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    <identifier>10.57760/sciencedb.16182</identifier>
    <datestamp>2024-02-28T10:22:17Z</datestamp>
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  <dc:date>2024-02-28</dc:date>
  <dc:title>Plutonium utilization in a Small Modular Molten-salt Reactor based on a batch fuel reprocessing scheme</dc:title>
  <dc:identifier>doi:10.57760/sciencedb.16182</dc:identifier>
  <dc:language>en</dc:language>
  <dc:description>In this study, we aim to verify the feasibility of a small modular MSR that utilizes plutonium as the starting fuel (SM-MSR-Pu), and highlight its advantages and disadvantages. First, the structural design and fuel management scheme of the SM-MSR-Pu were presented. Second, the neutronic characteristics, such as the graphite-irradiation lifetime, burn-up performance, and coefficient of temperature reactivity were calculated to analyze the physical characteristics of the SM-MSR-Pu. </dc:description>
  <dc:subject>Molten salt fuel; plutonium utilization; 233U production; TRUs mole fraction; temperature feedback coefficient</dc:subject>
  <dc:creator>赵学超</dc:creator>
  <dc:rights>RESTRICTED</dc:rights>
  <dc:type>dataset</dc:type>
  <dc:relation>http://www.doi.org/10.1007/s41365-024-01428-y</dc:relation>
  <dc:publisher>Science Data Bank</dc:publisher>
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