Circular No. 23/2012/TT-BKHCN guiding the safe transport of radioactive materials

CIRCULAR

Guidelines for the Safe Transport of Radioactive Materials

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Pursuant to the Atomic Energy Law dated June 3, 2008;

Pursuant to Decree No. 28/2008/NĐ-CP dated March 14, 2008, promulgated by the Government stipulating the functions, tasks, powers, and organizational structure of the Ministry of Science and Technology;

The Minister of Science and Technology issues guidelines for the safe transport of radioactive materials,

PART I

GENERAL PROVISIONS

Article 1. Scope of Regulation

1. These guidelines provide instructions to ensure the safe transport of radioactive materials, including from the design, manufacture, testing, packaging, and shipment of radioactive consignments to the transportation, storage during transit, and final receipt of radioactive materials and radioactive consignments under normal conditions as well as in case of incidents or accidents.

These guidelines do not apply to the transport of:

a) Radioactive materials within facilities conducting radiation work without using public roads;

b) Consumer goods containing radioactive substances that are allowed to be circulated and distributed;

c) Radioactive materials with individual activity lower than the individual activity limit for exempted radioactive materials or total activity lower than the activity limit for exempted shipments as specified in columns 4 and 5 of Table 1 and Table 2 of the Vietnamese Standard TCVN 6867-1:2001 "Radiation Safety - Safe Transport of Radioactive Material - Part 1: General Provisions" (referred to as TCVN 6867-1:2001);

d) Radioactive substances already introduced into the human body or living animals for diagnostic and therapeutic purposes.

Article 2. Applicability

These guidelines apply to organizations and individuals involved and related to the transport of solid, liquid, and gaseous radioactive materials via road, rail, waterway, and air transport means.

Article 3. Explanation of Terms

In this Circular, the following terms are understood as follows:

1. Units of measurement in these guidelines are abbreviated according to Appendix III of this Circular.

2. A₁ is the value used to determine the activity limit of special radioactive material in permitted radioactive consignments. Value A₁ is specified in column 2 of Table 1 and Table 2 of TCVN 6867-1:2001.

3. A₂ is the value used to determine the activity limit of non-special radioactive material in permitted radioactive consignments. Value A₂ is specified in column 3 of Table 1 and Table 2 of TCVN 6867-1:2001.

4. Specific activity of radioactive material is the activity per unit mass of the material in which the radioactive nuclide is uniformly distributed. Unit is Bq/g.

5. Low-toxicity alpha-emitting substance is natural uranium, depleted uranium, natural thorium, uranium-235, uranium-238, thorium-232, ore or concentrate containing thorium-228 and thorium-230, or alpha-emitting substances with a half-life shorter than 10 days.

6. Low-specific-activity radioactive material (LSA) is radioactive material intrinsically having low specific activity or radioactive material with medium-low specific activity below the limit set out in Article 8 of this Circular.

7. Low-dispersible radioactive material is radioactive material in solid form and not in powder form, or solid radioactive material enclosed in a sealed container to limit dispersion.

8. Fissile material is uranium-233, uranium-235, plutonium-239, plutonium-241, or any mixture thereof. Fissile material does not include natural uranium, unirradiated depleted uranium, or uranium only slightly irradiated in thermal reactors.

9. Surface-contaminated object (SCO) is a solid object that itself is not radioactive but has radioactive contamination on its surface.

10. Radioactive contamination is the presence of radioactive substances on surfaces in quantities greater than 0.4 (Bq/cm²) for beta-emitters, gamma-emitters, and low-toxicity alpha-emitters, or greater than 0.04 (Bq/cm²) for other alpha-emitters.

11. Loose radioactive contamination is radioactive contamination where the radioactive substance can leave the surface under normal transport conditions.

12. Fixed radioactive contamination is radioactive contamination not falling within the category defined in Clause 11, Article 3 of this Circular.

13. Unirradiated thorium contains no more than 10^-7 (g) uranium-233 in 1 (g) thorium-232.

14. Unirradiated uranium contains no more than 2 x 10³ (Bq) plutonium, no more than 9 x 10⁶ (Bq) fission products, and no more than 5 x 10^-3 (g) uranium-236 per 1 (g) uranium-235.

15. Natural uranium consists of 99.28% uranium-238 and 0.72% uranium-235 by weight.

16. Depleted uranium contains less than 0.72% uranium-235 by weight.

17. Enriched uranium contains more than 0.72% uranium-235 by weight.

18. Packaging is a structure consisting of necessary components to completely enclose radioactive material, protect against harm caused by radioactive material, and suit the characteristics of the transported radioactive material. Packaging may include one or more containers, absorber materials, separation structures, shielding, equipment for loading, unloading, venting, pressure relief, cooling, vibration reduction, insulation, movement... Packaging may be boxes, drums, containers, tanks.

19. Radioactive consignment (consignment) is a system comprising packaging and radioactive material inside the packaging prepared for transport.

20. Radioactive shipment (shipment) is one or more radioactive consignments transported in the same journey.

21. Container is a type of packaging designed for easy transport of goods by different means of transport without needing to unload or reload when changing transport means. Containers are characterized by being sealed, robust, reusable, and equipped with additional parts to facilitate transferring containers between transport means. Small containers have an outer maximum size of 1.5 (m) or an internal volume smaller than 3 (m³). Large containers are larger than small containers.

22. Tank is a container in drum or tank form used for transporting liquids, powders, grains, sludge, or solids with a capacity of at least 450 (L), and gases with a capacity of at least 1000 (L).

23. Design is a description of special radioactive material, low-dispersible radioactive material, consignment, or packaging allowing them to be accurately identified. Design includes technical characteristics, technical drawings, analysis proving compliance with national standards and relevant regulations.

24. Transport Index (TI) is an index of consignment or container containing radioactive material used to control radiation exposure during transport to ensure radiation safety. The method for determining TI is specified in Article 23 of this Circular.

25. Safety Limit Index (denoted as CSI) is the index of a shipment or container containing radioactive material for the purpose of controlling the quantity of radioactive material and arranging conditions during transportation to ensure that such radioactive material remains below the threshold level. The method for determining CSI is specified in Article 24 of this Circular.

26. United Nations Number (denoted as UN number) is a group of four digits assigned by the United Nations Committee of Experts on the Transport of Dangerous Goods to identify a specific substance or a group of substances.

27. Exclusive Use refers to the exclusive use of a means of transport or a large container by the consignor, with all loading and unloading activities during transportation to be carried out according to the instructions of the consignor or consignee.

28. Special Approval is an approval granted by the competent authority to allow the application of different guidelines in cases where the transportation of radioactive shipments does not fully comply with the provisions of this Circular.

Article 4. Safety Assurance Plan

Organizations and individuals involved in the transportation of radioactive materials must establish and implement a safety assurance plan. This plan shall include the following requirements:

1. Optimize radiation safety measures during transportation so that the radiation dose (referred to as dose) received by individuals is lower than the prescribed dose limit and measures are taken to reduce the dose and the number of people exposed.

2. Have radiation protection plans for individuals, conduct contamination checks on radioactive shipments, preparation areas, storage areas, and transport vehicles, and maintain and retain inspection records.

3. Personnel involved in transportation must be trained in radiation safety at authorized training facilities, understand fire prevention and firefighting rules, and comply with safe transportation regulations for radioactive materials.

4. Radioactive shipments must be isolated from transportation personnel and the public. Isolation distances are calculated based on dose limits as follows:

a) For transportation personnel, loaders, and packers: 5 (mSv/year);

b) For the public passing through areas with radioactive materials: 1 (mSv/year).

5. Radioactive shipments must be isolated from undeveloped film. The basis for calculating isolation distance is the dose limit: 0.1 (mSv/film lot).

Article 5. Security Assurance Plan

Organizations and individuals involved in the transportation of radioactive materials must establish and implement a security assurance plan in accordance with the guidelines of the Ministry of Science and Technology.

Article 6. Emergency Response Plan During Transportation

Organizations and individuals involved in the transportation of radioactive materials must establish and implement a facility-level emergency response plan in accordance with the guidelines of the Ministry of Science and Technology.

Article 7. Quality Assurance

Organizations and individuals involved in transportation activities must establish and implement a quality assurance program in accordance with the guidelines of the Radiation and Nuclear Safety Agency.

Chapter II

CLASSIFICATION OF RADIOACTIVE MATERIAL AND RADIOACTIVE SHIPMENTS

Section 1

CLASSIFICATION OF RADIOACTIVE MATERIAL

Article 8. Low-Specific Activity Radioactive Material

Low-specific activity radioactive material includes: LSA-I, LSA-II, and LSA-III.

1. LSA-I includes:

a) Uranium ore, thorium ore, or concentrates thereof, and other ores containing natural fissile materials used for producing these fissile materials;

b) Natural uranium, depleted uranium, natural thorium, compounds, or mixtures thereof, provided they have not been irradiated and are in solid or liquid form;

c) Radioactive material with an A value₂ not limited except for non-exempted fissile material as stipulated in Clause 1, Article 12 of this Circular;

d) Other radioactive material with uniform activity distribution and average specific activity not exceeding 30 times the concentration activity value specified in Column 4 of Table 1 and Column 4 of Table 2 of TCVN 6867-1:2001, except for non-exempted fissile material as stipulated in Clause 1, Article 12 of this Circular.

2. LSA-II includes:

a) Water with tritium concentration up to 0.8 (TBq/L);

b) Other radioactive material with uniform activity distribution and average specific activity not exceeding 10^-4 A₂ (TBq/g) for solids and gases, and 10^-5 A₂ (TBq/g) for liquids.

3. LSA-III includes:

a) Radioactive material distributed in solid form or radioactive material distributed in solidifying agents (such as concrete, asphalt, ceramics, etc.);

b) Insoluble radioactive material or insoluble radioactive material contained in packaging, in which case if the packaging is lost, the loss of radioactive material due to dissolution in water over 7 days does not exceed 0.1 A₂ (TBq);

c) Solid radioactive material with average specific activity (excluding shielding material) not exceeding 2 x 10^-3 A₂ (TBq/g).

Article 9. Surface Contaminated Objects (SCO)

Surface Contaminated Objects include SCO-I and SCO-II.

1. SCO-I is solid objects with the following characteristics:

a) Loose radioactive contamination on accessible surfaces, averaged over an area of 300 (cm²) (or the entire surface if it is less than 300 (cm²)), does not exceed 4 (Bq/cm²) for beta-emitting substances, gamma-emitting substances, and low-toxicity alpha-emitting substances, or does not exceed 0.4 (Bq/cm²) for other alpha-emitting substances;²b) Fixed radioactive contamination on accessible surfaces, averaged over an area of 300 (cm²), does not exceed 4 x 10⁴ (Bq/cm²) for beta-emitting substances, gamma-emitting substances, and low-toxicity alpha-emitting substances, or does not exceed 4 x 10⁴ (Bq/cm²) for other alpha-emitting substances;²c) The sum of loose radioactive contamination and fixed radioactive contamination on inaccessible surfaces, averaged over an area of 300 (cm²), does not exceed 4 x 10⁴ (Bq/cm²) for beta-emitting substances, gamma-emitting substances, and low-toxicity alpha-emitting substances, or does not exceed 4 x 10⁴ (Bq/cm²) for other alpha-emitting substances.²2. SCO-II is solid objects that may have fixed or loose radioactive contamination on surfaces exceeding the limits set for SCO-I, and also have the following characteristics:²a) Loose radioactive contamination on accessible surfaces, averaged over an area of 300 (cm²), does not exceed 400 (Bq/cm²) for beta-emitting substances, gamma-emitting substances, and low-toxicity alpha-emitting substances, or does not exceed 40 (Bq/cm²) for other alpha-emitting substances;

b) Fixed radioactive contamination on accessible surfaces, averaged over an area of 300 (cm²), does not exceed 8 x 10⁴ (Bq/cm²) for beta-emitting substances, gamma-emitting substances, and low-toxicity alpha-emitting substances, or does not exceed 8 x 10⁴ (Bq/cm²) for other alpha-emitting substances;²b) Fixed radioactive contamination on accessible surfaces, averaged over an area of 300 (cm²), does not exceed 4 x 10⁴ (Bq/cm²) for beta-emitting substances, gamma-emitting substances, and low-toxicity alpha-emitting substances, or does not exceed 4 x 10⁴ (Bq/cm²) for other alpha-emitting substances;²c) The sum of loose radioactive contamination and fixed radioactive contamination on inaccessible surfaces, averaged over an area of 300 (cm²), does not exceed 8 x 10⁴ (Bq/cm²) for beta-emitting substances, gamma-emitting substances, and low-toxicity alpha-emitting substances, or does not exceed 8 x 10⁴ (Bq/cm²) for other alpha-emitting substances.⁴ Article 10. Special Form Radioactive Material²1. Special form radioactive material is solid radioactive material or radioactive material contained in a sealed enclosure that does not release radioactive material into the surrounding environment. The sealed enclosure constituting special form radioactive material must be constructed so that it can only be opened by destroying it. Special form radioactive material has at least one dimension not less than 5 (mm).³ Article 10. Special Form Radioactive Material²a) Loose radioactive contamination on accessible surfaces, averaged over an area of 300 (cm²), does not exceed 400 (Bq/cm²) for beta-emitting substances, gamma-emitting substances, and low-toxicity alpha-emitting substances, or does not exceed 40 (Bq/cm²) for other alpha-emitting substances;

2. If there is a design for special form radioactive material, it must be approved by the national authority responsible for that design.²b) Fixed radioactive contamination on accessible surfaces, averaged over an area of 300 (cm²), does not exceed 4 x 10⁴ (Bq/cm²) for beta-emitting substances, gamma-emitting substances, and low-toxicity alpha-emitting substances, or does not exceed 4 x 10⁴ (Bq/cm²) for other alpha-emitting substances;²c) The sum of loose radioactive contamination and fixed radioactive contamination on inaccessible surfaces, averaged over an area of 300 (cm²), does not exceed 8 x 10⁴ (Bq/cm²) for beta-emitting substances, gamma-emitting substances, and low-toxicity alpha-emitting substances, or does not exceed 8 x 10⁴ (Bq/cm²) for other alpha-emitting substances.⁴ Article 10. Special Form Radioactive Material²Article 11. Low Dispersible Radioactive Material³ Article 10. Special Form Radioactive Material²1. Low dispersible radioactive material, if the total quantity of such radioactive material in a package results in a dose rate of radiation at a distance of 3 (m) from the unshielded radioactive material not exceeding 10 (mSv/h);

2. If there is a design for low dispersible radioactive material, it must be approved by the national authority responsible for that design and the country to which the material is being transported or through which it passes.

Article 12. Fissile Material²b) Fixed radioactive contamination on accessible surfaces, averaged over an area of 300 (cm²), does not exceed 4 x 10⁴ (Bq/cm²) for beta-emitting substances, gamma-emitting substances, and low-toxicity alpha-emitting substances, or does not exceed 4 x 10⁴ (Bq/cm²) for other alpha-emitting substances;²1. Packages containing fissile material are classified according to Table 7, Appendix I, except where one of the following conditions is met:²a) The mass limit of fissile material in a consignment with each package having an external dimension not less than 10 (cm):²a) Loose radioactive contamination on accessible surfaces, averaged over an area of 300 (cm²), does not exceed 400 (Bq/cm²) for beta-emitting substances, gamma-emitting substances, and low-toxicity alpha-emitting substances, or does not exceed 40 (Bq/cm²) for other alpha-emitting substances;

is the mass of uranium-235 (g);²b) Fixed radioactive contamination on accessible surfaces, averaged over an area of 300 (cm²), does not exceed 4 x 10⁴ (Bq/cm²) for beta-emitting substances, gamma-emitting substances, and low-toxicity alpha-emitting substances, or does not exceed 4 x 10⁴ (Bq/cm²) for other alpha-emitting substances;²is the mass of other fissile material (g);⁵ Article 10. Special Form Radioactive Material²X and Y are values determined in Table 2, Appendix I;⁴ Article 10. Special Form Radioactive Material²a) Loose radioactive contamination on accessible surfaces, averaged over an area of 300 (cm²), does not exceed 400 (Bq/cm²) for beta-emitting substances, gamma-emitting substances, and low-toxicity alpha-emitting substances, or does not exceed 40 (Bq/cm²) for other alpha-emitting substances;

and meets one of the following conditions: Each package contains no more than 15 (g) of fissile material; The fissile material is a homogeneous solution or mixture containing hydrogen with a mass ratio of fissile material to hydrogen not greater than 5%; There is no more than 5 (g) of fissile material in any 10 (L) volume;²b) Fixed radioactive contamination on accessible surfaces, averaged over an area of 300 (cm²), does not exceed 4 x 10⁴ (Bq/cm²) for beta-emitting substances, gamma-emitting substances, and low-toxicity alpha-emitting substances, or does not exceed 4 x 10⁴ (Bq/cm²) for other alpha-emitting substances;²is the mass of other fissile material (g);⁵ Article 10. Special Form Radioactive Material²b) Uranium-235 enriched up to a maximum of 1% by mass, with the total mass of plutonium and uranium-233 not exceeding 1% of the mass of uranium-235, provided that the fissile material is distributed almost uniformly. Stacking is not allowed if uranium-235 is in plate, oxide, or carbide form;⁴ Article 10. Special Form Radioactive Material²) for other alpha-emitters.

c) A nitrate solution of uranium containing uranium-235 enriched up to a maximum of 2% by mass, with the total mass of plutonium and uranium-233 not exceeding 0.002% of the mass of uranium, and the minimum atomic ratio of nitrogen to uranium is 2;

d) In a shipment, the mass of plutonium does not exceed 20% of the mass of fissile material, and the maximum mass of plutonium is 1 (kg). Otherwise, exclusive transport must be used.

2. Packages containing fissile material shall not contain:

a) A mass of fissile material different from the value approved for the package design;

b) Radioactive sources or fissile material different from those approved for the package design;

c) Fissile material with shapes, physical states, chemical compositions, or spatial arrangements different from those approved for the package design.

3. The design of packages containing fissile material must be approved by the national authority responsible for that design and the country to which the package is being transported or through which it passes.

1. Packages containing fissile material classified as Table 7, Appendix I, except where they satisfy one of the following conditions:

a) The limit on the quantity of fissile material in a consignment with each package having the smallest external dimension not less than 10 (cm):

Briefly describe technical improvements, production processes, raw materials, designs; new technology applications such as automation, digitalization, clean technology; management, marketing, distribution solutions; products winning awards or certifications related to innovation…):…₁ is the quantity of uranium-235 (g);

Briefly describe technical improvements, production processes, raw materials, designs; new technology applications such as automation, digitalization, clean technology; management, marketing, distribution solutions; products winning awards or certifications related to innovation…):…₂ is the quantity of other fissile material (g);

X and Y are values determined in Table 2, Appendix I;

and meet one of the following conditions: Each package contains no more than 15 (g) of fissile material; The fissile material is a homogeneous solution or mixture containing hydrogen at a mass ratio of fissile material to hydrogen less than 5%; There is no more than 5 (g) of fissile material in any 10 (L) volume;

b) Uranium-235 enriched up to a maximum of 1% by weight, with the total mass of plutonium and uranium-233 not exceeding 1% of the mass of uranium-235, provided that the fissile material is distributed almost uniformly. Stacking is not allowed if uranium-235 is in plate form, oxide form, or carbide form;

c) A solution of uranyl nitrate in which uranium-235 is enriched up to a maximum of 2% by weight, with the total mass of plutonium and uranium-233 not exceeding 0.002% of the mass of uranium, and the atomic ratio of nitrogen to uranium is at least 2;

d) In a shipment, the mass of plutonium does not exceed 20% of the mass of fissile material, and the maximum mass of plutonium is 1 (kg). For cases not covered by this Point, transportation must be exclusive;

2. Packages containing fissile material shall not contain:

a) A quantity of fissile material different from the approved value for the package design;

b) Radioactive sources or fissile material other than those approved for the package design;

c) Fissile material with shapes, physical, chemical states, or spatial arrangements different from those approved for the package design;

3. The design of packages containing fissile material must be approved by the national authority responsible for that design and the country to which or through which the package is transported;

Article 13. Uranium hexafluoride (UF6)₆)

Clause 1. Uranium hexafluoride is classified as in Table 7, Appendix I, and packages containing uranium hexafluoride shall not contain:

Point a) a mass of UF6₆ different from the value approved by the competent authority for the design of the package;

Point b) a mass of UF6₆ greater than the value leading to a loss of less than 5% at the maximum permitted temperature of the package;

Point c) UF6 not in solid form or internal pressure of the package greater than atmospheric pressure at the start of transport.

Clause 2. The design of packages containing a mass of 0.1 (kg) or more of UF6₆ must be approved by the national competent authority with that design. The design of packages containing a mass of 9,000 (kg) or more of UF6₆ must be approved by the national competent authority with that design and the country to which or through which the package is transported.

Section 2

CLASSIFICATION OF RADIATION SHIPMENTS

Article 14. Exempt Packages

Clause 1. Empty packaging that has contained radioactive material.

Clause 2. Packages containing tools, items, or radioactive materials with activity not exceeding the value specified in Table 1, Appendix I, of this Circular.

Clause 3. Packages containing items made from natural uranium, depleted uranium, or natural thorium.

Clause 4. The design of exempt packages does not require approval by the national competent authority with that design and the country to which or through which the package is transported.

Article 15. Industrial Packages

Industrial packages are packages containing LSA and SCO. The quantity of radioactive material in the package is limited so that the activity for the means of transport does not exceed the value specified in Table 4, Appendix I, of this Circular. Industrial packages include:

Clause 1. Type 1 industrial package (IP-1) contains:

Point a) LSA-I in solid form;

Point b) LSA-I in liquid form, exclusively for transport;

Point c) SCO-I.

Clause 2. Type 2 industrial package (IP-2) contains:

Point a) LSA-I in liquid form, not exclusively for transport;

Point b) LSA-II in solid form;

Point c) LSA-II in liquid and gaseous form, exclusively for transport;

Point d) LSA-III exclusively for transport;

Point đ) SCO-II.

Clause 3. Type 3 industrial package (IP-3) contains:

Point a) LSA-II in gaseous and liquid form, not exclusively for transport;

Point b) LSA-III not exclusively for transport.

Clause 4. The design of industrial packages does not require approval by the national competent authority with that design and the country to which or through which the package is transported.

Article 16. Type A Package

Clause 1. Packages containing special form radioactive material with activity not exceeding A₁ (TBq).

Clause 2. Packages containing other radioactive material with activity not exceeding A₂ (TBq).

Clause 3. Packages containing mixtures of radionuclides identified by name and activity, the activity of these radionuclides must satisfy:

Where:

A₁(i) the value A₁ of radionuclide i;

A₂(j) the value A₂ of radionuclide j;

B(i) is the activity of radionuclide i in special form radioactive material;

C(j) is the activity of radionuclide j in non-special form radioactive material.

Clause 4. The design of type A packages does not require approval by the national competent authority with that design and the country to which or through which the package is transported.

Article 17. Type B Package

Clause 1. Type B packages shall not contain:

Point a) radioactive material with activity greater than the value approved for the design of the package;

Point b) radionuclides other than those approved for the design of the package;

Point c) radioactive material with shape, physical state, or chemical form different from that approved for the design of the package.

Clause 2. If type B packages are transported by air, they must comply with the provisions of Clause 1 of this Article and the following conditions:

Point a) For packages containing special form radioactive material: activity shall not exceed 3,000A₁ (TBq) or 100,000A₂ (TBq);

Point b) For packages containing other radioactive material: activity shall not exceed 3,000A₂ (TBq).

Clause 3. Type B packages include types B(U) and B(M):

Point a) The design of type B(U) packages must be approved by the national competent authority with that design. In the case of type B(U) packages containing fissile material or low dispersible radioactive material, the design must be approved by the national competent authority with that design and the country to which or through which the package is transported.

Point b) The design of type B(M) packages must be approved by the national competent authority with that design and the country to which or through which the package is transported.

Article 18. Type C Packages

1. Type C packages shall not contain:

Point a) radioactive material with activity greater than the value approved for the design of the package;

Point b) radionuclides other than those approved for the design of the package;

Point c) radioactive material with shape, physical state, or chemical form different from that approved for the design of the package.

2. The design of type C packages must be approved by the national competent authority having such design. In cases where type C packages contain fissile materials, the package design must be approved by both the national competent authority having such design and the national authority to which the package is transported or passes through.

Chapter III

PROVISIONS FOR TRANSPORTATION

Article 19. Requirements Prior to Transportation

1. Packages used must meet the relevant requirements stipulated in this Circular.

2. For packages that have been approved and certified by the competent authority, they must comply with the requirements specified in the certificate.

3. For special radioactive materials and low dispersible radioactive materials that have been approved by the competent authority, they must comply with the requirements specified in the certificate.

4. For type B(U), B(M), and C packages, it must be ensured that they remain in a stable temperature and pressure state before transportation, except when these requirements are exempted by the competent authority approving the design.

5. Type B(U), B(M), C packages and packages containing fissile materials must be inspected prior to transportation to ensure there is no radioactive leakage.

Article 20. Transportation with Other Goods

1. Packages may not contain anything other than items necessary for the use of radioactive materials and ensuring that these items do not affect the safety of the package.

2. In cases where a container previously used to transport radioactive materials is used temporarily to store or transport other goods, it must be decontaminated to a level lower than 0.4 (Bq/cm²) for beta-emitting substances, gamma-emitting substances, and low-toxicity alpha-emitting substances, or 0.04 (Bq/cm²).²) for beta-emitting, gamma-emitting, and low-toxicity alpha-emitting substances, or 0.04 (Bq/cm²1. Low dispersible radioactive material, if the total quantity of such radioactive material in a package results in a dose rate of radiation at a distance of 3 (m) from the unshielded radioactive material not exceeding 10 (mSv/h);

3. During transportation, packages must be separated from food, beverages, and other hazardous goods.

Article 21. Control of Surface Radioactive Contamination

1. Loose radioactive contamination on the surface of packages shall not exceed the following limits:

a) 4 (Bq/cm²) for beta-emitting substances, gamma-emitting substances, and low-toxicity alpha-emitting substances;²) for beta-emitting, gamma-emitting, and low-toxicity alpha-emitting substances;

b) 0.4 (Bq/cm²)²1. Low dispersible radioactive material, if the total quantity of such radioactive material in a package results in a dose rate of radiation at a distance of 3 (m) from the unshielded radioactive material not exceeding 10 (mSv/h);

The limit values are averaged over an area of 300 (cm²) or the entire surface area if it is less than 300 (cm²).²) or the entire surface area if it is less than 300 (cm²).

2. Loose radioactive contamination on the outer and inner surfaces of packaging, containers, tanks, and transport vehicles shall not exceed the limits set forth in Clause 1 of this Article.

3. In cases where packages are damaged or leaking radioactive material or suspected of being damaged or leaking radioactive material, isolation and containment of the contaminated area must be carried out. A radioactive contamination assessment must be conducted on the packages, transport vehicles, and loading/unloading areas. If necessary, a radioactive contamination assessment must be conducted on all other items transported on the same vehicle.

Packages that are damaged or leaking radioactive material exceeding the permissible limits set forth in Articles 21 and 22 of this Circular must be transferred to an appropriate location for repair and decontamination until the initial conditions are restored before further transportation can occur.

4. Transport vehicles and equipment must be inspected to determine the level of radioactive contamination. The frequency of inspection depends on the degree of use but shall not be less than once per year.

Transport vehicles and equipment that are contaminated with radioactive material exceeding the limits set forth in Clause 1 of this Article or have a surface radiation dose rate greater than 5 (mSv/h) must be decontaminated and only used again when it is ensured that they do not exceed the limits set forth in Clause 1 of this Article and the surface radiation dose rate does not exceed 5 (mSv/h).

5. In exclusive use, the provisions of Clauses 1 and 4 of this Article regarding the control of internal surface contamination of unpackaged radioactive material containers, tanks, and transport vehicles are not required.

Article 22. Conditions for radiation dose rates during transport

1. For exempt packages, the surface dose rate on the package shall not exceed 5 (mSv/h).

2. For other types of packages, the external surface dose rate of the package shall not exceed 2 (mSv/h).

3. For unpackaged equipment or items, the dose rate at a point 10 (cm) from the external surface shall not exceed 0.1 (mSv/h).

4. For LSA or SCO contained within each industrial package type IP-1, IP-2, or IP-3, the dose rate at a point 3 (m) from the LSA or SCO without shielding shall not exceed 10 (mSv/h).

5. For exclusive use transportation:

a) By road or rail: the surface dose rate of each package may exceed 2 (mSv/h) but shall not exceed 10 (mSv/h) provided that the transport vehicle is protected or sealed to prevent unauthorized access throughout the transport period except for authorized personnel; securing to ensure the package remains fixed within the transport vehicle throughout the transport period; the package must not be added to or removed during transport;

b) By air or water: the surface dose rate of each package shall not exceed 2 (mSv/h). If it exceeds this level, it shall not exceed 10 (mSv/h) and must have permission from the Radiation and Nuclear Safety Agency (Ministry of Science and Technology).

6. For transport vehicles containing packages or containers, the dose rate at any point on the vehicle wall (including top and bottom) shall not exceed 2 (mSv/h) and the dose rate at a distance of 2 (m) from the external surface of the transport vehicle shall not exceed 0.1 (mSv/h).

7. At the seating position in the transport vehicle, the dose rate shall not exceed 0.02 (mSv/h) if those individuals are not shielded from radiation.

Article 23. Determination of Transport Index (TI) and Permitted TI

1. The TI for each package, container, or for unpackaged LSA-I or SCO-I material is determined as follows:

a) For packages containing non-fissile radioactive material, measure the maximum surface dose rate (unit of measurement is mSv/h) at a distance of 1 (m) from the external surface of the package. Multiply the value obtained by 100 and the resulting number is the TI;

b) For packages containing fissile material, the maximum surface dose rate at a distance of 1 (m) from the external surface of the package has the following values: 0.4 (mSv/h) for uranium and thorium physical concentrates; 0.3 (mSv/h) for thorium chemical concentrates; 0.02 (mSv/h) for uranium chemical concentrates excluding uranium hexafluoride. Multiply this value by 100 and the resulting number is the TI;

c) For containers and unpackaged LSA-I and SCO-I materials, measure the maximum surface dose rate (unit of measurement is mSv/h) at a distance of 1 (m) from the external surface of the container or LSA-I and SCO-I material. Multiply the measured value by the corresponding factor specified in Table 5 of Appendix I of this Circular and the resulting number is the TI;

d) The TI value obtained at Point a, b, and c Clause 1 of this Article shall be rounded up to the first decimal place (for example, 1.13 becomes 1.2), except for values equal to or less than 0.05 which are considered as 0.

2. The TI for a container or transport vehicle containing multiple packages is determined by the sum of the TIs of all packages or by directly measuring the dose rate as prescribed in Clause 1 of this Article.

3. Provisions for permitted TI:

a) The TI of each package shall not exceed 10 except in cases of exclusive use transportation;

b) The TI for containers or transport vehicles not used exclusively is specified in Table 8 of Appendix I of this Circular;

c) For transportation of LSA-I material, there is no limit on the total TI;

d) For exclusive use, there is no limit on the total TI.

Article 24. Determination of the Safety Index to Limit (CSI) and Permitted CSI for Transport

1. The CSI for packages containing fissile material is determined by dividing 50 by N, where N is the smaller value calculated under the following two conditions:

a) In normal transport conditions, "N" is determined by taking five times "N" of the package with packaging and arrangement conditions that allow maximum neutron production still within the limit as follows:

There is no separation between packages and the packages are arranged so that all surfaces are reflected by water walls at least 20 cm thick;

b) In assumed accident transport conditions, "N" is determined by taking twice "N" of the package with packaging and arrangement conditions that allow maximum neutron production still within the limit as follows:

Hydrogen absorbers are placed between packages and the packages are arranged so that all surfaces are reflected by water walls at least 20 cm thick.

2. The CSI for packages or containers carrying multiple packages is determined by the total CSI of all packages. A CSI of zero for a package or container means there is no limit on the number of packages below the limit in that package or container.

3. Regulations on permitted CSI:

a) The CSI of packages, containers, and individual items must not exceed 50 except for exclusive use transport. Shipments containing multiple packages or containers need to be arranged and stored in groups. The distance between groups must be at least 6 meters;

b) The total CSI of containers or vehicles used exclusively and non-exclusively is specified in Table 9 of Appendix I of this Circular.

Article 25. Marking Packages

1. The outer surface of the package must clearly indicate the following information:

a) Name of sender and recipient;

b) United Nations code as specified in Table 7 of Appendix I of this Circular;

c) Weight of the package if it exceeds 50 kg;

d) Package group symbol corresponding to design:

For industrial packages, mark: IP-1, IP-2, IP-3 (IF for packages containing fissile material); For Type A packages, mark: Type A (AF for packages containing fissile material); For Type B packages, mark: Type B(U) or Type B(M) (B(U)F or B(M)F for packages containing fissile material); For Type C packages, mark: Type C (CF for packages containing fissile material);

đ) For Type B(U), Type B(M), and Type C packages, the outer surface must have the radiation warning sign specified in Figure 1 of Appendix II of this Circular. This sign must be embossed or stamped, fire-resistant, and waterproof.

2. For LSA-I or SCO-I materials with surface contamination not exceeding ten times the level specified in Clause 9, Article 3 of this Circular, exclusive use must be applied, and the outer surface of the container or wrapping material must clearly state: "RADIOACTIVE LSA-I" or "RADIOACTIVE SCO-I".

3. In cases where the package is imported or exported, explanatory terms must be marked in Vietnamese or English.

Article 26. Labeling Packages

1. Packages are classified for labeling according to the conditions specified in Table 6 of Appendix I of this Circular and based on the following principles:

a) If the TI meets the condition for this category but the surface radiation dose meets the condition for another category, the package will be classified in the higher category;

b) The package must be labeled according to its category;

c) Labels for each category are specified in Figures 2, 3, and 4 of Appendix II of this Circular. Packages containing fissile material must also bear labels specified in Figure 6 of Appendix II of this Circular;

d) In cases where the package is imported or exported, label content must be marked in Vietnamese or English.

2. Labels unrelated to the contents of the package must be removed or covered.

3. Packages or containers exempt from labeling do not require labeling. Other types of packages or containers must be labeled on both sides of the outer surface of the package or container. For containers or tanks, labels must be affixed to four outer surfaces. For large containers, larger labels as specified in Figure 5 of Appendix II of this Circular must be affixed next to the labels specified in Figures 2, 3, and 4 of Appendix II of this Circular.

4. Labels must contain the following information:

a) Radioactive nuclide name (using symbols as specified in Table 1 of TCVN 6867-1: 2001) except for LSA-I. If it is a mixture of radioactive nuclides: the most important radioactive nuclide name must be marked on the label. For LSA-I, marking "LSA-I" is sufficient;

b) Activity: maximum activity of the radioactive nuclides, unit is Bq with appropriate prefixes (kBq, MBq...). For fissile material, record mass; unit is g;

c) TI: not required for I-WHITE label. For fissile material, additionally record CSI.

Article 27. Labeling Warning Labels on Containers and Transport Vehicles

1. Containers or tanks containing non-exempt packages must bear four yellow warning labels as specified in Diagram 5 of Appendix II of this Circular. In cases where the package is imported or exported goods, the word "RADIOACTIVE" may be written in English. The warning labels shall be affixed vertically on each side and at the edge of the container or tank. Alternatively, labels as specified in Diagrams 2, 3, and 4 of Appendix II of this Circular with a minimum size as specified in Diagram 5 of Appendix II of this Circular may replace the warning labels.

2. Transport vehicles carrying radioactive materials must have three yellow warning labels as specified in Diagram 5 of Appendix II of this Circular affixed to both sides and the rear of the transport vehicle.

3. Containers or tanks containing shipments classified as LSA-I or SCO-I that are not packaged or radioactive material shipments that are packaged for exclusive use must additionally record the United Nations number (UN Number) (Table 7 of Appendix I of this Circular) in black letters, with a height of no less than 65 (mm) at the bottom half of the label (Diagram 5 of Appendix II of this Circular).

Article 28. Isolation During Transportation and Intermediate Storage

1. During transportation and intermediate storage, packages or containers containing radioactive materials must be isolated from:

a) Locations where people and undeveloped film are present, in accordance with the provisions of Clauses 4 and 5 of Article 4 of this Circular;

b) Other dangerous goods: flammable, explosive, toxic.

2. Packages or shipments classified as Category II-GOLD or III-GOLD must not be placed in passenger compartments except when such compartments are reserved exclusively for specially permitted persons accompanying the shipment.

3. For the transportation of fissile material during storage, groups of packages or containers with a Criticality Safety Index (CSI) exceeding 50 must be separated by a minimum distance of 6 (m).

4. The carrier must ensure that necessary isolation is maintained throughout the transportation and intermediate storage process.

Article 29. Arrangement of Packages During Transportation and Intermediate Storage

1. Ensure safety and stability so that they do not shift, overturn, or fall.

2. Ensure that the average surface heat generation rate of the package does not exceed 15 (W/m²).²).

3. Load packages into containers or transport vehicles so that the surface radiation dose rate, TI, and CSI do not exceed the values specified in Clauses 6 of Article 22, Clause 3 of Article 23, and Clause 3 of Article 24 of this Circular.

Article 30. Provisions for the Transportation of Empty Packaging

Empty packaging that has previously contained radioactive material must be transported as exempt packages under the following conditions:

1. The empty packaging must be properly stored and ensure tightness.

2. Packaging made of uranium or thorium must be wrapped in metal or other sturdy material.

3. The level of loose radioactive contamination inside the packaging must not exceed 100 times the level specified in Point a of Clause 1 of Article 9 of this Circular.

4. Used labels must be covered or removed.

Article 31. Provisions for Road Transportation

Organizations and individuals involved in and related to road transportation of radioactive materials, in addition to complying with general provisions from Article 19 to Article 29, must also comply with the following provisions:

1. Only automobiles may be used to transport radioactive materials. Automobiles transporting radioactive materials must be highly safe.

2. It is prohibited to transport passengers in automobiles carrying radioactive cargo except for exempt packages.

3. Covered vehicles must be used when transporting water-permeable packages.

4. Trailers must not be used to transport radioactive materials.

5. The vehicle must bear labels as specified in Article 27 of this Circular, and the consignor must be responsible for accurately affixing the labels.

6. When parking, there must be a guard present unless the radiation dose rate at all points on the vehicle is lower than 5 (mSv/h) and the package compartment must be locked to prevent anyone from removing the packages. Parking must be at least 50 (m) away from residential areas, except when unloading into a warehouse.

7. The driver of the automobile must hold a radiation safety training certificate, be trained in handling incidents during transportation, and be equipped with appropriate dosimeters. If the driver does not meet these requirements, each shipment must have an escort (except for exempt packages). The escort must meet these requirements.

Article 32. Provisions for Rail Transport

Organizations and individuals participating in and related to the rail transport of radioactive materials, in addition to complying with general provisions from Article 19 to Article 29, must also comply with the following provisions:

1. Permitted to transport radioactive goods by freight train or in passenger train luggage cars. Freight cars carrying radioactive goods must have a roof when transporting moisture-sensitive items.

2. Freight cars carrying radioactive goods must be marked as prescribed in Article 27 of this Circular on both sides of the car body. In cases where there is no car body and containers are transported, the label on the container is sufficient. The consignor shall be responsible for accurately affixing the labels.

3. When transporting (except for exempted consignments), a guard must be present. The guard must hold a radiation safety training certificate, be trained in handling incidents during transportation, and be equipped with appropriate dosimeter devices.

Article 33. Provisions for Air Transport

Organizations and individuals participating in and related to the air transport of radioactive materials, in addition to complying with general provisions from Article 19 to Article 29, must also comply with the following provisions:

Packages or containers containing radioactive material with any of the following characteristics shall not be transported by air:

1. Type B(M) package exclusively in use.

2. Type B(M) package requiring external cooling during transport or containing flammable liquid.

3. Package with surface radiation dose rate greater than 2 (mSv/h) except in special approved cases.

Chapter IV

RESPONSIBILITY FOR RADIATION SAFETY

Article 34. Responsibilities of the Consignor

1. The consignor is responsible for ensuring radiation safety during transport from the stage of packaging inspection, item packing, surface decontamination (if necessary), sealing, labeling until handing over the consignment to the carrier. The consignor must prepare the consignment in accordance with the provisions of this Circular, national technical standards, and other regulations on cargo transport.

2. The consignor must submit a transport documentation file containing the following information:

a) The name specified for shipment as provided in Table 6 of Appendix I of this Circular;

b) United Nations cargo classification number: “7”;

c) United Nations number of radioactive material as provided in Table 7 of Appendix I of this Circular written after the word “UN”;

d) Name or symbol of the radioactive nuclide; for mixtures of radioactive nuclides, a suitable common name or list of the most important radioactive nuclides;

đ) Description of the chemical and physical form of the radioactive material or simply record “special radioactive material,” “low dispersible radioactive material” accordingly;

e) Maximum activity of the radioactive nuclide, unit in Bq with appropriate prefix (kBq, MBq...). Mass for fissile material, unit in g;

g) Package category: either I-WHITE, II-YELLOW, or III-YELLOW;

h) TI (for II-YELLOW, III-YELLOW); CSI (for transport of non-exempted fissile material);

i) Code issued by the national authority in the approval certificate (for special radioactive material, low dispersible radioactive material, special approval, package design);

k) For shipments consisting of packages within a container, detail the contents of each package inside the container. If the packages are removed from the container at an intermediate unloading point, appropriate transport documentation must be prepared in advance;

l) If the shipment is exclusively used, record “EXCLUSIVE USE TRANSPORTATION”;

m) Total activity of the shipment expressed as multiples of A₂ for LSA-II, LSA-III, SCO-I, SCOII. For radioactive material with unlimited A₂ value, the activity of that radioactive material will be 0.

3. The consignor must guarantee the goods in the shipment and must be fully and accurately described, classified, packed, marked, (labeled and comply with the transport conditions stipulated by current laws and international regulations (if the shipment passes through another country)). Clearly state the date, month, year, and sign.

4. The consignor needs to notify the carrier in writing within the transport documentation file of the necessary requirements including at least the following points:

a) Additional requirements regarding cargo arrangement, storage, loading and unloading, including special storage for thermal dispersion safety;

b) Restrictions on mode of transport or means of transport and necessary instructions during transport;

c) Handling procedures for incidents or accidents involving the shipment.

Article 35. Responsibilities of the Carrier

1. In addition to current regulations on cargo transportation, the carrier shall only accept transportation when:

a) All declarations, certificates approved by competent authorities, and transportation permits as prescribed by law and guidance for transportation are fully available;

b) Carefully inspecting consignments, shipments, containers to match the declarations and comply with the provisions of this Circular. In case of discovering discrepancies, they have the right to refuse transportation, prepare a record, and send copies to relevant parties (sender, receiver) and competent authorities.

2. Ensuring radiation safety throughout the transportation process, including storage at intermediate warehouses, including recording dose readings during transportation.

3. Providing specific plans and routes for radioactive material transportation to the Radiation and Nuclear Safety Administration and the Science and Technology Department of the local authority along the transportation route.

Article 36. Responsibilities of the Receiver

1. Cooperating with the sender organization or individual, and the carrier to safely and promptly release consignments from the receiving location.

2. Participating in remediation efforts together with related organizations or individuals in case of incidents.

3. Reporting immediately to the sender organization or individual and the Radiation and Nuclear Safety Administration if the received goods do not conform to the transportation contract regarding type, quantity, and show signs of damage, dismantling, or radioactive leakage.

Article 37. Responsibilities of the Intermediate Warehouse Keeper for Radioactive Consignments

1. Cooperating with the carrier and the receiver to safely and promptly release radioactive consignments from the receiving location.

2. Participating in remediation efforts together with related parties in case of incidents.

3. Reporting immediately to the Radiation and Nuclear Safety Administration if radioactive consignments show signs of damage, dismantling, or radioactive leakage; or if there are unclaimed radioactive consignments.

Article 38. Customs Inspection, Supervision, and Management Work

1. Customs shall only open inspections on consignments containing radioactive materials when there is suspicion that illegal goods are contained within.

2. The inspection must be conducted with the participation of representatives from the Radiation and Nuclear Safety Administration and the local Science and Technology Department, carried out in a location ensuring radiation safety and equipped with appropriate radiation detection tools.

3. Consignments opened according to regulations must be resealed before being handed back to the carrier or receiver.

4. Unclaimed radioactive goods must be reported by customs and coordinated with the Radiation and Nuclear Safety Administration for handling.

Article 39. Handling Incidents and Accidents During Transportation of Radioactive Materials

1. When an incident or accident occurs during transportation, the escort personnel or driver must take the following actions:

a) Immediately notify: the issuing authority for radioactive material transportation permits; local police and the Science and Technology Department of the place where the incident or accident occurred; the owner of the transport vehicle; the shipper; the receiver;

b) Move victims (if any) away from the incident or accident site (in the direction of the wind) to provide first aid and transport them to the nearest medical facility;

c) Check for fire or explosion risks (if any) and find ways to mitigate them;

d) Isolate civilians from the incident or accident area from 50 (m) to 200 (m) and prevent unauthorized persons from entering the area.

2. Upon receiving information about an incident or accident, the relevant parties mentioned in Point a Clause 1 of this Article must immediately dispatch staff and necessary equipment to the scene to handle and mitigate the aftermath according to pre-planned measures (as stipulated in Article 6 of this Circular). Depending on the severity of the incident or accident, the following appropriate measures should be taken:

a) Establish an incident or accident aftermath response team;

b) Conduct radiation measurements, isolate the incident or accident area to carry out handling work and restore the initial state;

c) Decontaminate the incident or accident area, transport vehicles, consignments, people, clothing, protective equipment;

d) Test water and food sources;

đ) Protect drainage systems;

e) Identify overexposed individuals for health monitoring;

g) Investigate the cause and document the incident or accident.

3. Immediately after an accident occurs, the carrier must submit a detailed written report on the accident to the Radiation and Nuclear Safety Administration, the Science and Technology Department, and the local police authority.

4. Upon discovering the loss of a radioactive consignment, immediately notify:

a) The Radiation and Nuclear Safety Administration;

b) The local police authority;

c) The local Science and Technology Department;

d) The shipper.

The carrier must provide necessary information to these authorities to facilitate the search and recovery of lost consignments.

5. Depending on the cause, level of violation, and consequences of the incident or accident, the shipper and carrier will bear legal responsibility.

Chapter V

IMPLEMENTING PROVISIONS

Article 40. Effective Date

1. This Circular takes effect 45 days from the date of signature and replaces Circular No. 14/2003/TT-BKHCN dated July 11, 2003, issued by the Ministry of Science and Technology guiding safe transportation of radioactive materials.

2. During implementation, if there are difficulties, agencies, organizations, and individuals are advised to promptly reflect them to the Ministry of Science and Technology for review and amendment./.