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    <responseDate>2026-10-14T20:35:43Z</responseDate>
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    <identifier>10.57760/sciencedb.010vc</identifier>
    <datestamp>2026-09-03T13:29:29Z</datestamp>
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  <dc:date>2026-09-03</dc:date>
  <dc:title>Dataset for Event-based GPU neutron transport and mesh tally methods for fixed-source Monte Carlo calculations in RMC</dc:title>
  <dc:identifier>doi:10.57760/sciencedb.010vc</dc:identifier>
  <dc:language>en</dc:language>
  <dc:description>This dataset provides the supporting data for the paper Event-based GPU neutron transport and mesh tally methods for fixed-source Monte Carlo calculations in RMC. It includes fixed-source Monte Carlo transport-performance data and batch-statistics analysis results for one helium-cooled ceramic breeder blanket (HCCB) model and two deep-penetration radiation shielding models. The performance data provide the transport times of the single-core CPU history-based algorithm and the single-GPU event-based algorithm, together with the corresponding GPU speedups, for total source particle populations ranging from 106 to 107.A maximum GPU particle-batch size of 107 was used for the CPU&amp;ndash;GPU performance comparisons. The batch-statistics data provide the relative errors obtained with the conventional CPU per-history mesh tally and with GPU batch statistics using 10, 100, and 1000 statistical batches for each mesh cell, enabling analysis of the influence of the number of statistical batches on relative-error estimation.</dc:description>
  <dc:subject>Monte Carlo; GPU; neutron transport</dc:subject>
  <dc:creator>Binji Wang</dc:creator>
  <dc:creator>Shichang Liu</dc:creator>
  <dc:rights>RESTRICTED</dc:rights>
  <dc:type>dataset</dc:type>
  <dc:publisher>Science Data Bank</dc:publisher>
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