skip to main content

DOE PAGESDOE PAGES

This content will become publicly available on October 12, 2016

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

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.
Authors:
 [1] ;  [1] ;  [1]
  1. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Publication Date:
OSTI Identifier:
1246339
Report Number(s):
LA-UR--14-28681
Journal ID: ISSN 0029-5639
Grant/Contract Number:
AC52-06NA25396
Type:
Accepted Manuscript
Journal Name:
Nuclear Science and Engineering
Additional Journal Information:
Journal Volume: 181; Journal Issue: 3; Journal ID: ISSN 0029-5639
Publisher:
American Nuclear Society
Research Org:
Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
Sponsoring Org:
USDOE
Country of Publication:
United States
Language:
English
Subject:
97 MATHEMATICS AND COMPUTING neutron transport; k-eigenvalue problem; moment-based acceleration; nonlinear diffusion acceleration; anisotropic scattering