A new procedure for solving steady-state and transient-state nonlinear radial conduction problems of nuclear fuel rods

A practical method for numerical evaluation of solutions of partial differential equations of the heat-conduction type

J Crank, P. Nicolson · Mathematical Proceedings of the Cambridge Philosophical Society · 1947 · 3.3K citations

Natural Sciences, Mathematics, Physics +17

A pragmatic approach to modelling thermal conductivity of irradiated UO2 fuel: Review and recommendations

P.G. Lucuta, Hj. Matzke, I.J. Hastings · Journal of Nuclear Materials · 1996 · 305 citations

Engineering, Materials Engineering, Materials Science +16

FRAP-T6: A computer code for the transient analysis of oxide fuel rods

L.J. Siefken, G.A. Berna, V.N. Shah · Nuclear Engineering and Design · 1985 · 114 citations · Full text

Engineering, Computational Engineering, Mechanical Engineering +11

Three dimensional coupled simulation of thermomechanics, heat, and oxygen diffusion in nuclear fuel rods

Chris Newman, Glen Hansen, Derek Gaston · Journal of Nuclear Materials · 2009 · 81 citations

Engineering, Mechanical Engineering, Nuclear Engineering +14

Simulations of heat and oxygen diffusion in UO2 nuclear fuel rods

Juan C. Ramirez, Marius Stan, Paul Dan Cristea · Journal of Nuclear Materials · 2006 · 74 citations

Engineering, Materials Engineering, Nuclear Engineering +14