Result
Identification
BAM name | ger. | Radioaktive Stoffe, geringe spezifische Aktivität (LSA-I), nicht spaltbar, flüssig, A2-Wert der enthaltenen Nuklide ist unbegrenzt |
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engl. | Radioactive material, low specific activity (LSA-I), non-fissile, liquid, nuclides for which the A2 value is unlimited | |
fr. | Matières radioactives de faible activité spécifique (LSA-I), non fissiles, liquides, pour lesquelles la valeur de A2 n'est pas limitée |
Classification
German proper shipping name
ADR 2023 | RADIOAKTIVE STOFFE MIT GERINGER SPEZIFISCHER AKTIVITÄT (LSA-I) |
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RID 2023 | RADIOAKTIVE STOFFE MIT GERINGER SPEZIFISCHER AKTIVITÄT (LSA-I) |
ADN 2023 | RADIOAKTIVE STOFFE MIT GERINGER SPEZIFISCHER AKTIVITÄT (LSA-I) |
IMDG-Code, Amdt. 41-22 | RADIOAKTIVE STOFFE MIT GERINGER SPEZIFISCHER AKTIVITÄT (LSA-I) |
English proper shipping name
ADR 2023 | RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY (LSA-I) |
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RID 2023 | RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY (LSA-I) |
ADN 2023 | RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY (LSA-I) |
IMDG-Code, Amdt. 41-22 | RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY (LSA-I) |
ICAO TI 2023 - 2024 | Radioactive material, low specific activity (LSA-I) |
UN Rec. 23rd rev. ed. | RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY (LSA-I) |
French proper shipping name
ADR 2023 | MATIÈRES RADIOACTIVES DE FAIBLE ACTIVITÉ SPÉCIFIQUE (LSA-I) |
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ADN 2023 | MATIÈRES RADIOACTIVES DE FAIBLE ACTIVITÉ SPÉCIFIQUE (LSA-I) |
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 |
Labelling for vehicles
Labelling for containers
ADR 2023 |
| ||||
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RID 2023 |
| ||||
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 |
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RID 2023 |
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ADN 2023 | Tanks not allowed according to ADN | ||||
IMDG-Code, Amdt. 41-22 |
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Proper shipping name necessary: RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY (LSA-I) |
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 | allowed |
ICAO TI 2023 - 2024 Cargo aircraft | allowed |
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 | Transport of excepted quantities is not allowed. |
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 | Transport of limited quantities is not allowed. |
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 | |
---|---|---|---|---|---|
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) |
LSA materialb) und SCO b) Industrial packages types 1, 2 or 3, non fissile and fissile excepted | 2912, 2913, 3321, 3322 |
- | |||
- package design | No | No | No | ||
- shipment | No | No | No |
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. |
Approval of shipments and notification according to ADR, RID, ADN, IMDG Code 5.1.5.1,5.1.5.2, 6.4.22, 6.4.23, ICAO TI 5;1.2.1, 5;1.1.2.2 and 6;7.21
Approvals for Radioactive material, low specific activity (LSA) are not required.
Notification to competent authorities according to ADR, RID, IMDG Code, ADN and ICAO TI isn`t necessary.
Security
ADR 2023 | This substance / article is NOT a high consequence dangerous good. |
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RID 2023 | This substance / article is NOT a high consequence dangerous good. |
ADN 2023 | This substance / article is NOT a high consequence dangerous good. |
IMDG-Code, Amdt. 41-22 | This substance / article is NOT a high consequence dangerous good. |
ICAO TI 2023 - 2024 | This substance / article is NOT a high consequence dangerous good. |
Requirements for packages
Packages, exclusive use: | |
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Package | Type IP-1 |
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
|
Special requirements | Requirements for industrial packages according to ADR, RID, IMDG Code 6.4.5.1 and ICAO TI 6;7.4.1; ADN according Part 6 of ADRAn Type IP-1 packages shall 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 smallest overall external dimension of the package must not be less than 10 cm. |
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):
|
Packages, non-exclusive use: | |||||||||||
---|---|---|---|---|---|---|---|---|---|---|---|
Package | Type IP-2 | ||||||||||
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
| ||||||||||
Special requirements | Requirements for industrial packages according to ADR, RID, IMDG Code 6.4.5 and ICAO TI 6;7.4; ADN according Part 6 of ADR
Alternative requirements for Type IP-2 packages according to ADR, RID, IMDG Code 6.4.5.4 and ICAO TI 6;7.4.4; ADN according Part 6 of ADR.
| ||||||||||
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
|
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 |
---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|
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 | - | - | - | - | - | - | - | - | - | - | - | - | - | - | - | - |
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. |