Nonlinear Diffusion Acceleration Method with Multigrid in Energy for k-Eigenvalue Neutron Transport Problems-Reference-Cited by-同舟云学术

Nonlinear Diffusion Acceleration Method with Multigrid in Energy for k-Eigenvalue Neutron Transport Problems

Published:2016-12 Issue:4 Volume:184 Page:514-526
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Cornejo Luke R.¹,Anistratov Dmitriy Y.¹

Affiliation:

1. North Carolina State University, Department of Nuclear Engineering, Raleigh, North Carolina

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NSE16-78

Reference2 articles.

1. “SCALE: A Comprehensive Modeling and Simulation Suite for Nuclear Safety Analysis and Design,” ORNL/TM-2005/39, Version 6.1, Oak Ridge National Laboratory (2011).

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