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    <identifier>10.57760/sciencedb.hjs.00167</identifier>
    <datestamp>2024-11-04T16:18:28Z</datestamp>
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  <dc:date>2024-11-04</dc:date>
  <dc:title>Analysis of CABRI-BI1 Loss of Flow Experiment based on ISAA-Na</dc:title>
  <dc:identifier>doi:10.57760/sciencedb.hjs.00167</dc:identifier>
  <dc:language>en</dc:language>
  <dc:description>[Background]: Sodium boiling is a critical transient phenomenon prior to severe accidents in sodium-cooled fast reactors. Accurate prediction of the two-phase state and thermodynamic parameters of the coolant during sodium boiling is essential for sodium-cooled fast reactors accident analysis. [Purpose]: This paper aims to develop a core thermal-hydraulic model for the sodium-cooled fast reactor integrated analysis program ISAA-Na, based on the multi-bubble liquid slug assumption. [Methods]: The ISAA-Na code was used to simulate and analyze the loss-of-flow experiment CABRI-BI1 (C&amp;oelig;ur &amp;agrave; Haut B&amp;ucirc;rnup Irradiation). [Results]: Comparison with experimental data shows that ISAA-Na provides more accurate predictions of coolant temperature and pressure prior to boiling compared to other codes such as SAS4A, ASTEC-Na, and SIMMER. However, after the onset of boiling, overestimations of bubble growth rate and two-phase interface movement were observed due to the lack of fuel melting and cladding failure models. [Conclusions]: Overall, the application of the multi-bubble liquid slug boiling model in ISAA-Na for the analysis of the CABRI-BI1 experiment is deemed reasonable and reliable.</dc:description>
  <dc:subject>Sodium fast reactor; CABRI experiment; Loss of flow; ISAA-Na</dc:subject>
  <dc:creator>Tang Shaowei</dc:creator>
  <dc:creator>Zhang Bin</dc:creator>
  <dc:rights>PUBLIC</dc:rights>
  <dc:rights>https://creativecommons.org/licenses/by-nc-sa/4.0/</dc:rights>
  <dc:type>dataset</dc:type>
  <dc:publisher>Science Data Bank</dc:publisher>
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