참고문헌
- D. Lanning, C. Beyer, Estimated Maximum Cladding Stresses for Bounding PWR Fuel Rods during Short Term Operations for Dry Cask Storage, Pacific Northwest National Laboratory, Richland, WA, 2004.
- "Interim Staff Guidance - 11, Cladding Considerations for the Transportation and Storage of Spent Fuel, Revision 3" Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, Spent Fuel Project Office, 2003.
- S.R. Greene, J.S. Medford, S.A. Macy, Storage and Transport Cask Data for Used Commercial Nuclear Fuel, 2013. ATI-TR-13047.
- K.J. Geelhood, W.G. Luscher, P.A. Raynaud, I.E. Porter, FRAPCON-4.0: a Computer Code for the Calculation of Steady-state, Thermal-Mechanical Behavior of Oxide Fuel Rods for High Burnup, Pacific Northwest National Laboratory, Richland, WA, 2015. PNNL-19417, Vol. 1 Rev. 2.
- K.J. Geelhood, C. Beyer, Used Nuclear Fuel Loading and Structural Performance under Normal Conditions of Transport - Supporting Material Properties and Modeling Inputs, U.S. Department of Energy, Used Fuel Disposition Campaign, 2013. FCRD-UFD-2013-20000123.
- "Standard Review Plan for Spent Fuel Storage Systems at a General License Facility," Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, 2010. NUREG-1536 Rev. 1.
- J.A. Fort, T.E. Michener, S.R. Suffield, D.J. Richmond, Thermal Modeling of a Loaded MAGNASTOR Storage System at Catawba Nuclear Station, U.S. Department of Energy, Used Fuel Disposition Campaign, 2016. FCRD-UFD-2016-20000068, PNNL-25871.
- J.B. Minne, et al. Specific Aspects of Internal Corrosion of Nuclear Cladding Made of Zircaloy, EDF R&D, France
- L. Desgranges, Internal corrosion layer in PWR fuel, in: OECD/NEA Seminar Proceedings, Thermal Performance of High Burn-up LWR Fuel. Cadarache, France, 1988.
- R.N. Bratton, M.A. Jessee, W.A. Wieselquist, Rod Internal Pressure Quantification and Distribution Analysis Using FRAPCON, U.S. Department of Energy, Used Fuel Disposition Campaign, 2015. ORNL/TM-2015/557, FCRD-UFD-2015-20000636.
- "End-of-Life Rod Internal Pressures in Spent Pressurized Water Reactor Fuel", EPRI, Palo Alto, CA, 2013, 3002001949.
피인용 문헌
- Improvement of delayed hydride cracking assessment of PWR spent fuel during dry storage vol.52, pp.3, 2018, https://doi.org/10.1016/j.net.2019.07.036