ML22271A460
| ML22271A460 | |
| Person / Time | |
|---|---|
| Site: | Orano USA |
| Issue date: | 08/18/2022 |
| From: | TN Americas LLC |
| To: | Division of Fuel Management |
| Garcia-Santos N | |
| Shared Package | |
| ML22271A128 | List:
|
| References | |
| A33010, EPID L-2022-DOT-0007 | |
| Download: ML22271A460 (13) | |
Text
Unrestricted Orano Orano NPS SAFETY ANALYSIS CHAPTER 1.6 REPORT COMPLIANCE WITH REGULATORY REQUIREMENTS
Prepared by 0 orano
FCC3 Checked by
Identification : DOS-19-021165-004-NPV Vers. 2.0 Page 1 / 13
Tableofcontents Statusofrevision 2
- 1. Purpose 3
- 2. Definitions 3
- 3. Managementsystem 4
- 4. Materialsclassification 4
- 5. Requirementsandchecksfortransport 4
- 6. Generalrequirementsforallpackagingsandpackages 5
- 7. Requirementsfortype2industrialpackages 7
- 8. ParticularrequirementsforTypeApackage 7
- 9. Requirementsforpackagescontainingfissilematerials 9
- 10. Testproceduresapplicableto packages 11 11.Packagetests 11 12.Behaviourofthepackagedesignsubjectedtoregulatorytests 12
- 13. References 13
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Status of revision
Version Date Purpose and record of revisions Prepared by / Verified by
Old reference: DOS-13-00081779-060
0 04/2012 First issue
1 10/2016 Updated to match IAEA regulation
New reference: DOS-19-021165-004
1.0 02/2019 Added possibility to define the package as type A Addition of reference [1]
Update according to the IAEA 2018 regulation:
o Deletion of Article 601 o Addition of Article 613A Precision on the analysis of the NCT tests o Of free drop (Article 722) 2.0 See 1st o And water spray (Articles 719 to 721) page Cross-reference to chapter 2.1-11 concerning the consideration of the effects of the cumulative drop tests in NCT and ACT (Articles 726 and 727)
Replacement of the cross-reference to the obsolete reference [2] by chapter 2.4 Addition of the Articles 538 to 542 related to labelling Formal updates
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- 1. Purpose According to the IAEA Regulations for shipment of radioactive materials (reference [1]), type 2 fissile industrial packages (IP-2) defined according to ar ticles 408, 624 and 673, or fissile type A packages defined according to articles 428, 635 and 673, which are not transported by air must be designed to satisfy the requirements for packagings as set forth in the following Articles of the Regulations. These requirements are referenced below:
Requirements 2018 Edition
Definitions 222 and 226 Management system 306
Materials classification 409 to 411 and 418
501 c), 504, 507, 508, 517, Requirements and checks for transport 521, 522, 526 to 528, 531 to 535, 538 to 542, 573 and 575 General requirements for all packagings and packages 607 to 618
Particular prescriptions for type 2 industrial packages (IP-2) 623, 624 and 636
Particular requirements for type A packages 429, 430 and 636 to 651 Particular requirements for packages containing fissile materials 673 to 686
Test procedures applicable to packages 701 to 703
Tests for packages 713 to 717 Tests for demonstrating ability to withstand normal conditions of 719 to 724 transport
Tests to prove capacity to withstand accidental conditions of transport 726 to 729
Tests to prove water-tightness of packages containing fissile materials 731 to 733
This chapter will demonstrate, ar ticle by article, compliance of the package model comprising the FCC3 packaging and its radioactive c ontent with these requirements.
- 2. Definitions
2.1. Article 222 The radioactive content transported in the F CC3 packaging and described in Chapter 1.3 is enriched with uranium 235. It therefore corresponds to the definition of fissile material according to this Article.
2.2. Article 226 Chapter 1.3 of this Report shows that the radioac tive content transported satisfies the definition of material of low specific activity.
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- 3. Management system
3.1. Article 306 The management system principles applicable to the FCC3 packaging are described in Chapter 1.9 of this Report.
- 4. Materials classification
4.1. Article 409 Chapter 1.3 of this Report shows that the material is classified LSA II for the purposes of transportation of enriched natural uranium, and that the material is classified LSA II or LSA III for the purposes of transportation of reprocessed uranium.
4.2. Article 410 The FCC3 packaging is not transported by air.
4.3. Article 411 Compliance with Articles 517 and 522 is demonstrated in sections 5.5 and 5.7.
4.4. Article 418 The definition of the transported content is described in Chapter 1.3 of this Report and conforms to this Article.
- 5. Requirements and checks for transport
5.1. Article 501 c)
The manufacturing test criteria for resin, as defined in Chapter 1.4 of this Report ensure conformity with this requirement.
5.2. Article 504 The FCC3 package model, as described in Chapter 1.4 of this Report, complies with this requirement.
5.3. Article 507 This Article concerns radioactive materials having other dangerous properties, such as explosiveness, flammability, pyrophoricity, chemical toxicity and corrosiveness. It therefore does not apply to the package model comprising the FCC3 packaging and its contents defined in Chapter 1.3.
5.4. Article 508 Verification of compliance with the specified cr iteria is required before shipment as described in Chapter 1.7.
5.5. Article 517 Chapter 1.3 of this Report demonstrates compliance with this Article.
5.6. Article 521 Chapter 1.2 of this Report demonstrates compliance with this Article.
5.7. Article 522 Chapter 1.2 of this Report reiterates this regulatory criterion which must be verified for compliance before shipment.
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5.8. Article 526 Chapter 1.7 of this Report includes these requirements.
5.9. Articles 527, 528, 573 and 575 Verification of compliance with the regulatory cr iteria for transport under "exclusive use" is accomplished by pre-shipment measures. Details of this verification procedure are given in Chapter 1.7 of this Report.
5.10. Articles 531 to 535 and 538 to 542 Verification of the regulatory conformity of labelling and markings on pa ckagings is required, prior to shipment, as defined in Chapter 1.7.
- 6. General requirements for all packagings and packages
6.1. Article 607 The performance of the packaging in routine condit ions of transport is demonstrated in Chapter 2.1. The packaging is designed so that the package can be handled and transported easily and safely. Handling can be performed in normal conditions of safety using standard lifting machinery, by means of slings and hooks. Two lifting modes are possible:
By means of the 4 lifting lugs welded on the upper shell, for handling the loaded or empty package and the lid by itself during opening operations, By means of the fork-lift pocke ts provided under the lower shell.
The packaging is also designed to be suitably tied down during transport. (See Appendices 2.1-2 and 2.1-3).
6.2. Article 608 The results of the lifting calculations (lifting by the lifting lugs - see Appendix 2.1-4) demonstrate that the FCC3 packaging has been designed so that no lifting attachment fails when used in the intended manner. The packaging therefore c onforms to Article 608 of the Regulations, reference [1].
6.3. Article 609 The loaded or empty package is raised by the lifti ng lugs on the upper shell or by means of the fork-lift pockets.
The packaging defined in Chapter 1.4 of this Report does not have any other irregularities on its outer surface capable of being used for lifting (see Chapter 1.4).
6.4. Article 610 The packaging defined in Chapter 1.4 of this Report is designed so that its outer surface does not have any projections other than those formed by the lifting lugs, the reinforcing angle bars, the enclosure flanges and the support skids.
The outer surfaces of the packaging are designed so as to be easily decontaminated. They are simple in form and coated with a polyureth ane type paint. The FCC3 containers are also subjected to a programme of regular inspections and maintenance which ensures that the paint system remains in good condition, as described in Chapter 1.7.
6.5. Article 611 The outer enclosure of the packaging is cylind rical in form: its shape prevents water from collecting and being retained on the surface.
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6.6. Article 612 Additions to the package constituting thermal ba rriers (transportation in holds, overpacks, etc.)
are permitted without restriction.
6.7. Article 613 The effects of acceleration, vibration or re sonance which may arise under conditions which should be those of routine transport must not det ract from the effectiveness of the closing devices or degrade the package as a whole.
Effectiveness of closing devices:
The hinge pins and locking pins are held in plac e axially by locking devices (ball-locking pins, retaining rings).
The tightening torque of the bolts ensures that they will not loosen during transport. They were sized in Chapter 2.1 to maintain a permanent tightening force.
Package integrity:
The constituent materials of the package and the quality of the welds were selected to withstand the stresses encountered during transport.
The experience acquired with the RCC packages confirms the effectiveness of this design.
6.8. Article 613A Appendix 1.4-5 of this report deals with the e ffects of ageing mechanisms on the components of the package.
6.9. Article 614 The constituent materials of the packaging and all internal components or structures were chosen to be physically and chemically compat ible with each other and with the intended radioactive contents of the package.
The constituent materials of the packaging (see Chapter 1.4 of this Report) are not degraded by the radiation to which they are exposed.
Furthermore, the materials which the packaging ma y contain are not susceptible to radiolytic decomposition.
The internal equipment is made exclusively of stainless steel, which protects these parts against corrosion risks. For the carbon steel parts (shell and cradle), the periodic inspection programme detailed in Chapter 1.7 includes moni toring the condition of the paint coatings so as to detect and remedy incipient corrosion.
6.10. Article 615 The valve mounted on the lower shell is a pressure-relieving valve. It is protected by a bolted plate which prohibits an y unauthorised manipulation.
6.11. Article 616 The probable ambient temperatures taken into account for the packages are defined in paragraph 9.8 of this document (Article 679).
In terms of ambient pressure, the package is not leakproof; the confinement is based upon the strength of the rods themselves during Regulat ory Conditions of Transport. Variations in ambient pressure on the claddings have no effect on the compliance of the package with the regulation.
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6.12. Article 617 The description of the content, defined in Chapt er 1.3 of this Report, represents the maximum radioactive content. Chapter 2.4 justifies that the content defined in Chapter 1.3 respects regulatory criteria in contact dur ing routine conditions of transport.
6.13. Article 618 This Article concerns radioactive materials having other dangerous properties, such as explosiveness, flammability, pyrophoricity, chemical toxicity and corrosiveness. It therefore does not apply to the package model comprising the FCC3 packaging and its contents defined in Chapter 1.3.
- 7. Requirements for type 2 industrial packages
7.1. Article 623 Article 623 renders Articles 607 to 618 and 636 appl icable. Articles 607 to 618 are covered in paragraph 6. Article 636 is covered in paragraph 7.3.
7.2. Article 624 In addition to compliance with Article 623, Article 624 calls for evidence to show that if the package were subjected to the free drop test (Article 722) and stacking test (Article 723), the following would not occur:
Loss or dispersal of the radioactive contents; and an increase of more than 20% in the maximum dose rate over the whole external surface of the package.
As shown in paragraph 12.2 below, the FCC3 package withstands the tests corresponding to accidental conditions of transport, in particula r a 9 metre drop and two 1 metre drops onto a 1.20 m bar without dispersal of the contents. These tests are much more severe than the test corresponding to the tests of Article 722 (1.2-metre free fall drop test). Therefore, the loss or dispersal of the radioactive content following this test is excluded.
The results of the stacking test are reiterat ed in paragraph 12.1.3 and show that the package is unaffected by this test.
Chapter 2.4 shows that during the tests simulati ng normal conditions of transport, the increase in dose equivalent rate at the surface of the package is under 20%.
7.3. Article 636 With regard to Article 636, the smallest overall outside dimension of the package is well above 10 cm (114 cm - see Chapter 1.4).
- 8. Particular requirements for Type A package
8.1. Article 429 The A2 value of enriched natural uranium (ENU) under 20% is unlimited according to [1]. The activity of a FCC3 packaging transport ing ENU is therefore less than 1 A 2.
8.2. Article 430 The A2 value for ENU under 20% is unlimited, which makes the activity equal to 0 A 2. The inequation of this article is therefore satisfied.
8.3. Article 636 This article is addressed in paragraph 7.3.
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8.4. Article 637 The FCC3 package is equipped with security s eals to guarantee that it is not being opened during transport operations. This operation is imposed in the instructions of use before shipment.
8.5. Article 638 The tie-down attachments of the package are loca ted on the external shell. In normal and accidental conditions of transport, the external shell may be locally deformed. However, these deformations of the shell are taken into account in the nuclear criticality study where a severe deformation of the outer shell is considered in accidental conditions of transport (see Chapter 2.5).
8.6. Article 639 The upper temperature limit (+70°C) is acceptab le for all package material (steels for the vessel and structural components, rubber for the shock mounts).
Regarding the lower temperatures, the complianc e with Article 679, addressed in chapters 1.3 and 1.4 (see paragraph 9.8) provides the demons tration of the good behaviour of the package components materials down to -40°C.
Regarding the bolts, standards NF A 25-100 state that the fixings used in the FCC3 can be used in the temperature range -50°C / + 300°C.
The shock absorber mechanical characterist ics are valid in the range -40°C / +70°C.
8.7. Article 640 The manufacturing of the package is done in accordance with standard manufacturing processes and standard materials (see Table 1.4-1 of chapter 1.4).
8.8. Article 641 The containment is ensured by the cladding of each rod and the welded plugs, in zirconium alloy (according to chapter 1.4). The mechanical re sistance of the rods in case of internal overpressure is addressed in Appendix 2.2-3.
8.9. Article 642 Not applicable
8.10. Article 643 Not applicable. The containment is ensured by a part of the package (by the cladding of rods).
8.11. Article 644 The containment system consists in the claddi ng of each fuel rod. The rods do not contain liquids or materials which may generate gas by chemical reaction or radiolysis. The rods contain only UO2 pellets and inert gas.
8.12. Article 645 Appendix 2.2-3 demonstrates that the relative internal pressure of a rod in accidental conditions may reach up to 89 bars. In these conditions, the containment performances remain ensured. This analysis shows that the containment system can retain a differential pressure of much more than 40 kPa (resulting from a decreas e of the ambient pressure from 100 kPa to 60 kPa).
8.13. Article 646 The valve fixed on the lower shell is a pressure-relieving valve. It is protected by a bolted plate which prohibits any unauthorised manipulation. It is not a part of the containment system.
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8.14. Article 647 The radiation shield is mainly composed of the resin included into the support frames and the doors. The doors are attached to the support frame with quick release pins which are resistant to normal and accidental conditions of transport. The cavity is bordered by the support frame, the doors and the head and foot plates. The fuel assemblies remain in the cavity, and so in the radiation shield, in any conditions of transport.
So this demonstrates that the radiation shield is constantly around the containment system consisting in the rods.
8.15. Article 648 Chapter 2.4 demonstrates that in normal conditions of transport, the dose rates at the external surface of the package increase in a limited wa y. Moreover, Appendix 2.2-3 demonstrates that there is no loss of material even in hypothetical accidental conditions and so in normal conditions of transport.
So the packaging is designed to prevent any loss of material and to generate limited increase in the dose rates.
8.16. Article 649 Not applicable. The packaging is designed to contain only solid content and not liquid radioactive material.
8.17. Article 650 Not applicable. The packaging is designed to contain only solid content and not liquid radioactive material.
8.18. Article 651 Not applicable. The packaging is designed to allow only solid content and not gases.
- 9. Requirements for packages containing fissile materials
9.1. Article 673 The fissile materials are packaged and shipped so that sub-criticality is maintained in all of the circumstances most frequently encountered in normal transport conditions and in case of accident.
The eventualities described in this Article are taken into consideration in the corresponding criticality studies (see paragraphs 9.9 to 9.11).
Compliance with Article 636 is addressed in paragraph 7.3.
With regard to Article 637, the packaging is fi tted with seals placed on the packaging closure flanges to guarantee that the package has not been opened during transport.
Compliance with Articles 676 to 686 is demonstrated below.
9.2. Article 570 The FCC3 packaging loaded with the contents descr ibed in Chapter 1.3 of this Report does not meet the requirements stated in Article 417. T herefore, it is not subject to the requirements laid out in Article 570.
9.3. Article 674 The package is not exempt from requirements for package models containing fissile materials.
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9.4. Article 675 The package is not exempt from requirements for package models containing fissile materials.
9.5. Article 676 The assumptions made concerning the modelling of the package content for the criticality safety studies are set out in Chapter 2.5 in accordance with the content description given in Chapter 1.3.
9.6. Article 677 The content transported is not composed of irradi ated fuel (see Chapter 1.3). This Article does not therefore apply to the FCC3 packaging.
9.7. Article 678 The condition of the package on completion of t he tests specified in Articles 719 to 724 is described in paragraph 12.1 and shows that:
the minimum overall outside dimensions of the package remain above 10 cm on completion of the tests, the non-opening of the half-shells ensures that it is not possible for a 10 cm cube to enter the packaging.
9.8. Article 679 The upper temperature limit (+38°C) is acceptable for all of the constituent materials of the packaging (steels for the enclosure and structur al components, rubber for the shock mounts) as defined in Chapter 1.4.
With regard to the lower temperature limit (- 40°C), the strength of the packaging components and the zirconium alloy claddings is analysed in Chapters 1.3 and 1.4.
9.9. Articles 680, 681 and 682 The criticality safety case for the package in isolation is made in Chapter 2.5.
The package has no special characteristics designed to prevent the infiltration of water (see Chapter 1.4); the presence of water is therefore assumed within the empty spaces of the package.
The isolating system is defined in Paragraph 5.5 - Chapter 1.4: it essentially consists of fuel rods, which remain intact on completion of the regulatory tests (see Chapter 2.1), and the packaging. Thus, a reflection by a 20 cm layer of water around the packaging is taken into account.
The model used to demonstrate the criticality safety case for the package takes into account the damage observed on completion of the cumulative regulatory tests representing normal and accidental conditions of transport (see paragraph 12). The model therefore bounds the conditions envisaged in Article 682.
The criticality studies thus show, for the FCC3 packaging in isolation and loaded with the content described in Chapter 1.3, that the cr iterion normally adopted to ensure the criticality safety of the package in isolation is met under conditions of maximum neutron multiplication.
9.10. Article 683 Not applicable as no air transportation is carried out (see Chapter 1.2).
9.11. Articles 684 and 685 The criticality safety case for a number of packages is made in Chapter 2.5.
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A reflection by a 20 cm layer of water around the package array is taken into account.
In normal conditions, i.e. for the package followi ng the tests as defined in Articles 719 to 724, the configuration studied in the criticality studies is an infinite array of packages (cylindrical model) filled with water and with a void space between packages.
In accidental conditions, i.e. for the package following the cumulative tests as defined in Articles 719 to 724 and Articles 726 to 729, the array is composed of damaged packages (parallelepiped model) for which the model is as described in paragraph 12. No material escapes from the containment system and the c onfigurations of any quantity of water inside the packaging are taken into account thus cove ring the requirements of Articles 731 to 733 and 729.
The criticality studies therefore show that:
In normal conditions of transport, an infinite number of FCC3 packages loaded with the content described in Chapter 1.3 satisfies the criterion normally adopted to ensure the criticality safety of multiple packages, In normal conditions of transport, a number N of FCC3 packages depending on the loaded content as described in Chapter 1.3, and with the conditions of maximum neutron multiplication, satisfies the criterion normally adopted to ensure the criticality safety of multiple packages.
9.12. Article 686 The criticality studies (Chapter 2.5) define the criticality safety index in relation to the content.
- 10. Test procedures applicable to packages
10.1. Articles 701 and 702 Demonstrations of compliance at Chapter VI of regulation in reference [1] are carried out in Section 2 (Chapters 2.1 to 2.5); they are notabl y based on the analysis of free drop tests carried out on specimen packages (also called prototypes) and on the basis of calculations or analyses as detailed in paragraph 12.
10.2. Article 703 This item relates to compliance with te st conditions rather than a criterion.
The leaching tests carried out in order to classify the material as LSA III are detailed in Chapter 1.3; the test conditions comply with the requirements of this Article.
- 11. Package tests
11.1. Article 713 Compliance of the FCC3 package with IAEA requ irements (reference [1 ]) is demonstrated by subjecting a full-scale test specimen (FCC4 packaging prototype) to the regulatory mechanical tests. This specimen conforms in all respects to the series model and only differs from the latter in the components (considered insignific ant) mentioned in Chapter 2.1 of this Report.
11.2. Article 714 Given that the specimen used for the tests is compliant with the package model, the containment system of the specimens is the same as that defined for the package model (described in Chapter 1.4), i.e. the rod claddings.
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11.3. Article 715 Given that the specimen used for the tests is compliant with the package model, the external areas of the specimens are identified in the same manner as for the package model (described in Chapter 1.4).
11.4. Article 716 The test reports are included or referenced in Chapter 2.1 of this Report and satisfy the requirements of this article.
11.5. Article 717 The targets used for the drop tests are referenced in the test reports included or referenced in Chapter 2.1.
- 12. Behaviour of the package design subjected to regulatory tests
12.1. Effects of tests for demonstrating ability to withstand normal conditions of transport
12.1.1. Articles 719, 720 and 721: Water spray test The effect of the constituent materials of the packaging is that the spray test has no impact on the mechanical behaviour in the free drop, stacking or penetration tests (steel shell, cleanliness seal, metallic materials).
The water spray test is not analysed as the pene tration of water in the packaging is taken into account in the criticality studies of chapter 2.5. Furthermore, the half-shells of the FCC3 packaging are entirely metallic and have a gasket that guaranties that no significant quantity of water can penetrate in side the packaging during the test. Finally, because of the shape of the packaging, no sign ificant quantity of water can be retained on the external surfaces during the test.
Thus, the performance of this test and its conclusions have no impact on the demonstration of compliance of the package with regulatory requirements.
12.1.2. Article 722: Free drop test The maximum mass of the loaded package is 4385 kg; therefore, the maximum height of free fall is 1.2 m.
A 9-metre drop was carried out on a specimen representative of the FCC4 model package (see paragraph 7.2) with no effect on the compliance of the package with regulatory requirements. The free drop test in normal conditions of transport has no effect on the compliance of the package with regulatory requirements.
12.1.3. Article 723: Stacking test The good behaviour of the package is demonstrated on the basis of a calculation taking into account a compressive force equal to 22,072.5 daN (equivalent to 5 times the mass of the package weighing a maximum of 4,500 kg). This force is applied uniformly on the 4 bearing points of the packages stacked for storage (support boxes)
The calculations describing the mechanical strength of the package are described in Chapter 2.1 and show that the stresses produc ed are below the elastic limit in the metal structures of the packaging. It is therefore concluded that the FCC3 packaging sustains no damage on completion of the stacking test.
12.1.4. Article 724: Penetration test It is demonstrated in Chapter 2.1 that this te st produces no perforation of the external enclosure of the FCC3 packaging.
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12.2. Cumulative effect of tests for demonstrating ability to withstand accidental conditions of transport
12.2.1. Article 726 and 727 The ability of the package to withstand tests in accident drop conditions is verified by the performance of a 9-meter drop and a drop onto a bar with full-scale prototypes. Chapter 2.1 presents the conditions and results of thes e tests. A complementary analysis is also performed in chapter 2.1-11 showing that the accumulation of the drops in normal and accidental conditions of transport does not mo dify the conclusions of the drop test in accidental conditions of transport.
12.2.2. Article 728: Thermal test On completion of the drop tests representative of accident drop conditions (Articles 726 and 727), the behaviour of the package during t he thermal fire test is described in Chapter 2.2 with the aid of a numerical model.
It is demonstrated by thermal-mechanical calc ulation in Chapter 2.2 that the claddings retain their integrity during and after the thermal fire test.
12.2.3. Article 729: Water immersion test The FCC3 packaging is not watertight, and the fuel rods are pressurised. No damage to the package is therefore anticipated. Furthermore, the model adopted for the criticality studies takes into account the presence of water around the assemblies.
12.2.4. Articles 731 to 733: Water-tightness test for packages containing fissile materials Given that the criticality studies in Chapter 2.5 take into account the presence of water in the void spaces of the packaging, these Articles are not applicable.
- 13. References
[1] Regulations for the Safe Transport of Radioacti ve Material - at the revision indicated in Chapter 1.2.
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