<p>The neutron capture cross section for <InlineEquation ID="IEq3"> <InlineMediaObject> <ImageObject Color="BlackWhite" FileRef="41365_2025_1763_Article_IEq1.gif" Format="GIF" Height="10" Rendition="HTML" Resolution="72" Type="Linedraw" Width="19" /> </InlineMediaObject> <EquationSource Format="TEX">\(^{165}\)</EquationSource> <EquationSource Format="MATHML"><math> <mmultiscripts> <mrow /> <mrow /> <mn>165</mn> </mmultiscripts> </math></EquationSource> </InlineEquation>Ho was measured at the backstreaming white neutron beam line (Back-n) of the China Spallation Neutron Source (CSNS) using total energy detection systems, composed of a set of four C<InlineEquation ID="IEq4"> <InlineMediaObject> <ImageObject Color="BlackWhite" FileRef="41365_2025_1763_Article_IEq4.gif" Format="GIF" Height="10" Rendition="HTML" Resolution="72" Type="Linedraw" Width="8" /> </InlineMediaObject> <EquationSource Format="TEX">\(_6\)</EquationSource> <EquationSource Format="MATHML"><math> <mmultiscripts> <mrow /> <mn>6</mn> <mrow /> </mmultiscripts> </math></EquationSource> </InlineEquation>D<InlineEquation ID="IEq5"> <InlineMediaObject> <ImageObject Color="BlackWhite" FileRef="41365_2025_1763_Article_IEq4.gif" Format="GIF" Height="10" Rendition="HTML" Resolution="72" Type="Linedraw" Width="8" /> </InlineMediaObject> <EquationSource Format="TEX">\(_6\)</EquationSource> <EquationSource Format="MATHML"><math> <mmultiscripts> <mrow /> <mn>6</mn> <mrow /> </mmultiscripts> </math></EquationSource> </InlineEquation> scintillator detectors coupled with pulse height weighting techniques. The resonance parameters were extracted using the multilevel multichannel R-matrix code SAMMY to fit the measured capture yields of the <InlineEquation ID="IEq6"> <InlineMediaObject> <ImageObject Color="BlackWhite" FileRef="41365_2025_1763_Article_IEq1.gif" Format="GIF" Height="10" Rendition="HTML" Resolution="72" Type="Linedraw" Width="19" /> </InlineMediaObject> <EquationSource Format="TEX">\(^{165}\)</EquationSource> <EquationSource Format="MATHML"><math> <mmultiscripts> <mrow /> <mrow /> <mn>165</mn> </mmultiscripts> </math></EquationSource> </InlineEquation>Ho(n,<InlineEquation ID="IEq7"> <InlineMediaObject> <ImageObject Color="BlackWhite" FileRef="41365_2025_1763_Article_IEq7.gif" Format="GIF" Height="12" Rendition="HTML" Resolution="72" Type="Linedraw" Width="13" /> </InlineMediaObject> <EquationSource Format="TEX">\(\gamma \)</EquationSource> <EquationSource Format="MATHML"><math> <mi>γ</mi> </math></EquationSource> </InlineEquation>) reaction in the neutron energy range below 100 eV. Subsequently, the resonance region’s capture cross sections were reconstructed based on the obtained parameters. Furthermore, the unresolved resonance average cross section of the <InlineEquation ID="IEq8"> <InlineMediaObject> <ImageObject Color="BlackWhite" FileRef="41365_2025_1763_Article_IEq1.gif" Format="GIF" Height="10" Rendition="HTML" Resolution="72" Type="Linedraw" Width="19" /> </InlineMediaObject> <EquationSource Format="TEX">\(^{165}\)</EquationSource> <EquationSource Format="MATHML"><math> <mmultiscripts> <mrow /> <mrow /> <mn>165</mn> </mmultiscripts> </math></EquationSource> </InlineEquation>Ho(n,<InlineEquation ID="IEq9"> <InlineMediaObject> <ImageObject Color="BlackWhite" FileRef="41365_2025_1763_Article_IEq7.gif" Format="GIF" Height="12" Rendition="HTML" Resolution="72" Type="Linedraw" Width="13" /> </InlineMediaObject> <EquationSource Format="TEX">\(\gamma \)</EquationSource> <EquationSource Format="MATHML"><math> <mi>γ</mi> </math></EquationSource> </InlineEquation>) reaction was determined relative to that of the standard sample <InlineEquation ID="IEq10"> <InlineMediaObject> <ImageObject Color="BlackWhite" FileRef="41365_2025_1763_Article_IEq10.gif" Format="GIF" Height="10" Rendition="HTML" Resolution="72" Type="Linedraw" Width="19" /> </InlineMediaObject> <EquationSource Format="TEX">\(^{197}\)</EquationSource> <EquationSource Format="MATHML"><math> <mmultiscripts> <mrow /> <mrow /> <mn>197</mn> </mmultiscripts> </math></EquationSource> </InlineEquation>Au within the neutron energy range of 2 keV to 1 MeV. The experimental data were compared with the recommended nuclear data from the ENDF/B-VIII.0 library, as well as with results of calculations performed using the TALYS<InlineEquation ID="IEq11"> <InlineMediaObject> <ImageObject Color="BlackWhite" FileRef="41365_2025_1763_Article_IEq11.gif" Format="GIF" Height="13" Rendition="HTML" Resolution="72" Type="Linedraw" Width="19" /> </InlineMediaObject> <EquationSource Format="TEX">\(-\)</EquationSource> <EquationSource Format="MATHML"><math> <mo>-</mo> </math></EquationSource> </InlineEquation>1.9 code. The comparison revealed agreement between the measured <InlineEquation ID="IEq12"> <InlineMediaObject> <ImageObject Color="BlackWhite" FileRef="41365_2025_1763_Article_IEq1.gif" Format="GIF" Height="10" Rendition="HTML" Resolution="72" Type="Linedraw" Width="19" /> </InlineMediaObject> <EquationSource Format="TEX">\(^{165}\)</EquationSource> <EquationSource Format="MATHML"><math> <mmultiscripts> <mrow /> <mrow /> <mn>165</mn> </mmultiscripts> </math></EquationSource> </InlineEquation>Ho(n,<InlineEquation ID="IEq13"> <InlineMediaObject> <ImageObject Color="BlackWhite" FileRef="41365_2025_1763_Article_IEq7.gif" Format="GIF" Height="12" Rendition="HTML" Resolution="72" Type="Linedraw" Width="13" /> </InlineMediaObject> <EquationSource Format="TEX">\(\gamma \)</EquationSource> <EquationSource Format="MATHML"><math> <mi>γ</mi> </math></EquationSource> </InlineEquation>) cross sections and these data. The present results are crucial for evaluating the <InlineEquation ID="IEq14"> <InlineMediaObject> <ImageObject Color="BlackWhite" FileRef="41365_2025_1763_Article_IEq1.gif" Format="GIF" Height="10" Rendition="HTML" Resolution="72" Type="Linedraw" Width="19" /> </InlineMediaObject> <EquationSource Format="TEX">\(^{165}\)</EquationSource> <EquationSource Format="MATHML"><math> <mmultiscripts> <mrow /> <mrow /> <mn>165</mn> </mmultiscripts> </math></EquationSource> </InlineEquation>Ho neutron capture cross section and thus enhance the quality of evaluated nuclear data libraries. They provide valuable guidance for nuclear theoretical models and nuclear astrophysical studies.</p>

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New measurement of \(^{165}\)Ho neutron capture cross sections

  • Su-Ya-La-Tu Zhang,
  • Yong-Shun Huang,
  • Wei Jiang,
  • Jie Ren,
  • Rui-Rui Fan,
  • De-Xin Wang,
  • Chun-Lei Zhang,
  • Guo Li,
  • Dan-Dan Niu,
  • Mei-Rong Huang

摘要

The neutron capture cross section for \(^{165}\) 165 Ho was measured at the backstreaming white neutron beam line (Back-n) of the China Spallation Neutron Source (CSNS) using total energy detection systems, composed of a set of four C \(_6\) 6 D \(_6\) 6 scintillator detectors coupled with pulse height weighting techniques. The resonance parameters were extracted using the multilevel multichannel R-matrix code SAMMY to fit the measured capture yields of the \(^{165}\) 165 Ho(n, \(\gamma \) γ ) reaction in the neutron energy range below 100 eV. Subsequently, the resonance region’s capture cross sections were reconstructed based on the obtained parameters. Furthermore, the unresolved resonance average cross section of the \(^{165}\) 165 Ho(n, \(\gamma \) γ ) reaction was determined relative to that of the standard sample \(^{197}\) 197 Au within the neutron energy range of 2 keV to 1 MeV. The experimental data were compared with the recommended nuclear data from the ENDF/B-VIII.0 library, as well as with results of calculations performed using the TALYS \(-\) - 1.9 code. The comparison revealed agreement between the measured \(^{165}\) 165 Ho(n, \(\gamma \) γ ) cross sections and these data. The present results are crucial for evaluating the \(^{165}\) 165 Ho neutron capture cross section and thus enhance the quality of evaluated nuclear data libraries. They provide valuable guidance for nuclear theoretical models and nuclear astrophysical studies.