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

J-PARC、ANNRIにおける$$^{241}$$Amの中性子全断面積及び中性子捕獲断面積測定

寺田 和司*; 木村 敦; 中尾 太郎*; 中村 詔司; 水山 一仁*; 岩本 信之; 岩本 修; 原田 秀郎 ; 片渕 竜也*; 井頭 政之*; 佐野 忠史*; 高橋 佳之*; Pyeon, C. H.*; 福谷 哲*; 藤井 俊行*; 八木 貴宏*; 高宮 幸一*; 堀 順一*

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 $$^{241}$$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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