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    <identifier>10.11922/sciencedb.j00113.00015</identifier>
    <datestamp>2022-04-22T15:19:55Z</datestamp>
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  <dc:date>2022-04-22</dc:date>
  <dc:title>Measurement of 232Th (n,&amp;gamma;) cross section at the CSNS Back-n facility in the unresolved resonance region from 4 keV to 100 keV</dc:title>
  <dc:identifier>doi:10.11922/sciencedb.j00113.00015</dc:identifier>
  <dc:language>en</dc:language>
  <dc:description>The data related to the article &amp;quot;Measurement of 232Th (n,&amp;gamma;) cross section at the CSNS Back-n facility in the unresolved resonance region from 4 keV to 100 keV&amp;quot; submitted to the journal of Chinese Physics B. The neutron capture cross section of 232Th was measured at the neutron time-of-flight facility Back-n of China Spallation Neutron Source (CSNS) for the first time. The measurement was performed with 4 hydrogen-free deuterated benzene C6D6 liquid scintillation detectors, in the ES#2 experiment station on the beam line, at a distance of about 76 m from the neutron-production assembly. The total energy detection principle in combination with the Pulse Height Weighting Technique (PHWT) was applied to analyze the measured data. Results of the 232Th (n,&amp;gamma;) reaction cross section in the unresolved resonance region from 4 keV to 100 keV are obtained, which shows a good agreement with the existing experimental data from EXFOR, as well as with the evaluated data from the ENDF/B-VIII.0 and CENDL-3.1. In addition, the excitation function of 232Th (n,&amp;gamma;)233Th reaction in the unresolved resonance region was theoretically calculated by using the code TALYS-1.95. The data files consists of 2 separate Excel files, which are obtained from the analysis results of experimental data, the related simulation results, and the public databases ENDF/B VIII-0, CENDL-3.1, and EXFOR. The details are described as follows:&amp;nbsp;Cross_sec.xlsx : Energy-cross section data from present measurement, the public EXFOR database, ENDF/B-VIII.0 database, CENDL-3.1 database, and TALYS calculation.Detector_eff.xlsx : Simulation results of the C6D6 detector efficiency from GEANT4 tookit. See the article for more details.</dc:description>
  <dc:subject>232Th neutron capture cross section; Unresolved resonance region;  CSNS Back-n facility; C6D6 detectors</dc:subject>
  <dc:creator>Bing Jiang</dc:creator>
  <dc:creator>Jianlong Han</dc:creator>
  <dc:creator>Jie Ren</dc:creator>
  <dc:creator>Wei Jiang</dc:creator>
  <dc:creator>Xiaohe Wang</dc:creator>
  <dc:creator>Zian Guo</dc:creator>
  <dc:creator>Jianglin Zhang</dc:creator>
  <dc:creator>Jifeng Hu</dc:creator>
  <dc:creator>Jingen Chen</dc:creator>
  <dc:creator>Xiangzhou Cai</dc:creator>
  <dc:creator>Hongwei Wang</dc:creator>
  <dc:creator>Longxiang Liu</dc:creator>
  <dc:creator>Xinxiang Li</dc:creator>
  <dc:creator>Xinrong Hu</dc:creator>
  <dc:creator>Yue Zhang</dc:creator>
  <dc:rights>PUBLIC</dc:rights>
  <dc:rights>https://creativecommons.org/publicdomain/zero/1.0/</dc:rights>
  <dc:type>dataset</dc:type>
  <dc:relation>http://www.doi.org/10.1088/1674-1056/ac5394</dc:relation>
  <dc:publisher>Chinese Physics B</dc:publisher>
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