Measurements of neutron total and capture cross sections of 241Am with ANNRI at J-PARC

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  • J-PARC、ANNRIにおける241Amの中性子全断面積及び中性子捕獲断面積測定
  • Measurements of neutron total and capture cross sections of <sup>241</sup>Am with ANNRI at J-PARC

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Neutron total and capture cross sections of $^{241}$Am have been measured with a new data acquisition system and a new neutron transmission measurement system installed in Accurate Neutron Nucleus Reaction measurement Instrument (ANNRI) at Materials and Life Science Experimental Facility (MLF) of Japan Proton Accelerator Research Complex (J-PARC). The neutron total cross sections of $^{241}$Am were determined by using a neutron time-of-flight method in the neutron energy region from 4 meV to 2 eV. The thermal total cross section of $^{241}$Am was derived with an uncertainty of 2.9\%. A pulse-height weighting technique was applied to determine neutron capture yields of $^{241}$Am. The neutron capture cross sections were determined by the time-of-flight method in the neutron energy region from the thermal to 100 eV, and the thermal capture cross section was obtained with an uncertainty of 4.1\%. The evaluation data of JENDL-4.0 and JEFF-3.2 were compared with the present results.

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