The americium-241 ( 241 Am) radioisotope has valuable nuclear properties that find broad industrial usage. Ensuring stable supplies of 241 Am is critical for supporting (and expanding) the existing 241 Am-application space and enabling emerging 241 Amtechnologies that are important for economic growth, energy, and national security. Unfortunately, the United States halted 241 Am production in 1984 and the existing inventory was depleted in the early 2000s. This situation recently changed when the U.S. Department of Energy Isotope Program established 241 Am recovery at Los Alamos National Laboratory. Today, large-scale quantities of 241 Am are now obtained using the Chloride Extraction and Actinide Recovery (CLEAR) process. This method uses a resin that has the di-(4-t-butylphenyl)-N,N-di-iso-butylcarbamoylmethylphosphine oxide (m-CMPO) extractant adsorbed on a resin bead to harvest 241 Am from plutonium-containing waste streams. To maintain and improve CLEAR processing of 241 Am, we have evaluated the extraction of 241 Am by m-CMPO as a function of three important processing relevant variables: (1) HCl concentration, (2) metal contaminant concentration, and (3) contact time. The performance of the m-CMPO resin was additionally compared against commercially available resins, namely, rare earth (RE) resin and a selected series of diglycolamide (DGA) resins. Our results suggested that the m-CMPO resin outperformed most of the commercially available alternatives. However, tetraoctyl-DGA (TODGA) and tetraethyl-hexyl-DGA (TEHDGA) prevailed on several fronts. The TODGA and TEHDGA resins quantitatively released 241 Am at low HCl concentrations (<0.5 M), were less susceptible to deleterious side effects from metal contaminants in the mobile phase and bound 241 Am faster. Based on these results, we concluded that 241 Am recovery yields have the potential to improve if TODGA or TEHDGA is used in place of m-CMPO for large-scale CLEAR processing of 241 Am.