Enhancing the ABAQUS thermomechanics code to simulate multipellet steady and transient LWR fuel rod behavior
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[1] R. L. Stoute,et al. Heat transfer coefficient between UO 2 and Zircaloy-2 , 1962 .
[2] K. R. Anderson,et al. Characterization and modeling of creep mechanisms in Zircaloy-4 , 2006 .
[3] Donald R. Olander,et al. Fundamental Aspects of Nuclear Reactor Fuel Elements , 1976 .
[4] Alicia Denis,et al. Simulation of isothermal fission gas release , 1996 .
[5] H. Matzke,et al. A Pragmatic Approach to Modelling Thermal Conductivity of Irradiated UO2 Fuel. Review and Recommendations , 1996 .
[6] D. D. Lanning,et al. FRAPCON-3: A computer code for the calculation of steady-state, thermal-mechanical behavior of oxide fuel rods for high burnup , 1997 .
[7] Derek Gaston,et al. MOOSE: A parallel computational framework for coupled systems of nonlinear equations , 2009 .
[8] Derek Gaston,et al. COMPUTATIONAL FOUNDATIONS FOR REACTOR FUEL PERFORMANCE MODELING , 2009 .
[9] M. Limbäck,et al. A Model for Analysis of the Effect of Final Annealing on the In- and Out-of-Reactor Creep Behavior of Zircaloy Cladding , 1996 .
[10] Suzanne L. Holcombe. National Technical Information Service , 2008 .
[11] A. R. Massih,et al. Diffusion theory of fission gas migration in irradiated nuclear fuel UO2 , 1985 .
[12] Glen Hansen,et al. Three dimensional coupled simulation of thermomechanics, heat, and oxygen diffusion in UO2 nuclear fuel rods , 2009 .
[13] Glen Hansen,et al. An Implicit Solution Framework for Reactor Fuel Performance Simulation , 2009 .
[14] R. L. Williamson,et al. Simulating Dynamic Fracture in Oxide Fuel Pellets Using Cohesive Zone Models , 2009 .
[15] I O Jahlstrom. REVIEW AND RECOMMENDATIONS , 1965 .
[16] J. K. Fink,et al. Thermophysical properties of uranium dioxide , 2000 .
[17] M. E. Kassner,et al. Creep of zirconium and zirconium alloys , 2006 .
[18] D. Plancq,et al. Multidimensional modeling of a ramp test with the PWR fuel performance code ALCYONE , 2007 .
[19] Victor C. Strasburger,et al. Review and Recommendations , 1983 .
[20] Glen Hansen,et al. Fully-coupled engineering and mesoscale simulations of thermal conductivity in UO2 fuel using an implicit multiscale approach , 2009 .
[21] Van Uffelen Paul,et al. Enlargement and Integration Workshop - Towards Nuclear Fuel Modelling in the Various Reactor Types Across Europe with TRANSURANUS - 23-24 June 2005 - Prague, Czech Republic - Organized by Institute for Transuranium ITU Karlsruhe/Germany and Nuclear Research Institute Rez/Czech Republic , 2005 .