This report presents a test plan to investigate radiolytic hydrogen generation in spent nuclear fuel (SNF) canisters containing Zr-based cladding materials. The initial primary contributor to the generation of radiolytic hydrogen is estimated to be the residual physisorbed water on the ZrO2 film, post-dryout. Over the longer term the primary hydrogen source is associated with the aluminum hydroxides and water vapor.The proposed testing to be conducted in FY22 would consist of lab-scale testing on non-radioactive surrogates of oxidized ZIRLO tubing and unalloyed zirconium using a miniature steel canister ("minicanister") designed to allow intermittent, in-situ sampling of the canister gas during irradiation. The minicanister approach for irradiation with in-situ monitoring system was used in a recent and on-going study Verst, 2020a &Verst et al., 2021] to measure radiolytic hydrogen generation from aluminum SNF cladding surrogate materials. This proposed testing will form part of the overall materials performance evaluation of the commercial SNF-in-canister system and is part of the technical bases for their continued safe dry storage.The proposed test plan draws on previous radiolysis testing focused on aluminum-clad spent nuclear fuel (research reactor fuel) as well as the previous analysis, "Evaluation of Hydrogen Generation in High Burnup Demonstration Dry Storage Cask" [d'Entremont et al., 2020b], which provided a best-estimate evaluation of residual water content (post-dryout) in the High Burnup (HBU) LWR Spent Fuel Demonstration project TN-32 cask and evaluated the expected radiolysis of the residual water, including free, physisorbed, and chemisorbed water in the sealed cask, based on literature data and models.Under gamma radiation, radiolytic breakdown of water remaining in a canister (free, physisorbed, or chemisorbed) causes the generation of hydrogen gas (H2). SNF fuel assemblies, clad in zirconium alloys, provide a large surface area to host surface-adsorbed water (physisorbed water). Various other components in the cask, including stainless steel and aluminum structural components and aluminum neutron absorbers also contribute to the total water inventory and radiolytic H2 generation in an SNF canister. Water adsorbed to the ZrO2 on the cladding surface may experience accelerated radiolysis compared to free water due to energy exchange with the oxide. In addition, water decomposed by radiolysis may be replenished by water vapor in the canister gas, providing a mechanism for accelerated radiolysis of the free water. The previous simplified analysis [d'Entremont et al., 2020b] predicted that radiolysis of physisorbed water on the Zr-alloy components would dominate the short-term H2 generation due to these factors.The proposed test plan therefore focuses on the contribution associated with the Zr-alloy components, i.e., surface-adsorbed water as well as interactions with free water vapor present in the gas phase. The radiolytic hydrogen generation will be empirically measured using in-situ gas samplin...