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
- Resource Type
- Authors
- 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
- Source
- Journal of Nuclear Science and Technology. 55(10):1198-1211
- Subject
- Language
- English
- ISSN
- 0022-3131
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.