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    <identifier>10.57760/sciencedb.j00186.00091</identifier>
    <datestamp>2024-05-07T12:17:04Z</datestamp>
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  <dc:date>2024-05-07</dc:date>
  <dc:title>Data of 'Preliminary safety analysis for heavy-water-moderated molten-salt reactor'</dc:title>
  <dc:identifier>doi:10.57760/sciencedb.j00186.00091</dc:identifier>
  <dc:language>en</dc:language>
  <dc:description>For transient calculations, &amp;nbsp;the code of HWMSR-2D is used to bring the reactor to steady state, after which various transient reactions are introduced, as detailed in the paper (Gaoang Wen,Jianhui Wu,Chunyan Zou,Xiangzhou Cai,Jingen Chen,Man Bao.(2024).Preliminary safety analysis for heavy-water-moderated molten-salt reactor.Nuclear Science and Techniques.doi:10.12074/202404.00319V1). In data processing, transients are introduced at 0 seconds, steady-state data is removed, and Origin software is used for plotting.For steady-state calculations, as mentioned in the paper, the fuel salt pipes are divided into 9 groups and longitudinally divided into 60 parts to provide convenient grid calculations.</dc:description>
  <dc:subject>heavy-water-moderated molten-salt reactor; Neutronics and thermal-hydraulics coupling; Transient analysis; Accident analysis</dc:subject>
  <dc:creator>Gaoang Wen</dc:creator>
  <dc:rights>PUBLIC</dc:rights>
  <dc:rights>https://creativecommons.org/licenses/by/4.0/</dc:rights>
  <dc:type>dataset</dc:type>
  <dc:relation>http://www.doi.org/https://doi.org/10.1007/s41365-024-01476-4</dc:relation>
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