The Idaho National Engineering and Environmental Laboratory (INEEL) developed an apparatus capable of supporting a wide variety of material studies and distinct component testing under impact loads. Material studies include material (metals, plastics, concrete, etc.) response due to bending, tension, shear, and compression loadings at elevated strain rates. Similar testing can also be performed on any distinct component fitting within the apparatus impact loading volume. This apparatus is referred to as the Impact Test Machine (ITM). The ITM is initially being used by the Department of Energy (DOE) to test 304L and 316L stainless steel tensile test specimens at various strain rates for comparison to static properties. The goal is to ultimately develop true stress-strain curves at various strain rates and temperatures for these steels. These curves can then be used in analytical simulations to more accurately predict the deformation and resulting material straining in spent nuclear fuel (SNF) containers, canisters, and casks under accidental drop events (Ref: Snow 1999, 2000). Test results can also help determine a basis for establishing allowable strain limits for these large deformation, inelastic events. This material investigation is currently in an early stage of development. This paper will discuss the results of tensile tests performed on test specimens employed in the formulation of the test process and initial checkout of the ITM.
- Pressure Vessels and Piping Division
Preliminary Elevated Strain Rate Material Testing to Support Accidental Drop Analyses of Radioactive Material Containers
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Snow, SD, Morton, DK, Rahl, TE, Blandford, RK, & Hill, TJ. "Preliminary Elevated Strain Rate Material Testing to Support Accidental Drop Analyses of Radioactive Material Containers." Proceedings of the ASME/JSME 2004 Pressure Vessels and Piping Conference. Transportation, Storage, and Disposal of Radioactive Materials. San Diego, California, USA. July 25–29, 2004. pp. 197-201. ASME. https://doi.org/10.1115/PVP2004-2802
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