Special packing provisions for radioactive material
Radioactive material, packagings and packages shall meet the requirements of Chapter 6.4.
The quantity of radioactive material in a package shall not exceed the limits specified in 188.8.131.52.2,
184.108.40.206.4.1, 220.127.116.11.4.4, 18.104.22.168.4.5, 22.214.171.124.4.6, special provision 336 of Chapter 3.3 and 126.96.36.199.
The types of packages for radioactive materials covered by ADR, are:
(a) Excepted package (see 188.8.131.52);
(b) Industrial package Type 1 (Type IP-1 package);
(c) Industrial package Type 2 (Type IP-2 package);
(d) Industrial package Type 3 (Type IP-3 package);
(e) Type A package;
(f) Type B(U) package;
(g) Type B(M) package;
(h) Type C package.
Packages containing fissile material or uranium hexafluoride are subject to additional requirements.
2 If the country of origin is not a Contracting Party to ADR, the competent authority of the first Contracting Party
to the ADR reached by the consignment.
The non-fixed contamination on the external surfaces of any package shall be kept as low as
practicable and, under routine conditions of transport, shall not exceed the following limits:
(a) 4 Bq/cm2 for beta and gamma emitters and low toxicity alpha emitters; and
(b) 0.4 Bq/cm2 for all other alpha emitters.
These limits are applicable when averaged over any area of 300 cm2 of any part of the surface.
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.
Except as provided in 7.5.11, CV33, the level of non-fixed contamination on the external and internal
surfaces of overpacks, containers, tanks, IBCs and vehicles shall not exceed the limits specified in
For radioactive material having other dangerous properties the package design shall take into account
those properties. Radioactive material with a subsidiary risk, packaged in packages that do not require
competent authority approval, shall be carried in packagings, IBCs, tanks or bulk containers fully
complying with the requirements of the relevant chapters of Part 6 as appropriate, as well as
applicable requirements of chapters 4.1, 4.2 or 4.3 for that subsidiary risk.
Before a packaging is first used to carry radioactive material, it shall be confirmed that it has been
manufactured in conformity with the design specifications to ensure compliance with the relevant
provisions of ADR and any applicable certificate of approval. The following requirements shall also
be fulfilled, if applicable:
(a) If the design pressure of the containment system exceeds 35 kPa (gauge), it shall be ensured
that the containment system of each packaging conforms to the approved design requirements
relating to the capability of that system to maintain its integrity under that pressure;
(b) For each packaging intended for use as a Type B(U), Type B(M) or Type C package and for
each packaging intended to contain fissile material, it shall be ensured that the effectiveness of
its shielding and containment and, where necessary, the heat transfer characteristics and the
effectiveness of the confinement system, are within the limits applicable to or specified for the
(c) For each packaging intended to contain fissile material, it shall be ensured that the
effectiveness of the criticality safety features is within the limits applicable to or specified for
the design and in particular where, in order to comply with the requirements of 184.108.40.206
neutron poisons are specifically included, checks shall be performed to confirm the presence
and distribution of those neutron poisons.
Before each shipment of any package, it shall be ensured that the package contains neither:
(a) Radionuclides different from those specified for the package design; nor
(b) Contents in a form, or physical or chemical state different from those specified for the package
Before each shipment of any package, it shall be ensured that all the requirements specified in the
relevant provisions of ADR and in the applicable certificates of approval have been fulfilled. The
following requirements shall also be fulfilled, if applicable:
(a) It shall be ensured that lifting attachments which do not meet the requirements of 220.127.116.11 have
been removed or otherwise rendered incapable of being used for lifting the package, in
accordance with 18.104.22.168;
(b) Each Type B(U), Type B(M) and Type C package shall be held until equilibrium conditions
have been approached closely enough to demonstrate compliance with the requirements for
temperature and pressure unless an exemption from these requirements has received unilateral
(c) For each Type B(U), Type B(M) and Type C package, it shall be ensured by inspection and/or
appropriate tests that all closures, valves and other openings of the containment system through
which the radioactive contents might escape are properly closed and, where appropriate, sealed
in the manner for which the demonstrations of compliance with the requirements of 22.214.171.124 and
126.96.36.199 were made;
(d) For packages containing fissile material the measurement specified in 188.8.131.52 (b) and the tests
to demonstrate closure of each package as specified in 184.108.40.206 shall be performed.
The consignor shall also have a copy of any instructions with regard to the proper closing of the
package and any preparation for shipment before making any shipment under the terms of the
Except for consignments under exclusive use, the transport index of any package or overpack shall not
exceed 10, nor shall the criticality safety index of any package or overpack exceed 50.
Except for packages or overpacks carried under exclusive use under the conditions specified in 7.5.11,
CV33 (3.5)(a), the maximum radiation level at any point on any external surface of a package or
overpack shall not exceed 2 mSv/h.
The maximum radiation level at any point on any external surface of a package or overpack under
exclusive use shall not exceed 10 mSv/h.
Requirements and controls for carriage of LSA material and SCO