A geometry conforming isogeometric method for the self-adjoint angular flux (SAAF) form of the neutron transport equation with a discrete ordinate (SN) angular discretisation

Abstract This paper presents the application of isogeometric analysis (IGA) to the spatial discretisation of the multi-group, self-adjoint angular flux (SAAF) form of the neutron transport equation with a discrete ordinate ( S N ) angular discretisation. The IGA spatial discretisation is based upon non-uniform rational B-spline (NURBS) basis functions for both the test and trial functions. In addition a source iteration compatible maximum principle is used to derive the IGA spatially discretised SAAF equation. It is demonstrated that this maximum principle is mathematically equivalent to the weak form of the SAAF equation. The rate of convergence of the IGA spatial discretisation of the SAAF equation is analysed using a method of manufactured solutions (MMS) verification test case. The results of several nuclear reactor physics verification benchmark test cases are analysed. This analysis demonstrates that for higher-order basis functions, and for the same number of degrees of freedom, the FE based spatial discretisation methods are numerically less accurate than IGA methods. The difference in numerical accuracy between the IGA and FE methods is shown to be because of the higher-order continuity of NURBS basis functions within a NURBS patch as well as the preservation of both the volume and surface area throughout the solution domain within the IGA spatial discretisation. Finally, the numerical results of applying the IGA SAAF method to the OECD/NEA, seven-group, two-dimensional C5G7 quarter core nuclear reactor physics verification benchmark test case are presented. The results, from this verification benchmark test case, are shown to be in good agreement with solutions of the first-order form as well as the second-order even-parity form of the neutron transport equation for the same order of discrete ordinate ( S N ) angular approximation.

[1]  Jim E. Morel,et al.  A Self-Adjoint Angular Flux Equation , 1999 .

[2]  T. Hughes,et al.  Isogeometric analysis : CAD, finite elements, NURBS, exact geometry and mesh refinement , 2005 .

[3]  Victor M. Calo,et al.  The cost of continuity: A study of the performance of isogeometric finite elements using direct solvers , 2012 .

[4]  J. Kraus,et al.  Multigrid methods for isogeometric discretization , 2013, Computer methods in applied mechanics and engineering.

[5]  J. A. Welch,et al.  Isogeometric analysis for the multigroup neutron diffusion equation with applications in reactor physics , 2017 .

[6]  R. P. Smedley-Stevenson,et al.  Streamline upwind Petrov–Galerkin methods for the steady-state Boltzmann transport equation , 2006 .

[7]  R. G. McClarren,et al.  On the Use of Symmetrized Transport Equation in Goal-Oriented Adaptivity , 2016 .

[8]  Giancarlo Sangalli,et al.  Fast formation of isogeometric Galerkin matrices by weighted quadrature , 2016, 1605.01238.

[9]  Alessandro Reali,et al.  Isogeometric Analysis of Structural Vibrations , 2006 .

[10]  John A. Evans,et al.  Bézier projection: A unified approach for local projection and quadrature-free refinement and coarsening of NURBS and T-splines with particular application to isogeometric design and analysis , 2014, 1404.7155.

[11]  Ernest Mund Spectral element solutions for the PN neutron transport equations , 2011 .

[12]  Jim E. Morel,et al.  The DANTE Boltzmann transport solver: An unstructured mesh, 3-D, spherical harmonics algorithm compatible with parallel computer architectures , 1997 .

[13]  Abdolhamid Minuchehr,et al.  Spatially adaptive hp refinement approach for PN neutron transport equation using spectral element method , 2015 .

[14]  Richard C. Martineau,et al.  Diffusion Acceleration Schemes for Self-Adjoint Angular Flux Formulation with a Void Treatment , 2014 .

[15]  C. Drumm,et al.  Discrete Ordinates Approximations to the First- and Second-Order Radiation Transport Equations , 2002 .

[16]  Jean-Yves Moller Eléments finis courbes et accélération pour le transport de neutrons , 2012 .

[17]  M. Eaton,et al.  An adaptive, hanging-node, discontinuous isogeometric analysis method for the first-order form of the neutron transport equation with discrete ordinate (SN) angular discretisation , 2017 .

[18]  Jean Ragusa,et al.  A Least-Squares Transport Equation Compatible with Voids , 2014 .

[19]  James J. Duderstadt,et al.  Finite element solutions of the neutron transport equation with applications to strong heterogeneities , 1977 .

[20]  Thomas J. R. Hughes,et al.  Isogeometric Analysis: Toward Integration of CAD and FEA , 2009 .

[21]  Les A. Piegl,et al.  The NURBS Book , 1995, Monographs in Visual Communication.

[22]  Taewan Noh,et al.  Spatial discretizations for self-adjoint forms of the radiative transfer equations , 2006, J. Comput. Phys..

[23]  Elmer E Lewis,et al.  Benchmark on deterministic 3-D MOX fuel assembly transport calculations without spatial homogenization , 2004 .

[24]  Ryan G. McClarren,et al.  An Accurate Globally Conservative Subdomain Discontinuous Least-Squares Scheme for Solving Neutron Transport Problems , 2016 .

[25]  A. R. Owens,et al.  A geometry preserving, conservative, mesh-to-mesh isogeometric interpolation algorithm for spatial adaptivity of the multigroup, second-order even-parity form of the neutron transport equation , 2017, J. Comput. Phys..

[26]  R. T. Ackroyd Least-squares derivation of extremum and weighted-residual methods for equations of reactor physics—I. The first-order Boltzmann equation and a first-order initial-value equation , 1983 .

[27]  E. Lewis,et al.  Computational Methods of Neutron Transport , 1993 .

[28]  Ryan G. McClarren,et al.  Globally Conservative, Hybrid Self-Adjoint Angular Flux and Least-Squares Method Compatible with Voids , 2016, 1605.05388.

[29]  Clemens Hofreither,et al.  Robust Multigrid for Isogeometric Analysis Based on Stable Splittings of Spline Spaces , 2016, SIAM J. Numer. Anal..

[30]  Piero Ravetto,et al.  The spectral element method for static neutron transport in AN approximation. Part II , 2013 .

[31]  Liangzhi Cao,et al.  A spherical harmonics—Finite element discretization of the self-adjoint angular flux neutron transport equation , 2007 .

[32]  Matthew D. Eaton,et al.  The application of isogeometric analysis to the neutron diffusion equation for a pincell problem with an analytic benchmark , 2012 .

[33]  J. Morel,et al.  Finite Element Solution of the Self-Adjoint Angular Flux Equation for Coupled Electron-Photon Transport , 1999 .

[34]  Thomas J. R. Hughes,et al.  Optimal and reduced quadrature rules for tensor product and hierarchically refined splines in isogeometric analysis , 2017 .

[35]  Luca F. Pavarino,et al.  BDDC PRECONDITIONERS FOR ISOGEOMETRIC ANALYSIS , 2013 .

[36]  Elmer E Lewis Second-Order Neutron Transport Methods , 2010 .

[37]  R. T. Ackroyd A finite element method for neutron transport—I. Some theoretical considerations , 1978 .

[38]  Melville Clark,et al.  The Variational Method Applied to the Monoenergetic Boltzmann Equation. Part I , 1963 .

[39]  A. R. Owens,et al.  Discontinuous isogeometric analysis methods for the first-order form of the neutron transport equation with discrete ordinate (SN) angular discretisation , 2016, J. Comput. Phys..

[40]  R. Martineau,et al.  A new mathematical adjoint for the modified SAAF-SN equations , 2015 .

[41]  Igor Zmijarevic,et al.  CRONOS2 and APOLL02 results for the NEA C5G7 MOX benchmark , 2004 .

[42]  P. Roache Code Verification by the Method of Manufactured Solutions , 2002 .

[43]  Roland Glowinski,et al.  An introduction to the mathematical theory of finite elements , 1976 .

[44]  Alessandro Reali,et al.  GeoPDEs: A research tool for Isogeometric Analysis of PDEs , 2011, Adv. Eng. Softw..

[45]  J. Lautard,et al.  MINARET, A DETERMINISTIC NEUTRON TRANSPORT SOLVER FOR NUCLEAR CORE CALCULATIONS , 2010 .

[46]  Derek Gaston,et al.  MOOSE: A parallel computational framework for coupled systems of nonlinear equations , 2009 .

[47]  John A. Evans,et al.  Isogeometric analysis using T-splines , 2010 .

[48]  R. T. Ackroyd,et al.  Finite Element Methods for Particle Transport: Applications to Reactor and Radiation Physics , 1997 .

[49]  W. H. Reed,et al.  Triangular mesh methods for the neutron transport equation , 1973 .

[50]  J. N. Reddy,et al.  Energy principles and variational methods in applied mechanics , 2002 .

[51]  Les A. Piegl,et al.  On NURBS: A Survey , 2004 .

[52]  A. R. Owens,et al.  Energy dependent mesh adaptivity of discontinuous isogeometric discrete ordinate methods with dual weighted residual error estimators , 2017, J. Comput. Phys..

[53]  R. P. Smedley-Stevenson,et al.  Space–time streamline upwind Petrov–Galerkin methods for the Boltzmann transport equation , 2006 .