4.5 Article

Continuous-energy Monte Carlo neutron transport on GPUs in the Shift code

期刊

ANNALS OF NUCLEAR ENERGY
卷 128, 期 -, 页码 236-247

出版社

PERGAMON-ELSEVIER SCIENCE LTD
DOI: 10.1016/j.anucene.2019.01.012

关键词

Radiation transport; Monte Carlo; GPU

资金

  1. Laboratory Directed Research and Development Program of Oak Ridge National Laboratory
  2. Exascale Computing Project (ECP) [17-SC-20-SC]
  3. Office of Science of the U.S. Department of Energy [DE-AC05-00OR22725]

向作者/读者索取更多资源

A continuous-energy Monte Carlo neutron transport solver executing on GPUs has been developed within the Shift code. Several algorithmic approaches are considered, including both history-based and event-based implementations. Unlike in previous work involving multigroup Monte Carlo transport, it is demonstrated that event-based algorithms significantly outperform a history-based approach for continuous-energy transport as a result of increased device occupancy and reduced thread divergence. Numerical results are presented for detailed full-core models of a small modular reactor (SMR), including a model containing depleted fuel materials. These results demonstrate the substantial gains in performance that are possible with the latest-generation of GPUs. On the depleted SMR core configuration, an NVIDIA P100 GPU with 56 streaming multiprocessors provides performance equivalent to 90 CPU cores, and the latest V100 GPU with 80 multiprocessors offers the performance of more than 150 CPU cores. (C) 2019 Elsevier Ltd. All rights reserved.

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