References
- US Nuclear Regulatory Commission: ‘Spent fuel transportation risk assessment: draft report for comment’, NUREG-2125, US Nuclear Regulatory Commission, Washington, DC, USA, 2012.
- Fischer LE, Chou CK, Gerhard MA, Kimura CY, Martin RW, Mensing RW, Mount ME and Witte MC: ‘Shipping container response to severe highway and railway accident conditions’, NUREG/CR 4829, Lawrence Livermore National Laboratory, Livermore, CA, USA, 1987.
- Sprung JL, Ammerman DJ, Breivik NL, Dukart RJ, Kanipe FL, Koski JA, Mills GS, Neuhaiuser KS, Radloff HD, Weiner RF and Yoshimura HR: ‘Re examination of spent fuel risk estimates’, NUREG/CR 6672, Sandia National Laboratories, Albuquerque, NM, USA, 2000.
- SIERRA Solid Mechanics Team: ‘Presto 4·14 User’s Guide’, SAND2009 7401, Sandia National Laboratories, Albuquerque, NM, USA, 2009.
- Yoshimura R, Harding D, Akin L, Kalan R, Lopez C, Jones P, Miller D, Schmale D, Knorovsky G, Morrow C and Weiner R: ‘PAT-1 safety analysis report addendum’, SAND2010-6109, revised, Sandia National Laboratories, Albuquerque, NM, USA, 2010.
- Kishimoto J, Tamaki H, Kimura T, Hode S and Yamamoto T: ‘Full-scale and subscale drop test for “MSF” transport and storage cask’, Proc. 15th Int. Symp. on ‘Packaging and transportation of radioactive materials’, Miami, FL, USA, October 2007, Institute of Nuclear Materials Management, paper No. 264.
- Musolff A, Müller K, Neumann M, Kadji A and Droste B: ‘Drop test results of the full-scale CONSTOR® V/TC prototype’, Proc. 15th Int. Symp. on ‘Packaging and transportation of radioactive materials’, Miami, FL, USA, October 2007, Institute of Nuclear Materials Management, paper No. 65.
- Blandford RK, Morton DK, Snow SD and Rahl TE: ‘Tensile stress-strain results for 304L and 316L stainless steel plate at temperature’, PVP2007 26096, Proc. Am. Soc. Mech. Eng. Press. Vessels Pip. Conf., San Antonio, TX, USA, July 2007, American Society of Mechanical Engineer, paper No. PVP2007 26096.
- US Nuclear Regulatory Commission: ‘United States Nuclear Regulatory Commission Package Performance Study Test Protocols’, NUREG 1768, US Nuclear Regulatory Commission, Washington, DC, USA, 2003.
- Ammerman DJ and Gwinn KW: ‘Collapse of the Cypress Street Viaduct—effect on a postulated spent fuel truck cask’, Proc. 45th Institute of Nuclear Materials Management Annual Meeting, Orlando, FL, USA, August 2004, Institute of Nuclear Materials Management, paper No. 304.
- Ammerman DJ, Stevens D and Barsotti M: ‘Numerical analyses of locomotive impacts on a spent fuel truck cask and trailer’, Proc. Am. Soc. Mech. Eng. Press. Vessels Pip. Conf., Denver, CO, USA, July 2005, paper No. PVP2005-71729.