Neutron total and capture cross sections of Am-241 have been measured with a new data acquisition system and a new neutron transmission measurement system installed in Accurate Neutron Nucleus Reaction measurement Instrument at Materials and Life Science Experimental Facility of Japan Proton Accelerator Research Complex. The neutron total cross sections of Am-241 were determined by using a neutron time-of-flight (TOF) method in the neutron energy region from 4meV to 2eV. The thermal total cross section of Am-241 was derived with an uncertainty of 2.9%. A pulse-height weighting technique was applied to determine neutron capture yields of Am-241. The neutron capture cross sections were determined by the TOF method in the neutron energy region from the thermal to 100eV, 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.