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Report No.

Measurements of neutron total and capture cross sections of $$^{241}$$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 $$^{241}$$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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Category:Nuclear Science & Technology



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