Result
Identification
BAM name | ger. | Radioaktive Stoffe, Typ B(U)-Versandstück, nicht spaltbar, in besonderer Form, Aktivität > 3000 A1 oder Aktivität > 100000 A2 |
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engl. | Radioactive material, Type B(U) package, non-fissile, special form, activity > 3000 A1 or activity > 100000 A2 | |
fr. | Matières radioactives en colis de type B(U), non fissiles, sous forme spéciale, activité > 3000 A1 ou activité > 100000 A2 |
Classification
German proper shipping name
ADR 2023 | RADIOAKTIVE STOFFE, TYP B(U)-VERSANDSTÜCK |
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RID 2023 | RADIOAKTIVE STOFFE, TYP B(U)-VERSANDSTÜCK |
ADN 2023 | RADIOAKTIVE STOFFE, TYP B(U)-VERSANDSTÜCK |
IMDG-Code, Amdt. 41-22 | RADIOAKTIVE STOFFE, TYP B(U)-VERSANDSTÜCK |
English proper shipping name
ADR 2023 | RADIOACTIVE MATERIAL, TYPE B(U) PACKAGE |
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RID 2023 | RADIOACTIVE MATERIAL, TYPE B(U) PACKAGE |
ADN 2023 | RADIOACTIVE MATERIAL, TYPE B(U) PACKAGE |
IMDG-Code, Amdt. 41-22 | RADIOACTIVE MATERIAL, TYPE B(U) PACKAGE |
ICAO TI 2023 - 2024 | Carriage forbidden |
UN Rec. 23rd rev. ed. | RADIOACTIVE MATERIAL, TYPE B(U) PACKAGE |
French proper shipping name
ADR 2023 | MATIÈRES RADIOACTIVES EN COLIS DE TYPE B(U) |
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ADN 2023 | MATIÈRES RADIOACTIVES EN COLIS DE TYPE B(U) |
Labelling
Labelling for packages and small container
ADR 2023 | |
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RID 2023 | |
ADN 2023 | |
IMDG-Code, Amdt. 41-22 | |
ICAO TI 2023 - 2024 | Carriage forbidden |
Labelling for vehicles
Labelling for containers
ADR 2023 |
| ||||
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RID 2023 |
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ADN 2023 | The containers have to be labelled according to ADR, RID or IMDG Code. | ||||
IMDG-Code, Amdt. 41-22 |
|
Labelling for tanks
ADR 2023 | Tanks not allowed according to ADR |
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RID 2023 | Tanks not allowed according to RID |
ADN 2023 | Tanks not allowed according to ADN |
IMDG-Code, Amdt. 41-22 | Tanks not allowed according to IMDG |
Labelling for unpackaged transport
ADR 2023 | Unpackaged transport not allowed according to ADR |
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RID 2023 | Unpackaged transport not allowed according to RID |
ADN 2023 | Unpackaged transport not allowed according to ADN |
IMSBC Code | Unpackaged transport not allowed according to IMSBC Code |
Transport exclusions
The transport according to the following regulations is:ADR 2023 | allowed |
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RID 2023 | allowed |
ADN 2023 | allowed |
IMDG-Code, Amdt. 41-22 | allowed |
ICAO TI 2023 - 2024 Passenger aircraft | forbidden |
ICAO TI 2023 - 2024 Cargo aircraft | forbidden |
Tunnel restriction code
ADR 2023 | Tunnel restriction code E: Passage forbidden through tunnels of category E. |
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Excepted and limited quantities
Excepted Quantities
ADR 2023 | E0: No exception according to chapter 3.5. |
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RID 2023 | E0: No exception according to chapter 3.5. |
ADN 2023 | E0: No exception according to chapter 3.5. |
IMDG-Code, Amdt. 41-22 | E0: No exception according to chapter 3.5. |
ICAO TI 2023 - 2024 | Carriage forbidden |
Limited Quantities
ADR 2023 | No exception according to 3.4.2. |
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RID 2023 | No exception according to 3.4.2. |
ADN 2023 | No exception according to 3.4.2. |
IMDG-Code, Amdt. 41-22 | No exception according to 3.4.2. |
ICAO TI 2023 - 2024 | Carriage forbidden |
Bulk
Bulk
The transport according to the following regulations is:ADR 2023 | forbidden |
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RID 2023 | forbidden |
ADN 2023 | forbidden |
IMSBC Code | forbidden |
Bulk Containers
The transport according to the following regulations is:ADR 2023 | forbidden |
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RID 2023 | forbidden |
IMDG-Code, Amdt. 41-22 | forbidden |
Regulations
Definitions of specific terms according to 2.2.7.1.3 (ADR, RID, ADN; 2.7.1.3 IMDG Code; 2;7.1.3 ICAO TI)
Special form radioactive material means either:
An indispersible solid radioactive material; or
A sealed capsule containing radioactive material.
Low dispersible radioactive material according to 2.2.7.2.3.4 (ADR, RID, ADN; 2.7.2.3.4 IMDG Code; 2;7.2.3.4 ICAO TI)
The design for low dispersible radioactive material shall require multilateral approval. Low dispersible radioactive material shall be such that the total amount of this radioactive material in a package, taking into account the provisions of 6.4.8.14 (ADR, RID, ADN, IMDG Code; 6;7.7.14 ICAO TI) , shall meet the following requirements:
The dose rate at 3 m from the unshielded radioactive material does not exceed 10 mSv/h;
If subjected to the tests specified in 6.4.20.3 and 6.4.20.4 (ADR, RID, ADN, IMDG Code; 6;7.19.3 und 6;7.19.4), the airborne release in gaseous and particulate forms of up to 100 µm aerodynamic equivalent diameter would not exceed 100 A2. A separate specimen may be used for each test; and
If subjected to the test specified in 2.2.7.2.3.4.3 (ADR, RID, ADN; 2.7.2.3.4.3 IMDG Code; 2;7.2.3.4.3 ICAO TI) the activity in the water would not exceed 100 A2. In the application of this test, the damaging effects of the tests specified in (b) above shall be taken into account.
Low dispersible radioactive material shall be tested as follows:
A specimen that comprises or simulates low dispersible radioactive material shall be subjected to the enhanced thermal test specified in 6.4.20.3 (ADR, RID, ADN, IMDG Code; 6;7.19.3 ICAO TI) and the impact test specified in 6.4.20.4 (ADR, RID, ADN, IMDG Code; 6;7.19.4 ICAO TI). A different specimen may be used for each of the tests. Following each test, the specimen shall be subjected to the leach test specified in 2.2.7.2.3.4.3 (ADR, RID, ADN; 2.7.2.3.4.3 IMDG Code; 2;7.2.3.4.3 ICAO TI). After each test it shall be determined if the applicable requirements in point 1) have been met.
A solid material sample representing the entire contents of the package shall be immersed for 7 days in water at ambient temperature. The volume of water to be used in the test shall be sufficient to ensure that at the end of the 7-day test period the free volume of the unabsorbed and unreacted water remaining shall be at least 10 % of the volume of the solid test sample itself. The water shall have an initial pH of 6-8 and a maximum conductivity of 1 mS/m at 20 °C. The total activity of the free volume of water shall be measured following the 7-day immersion of the test sample.
Demonstration of compliance with the performance standards in the points 1), 2) and 3) shall be in accordance with 6.4.12.1 and 6.4.12.2 (ADR, RID, ADN, IMDG Code; 6;7.11.1 und 6;7.11.2).
Definitions of specific terms according to 2.2.7.1.3 (ADR, RID, ADN; 2.7.1.3 IMDG Code; 2;7.1.3 ICAO TI)
Special form radioactive material means either:
An indispersible solid radioactive material; or
A sealed capsule containing radioactive material.
Special form radioactive material according to 2.2.7.2.3.3 (ADR, RID, ADN; 2.7.2.3.3 IMDG Code; 2;7.2.3.3 ICAO TI)
Special form radioactive material shall have at least one dimension not less than 5 mm. When a sealed capsule constitutes part of the special form radioactive material, the capsule shall be so manufactured that it can be opened only by destroying it. The design for special form radioactive material requires unilateral approval.
Special form radioactive material shall be of such a nature or shall be so designed that if it is subjected to the tests specified in point 4) to 8), it shall meet the following requirements:
It would not break or shatter under the impact, percussion and bending tests in point 5 a), b), c) and 6 a) as applicable;
It would not melt or disperse in the applicable heat test 5 d) or 6 b) as applicable; and
The activity in the water from the leaching tests specified in point 7) and 8) would not exceed 2 kBq; or alternatively for sealed sources, the leakage rate for the volumetric leakage assessment test specified in ISO 9978:1992 "Radiation Protection - Sealed Radioactive Sources - Leakage Test Methods", would not exceed the applicable acceptance threshold acceptable to the competent authority.
Demonstration of compliance with the performance standards in point 2) shall be in accordance with 6.4.12.1 and 6.4.12.2 (ADR, RID, ADN, IMDG Code; 6;7.11.1 and 6;7.11.2 ICAO TI).
Specimens that comprise or simulate special form radioactive material shall be subjected to the impact test, the percussion test, the bending test, and the heat test specified in point 5) or alternative tests as authorized in point 6). A different specimen may be used for each of the tests. Following each test, a leaching assessment or volumetric leakage test shall be performed on the specimen by a method no less sensitive than the methods given in point 7) for indispersible solid material or in point 8) for encapsulated material.
The relevant test methods are:
Impact test: The specimen shall drop onto the target from a height of 9 m. The target shall be as defined in 6.4.14 (ADR, RID, ADN, IMDG Code; 6;7.13 ICAO TI);
Percussion test: The specimen shall be placed on a sheet of lead which is supported by a smooth solid surface and struck by the flat face of a mild steel bar so as to cause an impact equivalent to that resulting from a free drop of 1.4 kg from a height of 1 m. The lower part of the bar shall be 25 mm in diameter with the edges rounded off to a radius of (3.0 ± 0.3) mm. The lead, of hardness number 3.5 to 4.5 on the Vickers scale and not more than 25 mm thick, shall cover an area greater than that covered by the specimen. A fresh surface of lead shall be used for each impact. The bar shall strike the specimen so as to cause maximum damage;
Bending test: The test shall apply only to long, slender sources with both a minimum length of 10 cm and a length to minimum width ratio of not less than 10. The specimen shall be rigidly clamped in a horizontal position so that one half of its length protrudes from the face of the clamp. The orientation of the specimen shall be such that the specimen will suffer maximum damage when its free end is struck by the flat face of a steel bar. The bar shall strike the specimen so as to cause an impact equivalent to that resulting from a free vertical drop of 1.4 kg from a height of 1 m. The lower part of the bar shall be 25 mm in diameter with the edges rounded off to a radius of (3.0 ± 0.3) mm;
Heat test: The specimen shall be heated in air to a temperature of 800 °C and held at that temperature for a period of 10 minutes and shall then be allowed to cool.
Specimens that comprise or simulate radioactive material enclosed in a sealed capsule may be excepted from:
The tests prescribed in point 5 a) and b) provided that the specimens are alternatively subjected to the impact test prescribed in ISO 2919:2012 "Radiation Protection - Sealed Radioactive Sources - General requirements and classification":
The Class 4 impact test if the mass of the special form radioactive material is less than 200 g;
The Class 5 impact test if the mass of the special form radioactive material is equal to or more than 200 g but is less than 500 g;
The test prescribed in point 5 d) provided they are alternatively subjected to the Class 6 temperature test specified in ISO 2919:2012 "Radiation protection - Sealed radioactive sources - General requirements and classification".
For specimens which comprise or simulate indispersible solid material, a leaching assessment shall be performed as follows:
The specimen shall be immersed for 7 days in water at ambient temperature. The volume of water to be used in the test shall be sufficient to ensure that at the end of the 7 day test period the free volume of the unabsorbed and unreacted water remaining shall be at least 10 % of the volume of the solid test sample itself. The water shall have an initial pH of 6-8 and a maximum conductivity of 1 mS/m at 20 °C;
The water and the specimen shall then be heated to a temperature of (50 ± 5) °C and maintained at this temperature for 4 hours;
The activity of the water shall then be determined;
The specimen shall then be kept for at least 7 days in still air at not less than 30 °C and relative humidity not less than 90 %;
The specimen shall then be immersed in water of the same specification as in a) above and the water and the specimen heated to (50 ± 5) °C and maintained at this temperature for 4 hours;
The activity of the water shall then be determined.
For specimens which comprise or simulate radioactive material enclosed in a sealed capsule, either a leaching assessment or a volumetric leakage assessment shall be performed as follows:
The leaching assessment shall consist of the following steps:
the specimen shall be immersed in water at ambient temperature. The water shall have an initial pH of 6-8 with a maximum conductivity of 1 mS/m at 20 °C;
the water and specimen must then be heated to a temperature of (50 ± 5) °C and maintained at this temperature for 4 hours;
the activity of the water shall then be determined;
the specimen shall then be kept for at least 7 days in still air at not less than 30 °C and relative humidity of not less than 90 %;
the process in (i), (ii) and (iii) shall be repeated;
The alternative volumetric leakage assessment shall comprise any of the tests prescribed in ISO 9978:1992 "Radiation Protection - Sealed radioactive sources - Leakage test methods", provided that they are acceptable to the competent authority.
Determination of activity limits
Determination of basic radionuclide values according to ADR, RID and ADN 2.2.7.2.2; IMDG Code 2.7.2.2 and ICAO TI 2;7.2.2
The following basic values for individual radionuclides are given in table of nuclides (ADR, RID, ADN Table 2.2.7.2.2.1; IMDG Code Table 2.7.2.2.1; ICAO TI Table 2-12):
A1 and A2 in TBq;
Activity concentration limits for exempt material in Bq/g; and
Activity limits for exempt consignments in Bq.
For individual radionuclides:
Which are not listed in Table of nuclides the determination of the basic radionuclide values referred to in 1) shall require multilateral approval. For these radionuclides, activity concentration limits for exempt material and activity limits for exempt consignments shall be calculated in accordance with the principles established in the Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards IAEA Safety Standards Series No. GSR PART 3, IAEA, Vienna (2014). It is permissible to use an A2 value calculated using a dose coefficient for the appropriate lung absorption type as recommended by the International Commission on Radiological Protection, if the chemical forms of each radionuclide under both normal and accident conditions of carriage are taken into consideration. Alternatively, the radionuclide values in Table below may be used without obtaining competent authority approval;
In instruments or articles in which the radioactive material is enclosed or is included as a component part of the instrument or other manufactured article and which meet 2.2.7.2.4.1.3 c), (ADR, RID, ADN; 2.7.2.4.1.3.3 IMDG Code and 2;7.2.4.1.1.3 c) ICAO TI) alternative basic radionuclide values to those in Table of nuclides for the activity limit for an exempt consignment are permitted and shall require multilateral approval. Such alternative activity limits for an exempt consignment shall be calculated in accordance with the principles set out in GSR Part 3.
Table - Basic radionuclide values for unknown radionuclides or mixtures
Radioactive contents A1 A2 Activity concentration limit for exempt material Activity limit for an exempt consignment (TBq) (TBq) (Bq/g) ((Bq) Only beta or gamma emitting nuclides are known to be present 0,1 0,02 1 * 101 1 * 104 Alpha emitting nuclides but no neutron emitters are known to be present 0,2 9 * 10-5 1 * 10-1 1 * 103 Neutron emitting nuclides are known to be present or no relevant data are available 0,001 9 * 10-5 1 * 10-1 1 * 103 In the calculations of A1 and A2 for a radionuclide not in Table of nuclides, a single radioactive decay chain in which the radionuclides are present in their naturally occurring proportions, and in which no progeny nu-clide has a half-life either longer than 10 days or longer than that of the parent nuclide, shall be considered as a single radionuclide; and the activity to be taken into account and the A1 or A2 value to be applied shall be those corresponding to the parent nuclide of that chain. In the case of radioactive decay chains in which any progeny nuclide has a half-life either longer than 10 days or greater than that of the parent nuclide, the parent and such progeny nuclides shall be considered as mixtures of different nuclides.
For mixtures of radionuclides, the basic radionuclide values referred to in 1) may be determined as follows
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 as appropriate for the radionuclide i; and 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. When the identity of each radionuclide is known but the individual activities of some of the radionuclides are not known, the radionuclides may be grouped and the lowest radionuclide value, as appropriate, for the radionuclides in each group may be used in applying the formulas in 4) and 2.2.7.2.4.4 (ADR, RID, ADN; 2.7.2.4.4 IMDG-Code und 2;7.2.4.4 ICAO TI). Groups may be based on the total alpha activity and the total beta/gamma activity when these are known, using the lowest radionuclide values for the alpha emitters or beta/gamma emitters, respectively.
For individual radionuclides or for mixtures of radionuclides for which relevant data are not available, the values shown in Table above shall be used.
Determination of transport index (TI) according to ADR, RID, ADN and IMDG Code 5.1.5.3 and ICAO 5;1.2.3
The transport index (TI) for a package, overpack or container, or for unpackaged LSA-I, SCO-I or SCO-III, shall be the number derived in accordance with the following procedure:
Determine the maximum dose rate in units of millisieverts per hour (mSv/h) at a distance of 1 m from the external surfaces of the package, overpack, container, or unpackaged LSA-I, SCO-I or SCO-III. The value determined shall be multiplied by 100 and the resulting number is the transport index.
For uranium and thorium ores and their concentrates, the maximum dose rate at any point 1 m from the external surface of the load may be taken as:
0,4 mSv/h for ores and physical concentrates of uranium and thorium;
0,3 mSv/h for chemical concentrates of thorium;
0,02 mSv/h for chemical concentrates of uranium, other than uranium hexafluoride;
For tanks, containers and unpackaged LSA-I, SCO-I and SCO-III, the value determined in step (a) above shall be multiplied by the appropriate factor from Table 5.1.5.3.1 (ADR, RID, ADN, IMDG Code; Table 5-1 ICAO TI);
The value obtained in steps (a) and (b) above shall be rounded up to the first decimal place (e.g. 1.13 becomes 1.2), except that a value of 0.05 or less may be considered as zero and the resulting number is the transport index value.
Table - Multiplication factors for tanks, containers and unpackaged LSA-I, SCO-I and SCO-III
Size of load(a) Multiplication factor size of load ≤ 1 m2 1 1 m2 < size of load ≤ 5 m2 2 5 m2 < size of load ≤ 20 m2 3 20 m2 < size of load 10 a) Largest cross-sectional area of the load being measured.
The TI for each rigid overpack, freight container or conveyance shall be determined as the sum of the TIs of all the packages contained therein. For a shipment from a single consignor, the consignor may determine the TI by direct measurement of dose rate.
The TI for a non-rigid overpack shall be determined only as the sum of the TIs of all the packages within the overpack.
Requirements for the determination of the criticality safety index (CSI) according to ADR, RID, ADN and IMDG-Code 5.1.3.3 and ICAO 5;1.2.3.1.3
The criticality safety index for each overpack or container shall be determined as the sum of the CSIs of all the packages contained. The same procedure shall be followed for determining the total sum of the CSIs in a consignment or aboard a vehicle/wagon/conveyance/aircraft.
Determination of the criticality safety index (CSI) according to ADR, RID and IMDG Code 6.4.11 and ICAO 6;7.10; ADN according Part 6 of ADR
For normal conditions of carriage a number "N" shall be derived, such that five times "N" packages shall be subcritical for the arrangement and package conditions that provide the maximum neutron multiplication consistent with the following:
-
here shall not be anything between the packages, and the package arrangement shall be reflected on all sides by at least 20 cm of water; and
-
The state of the packages shall be their assessed or demonstrated condition if they had been subjected to the tests for demonstrating ability to withstand normal conditions of carriage.
-
For accident conditions of carriage a number "N" shall be derived, such that two times "N" packages shall be subcritical for the arrangement and package conditions that provide the maximum neutron multiplication consistent with the following:
-
Hydrogenous moderation between packages, and the package arrangement reflected on all sides by at least 20 cm of water; and
-
The tests for demonstrating ability to withstand normal conditions of carriage followed by whichever of the following is the more limiting:
the mechanical tests for demonstrating ability to withstand accident conditions in carriage sub-point (b) and, either the mechanical test of sub-point (c) for packages having a mass not greater than 500 kg and an overall density not greater than 1,000 kg/m³ based on the external dimensions, or mechanical test of sub-point (a) for all other packages; followed by the test specified in thermal test for demonstrating ability to withstand accident conditions and completed by the water leakage test for packages containing fissile material; or
the water immersion test for demonstrating ability to withstand normal conditions of carriage; and
-
Where any part of the fissile material escapes from the containment system following the tests specified in 13) (b), it shall be assumed that fissile material escapes from each package in the array and all of the fissile material shall be arranged in the configuration and moderation that results in the maximum neutron multiplication with close reflection by at least 20 cm of water.
-
The criticality safety index (CSI) for packages containing fissile material shall be obtained by dividing the number 50 by the smaller of the two values of N derived in 12) and 13) (i.e. CSI = 50/N). The value of the criticality safety index may be zero, provided that an unlimited number of packages is subcritical (i.e. N is effectively equal to infinity in both cases).
Approval
Summary of approval and prior notification requirements according to ADR, RID, ADN 5.1.5
Subject | UN Number | Competent Authority approval required | Consignor required to notify the competent authorities of the country of origin and of the countries en route a) before each shipment | Reference | |
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Country of origin | Countries en routea) | ||||
Calculation of unlisted A1 and A2 values | - | Yes | Yes | No | 2.2.7.2.2.2 (a), 5.1.5.2.1 (d) |
Type B(U) packages b), non fissile and fissile excepted | 2916 | 5.1.5.1.4 (b), 5.1.5.2.1 (a), 6.4.22.2 | |||
- package design | Yes | No | See NOTE 1 | ||
- shipment | No | No | See NOTE 2 | ||
Special form radioactive material | 1.6.6.4, 5.1.5.2.1 (a), 6.4.22.5 | ||||
- design | - | Yes | No | No | |
- shipment | See NOTE 4 | See NOTE 4 | See NOTE 4 | See NOTE 4 |
a) | Countries from, through or into which the consignment is carried. |
b) | If the radioactive contents are fissile material which is not excepted from the provisions for packages containing fissile material, then the provisions for fissile material packages apply. |
NOTE 1 | Before first shipment of any package requiring competent authority approval of the design, the consignor shall ensure that a copy of the approval certificate for that design has been submitted to the competent authority of each country en route. |
NOTE 2 | Notification required if contents exceed 3 * 103 A1 or 3 * 103 A2 or 1,000 TBq |
NOTE 4 | See approval and prior notification provisions for the applicable package for carrying this material. |
These information do not apply for transports by air, because there the requirements for a Type C package must be met.
Approval of shipments and notification according to ADR, RID, ADN, IMDG Code 5.1.5.1 and ICAO TI 5;1.2.1
General
In addition to the approval of package designs described in Chapter 6.4, multilateral shipment approval is also required in certain circumstances (point 2 and 3). In some circumstances it is also necessary to notify competent authorities of a shipment (point 4).
Notification to competent authorities is required as follows:
Before the first shipment of any package requiring competent authority approval, the consignor shall ensure that copies of each applicable competent authority certificate applying to that package design have been submitted to the competent authority of the country of origin of the shipment and to the competent authority of each country through or into which the consignment is to be carried. The consignor is not required to await an acknowledgement from the competent authority, nor is the competent authority required to make such acknowledgement of receipt of the certificate;.
For each of the following types of shipments:
Type B(U) packages containing radioactive material with an activity greater than 3,000 A1 or 3,000 A2, as appropriate, or 1,000 TBq, whichever is the lower;
The consignor shall notify the competent authority of the country of origin of the shipment and the competent authority of each country through or into which the consignment is to be carried. This notification shall be in the hands of each competent authority prior to the commencement of the shipment, and preferably at least 7 days in advance;
The consignor is not required to send a separate notification if the required information has been included in the application for approval of shipment;
The consignment notification shall include:
sufficient information to enable the identification of the package or packages including all applicable certificate numbers and identification marks;
information on the date of shipment, the expected date of arrival and proposed routeing;
the name(s) of the radioactive material(s) or nuclide(s);
descriptions of the physical and chemical forms of the radioactive material, or whether it is special form radioactive material or low dispersible radioactive material; and
the maximum activity of the radioactive contents during carriage expressed in becquerels (Bq) with an appropriate SI prefix symbol. For fissile material, the mass of fissile material (or of each fissile nuclide for mixtures when appropriate) in grams (g), or multiples thereof, may be used in place of activity.
Certificates issued by the competent authority according to ADR, RID, ADN, IMDG Code 5.1.5.2 and ICAO TI 5;1.2.2
Certificates issued by the competent authority are required for the following:
Designs for:
special form radioactive material;
Type B(U) packages and Type B(M) packages;
The certificates shall confirm that the applicable requirements are met, and for design approvals shall attribute to the design an identification mark.
The certificates of approval for the package design and the shipment may be combined into a single certificate.
Certificates and applications for these certificates shall be in accordance with the requirements in 6.4.23 (ADR, RID, IMDG Code; ICAO TI 6;7.22).
The consignor shall be in possession of a copy of each applicable certificate.
For package designs where it is not required that a competent authority issue a certificate of approval, the consignor shall, on request, make available for inspection by the competent authority, documentary evidence of the compliance of the package design with all the applicable requirements.
Approvals of package designs and materials according to ADR, RID, IMDG Code 6.4.22 and ICAO TI 6;7.21, ADN according Part 6 of ADR
Each Type B(U) and Type C package design shall require unilateral approval, except that:
A package design for fissile material, which is also subject to 6.4.22.4 (ADR, RID, IMDG Code; ICAO TI 6;7.21.4), 6.4.23.7 (ADR, RID, IMDG Code), and 5.1.5.2.1 (ADR, RID, IMDG Code; ICAO TI 5;1,2,2,1) shall require multilateral approval; and
The design for special form radioactive material shall require unilateral approval. The design for low dispersible radioactive material shall require multilateral approval.
Only ADR, RID
Any design that requires unilateral approval originating in a country Contracting Party to ADR / RID Contracting State shall be approved by the competent authority of this country; if the country where the package design has been designed is not a Contracting Party to ADR / RID Contracting State, carriage is possible on condition that:
A certificate has been supplied by this country, proving that the package design satisfies the technical requirements of ADR, and that this certificate is validated by a competent authority of an ADR Contracting Party / a RID Contracting State;
If no certificate and no existing package design approval by a country Contracting Party to ADR / RID Contracting State has been supplied, the package design is approved by the competent authority of an ADR Contracting Party / a RID Contracting State.
For designs approved under the transitional measures see 1.6.6.
Applications and approvals for radioactive material carriage according to ADR, RID, IMDG Code 6.4.23, ICAO TI see 6.4.23 of the UN Rec, ADN according Part 6 of ADR
Application for approval of shipment
An application for approval of shipment shall include:
The period of time, related to the shipment, for which the approval is sought;
The actual radioactive contents, the expected modes of carriage, the type of vehicle, and the probable or proposed route; and
The details of how the precautions and administrative or operational controls, referred to in the certificate of approval for the package design, if applicable, issued under 5.1.5.2.1 (a) (v), (vi) or (vii) (ADR, RID; IMDG Code 5.1.5.2.1.1.5, 5.2.1.1.6 or 5.1.5.2.1.1.7), are to be put into effect.
Note of BAM: In the UN Recommendations and in the IMDG Code the numbering of subsection 6.4.23.2 ist different. The paragraph 6.4.23.2.1 is listed as 6.4.23.2 and the paragraph 6.4.23.2.2 is numbered as 6.4.23.2.1
An application for approval of Type B(U) or Type C package design shall include:
A detailed description of the proposed radioactive contents with reference to their physical and chemical states and the nature of the radiation emitted;
A detailed statement of the design, including complete engineering drawings and schedules of materials and methods of manufacture;
A statement of the tests which have been done and their results, or evidence based on calculative methods or other evidence that the design is adequate to meet the applicable requirements;
The proposed operating and maintenance instructions for the use of the packaging;
If the package is designed to have a maximum normal operating pressure in excess of 100 kPa gauge, a specification of the materials of manufacture of the containment system, the samples to be taken, and the tests to be made;
If the package is to be used for shipment after storage, a justification of considerations to ageing mechanisms in the safety analysis and within the proposed operating and maintenance instructions;
Where the proposed radioactive contents are irradiated nuclear fuel, a statement and a justification of any assumption in the safety analysis relating to the characteristics of the fuel and a description of any pre-shipment measurement as required by 6.4.11.5 b);
Any special stowage provisions necessary to ensure the safe dissipation of heat from the package considering the various modes of carriage to be used and type of vehicle or container;
A reproducible illustration, not larger than 21 cm by 30 cm, showing the make-up of the package;
A specification of the applicable management system; and
For packages which are to be used for shipment after storage, a gap analysis programme describing a systematic procedure for a periodic evaluation of changes of Regulations, changes in technical knowledge and changes of the state of the package design during storage.
An application for approval of design for special form radioactive material and design for low dispersible radioactive material shall include:
A detailed description of the radioactive material or, if a capsule, the contents; particular reference shall be made to both physical and chemical states;
A detailed statement of the design of any capsule to be used;
A statement of the tests which have been done and their results, or evidence based on calculations to show that the radioactive material is capable of meeting the performance standards, or other evidence that the special form radioactive material or low dispersible radioactive material meets the applicable requirements of this Regulation;
A specification of the applicable management system; and
Any proposed pre-shipment actions for use in the consignment of special form radioactive material or low dispersible radioactive material.
Each certificate of approval issued by a competent authority shall be assigned an identification mark. The identification mark shall be of the following generalized type:
VRI/Number/Type Code
Except as provided in 12), VRI represents the distinguishing sign used on vehicles in international road traffic of the country issuing the certificate. 1)
The number shall be assigned by the competent authority, and shall be unique and specific with regard to the particular design or shipment or alternative activity limit for exempt consignment. The identification mark of the approval of shipment shall be clearly related to the identification mark of the approval of design;
The following type codes shall be used in the order listed to indicate the types of certificate of approval issued:
B(U) Type B(U) package design [B(U) F if for fissile material] S Special form radioactive material T Shipment
These identification marks shall be applied as follows:
Each certificate and each package shall bear the appropriate identification mark, comprising the symbols prescribed in point 11 a), b) and c) above, except that, for packages, only the applicable design type codes including, shall appear following the second stroke, that is, the "T" or "X" shall not appear in the identification mark on the package. Where the approval of design and the approval of shipment are combined, the applicable type codes do not need to be repeated. For example:
A/132/B(M)F-96: A Type B(M) package design approved for fissile material, requiring multilateral approval, for which the competent authority of Austria has assigned the design number 132 (to be marked on both the package and on the certificate of approval for the package design); A/132/B(M)F-96T: The approval of shipment issued for a package bearing the identification mark elaborated above (to be marked on the certificate only); A/137/X: An approval of special arrangement issued by the competent authority of Austria, to which the number 137 has been assigned (to be marked on the certificate only); A/139/IF-96: An industrial package design for fissile material approved by the competent authority of Austria, to which package design number 139 has been assigned (to be marked on both the package and on the certificate of approval for the package design); and A/145/H(U)-96: A package design for fissile excepted uranium hexafluoride approved by the competent authority of Austria, to which package design number 145 has been assigned (to be marked on both the package and on the certificate of approval for the package design); Where multilateral approval is effected by validation in accordance with point 20), only the identification mark issued by the country of origin of the design or shipment shall be used. Where multilateral approval is effected by issue of certificates by successive countries, each certificate shall bear the appropriate identification mark and the package whose design was so approved shall bear all appropriate identification marks. For example:
A/132/B(M)F-96
CH/28/B(M)F-96would be the identification mark of a package which was originally approved by Austria and was subsequently approved, by separate certificate, by Switzerland. Additional identification marks would be tabulated in a similar manner on the package;
The revision of a certificate shall be indicated by a parenthetical expression following the identification mark on the certificate. For example, A/132/B(M)F-96 (Rev.2) would indicate revision 2 of the Austrian certificate of approval for the package design; or A/132/B(M)F-96 (Rev.0) would indicate the original issuance of the Austrian certificate of approval for the package design. For original issuances, the parenthetical entry is optional and other words such as "original issuance" may also be used in place of "Rev.0". Certificate revision numbers may only be issued by the country issuing the original certificate of approval;
Additional symbols (as may be necessitated by national regulations) may be added in brackets to the end of the identification mark; for example, A/132/B(M)F-96(SP503);
It is not necessary to alter the identification mark on the packaging each time that a revision to the design certificate is made. Such re-marking shall be required only in those cases where the revision to the package design certificate involves a change in the letter type codes for the package design following the second stroke.
Each certificate of approval issued by a competent authority for special form radioactive material or low dispersible radioactive material shall include the following information:
Type of certificate;
The competent authority identification mark;
The issue date and an expiry date;
List of applicable national and international regulations, including the edition of the IAEA Regulations for the Safe Transport of Radioactive Material under which the special form radioactive material or low dispersible radioactive material is approved;
The identification of the special form radioactive material or low dispersible radioactive material;
A description of the special form radioactive material or low dispersible radioactive material;
Design specifications for the special form radioactive material or low dispersible radioactive material which may include references to drawings;
A specification of the radioactive contents which includes the activities involved and which may include the physical and chemical form;
A specification of the applicable management system;
Reference to information provided by the applicant relating to specific actions to be taken prior to shipment;
If deemed appropriate by the competent authority, reference to the identity of the applicant;
Signature and identification of the certifying official.
Each certificate of approval for a shipment issued by a competent authority shall include the following information:
Type of certificate;
The competent authority identification mark(s);
The issue date and an expiry date;
List of applicable national and international regulations, including the edition of the IAEA Regulations for the Safe Transport of Radioactive Material under which the shipment is approved;
Any restrictions on the modes of carriage, type of vehicle, container, and any necessary routeing instructions;
The following statement: "This certificate does not relieve the consignor from compliance with any requirement of the government of any country through or into which the package will be carried.";
A detailed listing of any supplementary operational controls required for preparation, loading, carriage, unloading and handling of the consignment, including any special stowage provisions for the safe dissipation of heat or maintenance of criticality safety;
Reference to information provided by the applicant relating to specific actions to be taken prior to shipment;
Reference to the applicable certificate(s) of approval of design;
A specification of the actual radioactive contents, including any restrictions on the radioactive contents which might not be obvious from the nature of the packaging. This shall include the physical and chemical forms, the total activities involved (including those of the various isotopes, if appropriate), mass in grams (for fissile material or for each fissile nuclide when appropriate), and whether special form radioactive material, low dispersible radioactive material or fissile material excepted under2.2.7.2.3.5 f) (ADR, RID; IMDG Code 2.7.2.3.5.6) if applicable;
Any emergency arrangements deemed necessary by the competent authority;
A specification of the applicable management system;
If deemed appropriate by the competent authority, reference to the identity of the applicant;
Signature and identification of the certifying official.
Each certificate of approval of the design of a package issued by a competent authority shall include the following information:
Type of certificate;
The competent authority identification mark;
The issue date and an expiry date;
Any restriction on the modes of carriage, if appropriate;
List of applicable national and international regulations, including the edition of the IAEA Regulations for the Safe Transport of Radioactive Material under which the design is approved;
The following statement: "This certificate does not relieve the consignor from compliance with any requirement of the government of any country through or into which the package will be carried.";
References to certificates for alternative radioactive contents, other competent authority validation, or additional technical data or information, as deemed appropriate by the competent authority;
A statement authorizing shipment where approval of shipment is required under 5.1.5.1.2, if deemed appropriate;
Identification of the packaging;
Description of the packaging by a reference to the drawings or specification of the design. If deemed appropriate by the competent authority, a reproducible illustration, not larger than 21 cm by 30 cm, showing the make-up of the package shall also be provided, accompanied by a brief description of the packaging, including materials of manufacture, gross mass, general outside dimensions and appearance;
Specification of the design by reference to the drawings;
A specification of the authorized radioactive content, including any restrictions on the radioactive contents which might not be obvious from the nature of the packaging. This shall include the physical and chemical forms, the activities involved (including those of the various isotopes, if appropriate), mass in grams (for fissile material the total mass of fissile nuclides or the mass for each fissile nuclide, when appropriate) and whether special form radioactive material, low dispersible radioactive material or fissile material excepted under2.2.7.2.3.5 f) (ADR, RID; IMDG Code 2.7.2.3.5.6) if applicable;
A description of the containment system;
For package designs containing fissile material which require multilateral approval of the package design in accordance with 6.4.22.4:
a detailed description of the authorized radioactive contents;
a description of the confinement system;
the value of the criticality safety index;
reference to the documentation that demonstrates the criticality safety of the package;
any special features, on the basis of which the absence of water from certain void spaces has been assumed in the criticality assessment;
any allowance (based on 6.4.11.5 b)) for a change in neutron multiplication assumed in the criticality assessment as a result of actual irradiation experience; and
the ambient temperature range for which the package design has been approved;
For Type B(M) packages, a statement specifying those requirements of 6.4.7.5, 6.4.8.4, 6.4.8.5, 6.4.8.6 and 6.4.8.9 to 6.4.8.15 with which the package does not conform and any amplifying information which may be useful to other competent authorities;
For package designs subject to 1.6.6.2.1 (ADR and RID; IMDG Code 6.4.24.2), a statement specifying those requirements of the current regulations with which the package does not conform;
For packages containing more than 0.1 kg of uranium hexafluoride, a statement specifying those prescriptions of 6.4.6.4 which apply if any and any amplifying information which may be useful to other competent authorities;
A detailed listing of any supplementary operational controls required for preparation, loading, carriage, unloading and handling of the consignment, including any special stowage provisions for the safe dissipation of heat;
Reference to information provided by the applicant relating to the use of the packaging or specific actions to be taken prior to shipment;
A statement regarding the ambient conditions assumed for purposes of design if these are not in accordance with those specified in 6.4.8.5, 6.4.8.6 and 6.4.8.15, as applicable;
A specification of the applicable management system as required in 1.7.3;
Any emergency arrangements deemed necessary by the competent authority;
If deemed appropriate by the competent authority, reference to the identity of the applicant;
Signature and identification of the certifying official.
The competent authority shall be informed of the serial number of each packaging manufactured to a design approved by them under 1.6.6.2.1, 1.6.6.2.2, 6.4.22.2, 6.4.22.3 (only IMDG Code) and 6.4.22.4 (only IMDG Code).
Multilateral approval may be by validation of the original certificate issued by the competent authority of the country of origin of the design or shipment. Such validation may take the form of an endorsement on the original certificate or the issuance of a separate endorsement, annex, supplement, etc., by the competent authority of the country through or into which the shipment is made.
Footnote
Distinguishing sign of the State of registration used on motor vehicles and trailers in international road traffic, e.g. in accordance with the Geneva Convention on Road Traffic of 1949 or the Vienna Convention on Road Traffic of 1968.↑
These information do not apply for transports by air, because there the requirements for a Type C package must be met.
Security
ADR 2023 | High consequence dangerous good according to subsection 1.10.3.1, if the quantities of radioactive materials exceed that the activity is equal to or greater than a transport security threshold of 3 000 A2 per single package except for the following radionuclides where the transport security threshold is given in Table 1.10.3.1.3. |
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RID 2023 | High consequence dangerous good according to subsection 1.10.3.1, if the quantities of radioactive materials exceed that the activity is equal to or greater than a transport security threshold of 3 000 A2 per single package except for the following radionuclides where the transport security threshold is given in Table 1.10.3.1.3. |
ADN 2023 | High consequence dangerous good according to subsection 1.10.3.1, if the quantities of radioactive materials exceed that the activity is equal to or greater than a transport security threshold of 3 000 A2 per single package except for the following radionuclides where the transport security threshold is given in Table 1.10.3.1.3. |
IMDG-Code, Amdt. 41-22 | High consequence dangerous good according to subsection 1.4.3.1, if the quantities of radioactive materials exceed that the activity is equal to or greater than a transport security threshold of 3 000 A2 per single package except for the following radionuclides where the transport security threshold is given in Table 1.4.2. |
ICAO TI 2023 - 2024 | Carriage forbidden |
Requirements for packages
Packages, exclusive use: | |||||||||||||||||||
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Package | Type B(U) | ||||||||||||||||||
Max. radiation level | 10 mSv/h | ||||||||||||||||||
General requirements | General requirements for packages with radioactive material according to ADR, RID, IMDG Code 6.4.2 and ICAO TI 6;7.1; ADN according Part 6 of ADR
Additional requirements for packages transported by air according IMDG Code 6.4.3 und ICAO TI 6;7.2
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Special requirements | Requirements for Type B(M) packages according to ADR, RID, IMDG Code 6.4.9 and ICAO TI 6;7.8; ADN according Part 6 of ADRType B(U) packages must be designed to meet the general requirements specified in 6.4.2 (ADR, RID, IMDG Code; ICAO TI 6;7.1) and, in addition, shall meet the requirements of 6.4.3 (IMDG Code; ICAO TI 6;7.2) if carried by air, the requirements for Type A packages according 6.4.7 (ADR, RID, IMDG Code; ICAO TI 6;7.6) except 6.4.7.14 a) (ADR, RID und IMDG Code; ICAO TI 6;7.6.14 a)) and the following requirements.
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Test requirements | Test procedures and demonstration of compliance according ADR, RID, IMDG Code 6.4.12 and ICAO TI 6;7.11; ADN according Part 6 of ADR
Testing the integrity of the containment system and shielding and evaluating criticality safety according ADR, RID, IMDG Code 6.4.13 and ICAO TI 6;7.12; ADN according Part 6 of ADRAfter each test or group of tests or sequence of the applicable tests, as appropriate, specified in 6.4.15 to 6.4.21 (ADR, RID, IMDG Code; 6;7.14 to 6;7.20 ICAO TI):
Target for drop tests according ADR, RID, IMDG Code 6.4.14 and ICAO TI 6;7.13; ADN according Part 6 of ADRThe target for the drop tests shall be a flat, horizontal surface of such a character that any increase in its resistance to displacement or deformation upon impact by the specimen would not significantly increase the damage to the specimen. Tests for demonstrating ability to withstand normal conditions of carriage according ADR, RID, IMDG Code 6.4.15 and ICAO TI 6;7.14; ADN according Part 6 of ADR
Tests for demonstrating ability to withstand accident conditions in carriage according ADR, RID, IMDG Code 6.4.17 and ICAO TI 6;7.16; ADN according Part 6 of ADR
Enhanced water immersion test for Type B(U) and Type B(M) packages containing more than 105 A2 and Type C packages according ADR, RID, IMDG Code 6.4.18 and ICAO TI 6;7.17; ADN according Part 6 of ADREnhanced water immersion test: The specimen shall be immersed under a head of water of at least 200 m for a period of not less than one hour. For demonstration purposes, an external gauge pressure of at least 2 MPa shall be considered to meet these conditions. |
Packages, non-exclusive use: | |||||||||||||||||||
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Package | Type B(U) | ||||||||||||||||||
Max. radiation level | 2 mSv/h | ||||||||||||||||||
General requirements | General requirements for packages with radioactive material according to ADR, RID, IMDG Code 6.4.2 and ICAO TI 6;7.1; ADN according Part 6 of ADR
Additional requirements for packages transported by air according IMDG Code 6.4.3 und ICAO TI 6;7.2
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Special requirements | Requirements for Type B(M) packages according to ADR, RID, IMDG Code 6.4.9 and ICAO TI 6;7.8; ADN according Part 6 of ADRType B(U) packages must be designed to meet the general requirements specified in 6.4.2 (ADR, RID, IMDG Code; ICAO TI 6;7.1) and, in addition, shall meet the requirements of 6.4.3 (IMDG Code; ICAO TI 6;7.2) if carried by air, the requirements for Type A packages according 6.4.7 (ADR, RID, IMDG Code; ICAO TI 6;7.6) except 6.4.7.14 a) (ADR, RID und IMDG Code; ICAO TI 6;7.6.14 a)) and the following requirements.
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Test requirements | Test procedures and demonstration of compliance according ADR, RID, IMDG Code 6.4.12 and ICAO TI 6;7.11; ADN according Part 6 of ADR
Testing the integrity of the containment system and shielding and evaluating criticality safety according ADR, RID, IMDG Code 6.4.13 and ICAO TI 6;7.12; ADN according Part 6 of ADRAfter each test or group of tests or sequence of the applicable tests, as appropriate, specified in 6.4.15 to 6.4.21 (ADR, RID, IMDG Code; 6;7.14 to 6;7.20 ICAO TI):
Target for drop tests according ADR, RID, IMDG Code 6.4.14 and ICAO TI 6;7.13; ADN according Part 6 of ADRThe target for the drop tests shall be a flat, horizontal surface of such a character that any increase in its resistance to displacement or deformation upon impact by the specimen would not significantly increase the damage to the specimen. Tests for demonstrating ability to withstand normal conditions of carriage according ADR, RID, IMDG Code 6.4.15 and ICAO TI 6;7.14; ADN according Part 6 of ADR
Tests for demonstrating ability to withstand accident conditions in carriage according ADR, RID, IMDG Code 6.4.17 and ICAO TI 6;7.16; ADN according Part 6 of ADR
Enhanced water immersion test for Type B(U) and Type B(M) packages containing more than 105 A2 and Type C packages according ADR, RID, IMDG Code 6.4.18 and ICAO TI 6;7.17; ADN according Part 6 of ADREnhanced water immersion test: The specimen shall be immersed under a head of water of at least 200 m for a period of not less than one hour. For demonstration purposes, an external gauge pressure of at least 2 MPa shall be considered to meet these conditions. |
Mixed packing
A package shall not contain any items other than those that are necessary for the use of the radioactive material. The interaction between these items and the package under the conditions of carriage applicable to the design, shall not reduce the safety of the package.Mixed Loading, Stowage, Segregation
Mixed Loading | 1.1 | 1.2 | 1.3 | 1.4 | 1.5 | 1.6 | 2.1 | 2.2 | 2.3 | 3 | 4.1 | 4.1+1 | 4.2 | 4.3 | 5.1 | 5.2 | 5.2+1 | 6.1 | 6.2 | 7 | 8 | 9 |
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ADR 2023 | - | a | - | - | X | X | X | X | X | - | X | X | X | X | - | X | X | X | X | X | ||
RID 2023 | - | a | - | - | X | X | X | X | X | - | X | X | X | X | - | X | X | X | X | X | ||
IMDG-Code, Amdt. 41-22 | 2 | 2 | 2 | 2 | 2 | 2 | 2 | 1 | 1 | 2 | 2 | 2 | 2 | 1 | 2 | X | 3 | X | 2 | X | ||
ICAO TI 2023 - 2024 | Carriage forbidden |
Transport Documents
ADR 2023 | Extracts from chapter 5.4 Documentation5.4.0 General
5.4.1 Dangerous goods transport document and related information5.4.1.1 General information required in the transport document
5.4.1.2.5 Additional provisions for Class 7
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RID 2023 | Extracts from chapter 5.4 Documentation5.4.0 General
5.4.1 Dangerous goods transport document and related information5.4.1.1 General information required in the transport document
5.4.1.2.5 Additional provisions for Class 7
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ADN 2023 | Extracts from chapter 5.4 Documentation5.4.0 General
5.4.1 Dangerous goods transport document and related information5.4.1.1 General information required in the transport document5.4.1.1.1 General information required in the transport document for carriage in bulk or in packagesThe transport document(s) shall contain the following information for each dangerous substance, material or article offered for carriage:
The information required on a transport document shall be legible. Although upper case is used in Chapter 3.1 and in Table A of Chapter 3.2 to indicate the elements which shall be part of the proper shipping name, and although upper and lower case are used in this Chapter to indicate the information required in the transport document, the use of upper or of lower case for entering the information in the transport document is left optional. 5.4.1.2.5 Additional provisions for Class 7
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IMDG-Code, Amdt. 41-22 | Extracts from chapter 5.4 Documentation
5.4.1 Dangerous goods transport information5.4.1.1 General
5.4.1.2 Form of the transport document
5.4.1.3 Consignor, consignee and dateThe name and address of the consignor and the consignee of the dangerous goods shall be included on the dangerous goods transport document. The date the dangerous goods transport document or an electronic copy of it was prepared or given to the initial carrier shall be included. 5.4.1.4 Information required on the dangerous goods transport document
5.4.1.5.7 Radioactive material
Fußnote
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ICAO TI 2023 - 2024 | Extracts from Part 5 Chapter 4 Documentation5;4 DOCUMENTATIONNote.- These Instructions do not preclude the use of electronic data processing (EDP) and electronic data interchange (EDI) transmission techniques as an alternative to paper documentation. Unless otherwise indicated, all references to "dangerous goods transport document" in this chapter also include provision of the required information by use of EDP and EDI transmission techniques. 5;4.1 DANGEROUS GOODS TRANSPORT INFORMATION5;4.1.1 General
Note.- All references to "dangerous goods transport document" in this chapter also include provision of the required information by use of EDP and EDI transmission techniques. 5;4.1.2 Form of the transport document
5;4.1.3 Shipper and consigneeThe name and address of the shipper and the consignee of the dangerous goods must be included on the dangerous goods transport document. For the transport of radioactive material, it is recommended that the telephone number of the consignee is included to facilitate a prompt release at the airport of destination. 5;4.1.4 Information required on the dangerous goods transport document
5;4.1.5.7 Radioactive material
5;4.1.5.8 Additional requirements
5;4.1.6 Certification
5;4.2 AIR WAYBILLWhen an air waybill is issued for a consignment for which a dangerous goods transport document is required, the air waybill must contain a statement to indicate that the dangerous goods are described on an accompanying dangerous goods transport document. An air waybill issued for a consignment must, when applicable, indicate that the consignment must be loaded on cargo aircraft only. |