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

Terada, Kazushi*; Kimura, Atsushi   ; Nakao, Taro*; Nakamura, Shoji  ; Mizuyama, Kazuhito*; Iwamoto, Nobuyuki  ; Iwamoto, Osamu  ; Harada, Hideo   ; Katabuchi, Tatsuya*; Igashira, Masayuki*; Sano, Tadafumi*; Takahashi, Yoshiyuki*; Pyeon, C. H.*; Fukutani, Satoshi*; Fujii, Toshiyuki*; Yagi, Takahiro*; Takamiya, Koichi*; Hori, Junichi*

Neutron total and capture cross sections of 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 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 Am was derived with an uncertainty of 2.9%. A pulse-height weighting technique was applied to determine neutron capture yields of 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.