended by the International Commission on Radiological Protection, may be used if the chemical forms of each radionuclide under normal and accident conditions of transport are considered.
Alternative basic radionuclide values to those in Table-I for the activity limit for an exempt consignment may be used when the radioactive material is enclosed in or is included as a component part of the instrument or other manufactured article and the active material is completely enclosed by non- active components. A device performing the sole function of containing radioactive material shall not be considered to be an instrument or manufactured article.
In radioactive decay chains where any daughter nuclide has a half-life longer than 10 days or longer than that of the parent nuclide, the parent and such daughter nuclides must be considered as mixtures of different nuclides.
Mixtures of Radionuclides
For mixtures of radionuclides, the basic radionuclide values may be determined using the following formula:
Xm= 1 / ∑i (f(i) / X(i) )
where:
f(i) is the fraction of activity or activity concentration of radionuclide i in the mixture.
X(i) is the appropriate value of A1 or A2, or the activity concentration limit for exempt material or the activity limit for an exempt consignment for radionuclide i.
Xm is the derived value of A1 or A2, or the activity concentration limit for exempt material or the activity limit for an exempt consignment in the case of a mixture.
Radionuclides with Unknown Activity
When the identity of each radionuclide is known but the individual activities of some are not, the radionuclides may be grouped. The lowest radionuclide value for each group may be used in the formula for mixtures of radionuclides and the following condition:
∑i {B(i)/A1(i)} + ∑{C(j)/A2(j)} ≤ 1
where:
B(i) is the activity of radionuclide i as special form radioactive material.
A1(i) is the A1 value for radionuclide i.
C(j) is the activity of radionuclide j as other than special form radioactive material.
A2(j) is the A2 value for radionuclide j.
Groups may be based on total alpha activity and total beta/gamma activity when these are known, using the lowest radionuclide values for alpha emitters or beta/gamma emitters, respectively.
Activity Concentration and Limits for
Radioactive Materials
Actinium (89)
Ac-225: Activity Concentration Limit for Exempt Material is 8 × 10– Bq.g-1, Activity Limit for an Exempt Consignment is 6 × 10–3 TBq, A is 1 × 101 TBq, and A2 is 1 × 104 TBq. Ac-227: Activity Concentration Limit for Exempt Material is 9 × 10– Bq.g-1, Activity Limit for an Exempt Consignment is 9 × 10–5 TBq, A is 1 × 10–1 TBq, and A2 is 1 × 103 TBq. Ac-228: Activity Concentration Limit for Exempt Material is 6 × 10– Bq.g-1, Activity Limit for an Exempt Consignment is 5 × 10–1 TBq, A is 1 × 101 TBq, and A2 is 1 × 106 TBq.
Astatine (85)
At-211: Activity Concentration Limit for Exempt Material is 2 × 101 Bq.g-1, Activity Limit for an Exempt Consignment is 5 × 10–1 TBq, A is 1 × 103 TBq, and A2 is 1 × 107 TBq.
Gold (79)
Au-193: A1 is 7 × 100 TBq, A2 is 2 × 102 TBq, and Activity Limit for an Exempt Consignment is 1 × 106 Bq.g-1. Au-199: Activity Concentration Limit for Exempt Material is 1 × 101 Bq.g-1, Activity Limit for an Exempt Consignment is 6 × 10–1 TBq, A is 1 × 102 TBq, and A2 is 1 × 106 TBq.
Barium (56)
Ba-131: Activity Concentration Limit for Exempt Material is 2 × 100 Bq.g-1, Activity Limit for an Exempt Consignment is 2 × 100 TBq, A1 is 1 × 102 TBq, and A2 is 1 × 106 TBq. Ba-133: Activity Concentration Limit for Exempt Material is 3 × 100 Bq.g-1, Activity Limit for an Exempt Consignment is 3 × 100 TBq, A1 is 1 × 102 TBq, and A2 is 1 × 106 TBq. Ba-133m: Activity Concentration Limit for Exempt Material is 2 × 101 Bq.g-1, Activity Limit for an Exempt Consignment is 6 × 10–1 TBq, A is 1 × 102 TBq, and A2 is 1 × 106 TBq. Ba-140: Activity Concentration Limit for Exempt Material is 5 × 10– Bq.g-1, Activity Limit for an Exempt Consignment is 3 × 10–1 TBq, A is 1 × 101 TBq, and A2 is 1 × 105 TBq.
Beryllium (4)
Be-7: Activity Concentration Limit for Exempt Material is 2 × 101 Bq.g-1, Activity Limit for an Exempt Consignment is 2 × 101 TBq, A1 is 1 × 103 TBq, and A2 is 1 × 107 TBq. Be-10: Activity Concentration Limit for Exempt Material is 4 × 101 Bq.g-1, Activity Limit for an Exempt Consignment is 6 × 10–1 TBq, A is 1 × 104 TBq, and A2 is 1 × 106 TBq.
Bismuth (83)
Bi-205: Activity Concentration Limit for Exempt Material is 7 × 10– Bq.g-1, Activity Limit for an Exempt Consignment is 7 × 10–1 TBq, A is 1 × 101 TBq, and A2 is 1 × 106 TBq. Bi-206: Activity Concentration Limit for Exempt Material is 3 × 10– Bq.g-1, Activity Limit for an Exempt Consignment is 3 × 10–1 TBq, A is 1 × 101 TBq, and A2 is 1 × 105 TBq. Bi-207: Activity Concentration Limit for Exempt Material is 7 × 10– Bq.g-1, Activity Limit for an Exempt Consignment is 7 × 10–1 TBq, A is 1 × 101 TBq, and A2 is 1 × 106 TBq.
Bi-210: Activity Concentration Limit for Exempt Material is 1 × 100 Bq.g-1, Activity Limit for an Exempt Consignment is 6 × 10–1 TBq, A is 1 × 103 TBq, and A2 is 1 × 106 TBq. Bi-210m: Activity Concentration Limit for Exempt Material is 6 × 10– Bq.g-1, Activity Limit for an Exempt Consignment is 2 × 10–2 TBq, A is 1 × 101 TBq, and A2 is 1 × 105 TBq. Bi-212: Activity Concentration Limit for Exempt Material is 7 × 10– Bq.g-1, Activity Limit for an Exempt Consignment is 6 × 10–1 TBq, and A2 is 1 × 105 TBq.
Berkelium (97)
Bk-247: Activity Concentration Limit for Exempt Material is 8 × 100 Bq.g-1, Activity Limit for an Exempt Consignment is 8 × 10–4 TBq, A is 1 × 100 TBq, and A2 is 1 × 104 TBq. Bk-249: Activity Concentration Limit for Exempt Material is 4 × 101 Bq.g-1, Activity Limit for an Exempt Consignment is 3 × 10–1 TBq, A is 1 × 103 TBq, and A2 is 1 × 106 TBq.
Bromine (35)
Br-76: Activity Concentration Limit for Exempt Material is 4 × 10– Bq.g-1, Activity Limit for an Exempt Consignment is 4 × 10–1 TBq, A is 1 × 101 TBq, and A2 is 1 × 105 TBq. Br-77: Activity Concentration Limit for Exempt Material is 3 × 100 Bq.g-1, Activity Limit for an Exempt Consignment is 3 × 100 TBq, A1 is 1 × 102 TBq, and A2 is 1 × 106 TBq. Br-82: Activity Concentration Limit for Exempt Material is 4 × 10– Bq.g-1, Activity Limit for an Exempt Consignment is 4 × 10–1 TBq, A is 1 × 101 TBq, and A2 is 1 × 106 TBq.
Carbon (6)
C-11: Activity Concentration Limit for Exempt Material is 1 × 100 Bq.g-1, Activity Limit for an Exempt Consignment is 6 × 10–1 TBq, A is 1 × 101 TBq, and A2 is 1 × 106 TBq. C-14: Activity Concentration Limit for Exempt Material is 4 × 101 Bq.g-1, Activity Limit for an Exempt Consignment is 3 × 100 TBq, A1 is 1 × 104 TBq, and A2 is 1 × 107 TBq.
Calcium (20)
Ca-41: Activity Concentration Limit for Exempt Material is Unlimited Bq.g-1, Activity Limit for an Exempt Consignment is Unlimited TBq, A is 1 × 105 TBq, and A2 is 1 × 107 TBq. Ca-45: Activity Concentration Limit for Exempt Material is 4 × 101 Bq.g-1, Activity Limit for an Exempt Consignment is 1 × 100 TBq, A1 is 1 × 104 TBq, and A2 is 1 × 107 TBq. Ca-47: Activity Concentration Limit for Exempt Material is 3 × 100 Bq.g-1, Activity Limit for an Exempt Consignment is 3 × 10–1 TBq, A is 1 × 101 TBq, and A2 is 1 × 106 TBq.
Radioactive Material Classification and
Requirements
This document outlines the classification, design, and testing requirements for radioactive materials, packagings, and packages. It covers various types of radioactive materials and the conditions under which they can be classified.
Low Specific Activity (LSA) Material
LSA material is classified into three categories: LSA-I, LSA-II, and LSA-III. The classification depends on the type and concentration of radioactive material.
LSA-I: Includes uranium and thorium ores, concentrates of such ores, other ores containing naturally occurring radionuclides, and radioactive material with an unlimited A2 value. Fissile material may be included only if excepted under clause 4.6.1.1. LSA-II: Includes water with a tritium concentration of up to 0.8 TBq. LSA-III: Consists of solids (e.g., consolidated wastes, activated materials), excluding powders, meeting specific requirements. The radioactive material must be distributed throughout a solid or collection of solid objects, or uniformly distributed in a solid compact binding agent. The material must be relatively insoluble or intrinsically contained in a relatively insoluble matrix, limiting radioactive material loss to 0.1A2 per package after 7 days in water.
To be classified as LSA material, the conditions specified in clauses 4.2.2, 6.7.1 to 6.7.7 must be met.
Surface Contaminated Object (SCO)
Radioactive material can be classified as SCO if the conditions in clauses 4.3.2, 6.8.1 to 6.8.7 are met.
Special Form Radioactive Material
Radioactive material can be classified as special form radioactive material only if it meets the applicable requirements specified in clause 4.4.2 and is approved by the Competent Authority.
Special form radioactive material must maintain its integrity under specified tests. It should not break, shatter, melt, or disperse under impact, percussion, bending, and heat tests. The activity in water from leaching tests should not exceed 2 kBq. Alternatively, for sealed sources, the leakage rate for the volumetric leakage assessment test specified in ISO 9978 should be met.
Specimens must undergo impact, percussion, bending, and heat tests. After each test, a leaching assessment or volumetric leakage test is required.
Specimens enclosed in a sealed capsule may be excepted from impact and percussion tests if they undergo the impact test prescribed in ISO 2919.
Low Dispersible Radioactive Material
Radioactive material can be classified as low dispersible radioactive material only if it meets the applicable requirements specified in clause 4.5.2, taking into account the requirements of clause 5.9.3.14 and is approved by the Competent Authority.
The total amount of low dispersible radioactive material in a package must meet specific requirements. The radiation level at 3 m from the unshielded material should not exceed 10 mSv/h. The airborne release of gaseous and particulate forms up to 100 μm aerodynamic equivalent diameter should not exceed 100 A2 when subjected to the enhanced thermal test and the impact test specified for Type C packages. The activity in the water should not exceed 100 A2 when subjected to the leaching test.
Specimens must undergo the enhanced thermal test (clause 5.9.5.5.2) and the impact test (clause 5.9.5.5.3) specified for Type C packages.
Fissile Material
Fissile material must be classified under the relevant entry as ‘FISSILE’ unless excepted by provisions (a)–(f) of clause 4.6.1.1 and transported subject to the applicable requirements specified in clause 6.15.3.3. All provisions apply only to material in packages with a smallest overall external dimension of not less than 10 cm, unless unpackaged material is specifically allowed.
Exceptions include:
Uranium enriched in uranium-235 to a maximum of 1% by mass, with a total plutonium and uranium-233 content not exceeding 1% of the mass of uranium-235, provided that the fissile nuclides are distributed essentially homogeneously throughout the material. Liquid solutions of uranyl nitrate enriched in uranium-235 to a maximum of 2% by mass, with a total plutonium and uranium- content not exceeding 0.002% of the mass of uranium, and with a minimum nitrogen to uranium atomic ratio (N/U) of 2. Uranium with a maximum uranium enrichment of 5% by mass of uranium-235 provided there is no more than 3.5 g of uranium-235 per package, the total plutonium and uranium-233 content does not exceed 1% of the mass of uranium-235 per package, and transport of the package is subject to the limit that fissile material in packages classified in accordance with this sub-paragraph shall not be transported in a consignment with more than 45 g of fissile nuclides. Fissile nuclides with a total mass not greater than 2.0 g per package, provided the package is transported subject to the limit that fissile material in packages classified in accordance with this sub-paragraph shall not be transported in a consignment with more than 15 g of fissile nuclides.
A package must provide sufficient shielding to ensure that, under routine transport conditions and with maximum radioactive contents, the radiation level at any point on the external surface does not exceed 5 μSv/h for excepted packages, 2 mSv/h at the external surface, and a TI of 10.0 for other packages and overpacks, as applicable. These limits consider radiation levels for loading freight containers and accumulating packages, overpacks, and freight containers, which is 2 mSv/h at any point on, and 0. mSv/h at 2 m from, the conveyance's external surface, except for exclusive use consignments by road or rail and the limits specified for them. For radioactive material with other dangerous properties, the package design must consider those properties.
Additional Requirements for Packages
Transported By Air
For air transport, the temperature of accessible surfaces must not exceed 50°C at an ambient temperature of 38°C, regardless of insolation. Packages containing radioactive material for air transport must withstand an internal pressure that produces a pressure differential of not less than the maximum normal operating pressure plus 95 kPa, without loss or dispersal of radioactive contents. The design must also ensure that the quantity of radioactive material does not exceed the relevant limits for the package type.
Excepted Package
Classification as an Excepted Package
A package can be classified as an excepted package if it meets one of the following conditions: it is an empty package that previously contained radioactive material; it contains instruments or articles not exceeding the activity limits specified in Table-V; it contains articles manufactured of natural uranium, depleted uranium, or natural thorium; it contains radioactive material not exceeding the activity limits specified in Table-V; or it contains less than 0.1 kg of uranium hexafluoride not exceeding the activity limits specified in column 4 of Table-V.
Restrictions on Contents of an Excepted Packages
Radioactive material enclosed in or included as a component of an instrument or manufactured article may be classified under UN 2911, RADIOACTIVE MATERIAL, EXCEPTED PACKAGE — INSTRUMENTS OR ARTICLES, provided that the radiation level at 10 cm from any point on the external surface of any unpackaged instrument or article is not greater than 0.1 mSv/h. Each instrument or article must bear the marking ‘RADIOACTIVE’ on its external surface, with exceptions for consumer products with regulatory approval or not exceeding exempt consignment activity limits in Table-I (column 5), and for instruments/articles too small to mark, provided they are transported in a package with the ‘RADIOACTIVE’ marking visible upon opening. The active material must be completely
enclosed by non-active components. The limits specified in columns 2 and 3 of Table-V must be met for each individual item and package, respectively. For transport by post, the total activity in each excepted package must not exceed one-tenth of the relevant limits in column 3 of Table-V.
Radioactive material in forms other than specified above, with activity not exceeding the limits in column 4 of Table-V, may be classified under UN 2910, RADIOACTIVE MATERIAL, EXCEPTED PACKAGE — LIMITED QUANTITY OF MATERIAL, provided the package retains its radioactive contents under routine transport conditions. The package must bear the marking ‘RADIOACTIVE’ on either an internal surface visible upon opening or on the outside if marking the internal surface is impractical. For transport by post, the total activity in each excepted package must not exceed one-tenth of the relevant limits in column 4 of Table-V.
Uranium hexafluoride not exceeding the limits in column 4 of Table-V may be classified under UN 3507 URANIUM HEXAFLUORIDE, RADIOACTIVE MATERIAL, EXCEPTED PACKAGE, less than 0.1 kg per package, non-fissile or fissile-excepted, provided the mass of uranium hexafluoride is less than 0.1 kg and the conditions of clauses 4.7.2, 5.5.2.2 (a), and 5.5.2.2 (b) are met.
Articles manufactured of natural uranium, depleted uranium, or natural thorium, and articles where the sole radioactive material is unirradiated natural uranium, unirradiated depleted uranium, or unirradiated natural thorium, may be classified under UN 2909, RADIOACTIVE MATERIAL, EXCEPTED PACKAGE — ARTICLES MANUFACTURED FROM NATURAL URANIUM or DEPLETED URANIUM or NATURAL THORIUM, provided the outer surface of the uranium or thorium is enclosed in an inactive sheath made of metal or another substantial material.
An empty packaging that previously contained radioactive material may be classified under UN 2908, RADIOACTIVE MATERIAL, EXCEPTED PACKAGE — EMPTY PACKAGING, provided it is in a well-maintained condition and securely closed. The level of internal non-fixed contamination must not exceed 100 times the levels specified in clause 6.5.1. Any labels displayed in conformity with labelling requirements specified in clause 6.13.3.1 must no longer be visible.
Requirements for Excepted Package
The design of an excepted package must meet the general requirements for all packages and, if transported by air, the additional requirements for packages transported by air.
dispersal of the radioactive contents and more than a 20% increase in the maximum radiation level at any external surface of the freight containers.
Metal IBCs may also be used as Type IP-2 or Type IP-3, provided they satisfy the requirements for Type IP-1. They must be designed to satisfy the requirements prescribed for UN Packing Group I or II in Chapter 6.5 of the United Nations Recommendations on the Transport of Dangerous Goods, Model Regulations, and if subjected to the tests prescribed in that document, but with the drop test conducted in the most damaging orientation, they would prevent loss or dispersal of the radioactive contents and more than a 20% increase in the maximum radiation level at any external surface of the IBC.
Packages Containing Uranium Hexafluoride
Packages designed to contain uranium hexafluoride must meet the requirements that pertain to the radioactive and fissile properties of the material. Except as allowed in clause 5.7.3, uranium hexafluoride in quantities of 0.1 kg or more must meet specific requirements.
Uranium hexafluoride in quantities of 0.1 kg or more must be packaged and transported according to the provisions of ISO 7195: Packaging of Uranium Hexafluoride (UF6) for Transport. Each package designed to contain 0.1 kg or more of uranium hexafluoride must be designed to withstand, without leakage and without unacceptable stress, as specified in ISO 7195, the structural test as specified in this safety code. The specimen must be tested hydraulically at an internal pressure of at least 1.38 MPa, but when the test pressure is less than 2.76 MPa, the design must require multilateral approval.
Retesting Packaging
For retesting packaging, equivalent nondestructive testing may be applied, subject to multilateral approval, except as allowed in clause 5.7.3. The package must withstand the free drop test (clause 5.8.4.3) without loss or dispersal of uranium hexafluoride. It must also withstand the thermal test (clause 5.9.4.3.2) without rupture of the containment system, except as allowed in clause 5.7.3.
Multilateral Approval for Uranium Hexafluoride Packages
Multilateral approval is required for transporting packages containing 0. kg or more of uranium hexafluoride if the packages are designed to international or national standards other than ISO 7195. This approval is needed if the package is designed to withstand a test pressure of less than 2.76 MPa during the structural test (clause 5.7.4). Multilateral approval is also needed if the package is designed to contain 9000 kg or more of uranium hexafluoride and does not meet the requirement of clause 5.7.2.2(c). In all other aspects, clauses 5.7.1 and 5.7.2 must be satisfied.
Type A Package
Classification of Type A Packages
Packages containing radioactive material can be classified as Type A packages if the conditions of clause 5.8.2 are met.
Restrictions on Contents of Type A Packages
Type A packages must not contain activities greater than A1 for special form radioactive material or A2 for all other radioactive material. For mixtures of radionuclides with known identities and activities, the following condition must be met: ∑i {B(i)/A1(i)} + ∑j {C(j)/A2(j)} ≤ 1, where B(i) is the activity of radionuclide i as special form radioactive material, A1(i) is the A1 value for radionuclide i, C(j) is the activity of radionuclide j as other than special form radioactive material, and A2(j) is the A2 value for radionuclide j.
Requirements for Type A Packages
Type A packages must meet the general requirements for all packaging and packages (clause 5.3), additional requirements for packages transported by air (clause 5.4), and the requirements of clauses 5.8.3.2 to 5.8.3.17. The smallest overall external dimension of the package must not be less than 10 cm. The design and manufacturing techniques must adhere to national or international standards, or other requirements acceptable to the Competent Authority. The package must be designed to prevent loss or dispersal of radioactive contents or more than a 20% increase in the maximum radiation level at any external surface if subjected to the tests for normal conditions of transport (clauses 5.8.4.1 to 5.8.4.5). Packages intended for liquid radioactive material must provide ullage to accommodate temperature variations, dynamic effects, and filling dynamics.
Additional Requirements for Type A Packages Containing
Liquids
A Type A package designed to contain liquid radioactive material must meet the conditions specified in clause 5.8.3.14(a) if subjected to the tests in clause 5.8.4.6. It must also be provided with sufficient absorbent material to absorb twice the volume of the liquid contents, positioned to contact the liquid in case of leakage. Alternatively, it can have a containment system with primary inner and secondary outer components designed to completely enclose the liquid and ensure its retention within the secondary outer containment, even if the primary inner components leak.
Requirements for Type A Packages Containing Gases
A package designed for gases must prevent loss or dispersal of the radioactive contents if subjected to the tests specified in clause 5.8.4.6.
