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.
Skip Nav Destination
ASME/JSME 2004 Pressure Vessels and Piping Conference
July 25–29, 2004
San Diego, California, USA
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
0-7918-4678-4
PROCEEDINGS PAPER
Preliminary Elevated Strain Rate Material Testing to Support Accidental Drop Analyses of Radioactive Material Containers
Spencer D. Snow,
Spencer D. Snow
Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID
Search for other works by this author on:
D. Keith Morton,
D. Keith Morton
Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID
Search for other works by this author on:
Tommy E. Rahl,
Tommy E. Rahl
Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID
Search for other works by this author on:
Robert K. Blandford,
Robert K. Blandford
Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID
Search for other works by this author on:
Thomas J. Hill
Thomas J. Hill
Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID
Search for other works by this author on:
Spencer D. Snow
Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID
D. Keith Morton
Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID
Tommy E. Rahl
Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID
Robert K. Blandford
Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID
Thomas J. Hill
Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID
Paper No:
PVP2004-2802, pp. 197-201; 5 pages
Published Online:
August 12, 2008
Citation
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
Download citation file:
10
Views
Related Proceedings Papers
Related Articles
Some Mechanical Properties of Plastics and Metals Under Sustained Vibrations
Trans. ASME (February,1943)
Hot Deformation Behavior of Bearing Steels
J. Eng. Mater. Technol (July,2007)
Effect of Velocity on Tensile Impact Properties of Polymethyl Methacrylate
Trans. ASME (May,1952)
Related Chapters
Subsection NCA—General Requirements for Division 1 and Division 2
Companion Guide to the ASME Boiler & Pressure Vessel Code, Volume 1, Second Edition
Subsection NCA—General Requirements for Division 1 and Division 2
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 1, Third Edition
Introduction and Definitions
Handbook on Stiffness & Damping in Mechanical Design