References
- Marshall WJ and Wagner JC: ‘Impact of fuel failure on criticality safety of used nuclear fuel’, Proc. Conf. PSAM11, Helsinki, Finland, June 2012, Curran Associates, Inc. 16BS–We3–4.
- Marshall WJ and Wagner JC: ‘Consequences of fuel failure on criticality safety of used nuclear fuel’, ORNL/TM-2012/325, Oak Ridge National Laboratory, Oak Ridge, TN, USA, 2012.
- Elam KR, Wagner JC and Parks CV: ‘Effects of fuel failure on criticality safety and radiation dose for spent fuel casks’, NUREG/CR-6835, ORNL/TM-2002/255, Oak Ridge National Laboratory, Oak Ridge, TN, USA, 2003.
- Henderson DP: ‘Summary report of commercial reactor criticality data for LaSalle Unit 1’, B00000000-01717-5705-00138, Civilian Radioactive Waste Management System Management & Operating Contractor, OCRWM, Washington, DC, USA, 1999.
- Wagner JC and Parks CV: ‘Recommendations on the credit for cooling time in PWR burnup credit analysis’, NUREG/CR-6781 (ORNL/TM-2001/272), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge National Laboratory, Oak Ridge, TN, USA, 2003.
- Wagner JC: ‘Computational benchmark for estimation of reactivity margin from fission products and minor actinides in PWR burnup credit’, NUREG/CR-6747 (ORNL/TM-2000/306), prepared for the US Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge National Laboratory, Oak Ridge, TN, USA, 2001.
- ‘SCALE: a comprehensive modeling and simulation suite for nuclear safety analysis and design’, ORNL/TM-2005/39, Version 6.1, Oak Ridge National Laboratory, Oak Ridge, TN, USA, 2011.
- ‘Safety analysis report for the Holtec International Storage, Transport, and Repository Cask System (HI-STAR 100 Cask System)’, Table of Contents to Chapter 1, Holtec Report HI-951251, Revision 10, ADAMS Accession Number ML071940386, Holtec International, Jupiter, FL, USA, 2003.
- ‘Safety analysis report for the Holtec International Storage, Transport, and Repository Cask System (HI-STAR 100 Cask System)’, Chapter 2 through Chapter 4, Holtec Report HI-951251, Revision 10, ADAMS Accession Number ML071940391, Holtec International, Jupiter, FL, USA, 2003.
- ‘Safety analysis report for the Holtec International Storage, Transport, and Repository Cask System (HI-STAR 100 Cask System)’, Chapter 5 to end, Holtec Report HI-951251, Revision 10, ADAMS Accession Number ML071940408, Holtec International, Jupiter, FL, USA, 2003.
- Fennern LE: ‘ABWR seminar – reactor, core & neutronics’, GE Energy/Nuclear, US Department of Energy, Washington, DC, USA, available at: http://www.ne.doe.gov/np2010/pdfs/ABWRReactorCoreNeutronics.pdf (accessed 16 April 2012).
- Henderson DP: ‘Summary report of commercial reactor criticality data for quad cities unit 2’, B00000000-01717-5705-00096 Revision 01, Civilian Radioactive Waste Management System Management & Operating Contractor, OCRWM, Washington, DC, USA, 1999.
- Natrella MG: ‘Experimental statistics’, National Bureau of Standards Handbook 91; 1963, Ann Arbor, MI, University of Michigan Library.