<p><InlineEquation ID="IEq3"> <InlineMediaObject> <ImageObject Color="BlackWhite" FileRef="41365_2025_1754_Article_IEq3.gif" Format="GIF" Height="16" Rendition="HTML" Resolution="72" Type="Linedraw" Width="63" /> </InlineMediaObject> <EquationSource Format="TEX">\({^{147,149}{\textrm{Sm}}}\)</EquationSource> <EquationSource Format="MATHML"><math> <mrow> <mmultiscripts> <mrow /> <mrow /> <mrow> <mn>147</mn> <mo>,</mo> <mn>149</mn> </mrow> </mmultiscripts> <mtext>Sm</mtext> </mrow> </math></EquationSource> </InlineEquation> are slow neutron capture (s-process) nuclides in nuclear astrophysics, whose (n,<InlineEquation ID="IEq4"> <InlineMediaObject> <ImageObject Color="BlackWhite" FileRef="41365_2025_1754_Article_IEq4.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 are important input parameters in nucleosynthesis network calculations in the samarium (Sm) region. In addition, <InlineEquation ID="IEq5"> <InlineMediaObject> <ImageObject Color="BlackWhite" FileRef="41365_2025_1754_Article_IEq5.gif" Format="GIF" Height="16" Rendition="HTML" Resolution="72" Type="Linedraw" Width="42" /> </InlineMediaObject> <EquationSource Format="TEX">\({^{149}{\textrm{Sm}}}\)</EquationSource> <EquationSource Format="MATHML"><math> <mrow> <mmultiscripts> <mrow /> <mrow /> <mn>149</mn> </mmultiscripts> <mtext>Sm</mtext> </mrow> </math></EquationSource> </InlineEquation> is a fission product of <InlineEquation ID="IEq6"> <InlineMediaObject> <ImageObject Color="BlackWhite" FileRef="41365_2025_1754_Article_IEq6.gif" Format="GIF" Height="16" Rendition="HTML" Resolution="72" Type="Linedraw" Width="32" /> </InlineMediaObject> <EquationSource Format="TEX">\({^{235}{\textrm{U}}}\)</EquationSource> <EquationSource Format="MATHML"><math> <mrow> <mmultiscripts> <mrow /> <mrow /> <mn>235</mn> </mmultiscripts> <mtext>U</mtext> </mrow> </math></EquationSource> </InlineEquation> with a 1% yield, and its neutron resonance parameters play a critical role in reactor neutronics. According to the available nuclear evaluation databases, a significant disagreement has been observed in the resonance peaks of the <InlineEquation ID="IEq7"> <InlineMediaObject> <ImageObject Color="BlackWhite" FileRef="41365_2025_1754_Article_IEq3.gif" Format="GIF" Height="16" Rendition="HTML" Resolution="72" Type="Linedraw" Width="63" /> </InlineMediaObject> <EquationSource Format="TEX">\({^{147,149}{\textrm{Sm}}}\)</EquationSource> <EquationSource Format="MATHML"><math> <mrow> <mmultiscripts> <mrow /> <mrow /> <mrow> <mn>147</mn> <mo>,</mo> <mn>149</mn> </mrow> </mmultiscripts> <mtext>Sm</mtext> </mrow> </math></EquationSource> </InlineEquation> (n,<InlineEquation ID="IEq8"> <InlineMediaObject> <ImageObject Color="BlackWhite" FileRef="41365_2025_1754_Article_IEq4.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-sectional data within the energy range of 20–300&#xa0;eV. In this study, tutron capture cross section of a natural samarium target was measured at the back-streaming white neutron beamline of the China Spallation Neutron Source. The neutron capture yield was obtained, and the neutron resonance parameters for <InlineEquation ID="IEq10"> <InlineMediaObject> <ImageObject Color="BlackWhite" FileRef="41365_2025_1754_Article_IEq10.gif" Format="GIF" Height="16" Rendition="HTML" Resolution="72" Type="Linedraw" Width="42" /> </InlineMediaObject> <EquationSource Format="TEX">\({^{147}{\textrm{Sm}}}\)</EquationSource> <EquationSource Format="MATHML"><math> <mrow> <mmultiscripts> <mrow /> <mrow /> <mn>147</mn> </mmultiscripts> <mtext>Sm</mtext> </mrow> </math></EquationSource> </InlineEquation> at 107.0, 139.4, 241.7, and 257.3&#xa0;eV and <InlineEquation ID="IEq11"> <InlineMediaObject> <ImageObject Color="BlackWhite" FileRef="41365_2025_1754_Article_IEq5.gif" Format="GIF" Height="16" Rendition="HTML" Resolution="72" Type="Linedraw" Width="42" /> </InlineMediaObject> <EquationSource Format="TEX">\({^{149}{\textrm{Sm}}}\)</EquationSource> <EquationSource Format="MATHML"><math> <mrow> <mmultiscripts> <mrow /> <mrow /> <mn>149</mn> </mmultiscripts> <mtext>Sm</mtext> </mrow> </math></EquationSource> </InlineEquation> at 23.2, 24.6, 26.1, 28.0, 51.5, 75.2, 90.9, 125.3, and 248.4&#xa0;eV were extracted using the SAMMY code based on R-matrix theory. For the parameters <InlineEquation ID="IEq12"> <InlineMediaObject> <ImageObject Color="BlackWhite" FileRef="41365_2025_1754_Article_IEq12.gif" Format="GIF" Height="16" Rendition="HTML" Resolution="72" Type="Linedraw" Width="18" /> </InlineMediaObject> <EquationSource Format="TEX">\(\Gamma _{\textrm{n}}\)</EquationSource> <EquationSource Format="MATHML"><math> <msub> <mi mathvariant="normal">Γ</mi> <mtext>n</mtext> </msub> </math></EquationSource> </InlineEquation> and <InlineEquation ID="IEq13"> <InlineMediaObject> <ImageObject Color="BlackWhite" FileRef="41365_2025_1754_Article_IEq13.gif" Format="GIF" Height="19" Rendition="HTML" Resolution="72" Type="Linedraw" Width="19" /> </InlineMediaObject> <EquationSource Format="TEX">\(\Gamma _{{\gamma }}\)</EquationSource> <EquationSource Format="MATHML"><math> <msub> <mi mathvariant="normal">Γ</mi> <mi>γ</mi> </msub> </math></EquationSource> </InlineEquation> in these energies of <InlineEquation ID="IEq14"> <InlineMediaObject> <ImageObject Color="BlackWhite" FileRef="41365_2025_1754_Article_IEq3.gif" Format="GIF" Height="16" Rendition="HTML" Resolution="72" Type="Linedraw" Width="63" /> </InlineMediaObject> <EquationSource Format="TEX">\({^{147,149}{\textrm{Sm}}}\)</EquationSource> <EquationSource Format="MATHML"><math> <mrow> <mmultiscripts> <mrow /> <mrow /> <mrow> <mn>147</mn> <mo>,</mo> <mn>149</mn> </mrow> </mmultiscripts> <mtext>Sm</mtext> </mrow> </math></EquationSource> </InlineEquation>, the percentages consistent with the results of the CENDL-3.2, ENDF/B-VIII.0, JEFF-3.3, JENDL-4.0, and BROND-3.1 database are 27%, 65%, 65%, 42%, and 58%, respectively. However, 27% of the results were inconsistent with those of the major libraries. This work enriches experimental data of the <InlineEquation ID="IEq19"> <InlineMediaObject> <ImageObject Color="BlackWhite" FileRef="41365_2025_1754_Article_IEq3.gif" Format="GIF" Height="16" Rendition="HTML" Resolution="72" Type="Linedraw" Width="63" /> </InlineMediaObject> <EquationSource Format="TEX">\({^{147,149}{\textrm{Sm}}}\)</EquationSource> <EquationSource Format="MATHML"><math> <mrow> <mmultiscripts> <mrow /> <mrow /> <mrow> <mn>147</mn> <mo>,</mo> <mn>149</mn> </mrow> </mmultiscripts> <mtext>Sm</mtext> </mrow> </math></EquationSource> </InlineEquation> neutron capture resonance and helps clarify the differences between different evaluation databases at the above energies.</p>

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Experimental extraction of neutron resonance parameters at 20–300 eV for \({^{147,149}\textrm{Sm}}\)

  • Xin-Xiang Li,
  • Long-Xiang Liu,
  • Wei Jiang,
  • Ya-Ju Chen,
  • Jie Ren,
  • Hong-Wei Wang,
  • Gong-Tao Fan,
  • Wen Luo,
  • Song Feng,
  • Wen Xie,
  • Zi-Ang Lin,
  • Ting Jiang,
  • Gao-Le Yang,
  • Zhen-Dong An,
  • Xian-Kai Li,
  • Zhou-Ji Liao,
  • Jie-Ming Xue,
  • Xin-Yu Li,
  • Ning-Xin Peng,
  • De-Xin Wang,
  • Su-Ya-La-Tu Zhang,
  • Yue Zhang,
  • Xin-Rong Hu,
  • Zi-Rui Hao,
  • Bing Jiang,
  • Xiao-He Wang,
  • Ji-Feng Hu,
  • Ying-Du Liu,
  • Chun-Wang Ma,
  • Yu-Ting Wang,
  • Jian-Jun He,
  • Li-Yong Zhang

摘要

\({^{147,149}{\textrm{Sm}}}\) 147 , 149 Sm are slow neutron capture (s-process) nuclides in nuclear astrophysics, whose (n, \(\gamma\) γ ) cross sections are important input parameters in nucleosynthesis network calculations in the samarium (Sm) region. In addition, \({^{149}{\textrm{Sm}}}\) 149 Sm is a fission product of \({^{235}{\textrm{U}}}\) 235 U with a 1% yield, and its neutron resonance parameters play a critical role in reactor neutronics. According to the available nuclear evaluation databases, a significant disagreement has been observed in the resonance peaks of the \({^{147,149}{\textrm{Sm}}}\) 147 , 149 Sm (n, \(\gamma\) γ ) cross-sectional data within the energy range of 20–300 eV. In this study, tutron capture cross section of a natural samarium target was measured at the back-streaming white neutron beamline of the China Spallation Neutron Source. The neutron capture yield was obtained, and the neutron resonance parameters for \({^{147}{\textrm{Sm}}}\) 147 Sm at 107.0, 139.4, 241.7, and 257.3 eV and \({^{149}{\textrm{Sm}}}\) 149 Sm at 23.2, 24.6, 26.1, 28.0, 51.5, 75.2, 90.9, 125.3, and 248.4 eV were extracted using the SAMMY code based on R-matrix theory. For the parameters \(\Gamma _{\textrm{n}}\) Γ n and \(\Gamma _{{\gamma }}\) Γ γ in these energies of \({^{147,149}{\textrm{Sm}}}\) 147 , 149 Sm , the percentages consistent with the results of the CENDL-3.2, ENDF/B-VIII.0, JEFF-3.3, JENDL-4.0, and BROND-3.1 database are 27%, 65%, 65%, 42%, and 58%, respectively. However, 27% of the results were inconsistent with those of the major libraries. This work enriches experimental data of the \({^{147,149}{\textrm{Sm}}}\) 147 , 149 Sm neutron capture resonance and helps clarify the differences between different evaluation databases at the above energies.