This tool will assemble a clause tree from the International Atomic Energy Agency SSR-6, rev.2. Regulations for the Safe Transport of Radioactive Material, 2025 [link to full document].
Enter a clause, or a range of clauses from IAEA SSR6, and this will show that clause and all referenced clauses recursively. It gets very complicated very quickly when you’re in the 400’s. It is not recommended to read the output on a mobile phone, but it will still work.
It also does not show a clause that has already been displayed to make sure it doesn’t get into an infinite-requirement-loop (TM).
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Special Form RM [link]
Low-dispersible RM [link]
Clause 416
Radioactive material may be classified as low dispersible radioactive material only if it meets the definition in para. 225 and the requirements of para. 605, taking into account the requirements of paras 665 and 802. Fissile material
↳ Referenced in Clause 416:
Clause 225
Low dispersible radioactive material shall mean either a solid radioactive material or a solid radioactive material in a sealed capsule that has limited dispersibility and is not in powder form. Low specific activity material
Clause 605
Low dispersible radioactive material shall be such that the total amount of this radioactive material in a package shall meet the following requirements:
(a) The dose rate at 3 m from the unshielded radioactive material does not exceed 10 mSv/h.
(b) If subjected to the tests specified in paras 736 and 737, 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.
(c) If subjected to the test specified in para. 703, the activity in the water would not exceed 100 A2 . In the application of this test, the damaging effects of the tests specified in subparagraph (b) shall be taken into account.
↳ Referenced in Clause 605:
Clause 703
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
Clause 736
Enhanced thermal test: The conditions for this test shall be as specified in para. 728, except that the exposure to the thermal environment shall be for a period of 60 min.
↳ Referenced in Clause 736:
Clause 728
Thermal test: The specimen shall be in thermal equilibrium under conditions of an ambient temperature of 38°C, subject to the insolation conditions specified in Table 12 and subject to the design maximum rate of internal heat generation
(a) Exposure of a specimen for a period of 30 min to a thermal environment that provides a heat flux at least equivalent to that of a hydrocarbon fuel-air fire in sufficiently quiescent ambient conditions to give a minimum average flame emissivity coefficient of 0.9 and an average temperature of at least 800°C, fully engulfing the specimen, with a surface absorptivity coefficient of 0.8 or that value that the package may be demonstrated to possess if exposed to the fire specified.
(b) Exposure of the specimen to an ambient temperature of 38°C, subject to the insolation conditions specified in Table 12 and subject to the design maximum rate of internal heat generation within the package by the radioactive contents for a sufficient period to ensure that temperatures in the specimen are decreasing in all parts of the specimen and/or are approaching initial steady state conditions. Alternatively, any of these parameters are allowed to have different values following cessation of heating, provided due account is taken of them in the subsequent assessment of package response. During and following the test, the specimen shall not be artificially cooled and any combustion of materials of the specimen shall be permitted to proceed naturally.
Clause 737
Impact test: The specimen shall be subject to an impact on a target at a velocity of not less than 90 m/s, at such an orientation as to suffer maximum damage. The target shall be as specified in para. 717, except that the target surface may be at any orientation as long as the surface is normal to the specimen path.
↳ Referenced in Clause 737:
Clause 717
The target for the drop tests specified in paras 705, 722, 725(a), 727 and 735 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 damage to the specimen. Test for packagings designed to contain uranium hexafluoride
↳ Referenced in Clause 717:
Clause 705
Impact test: The specimen shall drop onto the target from a height of 9 m. The target shall be as specified in para. 717.
↳ Referenced in Clause 705:
Clause 717 (Details displayed above)
Clause 722
Free drop test: The specimen shall drop onto the target so as to suffer maximum damage in respect of the safety features to be tested:
(a) The height of the drop, measured from the lowest point of the specimen to the upper surface of the target, shall be not less than the distance specified in Table 14 for the applicable mass. The target shall be as specified in para. 717.
(b) For rectangular fibreboard or wood packages not exceeding a mass of 50 kg, a separate specimen shall be subjected to a free drop onto each corner from a height of 0.3 m.
(c) For cylindrical fibreboard packages not exceeding a mass of 100 kg, a separate specimen shall be subjected to a free drop onto each of the quarters of each rim from a height of 0.3 m.
↳ Referenced in Clause 722:
Clause 717 (Details displayed above)
Clause 725
A specimen, or separate specimens, shall be subjected to each of the following tests unless it can be demonstrated that one test is more severe for the specimen in question than the other, in which case one specimen shall be subjected to the more severe test:
(a) Free drop test: The specimen shall drop onto the target so as to suffer the maximum damage in respect of containment. The height of the drop, measured from the lowest part of the specimen to the upper surface of the target, shall be 9 m. The target shall be as specified in para. 717.
(b) Penetration test: The specimen shall be subjected to the test specified in para. 724, except that the height of the drop shall be increased to 1.7 m from the 1 m specified in para. 724(b).
↳ Referenced in Clause 725:
Clause 717 (Details displayed above)
Clause 724
Penetration test: The specimen shall be placed on a rigid, flat, horizontal surface that will not move significantly while the test is being carried out:
(a) A bar, 3.2 cm in diameter with a hemispherical end and a mass of 6 kg, shall be dropped and directed to fall with its longitudinal axis vertical onto the centre of the weakest part of the specimen so that, if it penetrates sufficiently far, it will hit the containment system . The bar shall not be significantly deformed by the test.
(b) The height of the drop of the bar, measured from its lower end to the intended point of impact on the upper surface of the specimen, shall be 1 m. Additional tests for Type A packages designed to contain liquids and gases
Clause 727
Mechanical test: The mechanical test consists of three different drop tests. Each specimen shall be subjected to the applicable drops, as specified in para. 659 or 685. The order in which the specimen is subjected to the drops shall be such that, on completion of the mechanical test, the specimen shall have suffered such damage as will lead to maximum damage in the thermal test that follows:
(a) For drop I, the specimen shall drop onto the target so as to suffer maximum damage, and the height of the drop, measured from the lowest point of the specimen to the upper surface of the target, shall be 9 m. The target shall be as specified in para. 717.
(b) For drop II, the specimen shall drop onto a bar rigidly mounted perpendicularly on the target so as to suffer maximum damage. The height of the drop, measured from the intended point of impact of the specimen to the upper surface of the bar, shall be 1 m. The bar shall be of solid mild steel of circular cross‑section, 15.0 ± 0.5 cm in diameter and 20 cm long, unless a longer bar would cause greater damage, in which case a bar of sufficient length to cause maximum damage shall be used. The upper end of the bar shall be flat and horizontal with its edge rounded off to a radius of not more than 6 mm. The target on which the bar is mounted shall be as specified in para. 717.
(c) For drop III, the specimen shall be subjected to a dynamic crush test by positioning the specimen on the target so as to suffer maximum damage by the drop of a 500 kg mass from 9 m onto the specimen. The mass shall consist of a solid mild steel plate with dimensions of 1 m × 1 m and shall fall in a horizontal attitude. The lower face of the steel plate shall have its edges and corners rounded off to a radius of not more than 6 mm. The height of the drop shall be measured from the underside of the plate to the highest point of the specimen. The target on which the specimen rests shall be as specified in para. 717.
↳ Referenced in Clause 727:
Clause 659
A package shall be so designed that if it were subjected to:
(a) The tests specified in paras 719-724, it would restrict the loss of radioactive contents to not more than 10 [−6] A2 per hour.
(b) The tests specified in paras 726, 727(b), 728 and 729 and either the test in: Para. 727(c), when the package has a mass not greater than 500 kg, an overall density not greater than 1000 kg/m [3] based on the external dimensions, and radioactive contents greater than 1000 A2 not as special form radioactive material ; or Para. 727(a), for all other packages.
(i) It would retain sufficient shielding to ensure that the dose rate 1 m from the surface of the package would not exceed 10 mSv/h with the maximum radioactive contents that the package is designed to contain.
(ii) It would restrict the accumulated loss of radioactive contents in a period of one week to not more than 100 TBq for krypton‑85 and not more than A2 for all other radionuclides. Where mixtures of different radionuclides are present, the provisions of paras 405-407 shall apply, except that for krypton‑85 an effective A2 (i) value equal to 100 TBq may be used. For the case in subparagraph (a), the assessment shall take into account the external non‑fixed contamination limits of para. 508.
↳ Referenced in Clause 659:
Clause 405
For mixtures of radionuclides, the basic radionuclide values referred to in para. 402 may be determined as follows:
↳ Referenced in Clause 405:
Clause 402
The following basic values for individual radionuclides are given in the Appendix:
(a) A1 and A2 in TBq;
(b) Activity concentration limits for exempt material in Bq/g;
(c) Activity limits for exempt consignments in Bq.
Clause 406
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 paras 405 and 430. 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.
↳ Referenced in Clause 406:
Clause 405 (Details displayed above)
Clause 430
For mixtures of radionuclides whose identities and respective activities are known, the following condition shall apply to the radioactive contents of a Type A package : B ��i C ��j �i A 1��i �j A 2 ��j
Clause 407
For individual radionuclides or for mixtures of radionuclides for which relevant data are not available, the values shown in Table 3 shall be used. 25
Clause 508
The non‑fixed contamination on the external surfaces of a package shall be kept as low as practicable and, under routine conditions of transport, shall not exceed the following limits:
(a) 4 Bq/cm [2] for beta and gamma emitters and low toxicity alpha emitters ;
(b) 0.4 Bq/cm [2] for all other alpha emitters. These limits are applicable when averaged over any area of 300 cm [2] of any part of the surface.
Clause 719
The tests are the water spray test, the free drop test, the stacking test and the penetration test. Specimens of the package shall be subjected to the free drop test, the stacking test and the penetration test, preceded in each case by the
Clause 720
The time interval between the conclusion of the water spray test and the succeeding test shall be such that the water has soaked in to the maximum extent, without appreciable drying of the exterior of the specimen. In the absence of any evidence to the contrary, this interval shall be taken to be 2 h if the water spray is applied from four directions simultaneously. No time interval shall elapse, however, if the water spray is applied from each of the four directions consecutively.
Clause 721
Water spray test: The specimen shall be subjected to a water spray test that simulates exposure to rainfall of approximately 5 cm per hour for at least 1 h.
Clause 722 (Details displayed above)
Clause 723
Stacking test: Unless the shape of the packaging effectively prevents stacking, the specimen shall be subjected, for a period of 24 h, to a compressive load equal to the greater of the following:
(a) The equivalent of 5 times the maximum mass of the package ;
(b) The equivalent of 13 kPa multiplied by the vertically projected area of the package . The load shall be applied uniformly to two opposite sides of the specimen, one of which shall be the base on which the package would typically rest.
Clause 724 (Details displayed above)
Clause 726
The specimen shall be subjected to the cumulative effects of the tests specified in paras 727 and 728, in that order. Following these tests, either this specimen or a separate specimen shall be subjected to the effect(s) of the water immersion test(s), as specified in para. 729 and, if applicable, para. 730.
↳ Referenced in Clause 726:
Clause 727 (Details displayed above)
Clause 728 (Details displayed above)
Clause 729
Water immersion test: The specimen shall be immersed under a head of water of at least 15 m for a period of not less than 8 h in the attitude that will lead to maximum damage. For demonstration purposes, an external gauge pressure of at least 150 kPa shall be considered to meet these conditions. Enhanced water immersion test for Type B(U) and Type B(M) packages containing more than 10 [5] A2 and for Type C packages
Clause 730
Enhanced 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 1 h. For demonstration purposes, an external gauge pressure of at least 2 MPa shall be considered to meet these conditions.
Clause 727 (Details displayed above)
Clause 728 (Details displayed above)
Clause 729 (Details displayed above)
Clause 685
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:
(a) Hydrogenous moderation between the packages and the package arrangement reflected on all sides by at least 20 cm of water.
(b) The tests specified in paras 719-724 followed by whichever of the following is the more limiting:
(i) The tests specified in para. 727(b) and in either para. 727(c) for packages having a mass not greater than 500 kg and an overall density not greater than 1000 kg/m [3] based on the external dimensions or para. 727(a) for all other packages, followed by the test specified in para. 728 and completed by the tests specified in paras 731-733; or
(ii) The test specified in para. 729.
(c) Where any part of the fissile material escapes from the containment system following the tests specified in subparagraph (b), it shall be assumed that fissile material escapes from each package in the array and that 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.
↳ Referenced in Clause 685:
Clause 719 (Details displayed above)
Clause 720 (Details displayed above)
Clause 721 (Details displayed above)
Clause 722 (Details displayed above)
Clause 723 (Details displayed above)
Clause 724 (Details displayed above)
Clause 727 (Details displayed above)
Clause 728 (Details displayed above)
Clause 729 (Details displayed above)
Clause 731
Packages for which the water in‑leakage or out‑leakage that results in greatest reactivity has been assumed for purposes of assessment under paras 680-685 shall be excepted from the water leakage test.
↳ Referenced in Clause 731:
Clause 680
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 para. 685(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 a maximum uranium enrichment of 5 mass percentage of uranium‑235:
(i) Packages where, following the tests prescribed in para. 685(b), there is no physical contact between the valve or the plug and any other component of the packaging other than at its original point of attachment and where, in addition, following the test prescribed in para. 728, the valve and the plug remain leaktight;
(ii) A high degree of quality control in the manufacture, maintenance and repair of packagings, coupled with tests to demonstrate the closure of each package before each shipment .
↳ Referenced in Clause 680:
Clause 685 (Details displayed above)
Clause 728 (Details displayed above)
Clause 681
It shall be assumed that neutrons that are emitted from the package are reflected by at least 20 cm of water.
Clause 682
The package shall be subcritical under the conditions of paras 680 and 681 and with the package conditions that result in the maximum neutron multiplication consistent with:
(a) Routine conditions of transport (incident free);
(b) The tests specified in para. 684(b);
(c) The tests specified in para. 685(b).
↳ Referenced in Clause 682:
Clause 680 (Details displayed above)
Clause 681 (Details displayed above)
Clause 684
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:
(a) There shall not be anything between the packages, and the package arrangement shall be reflected on all sides by at least 20 cm of water.
(b) The state of the packages shall be their assessed or demonstrated condition if they had been subjected to the tests specified in paras 719-724. Assessment of package arrays under accident conditions of transport
↳ Referenced in Clause 684:
Clause 719 (Details displayed above)
Clause 720 (Details displayed above)
Clause 721 (Details displayed above)
Clause 722 (Details displayed above)
Clause 723 (Details displayed above)
Clause 724 (Details displayed above)
Clause 685 (Details displayed above)
Clause 683
For packages to be transported by air:
(a) The package shall be subcritical under conditions consistent with the Type C package tests specified in para. 734, assuming that neutrons that are emitted
(b) In the assessment under para. 682, use of special features as specified in para. 680 is allowed provided that leakage of water into or out of the void spaces is prevented when the package is submitted to the Type C package tests specified in para. 734 followed by the water leakage test specified in para. 733. Assessment of package arrays under normal conditions of transport
↳ Referenced in Clause 683:
Clause 680 (Details displayed above)
Clause 682 (Details displayed above)
Clause 733
The specimen shall be immersed under a head of water of at least 0.9 m for a period of not less than 8 h and in the attitude for which maximum leakage is expected. Tests for Type C packages
Clause 734
Specimens shall be subjected to the effects of the following test sequences:
(a) The tests specified in paras 727(a), 727(c), 735 and 736, in this order;
(b) The test specified in para. 737. Separate specimens are allowed to be used for the sequence in subparagraph (a) and for subparagraph (b).
↳ Referenced in Clause 734:
Clause 727 (Details displayed above)
Clause 735
Puncture-tearing test: The specimen shall be subjected to the damaging effects of a vertical solid probe made of mild steel. The orientation of the package specimen and the impact point on the package surface shall be such as to cause maximum damage at the conclusion of the test sequence specified in para. 734(a):
(a) The specimen, representing a package having a mass of less than 250 kg, shall be placed on a target and subjected to a probe having a mass of 250 kg falling from a height of 3 m above the intended impact point. For this test the probe shall be a 20 cm diameter cylindrical bar with the striking end forming the frustum of a right circular cone with the following dimensions: 30 cm height and 2.5 cm diameter at the top with its edge rounded off to a radius of not more than 6 mm. The target on which the specimen is placed shall be as specified in para. 717.
(b) For packages having a mass of 250 kg or more, the base of the probe shall be placed on a target and the specimen dropped onto the probe. The height of the drop, measured from the point of impact with the specimen to the upper surface of the probe, shall be 3 m. The probe for this test shall have
↳ Referenced in Clause 735:
Clause 717 (Details displayed above)
Clause 734 (Details displayed above)
Clause 736 (Details displayed above)
Clause 737 (Details displayed above)
Clause 684 (Details displayed above)
Clause 685 (Details displayed above)
Clause 732
Before the specimen is subjected to the water leakage test specified in para. 733, it shall be subjected to the tests specified in para. 727(b) and in either para. 727(a) or (c), as required by para. 685, and the test specified in para. 728.
↳ Referenced in Clause 732:
Clause 685 (Details displayed above)
Clause 727 (Details displayed above)
Clause 728 (Details displayed above)
Clause 733 (Details displayed above)
Clause 733 (Details displayed above)
Clause 717 (Details displayed above)
Clause 735 (Details displayed above)
Clause 665
A package containing low dispersible radioactive material shall be so designed that any features added to the low dispersible radioactive material that are not part of it, or any internal components of the packaging, shall not adversely affect the performance of the low dispersible radioactive material .
Clause 802
Competent authority approval shall be required for the following:
(a) Designs for:
(i) Special form radioactive material (see paras 803, 804 and 823);
(ii) Low dispersible radioactive material (see paras 803 and 804);
(iii) Fissile material excepted under para. 417(f) (see paras 805 and 806);
(iv) Packages containing 0.1 kg or more of uranium hexafluoride (see para. 807);
(v) Packages containing fissile material, unless excepted by para. 417, 674 or 675 (see paras 814-816 and 820);
(vi) Type B(U) packages and Type B(M) packages (see paras 808-813 and 820);
(vii) Type C packages (see paras 808-810 and 820).
(b) Special arrangements (see paras 829-831).
(c) Certain shipments (see paras 825-828).
(d) Radiation protection programme for special use vessels (see para. 576(a)).
(e) Calculation of radionuclide values that are not listed in the Appendix (see para. 403(a)).
(f) Calculation of alternative activity limits for an exempt consignment of instruments or articles (see para. 403(b)). The certificates of approval for the package design and the shipment may be combined into a single certificate. 103
↳ Referenced in Clause 802:
Clause 403
For individual radionuclides:
(a) That are not listed in the Appendix, the determination of the basic radionuclide values referred to in para. 402 shall require multilateral approval . For these radionuclides, activity concentrations for exempt material and activity limits for exempt consignments shall be calculated in accordance with the principles established in GSR Part 3 [2]. 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 transport are taken into consideration. Alternatively, the radionuclide values in Table 3 may be used without obtaining competent authority approval .
(b) In instruments or articles in which the radioactive material is enclosed in or is included as a component part of the instrument or other manufactured article and which meets para. 423(c), alternative basic radionuclide values to those in the Appendix 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 [2].
↳ Referenced in Clause 403:
Clause 402 (Details displayed above)
Clause 423
Radioactive material that is enclosed in or is included as a component part of an instrument or other manufactured article may be classified under UN 2911, RADIOACTIVE MATERIAL, EXCEPTED PACKAGE – INSTRUMENTS or ARTICLES, provided that:
(a) The dose rate at 10 cm from any point on the external surface of any unpackaged instrument or article is not greater than 0.1 mSv/h. 31
(b) Each instrument or article bears the mark "RADIOACTIVE" on its external surface except for the following:
(i) Radioluminescent timepieces or devices do not require marks.
(ii) Consumer products that either have received regulatory authorization in accordance with para. 107(e) or do not individually exceed the activity limit for an exempt consignment specified in column 5 of the Appendix do not require marks, provided that such products are transported in a package that bears the mark "RADIOACTIVE" on its internal surface in such a manner that a warning of the presence of radioactive material is visible on opening the package .
(iii) Other instruments or articles too small to bear the mark "RADIOACTIVE" do not require marks, provided that they are transported in a package that bears the mark "RADIOACTIVE" on its internal surface in such a manner that a warning of the presence of radioactive material is visible on opening the package .
(c) The active material is completely enclosed by non‑active components. (A device performing the sole function of containing radioactive material shall not be considered to be an instrument or manufactured article.)
(d) The limits specified in columns 2 and 3 of Table 4 are met for each individual item and each package, respectively.
(e) For transport by post, the total activity in each excepted package shall not exceed one tenth of the relevant limits specified in column 3 of Table 4.
(f) If the package contains fissile material, one of the provisions of subparagraphs (a)-(h) of para. 417 shall apply.
↳ Referenced in Clause 423:
Clause 107
These Regulations 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 that 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 treatment.
(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 contamination .
(e) Radioactive material in consumer products that have received regulatory authorization, following their sale to the end user.
(f) Naturally occurring radioactive material, provided the activity concentration of the material does not exceed 10 times the values specified in the Appendix, or as calculated in accordance with paras 405 and 406. For naturally occurring radioactive material where the radionuclides are not in secular equilibrium, the calculation of the activity concentration shall be performed in accordance with para. 405.
(g) Non‑radioactive solid objects with radioactive substances present on any surface in quantities not in excess of the levels defined in para. 214.
↳ Referenced in Clause 107:
Clause 214
Contamination shall mean the presence of a radioactive substance on a surface in quantities in excess of 0.4 Bq/cm [2] for beta and gamma emitters and low toxicity alpha emitters, or 0.04 Bq/cm [2] for all other alpha emitters.
Clause 405 (Details displayed above)
Clause 406 (Details displayed above)
Clause 417
Fissile material and packages containing fissile material shall be classified under the relevant entry as "FISSILE" in accordance with Table 1 unless excepted by one of the provisions of subparagraphs (a)-(h) of this paragraph and transported subject to the requirements of para. 570. All provisions apply only to material in packages that meet the requirements of para. 636, unless unpackaged material is specifically allowed in the provision. The provisions for the exceptions are as follows:
(a) Uranium enriched in uranium‑235 to a maximum of 1% by mass, and with a total plutonium and uranium‑233 content not exceeding 1% of the mass of uranium‑235, provided that the fissile nuclides are distributed essentially homogeneously throughout the material. In addition, if uranium‑235 is present in metallic, oxide or carbide forms, it shall not form a lattice arrangement.
(b) Liquid solutions of uranyl nitrate enriched in uranium‑235 to a maximum of 2% by mass, with a total plutonium and uranium‑233 content not exceeding 0.002% of the mass of uranium, and with a minimum nitrogen to uranium atomic ratio (N/U) of 2.
(c) Uranium with a maximum uranium enrichment of 5% by mass of uranium‑235 provided that:
(i) There is no more than 3.5 g of uranium‑235 per package .
(ii) The total plutonium and uranium‑233 content does not exceed 1% of the mass of uranium‑235 per package .
(iii) Transport of the package is subject to the consignment limit provided in para. 570(c). 29
(d) Fissile nuclides with a total mass not greater than 2.0 g per package, provided that the package is transported subject to the consignment limit provided in para. 570(d).
(e) Fissile nuclides with a total mass not greater than 45 g, either packaged or unpackaged, subject to the requirements of para. 570(e).
(f) A fissile material that meets the requirements of paras 570(b), 606 and 802.
(g) Enriched uranium in the form of residual contamination on inner surfaces of clean and washed out cylinders that conform to the International Organization for Standardization document: Nuclear Energy – Packagings for the Transport of Uranium Hexafluoride (UF6) (ISO 7195) [17] and that have contained enriched uranium hexafluoride, provided that the average amount of uranium‑235 on the inner surfaces does not exceed 2.5 g/m², with a total mass of fissile nuclides not exceeding 15 g per package .
(h) Fissile nuclides with a total mass not greater than 15 g per package, provided that:
(i) The mass of fissile nuclides does not exceed 0.5% of the mass of solid material of the package (including packaging material).
(ii) The package is transported subject to the requirements of para. 570(f).
(iii) Lead, beryllium, hydrogenous material enriched in deuterium, graphite and other allotropic forms of carbon that may be present in the package shall not be included in determining the required mass of solid material.
↳ Referenced in Clause 417:
Clause 570
Fissile material meeting one of the provisions of subparagraphs (a)-(h) of para. 417 shall meet the following requirements:
(a) Only one of the provisions of subparagraphs (a)-(h) of para. 417 is allowed per consignment .
(b) Only one approved fissile material in packages classified in accordance with para. 417(f) is allowed per consignment unless multiple materials are authorized in the certificate of approval .
(c) Fissile material in packages classified in accordance with para. 417(c) shall be transported in a consignment with no more than 45 g of fissile nuclides .
(d) Fissile material in packages classified in accordance with para. 417(d) shall be transported in a consignment with no more than 15 g of fissile nuclides .
(e) Unpackaged or packaged fissile material classified in accordance with para. 417(e) shall be transported on a conveyance or in a large freight container under exclusive use with no more than 45 g of fissile nuclides on the conveyance .
(f) Fissile material in packages classified in accordance with para. 417(h) shall be transported in a consignment with no more than 45 g of fissile nuclides . Additional requirements relating to transport by rail and by road
↳ Referenced in Clause 570:
Clause 417 (Details displayed above)
Clause 606
Fissile material excepted from classification as "FISSILE" under para. 417(f) shall be subcritical without the need for accumulation control under the following conditions:
(a) The conditions of para. 673(a);
(b) The conditions consistent with the assessment provisions stated in paras 684(b) and 685(b) for packages ;
(c) The conditions specified in para. 683(a), if to be transported by air.
↳ Referenced in Clause 606:
Clause 417 (Details displayed above)
Clause 673
Fissile material shall be transported so as to:
(a) Maintain subcriticality during routine, normal and accident conditions of transport. In particular, the following contingencies shall be considered:
(i) Leakage of water into or out of packages ;
(ii) 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;
(vi) Temperature changes.
(b) Meet the requirements:
(i) Of para. 636, except for unpackaged material when specifically allowed by para. 417(e);
(ii) Prescribed elsewhere in these Regulations that pertain to the radioactive properties of the material;
(iii) Of para. 637, unless the material is excepted by para. 417;
(iv) Of paras 676-686, unless the material is excepted by para. 417, 674 or 675.
↳ Referenced in Clause 673:
Clause 417 (Details displayed above)
Clause 636
The smallest overall external dimension of the package shall not be less than 10 cm.
Clause 637
The outside of the package shall incorporate a feature such as a seal that is not readily breakable and that, while intact, will be evidence that the package has not been opened.
Clause 674
Packages containing fissile material that meets the requirements of subparagraph (d) and one of the provisions of subparagraphs (a)-(c) of this paragraph are excepted from the requirements of paras 676-686:
(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 CSI of the package is calculated using the following formula: CSI = 50 × 5 × {[mass of uranium‑235 in package (g)]/Z + [mass of other fissile nuclides [1 ] in package (g)]/280} where the values of Z are taken from Table 13.
(iii) The CSI of the 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 paras 719-724: 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 CSI of the package is calculated using the following formula: CSI = 50 × 2 × {[mass of uranium‑235 in package (g)]/Z + [mass of other fissile nuclides [1] in package (g)]/280} where the values of Z are taken from Table 13.
(iv) The CSI of the package does not exceed 10. 1 Plutonium may be of any isotopic composition provided that the amount of plutonium‑241 is less than that of plutonium‑240 in the package .
(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 paras 719-724: 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: CSI = 50 × 2 × {[mass of uranium‑235 in package (g)]/450 + [mass of other fissile nuclides [1] in package (g)]/280}
(iv) The total mass of fissile nuclides in the 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 the total concentration of these materials does not exceed 1 g in any 1000 g of material. Beryllium incorporated in copper alloys up to 4% by mass of the alloy does not need to be considered.
↳ Referenced in Clause 674:
Clause 676
Where the chemical or physical form, isotopic composition, mass or concentration, moderation ratio or density, or geometric configuration is not known, the assessments of paras 680-685 shall be performed assuming that each parameter that is not known has the value that gives the maximum neutron multiplication consistent with the known conditions and parameters in these assessments.
↳ Referenced in Clause 676:
Clause 680 (Details displayed above)
Clause 681 (Details displayed above)
Clause 682 (Details displayed above)
Clause 683 (Details displayed above)
Clause 684 (Details displayed above)
Clause 685 (Details displayed above)
Clause 677
For irradiated nuclear fuel, the assessments in paras 680-685 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. Geometry and temperature requirements
↳ Referenced in Clause 677:
Clause 680 (Details displayed above)
Clause 681 (Details displayed above)
Clause 682 (Details displayed above)
Clause 683 (Details displayed above)
Clause 684 (Details displayed above)
Clause 685 (Details displayed above)
Clause 678
The package, after being subjected to the tests specified in paras 719-724, shall:
(a) Preserve the minimum overall outside dimensions of the package to at least 10 cm;
(b) Prevent the entry of a 10 cm cube.
↳ Referenced in Clause 678:
Clause 719 (Details displayed above)
Clause 720 (Details displayed above)
Clause 721 (Details displayed above)
Clause 722 (Details displayed above)
Clause 723 (Details displayed above)
Clause 724 (Details displayed above)
Clause 679
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 .
Clause 680 (Details displayed above)
Clause 681 (Details displayed above)
Clause 682 (Details displayed above)
Clause 683 (Details displayed above)
Clause 684 (Details displayed above)
Clause 685 (Details displayed above)
Clause 686
The 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 paras 684 and 685 (i.e. CSI = 50/N). The value of the CSI shall not be rounded down except that a value of 0.05 or less for a package may be considered as zero.
↳ Referenced in Clause 686:
Clause 684 (Details displayed above)
Clause 685 (Details displayed above)
Clause 719 (Details displayed above)
Clause 720 (Details displayed above)
Clause 721 (Details displayed above)
Clause 722 (Details displayed above)
Clause 723 (Details displayed above)
Clause 724 (Details displayed above)
Clause 675
Packages containing not more than 1000 g of plutonium are excepted from the application of paras 676-686 provided that:
(a) Not more than 20% of the plutonium by mass is fissile nuclides .
(b) The CSI of the package is calculated using the following formula: CSI = 50 × 2 × [mass of plutonium (g)/1000]
(c) If uranium is present with the plutonium, the mass of uranium shall be no more than 1% of the mass of the plutonium. Contents specification for assessments of package designs containing fissile material
↳ Referenced in Clause 675:
Clause 676 (Details displayed above)
Clause 677 (Details displayed above)
Clause 678 (Details displayed above)
Clause 679 (Details displayed above)
Clause 680 (Details displayed above)
Clause 681 (Details displayed above)
Clause 682 (Details displayed above)
Clause 683 (Details displayed above)
Clause 684 (Details displayed above)
Clause 685 (Details displayed above)
Clause 686 (Details displayed above)
Clause 676 (Details displayed above)
Clause 677 (Details displayed above)
Clause 678 (Details displayed above)
Clause 679 (Details displayed above)
Clause 680 (Details displayed above)
Clause 681 (Details displayed above)
Clause 682 (Details displayed above)
Clause 683 (Details displayed above)
Clause 684 (Details displayed above)
Clause 685 (Details displayed above)
Clause 686 (Details displayed above)
Clause 683 (Details displayed above)
Clause 684 (Details displayed above)
Clause 685 (Details displayed above)
Clause 636 (Details displayed above)
Clause 802 (Details displayed above)
Clause 417 (Details displayed above)
Clause 576
The transport of consignments by means of a special use vessel that, by virtue of its design, or by reason of its being chartered, is dedicated to the purpose of carrying radioactive material, shall be excepted from the requirements specified in para. 566 provided that the following conditions are met:
(a) A radiation protection programme for the shipment shall be approved by the competent authority of the flag State of the vessel and, when requested, by the competent authority at each port of call.
(b) Stowage arrangements shall be predetermined for the whole voyage, including any consignments to be loaded at ports of call en route.
(c) The loading, carriage and unloading of the consignments shall be supervised by persons qualified in the transport of radioactive material . Additional requirements relating to transport by air
↳ Referenced in Clause 576:
Clause 566
Loading of packages and overpacks in freight containers and accumulation of packages, overpacks and freight containers aboard conveyances shall be controlled as follows:
(a) Except under the condition of exclusive use, and for consignments of LSA‑I material, the total number of packages and overpacks in a freight container and of packages, overpacks and freight containers aboard a single conveyance shall be limited so that the sum of the TIs in the freight container and aboard the conveyance, respectively, does not exceed the values shown in Table 10.
(b) The dose rate under routine conditions of transport shall not exceed 2 mSv/h at any point on the external surface of the vehicle or freight container, and 0.1 mSv/h at 2 m from the external surface of the vehicle or freight container, except for vehicles or large freight containers under exclusive use by road or rail for which the dose rate limits around the vehicle are specified in paras 573(b) and (c).
(c) The sum of the CSIs in a freight container and aboard a conveyance shall not exceed the values shown in Table 11.
(i) Hold, compartment or defined deck area : Packages [d,e], overpacks [f], small freight containers 50 Large freight containers 200
(ii) Total vessel : Packages [d,e], overpacks [f], small freight containers 200 Large freight containers No limit a For packages contained in an overpack, the TI of the overpack shall be used to evaluate the sum of the TIs. b For packages contained in an overpack, the TI of the overpack shall be used to evaluate the sum of the TIs . For packages or overpacks loaded in a freight container, the TI of the freight container shall be used to evaluate the sum of the TIs . c Packages or overpacks carried in or on a vehicle that are in accordance with the provisions of para. 573 may be transported by vessels provided that they are not removed from the vehicle at any time while on board the vessel . d For freight containers used as packaging and packages loaded in a freight container, the TI limit for either small freight containers or large freight containers, as appropriate, shall apply. e For packages contained in an overpack, the TI limit for overpacks shall apply. f For overpacks contained in a freight container, the TI limit for small freight containers or large freight containers, as appropriate, shall apply.
(i) Hold, compartment or defined deck area 50 100
(ii) Total vessel : Packages, overpacks, small freight containers 200 [b] 200 [c] Large freight containers No limit [b] No limit [c] a Requires shipment approval in accordance with para. 825(c), as applicable. b The consignments shall be so handled and stowed that the sum of CSIs in any group does not exceed 50 and that each group is handled and stowed so as to maintain a spacing of at least 6 m from other groups. c The consignments shall be so handled and stowed that the sum of CSIs in any group does not exceed 100 and that each group is handled and stowed so as to maintain a spacing of at least 6 m from other groups or other conveyances carrying radioactive material . The intervening space between groups may be occupied by other cargo in accordance with para. 506.
↳ Referenced in Clause 566:
Clause 506
Consignments shall be segregated from other dangerous goods during transport in compliance with the relevant transport regulations for dangerous
Clause 573
For vehicles or large freight containers under exclusive use, the dose rate shall not exceed:
(a) 10 mSv/h at any point on the external surface of a package, a freight container used as packaging or an overpack, and may only exceed 2 mSv/h provided that:
(i) The vehicle is equipped with an enclosure that, during routine conditions of transport, prevents the access of unauthorized persons to the interior of the enclosure.
(ii) Provisions are made to secure the package, the freight container used as packaging or the overpack so that its position within the vehicle enclosure remains fixed during routine conditions of transport.
(iii) There is no loading or unloading during the shipment .
(b) 2 mSv/h at any point on the outer surfaces of the vehicle, including the upper and lower surfaces, or, in the case of an open vehicle, at any point on the vertical planes projected from the outer edges of the vehicle, on the upper surface of the load and on the lower external surface of the vehicle .
(c) 0.1 mSv/h at any point 2 m from the vertical planes represented by the outer lateral surfaces of the vehicle, or, if the load is transported in an open vehicle, at any point 2 m from the vertical planes projected from the outer edges of the vehicle .
Clause 825
Multilateral approval shall be required for:
(a) The shipment of Type B(M) packages not conforming with the requirements of para. 639 or designed to allow controlled intermittent venting.
(b) The shipment of Type B(M) packages containing radioactive material with an activity greater than 3000 A1 or 3000 A2, as appropriate, or 1000 TBq, whichever is the lower.
(c) The shipment of packages containing fissile material if the sum of the CSIs of the packages in a single freight container or in a single conveyance exceeds 50. Excluded from this requirement shall be shipments by sea‑going vessels if the sum of the CSIs does not exceed 50 for any hold, compartment 112
(d) Radiation protection programme s for shipments by special use vessel s in accordance with para. 576(a).
(e) The shipment of SCO‑III .
↳ Referenced in Clause 825:
Clause 576 (Details displayed above)
Clause 639
The design of the package shall take into account temperatures ranging from −40°C to +70°C for the components of the packaging . Attention shall be given to freezing temperatures for liquids and to the potential degradation of packaging materials within the given temperature range.
Clause 674 (Details displayed above)
Clause 675 (Details displayed above)
Clause 803
The design for special form radioactive material shall require unilateral approval . The design for low dispersible radioactive material shall require multilateral approval . In both cases, an application for approval shall include:
(a) A detailed description of the radioactive material or, if a capsule, the contents. Particular reference shall be made to both physical and chemical states.
(b) A detailed statement of the design of any capsule to be used.
(c) A statement of the tests that have been performed 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 these Regulations.
(d) A specification of the applicable management system, as required in para. 306.
(e) Any pre‑shipment actions for use in the consignment of special form radioactive material or low dispersible radioactive material .
↳ Referenced in Clause 803:
Clause 306
A management system based on international, national or other standards acceptable to the competent authority shall be established and implemented for all activities within the scope of these Regulations, as identified in para. 106, to ensure compliance with the relevant provisions of these Regulations. Certification that the design specification has been fully implemented shall be available to the competent authority . The manufacturer, consignor or user shall be prepared:
(a) To provide facilities for inspection during manufacture and use;
(b) To demonstrate compliance with these Regulations to the competent authority. Where competent authority approval is required, such approval shall take into account, and be contingent upon, the adequacy of the management system .
↳ Referenced in Clause 306:
Clause 106
These Regulations apply to the transport of radioactive material by all modes on land, water, or in the air, including transport that is incidental to the use of the radioactive material . Transport 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 in‑transit storage,
(a) Routine conditions of transport (incident free);
(b) Normal conditions of transport (minor mishaps);
(c) Accident conditions of transport.
Clause 804
The competent authority shall establish a certificate of approval stating that the approved design meets the requirements for special form radioactive material or low dispersible radioactive material and shall attribute to that design an identification mark.
Clause 805
The design for fissile material excepted from "FISSILE" classification in accordance with Table 1, under para. 417(f) shall require multilateral approval . An application for approval shall include:
(a) A detailed description of the material. Particular reference shall be made to both the physical and chemical states.
(b) A statement of the tests that have been performed and their results, or evidence based on calculations, to show that the material is capable of meeting the requirements specified in para. 606. 104
(c) A specification of the applicable management system, as required in para. 306.
(d) A statement of specific actions to be taken prior to shipment .
↳ Referenced in Clause 805:
Clause 306 (Details displayed above)
Clause 417 (Details displayed above)
Clause 606 (Details displayed above)
Clause 806
The competent authority shall establish a certificate of approval stating that the approved material meets the requirements for fissile material excepted by the competent authority in accordance with para. 606 and shall attribute to that design an identification mark.
↳ Referenced in Clause 806:
Clause 606 (Details displayed above)
Clause 807
The approval of designs for packages containing 0.1 kg or more of uranium hexafluoride requires that:
(a) Each design that meets the requirements of para. 634 shall require multilateral approval .
(b) Each design that meets the requirements of paras 631-633 shall require unilateral approval by the competent authority of the country of origin of the design, unless multilateral approval is otherwise required by these Regulations.
(c) The application for approval shall include all information necessary to satisfy the competent authority that the design meets the requirements of para. 631 and a specification of the applicable management system, as required in para. 306.
(d) The competent authority shall establish a certificate of approval stating that the approved design meets the requirements of para. 631 and shall attribute to that design an identification mark. Approval of Type B(U) and Type C package designs
↳ Referenced in Clause 807:
Clause 306 (Details displayed above)
Clause 631
Packages designed to contain uranium hexafluoride shall meet the requirements that pertain to the radioactive and fissile properties of the material prescribed elsewhere in these Regulations. Except as allowed in para. 634, uranium hexafluoride in quantities of 0.1 kg or more shall also be packaged and transported in accordance with the provisions of ISO 7195 [17], and the requirements of paras 632 and 633.
↳ Referenced in Clause 631:
Clause 632
Each package designed to contain 0.1 kg or more of uranium hexafluoride shall be so designed that the package will meet the following requirements:
(a) Withstand, without leakage and without unacceptable stress, as specified in ISO 7195 [17], the structural test as specified in para. 718, except as allowed in para. 634;
(b) Withstand, without loss or dispersal of the uranium hexafluoride, the free drop test specified in para. 722;
(c) Withstand, without rupture of the containment system, the thermal test specified in para. 728, except as allowed in para. 634.
↳ Referenced in Clause 632:
Clause 634
Subject to multilateral approval, packages designed to contain 0.1 kg or more of uranium hexafluoride may be transported if the packages are designed:
(a) To international or national standards other than ISO 7195 [17], provided an equivalent level of safety is maintained; and/or
(b) To withstand, without leakage and without unacceptable stress, a test pressure of less than 2.76 MPa as specified in para. 718; and/or
(c) To contain 9000 kg or more of uranium hexafluoride and the packages do not meet the requirement of para. 632(c). In all other respects, the requirements specified in paras 631-633 shall be satisfied.
↳ Referenced in Clause 634:
Clause 631 (Details displayed above)
Clause 632 (Details displayed above)
Clause 633
Packages designed to contain 0.1 kg or more of uranium hexafluoride shall not be provided with pressure relief devices.
Clause 718
Specimens that comprise or simulate packagings designed to contain 0.1 kg or more of uranium hexafluoride shall be tested hydraulically at an internal pressure of at least 1.38 MPa, but when the test pressure is less than 2.76 MPa, the design shall require multilateral approval . For retesting packagings, any other equivalent non‑destructive testing may be applied, subject to multilateral approval . Tests for demonstrating the ability to withstand normal conditions of transport
Clause 718 (Details displayed above)
Clause 722 (Details displayed above)
Clause 728 (Details displayed above)
Clause 633 (Details displayed above)
Clause 634 (Details displayed above)
Clause 632 (Details displayed above)
Clause 633 (Details displayed above)
Clause 634 (Details displayed above)
Clause 808
Each Type B(U) and Type C package design shall require unilateral approval, except that:
(a) A package design for fissile material, which is also subject to paras 814-816, shall require multilateral approval .
(b) A Type B(U) package design for low dispersible radioactive material shall require multilateral approval . 105
↳ Referenced in Clause 808:
Clause 814
Each package design for fissile material that is not excepted by para. 417, 674 or 675 shall require multilateral approval .
↳ Referenced in Clause 814:
Clause 417 (Details displayed above)
Clause 674 (Details displayed above)
Clause 675 (Details displayed above)
Clause 815
An application for approval shall include all information necessary to satisfy the competent authority that the design meets the requirements of para. 673 and a specification of the applicable management system, as required in para. 306.
↳ Referenced in Clause 815:
Clause 306 (Details displayed above)
Clause 673 (Details displayed above)
Clause 816
The competent authority shall establish a certificate of approval stating that the approved design meets the requirements of para. 673 and shall attribute to that design an identification mark.
↳ Referenced in Clause 816:
Clause 673 (Details displayed above)
Clause 809
An application for approval shall include:
(a) A detailed description of the radioactive contents with reference to their physical and chemical states and the nature of the radiation emitted.
(b) A detailed statement of the design, including complete engineering drawings and schedules of materials and methods of manufacture.
(c) A statement of the tests that have been performed and their results, or evidence based on calculations or other evidence that the design is adequate to meet the applicable requirements.
(d) The operating and maintenance instructions for the use of the packaging .
(e) 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 performed.
(f) A justification of considerations to ageing mechanisms in the safety analysis and within the operating and maintenance instructions.
(g) Where the radioactive contents are irradiated nuclear fuel, the applicant shall state and justify any assumption in the safety analysis relating to the characteristics of the fuel and describe any pre‑shipment measurement required by para. 677(b).
(h) Any special stowage provisions necessary to ensure the safe dissipation of heat from the package considering the various modes of transport to be used and the type of conveyance or freight container .
(i) A reproducible illustration, not larger than 21 cm × 30 cm, showing the make‑up of the package .
(j) A specification of the applicable management system, as required in para. 306.
(k) For packages that 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.
↳ Referenced in Clause 809:
Clause 306 (Details displayed above)
Clause 677 (Details displayed above)
Clause 810
The competent authority shall establish a certificate of approval stating that the approved design meets the requirements for Type B(U) or Type C packages and shall attribute to that design an identification mark. Approval of Type B(M) package designs
Clause 811
Each Type B(M) package design, including those for fissile material, which are also subject to paras 814-816, and those for low dispersible radioactive material, shall require multilateral approval. 106
↳ Referenced in Clause 811:
Clause 814 (Details displayed above)
Clause 815 (Details displayed above)
Clause 816 (Details displayed above)
Clause 812
An application for approval of a Type B(M) package design shall include the information required in para. 809 for Type B(U) packages and in addition, when the provisions of para. 667(a) apply, the following:
(a) A list of the requirements specified in paras 639, 653-655, 657 and 660-666 with which the package does not conform;
(b) Any proposed supplementary operational controls to be applied during transport that are not provided for in these Regulations but that are necessary to ensure the safety of the package or to compensate for the deficiencies listed in subparagraph (a);
(c) A statement relative to any restrictions on the mode of transport and to any special loading, carriage, unloading or handling procedures;
(d) A statement of the range of ambient conditions (e.g. temperature, insolation) that are expected to be encountered during transport and that have been taken into account in the design .
↳ Referenced in Clause 812:
Clause 639 (Details displayed above)
Clause 653
A package shall be so designed that, under an ambient temperature of 38°C and the insolation conditions specified in Table 12 applied prior to the tests, heat generated within the package by the radioactive contents shall not, under normal conditions of transport, as demonstrated by the tests specified in paras 719-724, adversely affect the package in such a way that it would fail to meet the applicable requirements for containment and shielding if left unattended for a period of one week. Particular attention shall be paid to the effects of heat that may cause one or more of the following:
(a) Alteration of the arrangement, the geometrical form or the physical state of the radioactive contents or, if the radioactive material is enclosed in a can or receptacle (e.g. clad fuel elements), cause the can, receptacle or radioactive material to deform or melt;
(b) Lessening of the efficiency of the packaging through differential thermal expansion, or cracking or melting of the radiation shielding material;
(c) Acceleration of corrosion when combined with moisture.
↳ Referenced in Clause 653:
Clause 719 (Details displayed above)
Clause 720 (Details displayed above)
Clause 721 (Details displayed above)
Clause 722 (Details displayed above)
Clause 723 (Details displayed above)
Clause 724 (Details displayed above)
Clause 654
A package shall be so designed that, under an ambient temperature of 38°C and in the absence of insolation, the temperature of the accessible surfaces of a package shall not exceed 50°C, unless the package is transported under exclusive use .
Clause 655
Except as required in para. 619 for a package to be transported by air, the maximum temperature of any surface readily accessible during transport of a package under exclusive use shall not exceed 85°C in the absence of insolation
↳ Referenced in Clause 655:
Clause 619
For packages to be transported by air, the temperature of the accessible surfaces shall not exceed 50°C at an ambient temperature of 38°C with no account taken for insolation.
Clause 660
A package for radioactive contents with activity greater than 10 [5] A2 shall be so designed that if it were subjected to the enhanced water immersion test specified in para. 730, there would be no rupture of the containment system .
↳ Referenced in Clause 660:
Clause 730 (Details displayed above)
Clause 661
Compliance with the permitted activity release limits shall depend neither upon filters nor upon a mechanical cooling system.
Clause 662
A package shall not include a pressure relief system from the containment system that would allow the release of radioactive material to the environment under the conditions of the tests specified in paras 719-724 and 726-729.
↳ Referenced in Clause 662:
Clause 719 (Details displayed above)
Clause 720 (Details displayed above)
Clause 721 (Details displayed above)
Clause 722 (Details displayed above)
Clause 723 (Details displayed above)
Clause 724 (Details displayed above)
Clause 726 (Details displayed above)
Clause 727 (Details displayed above)
Clause 728 (Details displayed above)
Clause 729 (Details displayed above)
Clause 663
A package shall be so designed that if it were at the maximum normal operating pressure and it were subjected to the tests specified in paras 719-724 and 726-729, the levels of strain in the containment system would not attain values that would adversely affect the package in such a way that it would fail to meet the applicable requirements.
↳ Referenced in Clause 663:
Clause 719 (Details displayed above)
Clause 720 (Details displayed above)
Clause 721 (Details displayed above)
Clause 722 (Details displayed above)
Clause 723 (Details displayed above)
Clause 724 (Details displayed above)
Clause 726 (Details displayed above)
Clause 727 (Details displayed above)
Clause 728 (Details displayed above)
Clause 729 (Details displayed above)
Clause 664
A package shall not have a maximum normal operating pressure in excess of a gauge pressure of 700 kPa.
Clause 665 (Details displayed above)
Clause 666
A package shall be designed for an ambient temperature range of −40°C to +38°C.
Clause 667
Type B(M) packages shall meet the requirements for Type B(U) packages specified in para. 652, except that:
(a) For a package to be transported solely within a specified country or solely between specified countries, ambient temperatures and insolation conditions other than those given in paras 653-655 and 657 and conditions other than those given in paras 639 and 660-666 may be assumed with the approval of the competent authorities of these countries. The requirements for Type B(U) packages specified in paras 655 and 660-666 shall be met as far as practicable.
(b) For a package containing only solid radioactive material for which the conditions of paras 409(b)(ii) or (c) or the conditions of paras 413(a) or (b) are met, the requirements given in paras 659(a) and (b)(ii) shall not be applicable, provided that, if it were subjected to:
(i) The tests specified in paras 719-724, it would prevent loss or dispersal of the radioactive contents ;
(ii) The tests specified in para. 659(b), any radioactive material released from the package would be taken into account in demonstration of compliance with the dose rate limit in para. 659(b)(i).
↳ Referenced in Clause 667:
Clause 409
LSA material shall be in one of three groups:
(a) LSA‑I :
(i) Uranium and thorium ores and concentrates of such ores, and other ores containing naturally occurring radionuclides .
(ii) Natural uranium, depleted uranium, natural thorium or their compounds or mixtures, that are unirradiated and in solid or liquid form.
(iii) Radioactive material for which the A2 value is unlimited. Fissile material may be included only if excepted under para. 417.
(iv) Other radioactive material in which the activity is distributed throughout and the estimated average specific activity does not 26
(b) LSA‑II :
(i) Tritiated water with an activity concentration of up to 0.8 TBq/L;
(ii) Other material in which the activity is distributed throughout and the estimated average specific activity does not exceed 10 [−4] A2 /g for solids and gases, and 10 [−5] A2 /g for liquids.
(c) LSA‑III : Solids (e.g. consolidated wastes, activated materials), excluding powders, in which:
(i) The radioactive material is distributed throughout a solid or a collection of solid objects or is essentially uniformly distributed in a solid compact binding agent (e.g. concrete, bitumen, ceramic).
(ii) The estimated average specific activity of the solid, excluding any shielding material, does not exceed 2 × 10 [−3] A2 /g.
↳ Referenced in Clause 409:
Clause 417 (Details displayed above)
Clause 413
SCO shall be in one of three groups:
(a) SCO‑I : A solid object on which:
(i) The non‑fixed contamination on the accessible surface averaged over 300 cm [2] (or the area of the surface if less than 300 cm [2] ) does not exceed 4 Bq/cm [2] for beta and gamma emitters and low toxicity alpha emitters, or 0.4 Bq/cm [2] for all other alpha emitters.
(ii) The fixed contamination on the accessible surface averaged over 300 cm [2] (or the area of the surface if less than 300 cm [2] ) does not exceed 4 × 10 [4] Bq/cm [2] for beta and gamma emitters and low toxicity alpha emitters, or 4000 Bq/cm [2] for all other alpha emitters. 27
(iii) The non‑fixed contamination plus the fixed contamination on the inaccessible surface averaged over 300 cm [2] (or the area of the surface if less than 300 cm [2] ) does not exceed 4 × 10 [4] Bq/cm [2] for beta and gamma emitters and low toxicity alpha emitters, or 4000 Bq/cm [2] for all other alpha emitters.
(b) SCO‑II : A solid object on which either the fixed or non‑fixed contamination on the surface exceeds the applicable limits specified for SCO‑I in subparagraph (a) above and on which:
(i) The non‑fixed contamination on the accessible surface averaged over 300 cm [2] (or the area of the surface if less than 300 cm [2] ) does not exceed 400 Bq/cm [2] for beta and gamma emitters and low toxicity alpha emitters, or 40 Bq/cm [2] for all other alpha emitters.
(ii) The fixed contamination on the accessible surface averaged over 300 cm [2] (or the area of the surface if less than 300 cm [2] ) does not exceed 8 × 10 [5] Bq/cm [2] for beta and gamma emitters and low toxicity alpha emitters, or 8 × 10 [4] Bq/cm [2] for all other alpha emitters.
(iii) The non‑fixed contamination plus the fixed contamination on the inaccessible surface averaged over 300 cm [2] (or the area of the surface if less than 300 cm [2] ) does not exceed 8 × 10 [5] Bq/cm [2] for beta and gamma emitters and low toxicity alpha emitters, or 8 × 10 [4] Bq/cm [2] for all other alpha emitters.
(c) SCO‑III : A large solid object that, because of its size, cannot be transported in a type of package described in these Regulations and for which:
(i) All openings are sealed to prevent release of radioactive material during the conditions specified in para. 520(e).
(ii) The inside of the object is as dry as practicable.
(iii) The non‑fixed contamination on the external surfaces does not exceed the limits specified in para. 508.
(iv) The non‑fixed contamination plus the fixed contamination on the inaccessible surface averaged over 300 cm [2] does not exceed 8 × 10 [5 ] Bq/cm [2] for beta and gamma emitters and low toxicity alpha emitters, or 8 × 10 [4] Bq/cm [2] for all other alpha emitters.
↳ Referenced in Clause 413:
Clause 508 (Details displayed above)
Clause 520 not found.
Clause 639 (Details displayed above)
Clause 652
Type B(U) packages shall be designed to meet the requirements specified in paras 607-618, the requirements specified in paras 619-621 if carried by air, and in paras 636-649, except as specified in para. 648(a), and, in addition, the requirements specified in paras 653-666.
↳ Referenced in Clause 652:
Clause 607
The package shall be so designed in relation to its mass, volume and shape that it can be easily and safely transported. In addition, the package shall be so designed that it can be properly secured in or on the conveyance during transport.
Clause 608
The design shall be such that any lifting attachments on the package will not fail when used in the intended manner and that if failure of the attachments should occur, the ability of the package to meet other requirements of these Regulations would not be impaired. The design shall take account of appropriate safety factors to cover snatch lifting.
Clause 609
Attachments and any other features on the outer surface of the package that could be used to lift it either shall be designed to support its mass in accordance with the requirements of para. 608 or shall be removable or otherwise rendered incapable of being used during transport.
↳ Referenced in Clause 609:
Clause 608 (Details displayed above)
Clause 610
As far as practicable, the packaging shall be so designed that the external surfaces are free from protruding features and can be easily decontaminated.
Clause 611
As far as practicable, the outer layer of the package shall be so designed as to prevent the collection and the retention of water.
Clause 612
Any features added to the package at the time of transport that are not part of the package shall not reduce its safety.
Clause 613
The package shall be capable of withstanding the effects of any acceleration, vibration or vibration resonance that may arise under routine conditions of transport without any deterioration in the effectiveness of the closing devices on the various receptacles or in the integrity of the package as a whole. In particular, nuts, bolts and other securing devices shall be so designed as to prevent them from becoming loose or being released unintentionally, even after repeated use.
Clause 614
The materials of the packaging and any components or structures shall be physically and chemically compatible with each other and with the radioactive contents . Account shall be taken of their behaviour under irradiation.
Clause 615
All valves through which the radioactive contents could escape shall be protected against unauthorized operation.
Clause 616
The design of the package shall take into account ambient temperatures and pressures that are likely to be encountered in routine conditions of transport.
Clause 617
A package shall be so designed that it provides sufficient shielding to ensure that, under routine conditions of transport and with the maximum radioactive contents that the package is designed to contain, the dose rate at any point on the external surface of the package would not exceed the values specified in para. 516, 527 or 528, as applicable, with account taken of paras 566(b) and 573.
↳ Referenced in Clause 617:
Clause 516
The dose rate at any point on the external surface of an excepted package shall not exceed 5 μSv/h.
Clause 527
The maximum dose rate at any point on the external surface of a package, a freight container used as packaging or an overpack shall not exceed 2 mSv/h, except for packages, freight containers used as packaging or overpacks transported under the following:
(a) Exclusive use by rail or by road, under the conditions specified in para. 573(a);
(b) Exclusive use or special arrangement by vessel, under the conditions specified in para. 575;
(c) Special arrangement by air, under the conditions specified in para. 579.
↳ Referenced in Clause 527:
Clause 573 (Details displayed above)
Clause 575
Packages, freight containers used as packagings or overpacks having a surface dose rate greater than 2 mSv/h, unless being carried in or on a vehicle under exclusive use in accordance with Table 10, footnote (c), shall not be transported by vessel except under special arrangement .
Clause 579
Packages, freight containers used as packagings or overpacks having a surface dose rate greater than 2 mSv/h shall not be transported by air except under special arrangement . Additional requirements relating to transport by post
Clause 528
The maximum dose rate at any point on the external surface of a package, a freight container used as packaging or an overpack under exclusive use shall not exceed 10 mSv/h.
Clause 566 (Details displayed above)
Clause 573 (Details displayed above)
Clause 618
For radioactive material having other dangerous properties, the package design shall take into account those properties (see paras 110 and 507).
↳ Referenced in Clause 618:
Clause 110
For radioactive material having other dangerous properties, and for transport of radioactive material with other dangerous goods, the relevant transport regulations for dangerous goods shall apply in addition to these Regulations.
Clause 507
In addition to the radioactive and fissile properties, any other dangerous properties of the contents of the package, such as explosiveness, flammability, pyrophoricity, chemical toxicity and corrosiveness, shall be taken into account in the classification, packing, labelling, marking, placarding, storage and transport in order to be in compliance with the relevant transport regulations for dangerous goods of each of the countries through or into which the materials will be transported, and, where applicable, with the regulations of the relevant transport organizations, as well as these Regulations.
Clause 619 (Details displayed above)
Clause 620
Packages to be transported by air shall be so designed that if they were exposed to ambient temperatures ranging from −40°C to +55°C, the integrity of containment would not be impaired.
Clause 621
Packages containing radioactive material to be transported by air shall be capable of withstanding, without loss or dispersal of radioactive contents from the containment system, an internal pressure that produces a pressure differential of not less than maximum normal operating pressure plus 95 kPa.
Clause 636 (Details displayed above)
Clause 637 (Details displayed above)
Clause 638
Any tie‑down attachments on the package shall be so designed that, under normal and accident conditions of transport, the forces in those attachments shall not impair the ability of the package to meet the requirements of these Regulations.
Clause 639 (Details displayed above)
Clause 640
The design and manufacturing techniques shall be in accordance with national or international standards, or other requirements acceptable to the competent authority .
Clause 641
The design shall include a containment system securely closed by a positive fastening device that cannot be opened unintentionally or by a pressure that may arise within the package .
Clause 642
Special form radioactive material may be considered as a component of the containment system .
Clause 643
If the containment system forms a separate unit of the package, the containment system shall be capable of being securely closed by a positive fastening device that is independent of any other part of the packaging .
Clause 644
The design of any component of the containment system shall take into account, where applicable, the radiolytic decomposition of liquids and other vulnerable materials and the generation of gas by chemical reaction and radiolysis.
Clause 645
The containment system shall retain its radioactive contents under a reduction of ambient pressure to 60 kPa.
Clause 646
All valves, other than pressure relief valves, shall be provided with an enclosure to retain any leakage from the valve.
Clause 647
Radiation shielding that encloses a component of the package specified as a part of the containment system shall be so designed as to prevent the unintentional release of that component from the shielding. Where the shielding and such a component within it form a separate unit, the shielding shall be capable of being securely closed by a positive fastening device that is independent of any other packaging structure.
Clause 648
A package shall be so designed that if it were subjected to the tests specified in paras 719-724, it would prevent:
(a) Loss or dispersal of the radioactive contents ;
(b) More than a 20% increase in the maximum dose rate at any external surface of the package, except for a package whose maximum dose rate at its external surface is below 50 µSv/h, for which there shall be no increase of more than 10 µSv/h in the maximum dose rate at any external surface of the package.
↳ Referenced in Clause 648:
Clause 719 (Details displayed above)
Clause 720 (Details displayed above)
Clause 721 (Details displayed above)
Clause 722 (Details displayed above)
Clause 723 (Details displayed above)
Clause 724 (Details displayed above)
Clause 649
The design of a package intended for liquid radioactive material shall make provision for ullage to accommodate variations in the temperature of the contents, dynamic effects and filling dynamics.
Clause 653 (Details displayed above)
Clause 654 (Details displayed above)
Clause 655 (Details displayed above)
Clause 656
This paragraph has been deleted.
Clause 657
The insolation conditions shall be assumed to be as specified in Table 12.
Clause 658
A package that includes thermal protection for the purpose of satisfying the requirements of the thermal test specified in para. 728 shall be so designed that such protection will remain effective if the package is subjected to the tests specified in paras 719-724 and either paras 727(a) and (b), or paras 727(b) and (c), as appropriate. Any such protection on the exterior of the package shall not be rendered ineffective by ripping, cutting, skidding, abrading or rough handling.
↳ Referenced in Clause 658:
Clause 719 (Details displayed above)
Clause 720 (Details displayed above)
Clause 721 (Details displayed above)
Clause 722 (Details displayed above)
Clause 723 (Details displayed above)
Clause 724 (Details displayed above)
Clause 727 (Details displayed above)
Clause 728 (Details displayed above)
Clause 659 (Details displayed above)
Clause 660 (Details displayed above)
Clause 661 (Details displayed above)
Clause 662 (Details displayed above)
Clause 663 (Details displayed above)
Clause 664 (Details displayed above)
Clause 665 (Details displayed above)
Clause 666 (Details displayed above)
Clause 653 (Details displayed above)
Clause 654 (Details displayed above)
Clause 655 (Details displayed above)
Clause 659 (Details displayed above)
Clause 660 (Details displayed above)
Clause 661 (Details displayed above)
Clause 662 (Details displayed above)
Clause 663 (Details displayed above)
Clause 664 (Details displayed above)
Clause 665 (Details displayed above)
Clause 666 (Details displayed above)
Clause 719 (Details displayed above)
Clause 720 (Details displayed above)
Clause 721 (Details displayed above)
Clause 722 (Details displayed above)
Clause 723 (Details displayed above)
Clause 724 (Details displayed above)
Clause 809 (Details displayed above)
Clause 813
The competent authority shall establish a certificate of approval stating that the approved design meets the applicable requirements for Type B(M) packages and shall attribute to that design an identification mark. Approval of package designs to contain fissile material
Clause 814 (Details displayed above)
Clause 815 (Details displayed above)
Clause 816 (Details displayed above)
Clause 823
Special form radioactive material manufactured to a design that had received unilateral approval by the competent authority under the 1985, 1985 (As Amended 1990), 1996 Edition, 1996 Edition (Revised), 1996 (As Amended 2003), 2005, 2009, 2012 or 2018 Editions of these Regulations may continue to be used when in compliance with the mandatory management system in accordance with the applicable requirements of para. 306. There shall be no new manufacture of special form radioactive material to a design that had received unilateral approval by the competent authority under the 1985 or 1985 (As Amended 1990) Editions of these Regulations. No new manufacture of special form radioactive material to a design that had received unilateral approval by the competent authority under the 1996 Edition, 1996 Edition (Revised), 1996 (As Amended 2003), 2005, 2009 or 2012 Editions of these Regulations shall be permitted to commence after 31 December 2025. No new manufacture of special form radioactive material to a design that had received unilateral approval by the competent authority under the 2018 Edition of these Regulations shall be permitted to commence after 31 December 2035.
↳ Referenced in Clause 823:
Clause 306 (Details displayed above)
Clause 825 (Details displayed above)
Clause 826
A competent authority may authorize transport through or into its country without shipment approval, by a specific provision in its design approval .
Clause 827
An application for approval of shipment shall include:
(a) The period of time, related to the shipment, for which the approval is sought;
(b) The radioactive contents, the modes of transport, the type of conveyance and the probable or proposed route;
(c) The details of how the precautions and administrative or operational controls, referred to in the certificates of approval for the package design, if applicable, issued under paras 810, 813 and 816, are to be put into effect.
↳ Referenced in Clause 827:
Clause 810 (Details displayed above)
Clause 813 (Details displayed above)
Clause 816 (Details displayed above)
Clause 828
Upon approval of the shipment, the competent authority shall issue a certificate of approval . 113
Clause 829
Each consignment transported under special arrangement shall require multilateral approval .
Clause 830
An application for approval of shipments under special arrangement shall include all the information necessary to satisfy the competent authority that the overall level of safety in transport is at least equivalent to that which would be provided if all the applicable requirements of these Regulations had been met. The application shall also include:
(a) A statement of the respects in which, and of the reasons why, the shipment cannot be made in full accordance with the applicable requirements;
(b) A statement of any special precautions or special administrative or operational controls that are to be employed during transport to compensate for the failure to meet the applicable requirements.
Clause 831
Upon approval of shipments under special arrangement, the competent authority shall issue a certificate of approval .
