Enhancing the ABAQUS thermomechanics code to simulate multipellet steady and transient LWR fuel rod behavior

A powerful multidimensional fuels performance capability, applicable to both steady and transient fuel behavior, is developed based on enhancements to the commercially available ABAQUS general-purpose thermomechanics code. Enhanced capabilities are described, including: UO2 temperature and burnup dependent thermal properties, solid and gaseous fission product swelling, fuel densification, fission gas release, cladding thermal and irradiation creep, cladding irradiation growth , gap heat transfer, and gap/plenum gas behavior during irradiation. The various modeling capabilities are demonstrated using a 2D axisymmetric analysis of the upper section of a simplified multi-pellet fuel rod, during both steady and transient operation. Computational results demonstrate the importance of a multidimensional fully-coupled thermomechanics treatment. Interestingly, many of the inherent deficiencies in existing fuel performance codes (e.g., 1D thermomechanics, loose thermo-mechanical coupling, separate steady and transient analysis, cumbersome pre- and post-processing) are, in fact, ABAQUS strengths.

[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 .