Nuclear Science and Engineering / Volume 192 / Number 2 / November 2018 / Pages 208-217
Technical Paper / dx.doi.org/10.1080/00295639.2018.1499338
We present a local adaptive diffusion synthetic acceleration (DSA) method for neutron transport calculations. This new DSA method, called DG-DSA, solves the diffusion equation on a coarse mesh using the interior penalty discontinuous Galerkin (DG) methods. We investigate various numerical aspects of the DG-DSA method such as convergence performance and local adaptation. We demonstrate that our DG-DSA method can effectively and efficiently accelerate transport source iterations.