References
- M. TSCHILTZ, “Addressing the Challenges with Establishing the Infrastructure for the Front-End of the Fuel Cycle for Advanced Reactors,” Nuclear Energy Institute (Jan. 2018).
- Code of Federal Regulations, Title 49, “Transportation,” Sec. 173.420, “Uranium Hexafluoride (Fissile, Fissile Excepted and Non-Fissile),” p. 716, U.S. Nuclear Regulatory Commission (2014); https://www.govinfo.gov/content/pkg/CFR-2014-title49-vol2/pdf/CFR-2014-title49-vol2.pdf ( current as of Apr. 17, 2020).
- ANSI N14.1-2001, “Uranium Hexafluoride – Packaging for Transport,” American National Standards Institute, New York (2001).
- Code of Federal Regulations, Title 10, “Energy,” Sec. 71.55, “General Requirements for Fissile Material Packages,” p. 350, U.S. Nuclear Regulatory Commission (2014); https://www.govinfo.gov/content/pkg/CFR-2014-title10-vol2/pdf/CFR-2014-title10-vol2.pdf ( current as of May 28, 2020).
- J. JARRELL, “A Proposed Path Forward for Transportation of High-Assay Low-Enriched Uranium,” INL/EXT-18-51518, Rev. 0, Idaho National Laboratory (Sep. 2018).
- “Safeguard Categories of SNM,” U.S. Nuclear Regulatory Commission; https://www.nrc.gov/security/domestic/mca/snm.html ( current as of Apr. 17, 2020).
- M. C. REGALBUTO, “INL HALEU Program,” presented at Micro-Reactor Workshop, Idaho Falls, Idaho, June 18-19, 2019.
- D. VADEN, “Isotopic Characterization of HALEU from EBR-II Drive Fuel Processing,” INL/EXT-18-51906, Rev. 0, Idaho National Laboratory (Nov. 2018).
- M. PATTERSON, “Isotopic Characterization of HALEU from EBR-II Driver Processing,” TEV-3537, Rev. 1, Idaho National Laboratory (Apr. 2020).
- “Transportation of Radioactive Material,” U.S. Nuclear Regulatory Commission; https://www.nrc.gov/reading-rm/basic-ref/students/for-educators/11.pdf ( current as of Apr. 29, 2020).
- Code of Federal Regulations, Title 10, “Energy,” Sec. 71.4, “Definitions,” p. 334, U.S. Nuclear Regulatory Commission (2014); https://www.govinfo.gov/content/pkg/CFR-2014-title10-vol2/pdf/CFR-2014-title10-vol2.pdf (current as of May 28, 2020).
- Code of Federal Regulations, Title 10, “Energy,” Appendix A to Part 71, “Determination of A1 and A2,” p. 369, U.S. Nuclear Regulatory Commission (2014); https://www.govinfo.gov/content/pkg/CFR-2014-title10-vol2/pdf/CFR-2014-title10-vol2.pdf ( current as of May 28, 2020).
- “RAMPAC Radioactive Material Packaging,” U.S. Department of Energy; https://rampac.energy.gov/ ( current as of Apr. 17, 2020).
- S. SISLEY, J. ENGLAND, and J. SUBIRY, “NAC’s OPTIMUSTM Packaging for Research and Test Reactor Fuels and Wastes,” Proc. Int. Mtg. Reduced Enrichment for Research and Test Reactors, Zagreb, Croatia, October 6–9, 2019.
- “Introducing OPTIMUSTM-H and OPTIMUSTM-L OPTImal Modular Universal Shipping Cask,” NAC International; https://www.nacintl.com/images/pdf/NAC_OPTIMUS_2018.pdf ( current as of Apr. 17, 2020).
- “OPTIMUSTM Transport Packages,” NAC International; https://www.nacintl.com/images/pdf/NAC-Product%20Flyer-Optimus-Transformer-101619.pdf ( current as of Apr. 17, 2020).
- “OPTIMUSTM,” NAC International; https://www.nacintl.com/solutions/transportation/transportation-systems/optimus ( current as of Apr. 17, 2020).
- “SCALE Code System,” ORNL/TM-2005/39, Version 6.2.3, B. T. REARDEN and M. A. JESSEE, Eds., Oak Ridge National Laboratory (Mar. 2018).
- R. A. HALL et al., “Assessment of Critical Experiment Benchmark Applicability to a Large-Capacity HALEU Transportation Package Concept,” Nucl. Sci. Eng., 195, 310 (2021); https://doi.org/10.1080/00295639.2020.1801319.
- Code of Federal Regulations, Title 10, “Energy,” Sec. 71.71, “Normal Conditions of Transport,” p. 353, U.S. Nuclear Regulatory Commission (2014); https://www.govinfo.gov/content/pkg/CFR-2014-title10-vol2/pdf/CFR-2014-title10-vol2.pdf ( current as of May 28, 2020).
- Code of Federal Regulations, Title 10, “Energy,” Sec. 71.73, “Hypothetical Accident Conditions,” p. 354, U.S. Nuclear Regulatory Commission (2014); https://www.govinfo.gov/content/pkg/CFR-2014-title10-vol2/pdf/CFR-2014-title10-vol2.pdf ( current as of May 28, 2020).
- “Standard Review Plan for Transportation Packages for Radioactive Material,” NUREG-1609, U.S. Nuclear Regulatory Commission (Mar. 1999)
- Code of Federal Regulations, Title 10, “Energy,” Sec. 71.59, “Standards for Arrays of Fissile Material Packages,” p. 351, U.S. Nuclear Regulatory Commission (2014); https://www.govinfo.gov/content/pkg/CFR-2014-title10-vol2/pdf/CFR-2014-title10-vol2.pdf ( current as of May 28, 2020).
- Code of Federal Regulations, Title 10, “Energy,” “External Radiation Standards for All Packages,” Sec. 71.47, p. 349, U.S. Nuclear Regulatory Commission (2014); https://www.govinfo.gov/content/pkg/CFR-2014-title10-vol2/pdf/CFR-2014-title10-vol2.pdf ( current as of May 28, 2020).
- Code of Federal Regulations, Title 49, “Transportation,” Sec. 177.842, “Class 7 (Radioactive) Material,” p. 873, U.S. Nuclear Regulatory Commission (2014); https://www.govinfo.gov/content/pkg/CFR-2014-title49-vol2/pdf/CFR-2014-title49-vol2.pdf ( current as of May 28, 2020).
- Code of Federal Regulations, Title 10, “Energy,” Sec. 71.51, “Additional Requirements for Type B Packages,” p. 349, U.S. Nuclear Regulatory Commission (2014); https://www.govinfo.gov/content/pkg/CFR-2014-title10-vol2/pdf/CFR-2014-title10-vol2.pdf ( current as of May 28, 2020).
- J. C. CLAYTON and S. ARONSON, “Some Preparation Methods and Physical Characteristics of UO2 Powders,” WAPD-178, Westinghouse Electric Corporation (Dec. 1958).
- ASME Boiler and Pressure Vessel Code, Sec. III, “Rules for Construction of Nuclear Facility Components,” Division 3, “Containment Systems & Transport Packagings for Spent Nuclear Fuel Transporation & High-Level Radiactive Waste,” American Society of Mechanical Engineers, New York (2019).
- ASME Boiler and Pressure Vessel Code, Sec. II, “Materials,” Part D, “Properties,” American Society of Mechanical Engineers, New York (2019).
- ASME Boiler and Pressure Vessel Code, Sec. III, “Rules for Construction of Nuclear Facility Components,” Division 1, “Case N-519. Use of 6061-T6 and 6061-T651 Aluminium for Class 1 Nuclear Components,” American Society of Mechanical Engineers, New York (1994).
- “Neutron Absorber Materials for Fresh and Spent Fuel Applications,” Ceradyne Canada.
- “OPTIMUSTM-L Safety Analysis Report,” Rev. 19A, NAC International (Mar. 2019).
- “AISI Type 304 Stainless Steel,” Aerospace Specifications Metals Inc.; http://asm.matweb.com/search/SpecificMaterial.asp?bassnum=mq304a ( current as of Apr. 17, 2020).
- “Aluminum 6061-T6; 6061-T651,” Aerospace Specifications Metals Inc., http://asm.matweb.com/search/SpecificMaterial.asp?bassnum=MA6061T6 ( current as of Apr. 17, 2020).
- L. WANG, “Evaluation of Aluminum-Boron Carbide Neutron Absorbing Materials for Interim Storage of Used Nuclear Fuel,” NEUP 10-603, U.S. Department of Energy, Nuclear Energy University Programs (Dec. 2015).
- “Compilation of Existing State Truck Size and Weight Limits,” U.S. Department of Transportation, https://ops.fhwa.dot.gov/FREIGHT/policy/rpt_congress/truck_sw_laws/app_a.htm ( current as of Apr. 17, 2020).