References
- K.J. Geelhood, W.G. Luscher, C.E. Beyer, FRAPCON-3.4: a Computer Code for the Calculation of Steady-state, Thermalemechanical Behavior of Oxide Fuel Rods for High-burnup, NUREG/CR-7022, vol. 1, 2011.
- C.M. Allison, G.A. Berna, R. Chambers, E.W. Coryell, K.L. Davis, D.L. Hagrman, D.T. Hagrman, N.L. Hampton, J.K. Hohorst, R.E. Mason, M.L. McComas, K.A. McNeil, R.L. Miller, C.S. Olsen, G.A. Reymann, L.J. Siefken, SCDAP/RELAP/MOD3.1 Code Manual, Volume: MATPROda library of materials properties for light-water-reactor Accident Analysis, NUREG/CR-6150, EGG-2720 4, November 1993.
- Final Safety Analysis Report (FSAR), BUSHEHR VVER-1000 reactor, Ministry of Russian Federation of Atomic Energy (Atomenergoproekt), Moscow, 2003.
- MATLAB and Statistics Toolbox Release, The MathWorks, Inc, Natick, MA, USA, 2012b.
- N.E. Todreas, M.S. Kazimi, Nuclear Systems Volume 1: Thermal Hydraulic Fundamentals, 2011.
- Y. Yuan, The Design of High Power Density Annular Fuel for LWRs, Massachusetts Institute of Technology, 2006.
- J. Weisman, Comparison of pellet-cladding mechanical interaction for zircaloy and silicon carbide clad Fuel rods in pressurized water reactors, 2003.
- H.S. Aybar, P. Ortego, A review of nuclear fuel performance codes, Prog. Nucl. Energy 46 (2005) 127-141. https://doi.org/10.1016/j.pnucene.2005.01.004
- D.M. Carpenter, Assessment of innovative Fuel designs for high performance light water reactors, M.S. Thesis, Massachusetts Institute of Technology, June 2006.
- K.J. Lanning, G.A. Berna, C.E. Beyer, FRAPCON-3: integral Assessment, NUREG/CR-6534 vol. 3, Taylor & Francis, December 1997.
- IAEA-TECDOC-1496, Thermophysical properties database of materials for light water reactors and heavy water reactors, June 2006, p. 125.
-
P.G. Lucuta, H.S. Matzke, I.J. Hastings, A pragmatic approach to modeling thermal conductivity of irradiated
$UO_2$ fuel: review and recommendations, J. Nucl. Mater. 232 (1996), pp. 166-180. https://doi.org/10.1016/S0022-3115(96)00404-7