[en] The unrecognized oxidation of plutonium in open-quotes sealedclose quotes canisters poses a unique problem for both material control and accountability. A feasibility study was performed to address the use of randomly pulsed neutron measurements with ²⁵²Cf to determine if plutonium metal in a canister has oxidized without opening the container. The Monte Carlo code MCNP-DSP was used to determine if time-of-flight transmission measurements could be used to determine oxidation of plutonium in open-quotes sealedclose quotes cans. In the Monte Carlo models, a plutonium button in a can was positioned between a ²⁵²Cf source and a scintillation detector, and the time distribution of counts after ²⁵²Cf fission in the detector was calculated. The time distribution of counts after ²⁵²Cf fission differs between plutonium metal and plutonium oxide because resonances in oxygen will affect transmission of certain energy neutrons from ²⁵²Cf sources in ionization chambers. This method could be used to determine the presence of other materials that react with plutonium in open-quotes sealedclose quotes cans