Requirements for Type C packages

Type C packages shall be designed to meet the requirements specified in 6.4.2 and of 6.4.7.2 to
6.4.7.15, except as specified in 6.4.7.14 (a), and of the requirements specified in 6.4.8.2 to 6.4.8.6,
6.4.8.10 to 6.4.8.15, and, in addition, of 6.4.10.2 to 6.4.10.4.

A package shall be capable of meeting the assessment criteria prescribed for tests in 6.4.8.8 (b)
and 6.4.8.12 after burial in an environment defined by a thermal conductivity of 0.33 W.m-1.K-1 and a
temperature of 38 °C in the steady state. Initial conditions for the assessment shall assume that any
thermal insulation of the package remains intact, the package is at the maximum normal operating
pressure and the ambient temperature is 38 °C.

A package shall be so designed that, if it were at the maximum normal operating pressure and
subjected to:
(a) The tests specified in 6.4.15, it would restrict the loss of radioactive contents to not more
than 10-6 A2 per hour; and
(b) The test sequences in 6.4.20.1,
(i) it would retain sufficient shielding to ensure that the radiation level at 1 m from the
surface of the package would not exceed 10 mSv/h with the maximum radioactive
contents which the package is designed to contain; and
(ii) it would restrict the accumulated loss of radioactive contents in a period of 1 week to
not more than 10 A2 for krypton-85 and not more than A2 for all other radionuclides.
Where mixtures of different radionuclides are present, the provisions of 2.2.7.2.2.4 to 2.2.7.2.2.6 shall
apply except that for krypton-85 an effective A2(i) value equal to 10 A2 may be used. For case (a)
above, the assessment shall take into account the external contamination limits of 4.1.9.1.2.

A package shall be so designed that there will be no rupture of the containment system following
performance of the enhanced water immersion test specified in 6.4.18.

Requirements for packages containing fissile material

Fissile material shall be carried so as to:
(a) Maintain sub-criticality during routine, normal and accident conditions of carriage; in
particular, the following contingencies shall be considered:
(i) water leaking into or out of packages;
(ii) the loss of efficiency of built-in neutron absorbers or moderators;
(iii) rearrangement of the contents either within the package or as a result of loss from the
package;
(iv) reduction of spaces within or between packages;
(v) packages becoming immersed in water or buried in snow; and
(vi) temperature changes; and
(b) Meet the requirements:
(i) of 6.4.7.2 except for unpackaged material when specifically allowed by 2.2.7.2.3.5 (e);
(ii) prescribed elsewhere in ADR which pertain to the radioactive properties of the material;
(iii) of 6.4.7.3 unless the material is excepted by 2.2.7.2.3.5;
(iv) of 6.4.11.4 to 6.4.11.14, unless the material is excepted by 2.2.7.2.3.5, 6.4.11.2 or
6.4.11.3.

 

Packages containing fissile material that meet the provisions of subparagraph (d) and one of the
provisions of (a) to (c) below are excepted from the requirements of 6.4.11.4 to 6.4.11.14.
(a) Packages containing fissile material in any form provided that:
(i) The smallest external dimension of the package is not less than 10 cm;
(ii) The criticality safety index of the package is calculated using the following formula:
 
 
* Plutonium may be of any isotopic composition provided that the amount of Pu-241 is less than
that of Pu-240 in the package
 
where the values of Z are taken from Table 6.4.11.2;
 
(iii)     The CSI of any package does not exceed 10;
 
(b)      Packages containing fissile material in any form provided that:
 
(i)       The smallest external dimension of the package is not less than 30 cm;
 
(ii)      The package, after being subjected to the tests specified in 6.4.15.1 to 6.4.15.6:
 
-     Retains its fissile material contents;
 
-    Preserves the minimum overall outside dimensions of the package to at least 30 cm;
 
-     Prevents the entry of a 10 cm cube;
 
(iii)     The criticality safety index of the package is calculated using the following formula:
 

* Plutonium may be of any isotopic composition provided that the amount of Pu-241 is less than
that of Pu-240 in the package
 
where the values of Z are taken from Table 6.4.11.2;
(iv)     The criticality safety index of any package does not exceed 10;
 
(c)       Packages containing fissile material in any form provided that:
 
(i)       The smallest external dimension of the package is not less than 10 cm;
 
(ii)      The package, after being subjected to the tests specified in 6.4.15.1 to 6.4.15.6:
 
-     Retains its fissile material contents;
 
-    Preserves the minimum overall outside dimensions of the package to at least 10 cm;
 
-     Prevents the entry of a 10 cm cube;,
 
 
(iii) The CSI of the package is calculated using the following formula:
 
 
* Plutonium may be of any isotopic composition provided that the amount of Pu-241 is less than
that of Pu-240 in the package
 
(iv)     The maximum mass of fissile nuclides in any package does not exceed 15 g;
 
(d) The total mass of beryllium, hydrogenous material enriched in deuterium, graphite and other 
allotropic forms of carbon in an individual package shall not be greater than the mass of fissile 
nuclides in the package except where their total concentration does not exceed 1 g in any 1 000 g 
of material. Beryllium incorporated in copper alloys up to 4% in weight of the alloy does not need 
to be considered.
 
Table 6.4.11.2      Values of Z for calculation of criticality safety index in accordance with 
6.4.11.2
 
 

Enrichementa

Z

Uranium enriched up to 1.5%

2200

Uranium enriched up to 5%

850

Uranium enriched up to 10%

660

Uranium enriched up to 20%

580

Uranium enriched up to 100%

450

a If a package contains uranium with varying enrichments of U-235, then the value
corresponding to the highest enrichment shall be used for Z.

 
Packages containing not more than 1 000 g of plutonium are excepted from the application of 
6.4.11.4
to 6.4.11.14 provided that:
 
(a)      Not more than 20% of the plutonium by mass is fissile nuclides;
 
(b)      The criticality safety index of the package is calculated using the following formula:
 
 
(c) If uranium is present with the plutonium, the mass of uranium shall be no more than 1% of the
mass of the plutonium.

 

Where the chemical or physical form, isotopic composition, mass or concentration, moderation ratio
or density, or geometric configuration is not known, the assessments of 6.4.11.8 to 6.4.11.13 shall be
performed assuming that each parameter that is not known has the value which gives the maximum
neutron multiplication consistent with the known conditions and parameters in these assessments.

For irradiated nuclear fuel the assessments of 6.4.11.8 to 6.4.11.13 shall be based on an isotopic
composition demonstrated to provide either:
(a) The maximum neutron multiplication during the irradiation history; or
(b) A conservative estimate of the neutron multiplication for the package assessments. After
irradiation but prior to shipment, a measurement shall be performed to confirm the
conservatism of the isotopic composition.

The package, after being subjected to the tests specified in 6.4.15, shall:
(a) Preserve the minimum overall outside dimensions of the package to at least 10 cm; and
(b) Prevent the entry of a 10 cm cube.

The package shall be designed for an ambient temperature range of -40°C to + 38°C unless the
competent authority specifies otherwise in the certificate of approval for the package design.

 
For a package in isolation, it shall be assumed that water can leak into or out of all void spaces 
of the package, including those within the containment system. However, if the design incorporates 
special features to prevent such leakage of water into or out of certain void spaces, even as a 
result of error, absence of leakage may be assumed in respect of those void spaces. Special 
features shall include either of the following:
 
(a)    Multiple high standard water barriers, not less than two of which would remain watertight if 
    the package were subject to the tests prescribed in 6.4.11.13 (b), a high degree of quality 
control in the manufacture, maintenance and repair of packagings and tests to demonstrate the 
closure of each package before each shipment; or
 
(b) For packages containing uranium hexafluoride only, with  maximum enrichment  of 5 mass  percent 
uranium-235:
 
(i) packages where, following the tests prescribed in 6.4.11.13 (b),  there  is no  physical  
contact between the valve and any other component of the packaging other than at its original point 
of  attachment  and  where,  in  addition,  following  the  test  prescribed  in 6.4.17.3 the 
valves remain leaktight; and
 
(ii) a high degree of quality control in the manufacture, maintenance  and  repair  of  packagings 
coupled with tests to demonstrate closure of each package before each shipment.
 

It shall be assumed that the confinement system is closely reflected by at least 20 cm of water or such
greater reflection as may additionally be provided by the surrounding material of the packaging.
However, when it can be demonstrated that the confinement system remains within the packaging
following the tests prescribed in 6.4.11.13 (b), close reflection of the package by at least 20 cm of
water may be assumed in 6.4.11.10 (c).
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