Implementation and performance analysis of the massively parallel method of characteristics based on GPU

Author:

Song Peitao,Zhang Zhijian,Liang Liang,Zhang Qian,Zhao Qiang

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference22 articles.

1. Boyd, W.R., Smith, K., Forget, B., 2013. A massively parallel method of characteristics neutral particle transport code for GPUs. In: Proceedings of the International conference on mathematics and computational method applied to nuclear science and engineering (M&C 2013), Sun Valley, Idaho, USA, May 5–9.

2. The OpenMOC method of characteristics neutral particle transport code;Boyd;Ann. Nucl. Energy,2014

3. A framework for performance tuning and analysis on parallel computing platforms;Cehrke,2015

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

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

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1. A cyclic-track decomposition method for 3D MOC neutron transport simulation;Nuclear Engineering and Design;2024-06

2. ANT-MOC: Scalable Neutral Particle Transport Using 3D Method of Characteristics on Multi-GPU Systems;Proceedings of the International Conference for High Performance Computing, Networking, Storage and Analysis;2023-11-11

3. Analysis of the fine-mesh subgroup method and its feasible improvement;Frontiers in Energy Research;2023-01-06

4. Development of High-Fidelity Neutron Transport Solver of Alpha;Springer Proceedings in Physics;2023

5. Development and verification of a GPU-based MOC transient solver;Annals of Nuclear Energy;2022-09

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