Archived Web Page: Draft Regulatory Document RD-364Joint Canada - United States Guide for Approval of Type B(U) and Fissile Material Transportation Packages
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REFERENCES
- American National Standards Institute, American National Standard for Radioactive Materials-Leakage Tests on Packages for Shipment. ANSI N14.5-1997. New York, 1997.
- - - -. Characterizing Damaged Spent Nuclear Fuel for the Purpose of Storage and Transport. ANSI N14.33-2005. New York, 2005.
- - - -. Special Lifting Devices for Shipping Containers Weighing 10000 Pounds (4500 kg) or More. ANSI N14.6-1993. New York, 1980.
- American National Standards Institute, American Society of Mechanical Engineers. Quality Assurance Program Requirements for Nuclear Power Facilities. ANSI/ASME NQA-1-1983. New York, 1983.
- American Nuclear Society. American National Standard for Neutron and Gamma-Ray Flux to Dose Factors. ANSI/ANS 6.1.1. La Grange Park, Illinois, 1977.
- American Society of Mechanical Engineers. Boiler and Pressure Vessel Code Section III- Rules for Construction of Nuclear Facility Components-Div 3 Containments for Transportation & Storage of Spent Nuclear Fuel & High Level Radioactive Materials & Waste . BPVC-III-3-2007. New York, 2007.
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- International Organization for Standardization. Quality Management Systems. ISO 9000:2005. Third Edition. Geneva, 2005.
- - - -. Safe Transport of Radioactive Material - Leakage Testing of Packages. ISO 12807:1996(E). Geneva, 1996.
- Oak Ridge National Laboratory. Standardized Computer Analyses for Licensing Evaluation (SCALE), Tools for Sensitivity and Uncertainty Methodology Implementation (TSUNAMI) . Revision 5.1. December, 2005.
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- United States Nuclear Regulatory Commission. Averaging of Radiation Levels Over the Detector Probe Area, HPPOS-13, in Health Physics Positions Data Base . NUREG/CR-5569, Rev. 1, 1992.
- - - -. Classification of Transportation Packaging and Dry Spent Fuel Storage System Components According to Importance to Safety . NUREG/CR-6407. Washington, DC, 1996.
- - - -. Containment Analysis for Type B Packages Used to Transport Various Contents. NUREG/CR-6487. 1996.
- - - -. Control of Heavy Loads at Nuclear Power Plants. NUREG-0612. 1980.
- - - -. Design Criteria for the Structural Analysis of Shipping Cask Containment Vessels. Regulatory Guide 7.6. 1978.
- - - -. Engineering Drawings for 10 CFR Part 71 Package Approvals. NUREG/CR-5502. 1998.
- - - -. Fabrication Criteria for Shipping Containers. NUREG/CR-3854. 1985.
- - - -. Fracture Toughness Criteria of Base Material for Ferritic Steel Shipping Cask Containment Vessels with a Maximum Wall Thickness of 4 Inches (0.1 m) . Regulatory Guide 7.11. 1991.
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- - - -. Guide for Preparing Operating Procedures for Shipping Packages. NUREG/CR-4775. December 1988.
- - - -. Load Combinations for the Structural Analysis of Shipping Casks for Radioactive Material. Regulatory Guide 7.8. 1989.
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- - - -. Recommended Welding Criteria for Use in the Fabrication of Shipping Containers for Radioactive Materials. NUREG/CR-3019. 1985.
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