Packages approved under the 1973, 1973 (as amended), 1985 and 1985 (as amended 1990) editions of IAEA Safety Series No. 6
full unless the following conditions are met:
(a) The packagings were manufactured to a package design approved by the competent authority
under the provisions of the 1973 or 1973 (as amended) or the 1985 or 1985 (as amended 1990)
Editions of IAEA Safety Series No.6;
(b) The package design is subject to multilateral approval;
(c) The applicable requirements of 1.7.3 are applied;
(d) The activity limits and classification in 2.2.7 are applied;
(e) The requirements and controls for carriage in Parts 1, 3, 4, 5 and 7 are applied;
(g) For packages that meet the requirements of the 1973 or 1973 (as amended) Editions of IAEA
Safety Series No. 6:
(i) The packages retain sufficient shielding to ensure that the radiation level at 1 m from
the surface of the package would not exceed 10 mSv/h in the accident conditions of
carriage defined in the 1973 Revised or 1973 Revised (as amended) Editions of IAEA
Safety Series No.6 with the maximum radioactive contents which the package is
authorized to contain;
(ii) The packages do not utilize continuous venting;
(iii) A serial number in accordance with the provision of 18.104.22.168.5 is assigned to and marked
on the outside of each packaging.
No new manufacture of packagings to a package design meeting the provisions of the 1973, 1973 (as
amended), 1985, and 1985 (as amended 1990) Editions of IAEA Safety Series No.6 shall be permitted
Packages excepted from the requirements for fissile materials under the 2011 and 2013 editions of ADR (2009 Edition of IAEA Safety Standard Series No.TS-R-1)
Packages containing fissile material that is excepted from classification as "FISSILE" according to
22.214.171.124.3.5 (a) (i) or (iii) of the 2011 and 2013 editions of ADR (paras. 417 (a) (i) or (iii) of the 2009
Edition of IAEA Regulations for the Safe Transport of Radioactive Material) prepared for carriage
before 31 December 2014 may continue in carriage and may continue to be classified as non-fissile or
fissile-excepted except that the consignment limits in Table 126.96.36.199.3.5 of these editions shall apply to
the vehicle. The consignment shall be carried under exclusive use.
Special form radioactive material approved under the 1973, 1973 (as amended), 1985 and 1985 (as amended 1990) Editions of IAEA Safety Series No. 6
Special form radioactive material manufactured to a design which had received unilateral approval by
the competent authority under the 1973, 1973 (as amended), 1985 or 1985 (as amended 1990)
Editions of IAEA Safety Series No. 6 may continue to be used when in compliance with the
mandatory management system in accordance with the applicable requirements of 1.7.3. No new
manufacture of such special form radioactive material shall be permitted to commence.
GENERAL PROVISIONS CONCERNING RADIOACTIVE MATERIAL
Scope and application
NOTE 1: In the event of accidents or incidents during the carriage of radioactive material,
emergency provisions, as established by relevant national and/or international organizations, shall be
observed to protect persons, property and the environment. Appropriate guidelines for such
provisions are contained in "Planning and Preparing for Emergency Response to Transport Accidents
Involving Radioactive Material", Safety Standard Series No. TS-G-1.2 (ST-3), IAEA, Vienna (2002).
NOTE 2: Emergency procedures shall take into account the formation of other dangerous substances
that may result from the reaction between the contents of a consignment and the environment in the
event of an accident.
ADR establishes standards of safety which provide an acceptable level of control of the radiation,
criticality and thermal hazards to persons, property and the environment that are associated with the
carriage of radioactive material. These standards are based on the IAEA Regulations for the Safe
Transport of Radioactive material, 2012 Edition, IAEA Safety Standards Series No. SSR–6, IAEA,
Vienna (2012). Explanatory material can be found in “Advisory Material for the IAEA Regulations
for the Safe Transport of Radioactive Material (2012 Edition)”, IAEA Safety Standards Series No.
SSG-26, IAEA, Vienna (2014).
The objective of ADR is to establish requirements that shall be satisfied to ensure safety and to protect
persons, property and the environment from the effects of radiation in the carriage of radioactive
material. This protection is achieved by requiring:
(a) Containment of the radioactive contents;
(b) Control of external radiation levels;
(c) Prevention of criticality; and
(d) Prevention of damage caused by heat.
These requirements are satisfied firstly by applying a graded approach to contents limits for packages
and vehicles and to performance standards applied to package designs depending upon the hazard of
the radioactive contents. Secondly, they are satisfied by imposing conditions on the design and
operation of packages and on the maintenance of packagings, including a consideration of the nature
of the radioactive contents. Finally, they are satisfied by requiring administrative controls including,
where appropriate, approval by competent authorities.
the use of the radioactive material. Carriage comprises all operations and conditions associated with
and involved in the movement of radioactive material; these include the design, manufacture,
maintenance and repair of packaging, and the preparation, consigning, loading, carriage including intransit
storage, unloading and receipt at the final destination of loads of radioactive material and
packages. A graded approach is applied to the performance standards in ADR that are characterized
by three general severity levels:
(a) Routine conditions of carriage (incident free);
(b) Normal conditions of carriage (minor mishaps);
(c) Accident conditions of carriage.
The provisions laid down in ADR do not apply to any of the following:
(a) Radioactive material that is an integral part of the means of transport;
(b) Radioactive material moved within an establishment which is subject to appropriate safety
regulations in force in the establishment and where the movement does not involve public
roads or railways;
(c) Radioactive material implanted or incorporated into a person or live animal for diagnosis or
(d) Radioactive material in or on a person who is to be transported for medical treatment because
the person has been subject to accidental or deliberate intake of radioactive material or to
(e) Radioactive material in consumer products which have received regulatory approval, following
their sale to the end user;
(f) Natural material and ores containing naturally occurring radionuclides (which may have been
processed), provided the activity concentration of the material does not exceed 10 times the
values specified in Table 188.8.131.52.2.1, or calculated in accordance with 184.108.40.206.2.2 (a) and
220.127.116.11.2.3 to 18.104.22.168.2.6. For natural materials and ores containing naturally occurring
radionuclides that are not in secular equilibrium the calculation of the activity concentration
shall be performed in accordance with 22.214.171.124.2.4;
(g) Non-radioactive solid objects with radioactive substances present on any surfaces in quantities
not in excess of the limit set out in the definition for "contamination" in 126.96.36.199.2.
Specific provisions for the carriage of excepted packages
Excepted packages which may contain radioactive material in limited quantities, instruments,
manufactured articles or empty packagings as specified in 188.8.131.52.4.1 shall be subject only to the
following provisions of Parts 5 to 7:
(a) The applicable provisions specified in 184.108.40.206, 220.127.116.11, 18.104.22.168.2, 22.214.171.124.3, 126.96.36.199, 188.8.131.52,
7.5.11 CV33 (3.1), (5.1) to (5.4) and (6); and
(b) The requirements for excepted packages specified in 6.4.4.
except when the radioactive material possesses other hazardous properties and has to be classified in a
class other than Class 7 in accordance with special provision 290 or 369 of Chapter 3.3, where the
provisions listed in (a) and (b) above apply only as relevant and in addition to those relating to the
Excepted packages are subject to the relevant provisions of all other parts of ADR. If the excepted
package contains fissile material, one of the fissile exceptions provided by 184.108.40.206.3.5 shall apply and
the requirements of 7.5.11 CV33 (4.3) shall be met.
Radiation protection programme