Measurement of neutron-induced reactions on $^{242m}$Am

Neutron-induced reaction cross sections of $^{242m}$Am were measured at the Los Alamos Neutron Science Center using the Detector for Advanced Neutron-Capture Experiments array along with a compact parallel-plate avalanche counter for fission-fragment detection. A new neutron-capture cross section was determined relative to a simultaneous measurement of the well-known $^{242m}$Am(n,f) cross section. The (n,$\gamma$) cross section was measured from thermal to an incident energy of 1 eV. Our new $^{242m}$Am fission cross section was normalized to ENDF/B-VII.1 and agreed well with the (n,f) cross section reported in the literature from thermal energy to 1 keV. The capture-to-fission ratio was determined from thermal energy to E$_{n}$ = 0.1 eV, and it was found to be (n,$\gamma$)/(n,f) = 26(4)$\%$ compared to 19$\%$ from ENDF/B-VII.1. Our latest results will be reported.