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The material-region-based 2D/1D transport method

  • Published:2019-06 Issue: Volume:128 Page:1-11
  • ISSN:0306-4549
  • Container-title:Annals of Nuclear Energy
  • language:en
  • Short-container-title:Annals of Nuclear Energy

Author:

Liu Zhouyu,Zhao Chen,Cao Lu,Wu Hongchun,Cao LiangzhiORCID

Funder

National Natural Science Foundation of China

Science Challenge Program

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference21 articles.

1. Development and Verifications of the High-fidelity Neutronics Code NECP-X;Chen,2017

2. A new high-fidelity neutronics code NECP-X;Chen;Ann. Nucl. Energy,2018

3. Fusion of method of characteristics and nodal method for 3-D whole-core transport calculation;Cho;Trans. Am. Nucl. Soc.,2002

4. Assessment of the 2D/1D implementation in MPACT;Collins,2014

5. Stability and accuracy of 3D neutron transport simulations using the 2D/1D method in MPACT;Collins;J. Comput. Phys.,2016

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