Applying nonlinear diffusion acceleration to the neutron transport k-Eigenvalue problem with anisotropic scattering

Journal Article · 31 October 2015 · Nuclear Science and Engineering

DOI: https://doi.org/10.13182/NSE14-131 · OSTI ID:1246339

Willert, Jeffrey ^[1]; Park, H. ^[1]; Taitano, William ^[1]

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1. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

High-order/low-order (or moment-based acceleration) algorithms have been used to significantly accelerate the solution to the neutron transport k-eigenvalue problem over the past several years. Recently, the nonlinear diffusion acceleration algorithm has been extended to solve fixed-source problems with anisotropic scattering sources. In this paper, we demonstrate that we can extend this algorithm to k-eigenvalue problems in which the scattering source is anisotropic and a significant acceleration can be achieved. Lastly, we demonstrate that the low-order, diffusion-like eigenvalue problem can be solved efficiently using a technique known as nonlinear elimination.

• Research Organization: Los Alamos National Laboratory (LANL)
• Sponsoring Organization: USDOE
• Grant/Contract Number: AC52-06NA25396
• OSTI ID: 1246339
• Report Number(s): LA-UR-14-28681
• Journal Information: Nuclear Science and Engineering, Journal Name: Nuclear Science and Engineering Journal Issue: 3 Vol. 181; ISSN 0029-5639
• Country of Publication: United States
• Language: English