Analysis of Anderson Acceleration on a Simplified Neutronics/Thermal Hydraulics System

Conference · Thu Jan 01 00:00:00 EST 2015

OSTI ID:1265290

Toth, Alex ^[1]; Kelley, C. T. ^[1]; Slattery, Stuart R ^[2]; Hamilton, Steven P ^[2]; Clarno, Kevin T ^[2]; Pawlowski, R. P. P. ^[3]

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1. North Carolina State University (NCSU), Raleigh
2. ORNL
3. Sandia National Laboratories (SNL)

ABSTRACT A standard method for solving coupled multiphysics problems in light water reactors is Picard iteration, which sequentially alternates between solving single physics applications. This solution approach is appealing due to simplicity of implementation and the ability to leverage existing software packages to accurately solve single physics applications. However, there are several drawbacks in the convergence behavior of this method; namely slow convergence and the necessity of heuristically chosen damping factors to achieve convergence in many cases. Anderson acceleration is a method that has been seen to be more robust and fast converging than Picard iteration for many problems, without significantly higher cost per iteration or complexity of implementation, though its effectiveness in the context of multiphysics coupling is not well explored. In this work, we develop a one-dimensional model simulating the coupling between the neutron distribution and fuel and coolant properties in a single fuel pin. We show that this model generally captures the convergence issues noted in Picard iterations which couple high-fidelity physics codes. We then use this model to gauge potential improvements with regard to rate of convergence and robustness from utilizing Anderson acceleration as an alternative to Picard iteration.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Consortium for Advanced Simulation of LWRs (CASL)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC05-00OR22725
• OSTI ID: 1265290
• Resource Relation: Conference: NS MC2015 - Joint International Conference on Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method, Nashville, TN, USA, 20150419, 20150423
• Country of Publication: United States
• Language: English