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).
Short-cut to LSA [link]
Short cut to SCO [link]
Special Form RM [link]
Low-dispersible RM [link]
CLASSIFICATION OF MATERIAL
Clause 408
Radioactive material may only be classified as LSA material if the conditions of paras 226, 409-411 and 517-522 are met.
↳ Referenced in Clause 408:
STRUCTURE
Clause 226
Low specific activity (LSA) material shall mean radioactive material that by its nature has a limited specific activity, or radioactive material for which limits of estimated average specific activity apply. External shielding materials surrounding the LSA material shall not be considered in determining the estimated average specific activity.
CLASSIFICATION OF MATERIAL
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 exceed 30 times the values for the activity concentration specified in paras 402-407. Fissile material may be included only if excepted under para. 417.
(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 x 10^-3 A2/g.
↳ Referenced in Clause 409:
BASIC RADIONUCLIDE VALUES
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.
DETERMINATION OF BASIC RADIONUCLIDE VALUES
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. 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.
↳ Referenced in Clause 403:
Clause 402 (Details displayed above)
CLASSIFICATION OF PACKAGES
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.
(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:
SCOPE
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:
STRUCTURE
Clause 214
Contamination shall mean the presence of a radioactive substance on a surface in quantities in excess of 0.4 Bq/cm² for beta and gamma emitters and low toxicity alpha emitters, or 0.04 Bq/cm² for all other alpha emitters.
DETERMINATION OF BASIC RADIONUCLIDE VALUES
Clause 405
For mixtures of radionuclides, the basic radionuclide values referred to in para. 402 may be determined as follows: Xm = 1 / Sum( f(i) / X(i) ) where f(i) is the fraction of activity or activity concentration of radionuclide i in the mixture; X(i) is the appropriate value of A1 or A2, or the activity concentration limit for exempt material or the activity limit for an exempt consignment as appropriate for radionuclide i; Xm is the derived value of A1 or A2, or the activity concentration limit for exempt material or the activity limit for an exempt consignment in the case of a mixture.
↳ Referenced in Clause 405:
Clause 402 (Details displayed above)
CLASSIFICATION OF MATERIAL
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).
(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) 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:
TRANSPORT AND STORAGE IN TRANSIT
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)
REQUIREMENTS FOR TYPE A PACKAGES
Clause 636
The smallest overall external dimension of the package shall not be less than 10 cm.
DETERMINATION OF BASIC RADIONUCLIDE VALUES
Clause 404
In the calculations of A1 and A2 for a radionuclide not listed in the Appendix, a single radioactive decay chain in which the radionuclides are present in their naturally occurring proportions, and in which no progeny nuclide has a half-life either longer than 10 days or longer than that of the parent nuclide, shall be considered as a single radionuclide; the activity to be taken into account and the A1 or A2 value to be applied shall be that corresponding to the parent nuclide of that chain. In the case of radioactive decay chains in which any progeny nuclide has a half-life either longer than 10 days or longer than that of the parent nuclide, the parent and such progeny nuclides shall be considered as mixtures of different nuclides.
Clause 405 (Details displayed above)
DETERMINATION OF BASIC RADIONUCLIDE VALUES
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)
DETERMINATION OF BASIC RADIONUCLIDE VALUES
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. Low specific activity material
Clause 417 (Details displayed above)
CLASSIFICATION OF MATERIAL
Clause 410
A single package of non-combustible solid LSA-II or LSA-III material, if carried by air, shall not contain an activity greater than 3000 A2.
CLASSIFICATION OF MATERIAL
Clause 411
The radioactive contents in a single package of LSA material shall be so restricted that the dose rate specified in para. 517 shall not be exceeded, and the activity in a single package shall also be so restricted that the activity limits for a conveyance specified in para. 522 shall not be exceeded. Surface contaminated object
↳ Referenced in Clause 411:
REQUIREMENTS AND CONTROLS FOR TRANSPORT OF LSA MATERIAL AND SCO IN INDUSTRIAL PACKAGES OR UNPACKAGED
Clause 517
The quantity of LSA material and SCO in a single Type IP-1, Type IP-2 or Type IP-3 package, or unpackaged LSA material and SCO, whichever is appropriate, shall be so restricted that the sum of the external dose rates at 3 m from the following unshielded items does not exceed 10 mSv/h:
(a) The LSA material (for a single group of LSA material) or each group of LSA material (when different groups of LSA material are packed together);
(b) The SCO (for a single SCO) or each SCO in a collection of SCOs (when different SCOs are packed together);
(c) Each group of LSA material and each SCO (when different groups of LSA material and SCOs are packed together).
REQUIREMENTS AND CONTROLS FOR TRANSPORT OF LSA MATERIAL AND SCO IN INDUSTRIAL PACKAGES OR UNPACKAGED
Clause 522
The total activity in a single hold or compartment of an inland waterway craft, or in another conveyance, for carriage of LSA material or SCO in a Type IP-1, Type IP-2, Type IP-3 package or unpackaged, shall not exceed the limits shown in Table 6. When different groups of LSA material and SCO are carried in the same hold or compartment of an inland waterway craft, or in another conveyance, the total activity in the hold or compartment, or in the other conveyance, shall not exceed the lowest appropriate limit indicated in Table 6. For SCO-III, the limits in Table 6 may be exceeded provided that the transport plan contains precautions that are to be employed during transport to obtain an overall level of safety at least equivalent to that which would be obtained if the limits had been applied.
Clause 517 (Details displayed above)
REQUIREMENTS AND CONTROLS FOR TRANSPORT OF LSA MATERIAL AND SCO IN INDUSTRIAL PACKAGES OR UNPACKAGED
Clause 518
For LSA material and SCO that are, or contain, fissile material that is not excepted under para. 417, the applicable requirements of paras 568 and 569 shall be met.
↳ Referenced in Clause 518:
Clause 417 (Details displayed above)
TRANSPORT AND STORAGE IN TRANSIT
Clause 568
Any group of packages, overpacks and freight containers containing fissile material stored in transit in any one storage area shall be so limited that the sum of the CSIs in the group does not exceed 50. Each group shall be stored so as to maintain a spacing of at least 6 m from other such groups.
REQUIREMENTS AND CONTROLS FOR TRANSPORT OF LSA MATERIAL AND SCO IN INDUSTRIAL PACKAGES OR UNPACKAGED
Clause 519
For LSA material and SCO that are, or contain, fissile material, the applicable requirements of para. 673 shall be met.
↳ Referenced in Clause 519:
REQUIREMENTS FOR PACKAGES CONTAINING FISSILE MATERIAL
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 (Details displayed above)
REQUIREMENTS FOR TYPE A PACKAGES
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.
REQUIREMENTS FOR PACKAGES CONTAINING FISSILE MATERIAL
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:
REQUIREMENTS FOR PACKAGES CONTAINING FISSILE MATERIAL
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:
REQUIREMENTS FOR PACKAGES CONTAINING FISSILE MATERIAL
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/m3 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. Determination of the criticality safety index for packages
↳ Referenced in Clause 685:
TESTS FOR PACKAGES
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 water spray test. One specimen may be used for all the tests, provided that the requirements of para. 720 are fulfilled.
↳ Referenced in Clause 719:
TESTS FOR PACKAGES
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 720 (Details displayed above)
TESTS FOR PACKAGES
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.
TESTS FOR PACKAGES
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:
TESTS FOR PACKAGES
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:
TESTS FOR SPECIAL FORM RADIOACTIVE MATERIAL
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)
TESTS FOR PACKAGES
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.
TESTS FOR PACKAGES
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
TESTS FOR PACKAGES
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:
REQUIREMENTS FOR TYPE A PACKAGES
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/m3 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 (Details displayed above)
Clause 406 (Details displayed above)
Clause 407 (Details displayed above)
REQUIREMENTS AND CONTROLS FOR CONTAMINATION AND FOR LEAKING PACKAGES
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/cm2 for beta and gamma emitters and low toxicity alpha emitters;
(b) 0.4 Bq/cm2 for all other alpha emitters. These limits are applicable when averaged over any area of 300 cm2 of any part of the surface.
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)
TESTS FOR PACKAGES
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)
TESTS FOR PACKAGES
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
TESTS FOR 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. Water leakage test for packages containing fissile material
Clause 727 (Details displayed above)
Clause 717 (Details displayed above)
TESTS FOR PACKAGES
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 within the package from the radioactive contents. Alternatively, any of these parameters are allowed to have different values prior to, and during, the test, provided due account is taken of them in the subsequent assessment of package response. The thermal test shall then consist of subparagraph (a) followed by subparagraph (b).
(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 729 (Details displayed above)
TESTS FOR PACKAGES
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 (Details displayed above)
REQUIREMENTS FOR PACKAGES CONTAINING FISSILE MATERIAL
Clause 681
It shall be assumed that neutrons that are emitted from the package are reflected by at least 20 cm of water.
REQUIREMENTS FOR PACKAGES CONTAINING FISSILE MATERIAL
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)
REQUIREMENTS FOR PACKAGES CONTAINING FISSILE MATERIAL
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)
REQUIREMENTS FOR PACKAGES CONTAINING FISSILE MATERIAL
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 from the package are reflected by at least 20 cm of water but that there is no water in-leakage.
(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)
TESTS FOR PACKAGES
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
TESTS FOR 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)
TESTS FOR PACKAGES
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. SECTION VIII. APPROVAL AND ADMINISTRATIVE REQUIREMENTS
↳ Referenced in Clause 737:
Clause 717 (Details displayed above)
Clause 684 (Details displayed above)
Clause 685 (Details displayed above)
TESTS FOR PACKAGES
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 728 (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)
REQUIREMENTS FOR PACKAGES CONTAINING FISSILE MATERIAL
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)
REQUIREMENTS FOR PACKAGES CONTAINING FISSILE MATERIAL
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)
REQUIREMENTS FOR PACKAGES CONTAINING FISSILE MATERIAL
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. Assessment of an individual package in isolation
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)
REQUIREMENTS FOR PACKAGES CONTAINING FISSILE MATERIAL
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. SECTION VII. TEST PROCEDURES
↳ Referenced in Clause 686:
Clause 684 (Details displayed above)
REQUIREMENTS AND CONTROLS FOR TRANSPORT OF LSA MATERIAL AND SCO IN INDUSTRIAL PACKAGES OR UNPACKAGED
Clause 520
LSA-I material and SCO-I may be transported unpackaged, and SCO-III shall be transported unpackaged, under the following conditions:
(a) All unpackaged material other than ores containing only naturally occurring radionuclides shall be transported in such a manner that under routine conditions of transport there will be no escape of the radioactive contents from the conveyance, nor will there be any loss of shielding.
(b) Each conveyance or large freight container shall be under exclusive use, except when only transporting SCO-I on which the contamination on the accessible and the inaccessible surfaces is not greater than 10 times the applicable level specified in para. 214.
(c) For SCO-I where it is suspected that non-fixed contamination exists on inaccessible surfaces in excess of the values specified in para. 413(a)(i), measures shall be taken to ensure that the radioactive material is not released into the conveyance.
(d) Unpackaged fissile material shall meet the requirement of para. 417(e).
(e) For SCO-III:
(i) The conveyance shall be under exclusive use by road, rail, inland waterway or sea.
(ii) Stacking shall not be permitted.
(iii) All activities associated with the shipment, including radiation protection, emergency response and any special precautions or special administrative or operational controls that are to be employed during transport shall be described in a transport plan. The transport plan shall demonstrate that the overall level of safety in transport is at least equivalent to that which would be provided if the requirements of para. 648 (only for the test specified in para. 724, preceded by the tests specified in paras 720 and 721) had been met.
(iv) The requirements of para. 624 for a Type IP-2 package shall be satisfied, except that the maximum damage referred to in para. 722 may be determined based on provisions in the transport plan, and the requirements of para. 723 are not applicable.
(v) The object and any shielding are secured to the conveyance in accordance with para. 607.
(vi) The shipment shall be subject to multilateral approval.
↳ Referenced in Clause 520:
Clause 214 (Details displayed above)
CLASSIFICATION OF MATERIAL
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 cm2 (or the area of the surface if less than 300 cm2) does not exceed 4 Bq/cm2 for beta and gamma emitters and low toxicity alpha emitters, or 0.4 Bq/cm2 for all other alpha emitters.
(ii) The fixed contamination on the accessible surface averaged over 300 cm2 (or the area of the surface if less than 300 cm2) does not exceed 4 x 10^4 Bq/cm2 for beta and gamma emitters and low toxicity alpha emitters, or 4000 Bq/cm2 for all other alpha emitters.
(iii) The non-fixed contamination plus the fixed contamination on the inaccessible surface averaged over 300 cm2 (or the area of the surface if less than 300 cm2) does not exceed 4 x 10^4 Bq/cm2 for beta and gamma emitters and low toxicity alpha emitters, or 4000 Bq/cm2 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 cm2 (or the area of the surface if less than 300 cm2) does not exceed 400 Bq/cm2 for beta and gamma emitters and low toxicity alpha emitters, or 40 Bq/cm2 for all other alpha emitters.
(ii) The fixed contamination on the accessible surface averaged over 300 cm2 (or the area of the surface if less than 300 cm2) does not exceed 8 x 10^5 Bq/cm2 for beta and gamma emitters and low toxicity alpha emitters, or 8 x 10^4 Bq/cm2 for all other alpha emitters.
(iii) The non-fixed contamination plus the fixed contamination on the inaccessible surface averaged over 300 cm2 (or the area of the surface if less than 300 cm2) does not exceed 8 x 10^5 Bq/cm2 for beta and gamma emitters and low toxicity alpha emitters, or 8 x 10^4 Bq/cm2 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 cm2 does not exceed 8 x 10^5 Bq/cm2 for beta and gamma emitters and low toxicity alpha emitters, or 8 x 10^4 Bq/cm2 for all other alpha emitters.
↳ Referenced in Clause 413:
Clause 508 (Details displayed above)
Clause 520 (Details displayed above)
Clause 417 (Details displayed above)
GENERAL REQUIREMENTS FOR ALL PACKAGINGS AND PACKAGES
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.
REQUIREMENTS FOR INDUSTRIAL PACKAGES
Clause 624
A package to be qualified as Type IP-2 shall be designed to meet the requirements for Type IP-1 as specified in para. 623 and, in addition, if it were subjected to the tests specified in paras 722 and 723, 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. Requirements for Type IP-3
↳ Referenced in Clause 624:
REQUIREMENTS FOR INDUSTRIAL PACKAGES
Clause 623
A Type IP-1 package shall be designed to meet the requirements specified in paras 607–618 and 636 and, in addition, the requirements of paras 619–621 if carried by air. Requirements for Type IP-2
↳ Referenced in Clause 623:
Clause 607 (Details displayed above)
GENERAL REQUIREMENTS FOR ALL PACKAGINGS AND PACKAGES
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.
GENERAL REQUIREMENTS FOR ALL PACKAGINGS AND PACKAGES
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)
GENERAL REQUIREMENTS FOR ALL PACKAGINGS AND PACKAGES
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.
GENERAL REQUIREMENTS FOR ALL PACKAGINGS AND PACKAGES
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.
GENERAL REQUIREMENTS FOR ALL PACKAGINGS AND PACKAGES
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.
GENERAL REQUIREMENTS FOR ALL PACKAGINGS AND PACKAGES
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. 613A. The design of the package shall take into account ageing mechanisms.
GENERAL REQUIREMENTS FOR ALL PACKAGINGS AND PACKAGES
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.
GENERAL REQUIREMENTS FOR ALL PACKAGINGS AND PACKAGES
Clause 615
All valves through which the radioactive contents could escape shall be protected against unauthorized operation.
GENERAL REQUIREMENTS FOR ALL PACKAGINGS AND PACKAGES
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.
GENERAL REQUIREMENTS FOR ALL PACKAGINGS AND PACKAGES
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:
REQUIREMENTS AND CONTROLS FOR TRANSPORT OF EXCEPTED PACKAGES
Clause 516
The dose rate at any point on the external surface of an excepted package shall not exceed 5 uSv/h.
TRANSPORT AND STORAGE IN TRANSIT
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.
↳ Referenced in Clause 566:
TRANSPORT AND STORAGE IN TRANSIT
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.
GENERAL REQUIREMENTS FOR ALL PACKAGINGS AND PACKAGES
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:
SCOPE
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.
ADDITIONAL REQUIREMENTS FOR PACKAGES TO BE TRANSPORTED BY AIR
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.
ADDITIONAL REQUIREMENTS FOR PACKAGES TO BE TRANSPORTED BY AIR
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.
ADDITIONAL REQUIREMENTS FOR PACKAGES TO BE TRANSPORTED BY AIR
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 722 (Details displayed above)
REQUIREMENTS FOR TYPE A PACKAGES
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 720 (Details displayed above)
Clause 722 (Details displayed above)
Clause 723 (Details displayed above)
Clause 724 (Details displayed above)
REQUIREMENTS AND CONTROLS FOR TRANSPORT OF LSA MATERIAL AND SCO IN INDUSTRIAL PACKAGES OR UNPACKAGED
Clause 521
LSA material and SCO, except as otherwise specified in para. 520, shall be packaged in accordance with Table 5. When different groups of LSA material and SCO are packed in the same industrial package, and when those different groups satisfy the condition for different types of industrial package, the material shall be transported in the higher type of industrial package (where Type IP-1 is the lowest and Type IP-3 is the highest).
↳ Referenced in Clause 521:
Clause 520 (Details displayed above)
Clause 522 (Details displayed above)
