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Requirements for Transport of Radioactive Materials

A Survey of Codes and Standards in the USA Relevant to the Prevention of Brittle Fracture in Cask Containment Boundaries

Pages 133-136 | Published online: 19 Jul 2013

Reference

  • United States Code of Federal Regulations, Title 10, Part 71. Packaging and Transportation of Radioactive Material (1994).
  • International Atomic Energy Agency, Safety Series No 6, Regulations for the Safe Transport of Radioactive Material, 1985 Edition (As Amended 1990) (Vienna: IAEA).
  • US Nuclear Regulatory Commission, Regulatory Guide 7.6. Design Criteria for the Structural Analysis of Shipping Cask Containment Vessels, Revision I (March 1978).
  • American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section HI. Rules for Construction of Nuclear Power Plant Components (1992).
  • US Nuclear Regulatory Commission, Regulatory Guide 7.11. Fracture Toughness Criteria of Base Material for Ferritic Steel Shipping Containment Vessels with a Maximum Wall Thickness of 4 Inches (0.1 m) (June 1991). •
  • US Nuclear Regulatory Commission, Regulatory Guide 7.12. Fracture Toughness Criteria of Base Material for Ferritic Steel Shipping Cask Containment Vessels with a Wall Thickness Greater Than 4 Inches (0.1 m) but not Exceeding 12 Inches (0.3 m) (June 1991).
  • American Society for Testing and Materials. Standard Test Method for Conducting Drop-Weight Test to Determine Nil-Ductility Transition Temperature of Ferritic Steels, E208-91 (1994).
  • Appendix G, Section III, of the ASME Boiler and Pressure Vessel Code. Protection Against Nonductile Failure (1992).
  • Appendix A, Section XI, of the ASME Boiler and Pressure Vessel Code. Analysis of Flaw Indications (1992).
  • International Atomic Energy Agency, IAEA TECDOC 717, Guidelines for Safe Design of Shipping Packages Against Brittle Fracture (Vienna: IAEA) (August 1993).

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