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Impact Tensile Testing of Stainless Steels at Various Temperatures.

DE2008933178

Publication Date	2008
Personal Author	Morton, D. K.; Bladnford, R. K.
Page Count	162
Abstract	Stainless steels are used for the construction of numerous spent nuclear fuel or radioactive material containers that may be subjected to high strains and moderate strain rates during accidental drop events. Mechanical characteristics of these base materials and their welds under dynamic loads in the strain rate range of concern (1 to 300 per second) are not well documented. However, research is being performed at the Idaho National Laboratory to quantify these characteristics. The work presented herein discusses tensile impact testing of dual-marked 304/304L and 316/316L stainless steel material specimens. Both base material and welded material specimens were tested at -20 degrees F, room temperature, 300 degrees F, and 600 degrees F conditions. Utilizing a drop weight impact test machine and 1/4-inch and 1/2-inch thick dog bone-shaped test specimens, a strain rate range of approximately 4 to 40 per second (depending on initial temperature conditions) was achieved. Factors were determined that reflect the amount of increased strain energy the material can absorb due to strain rate effects. Using the factors, elevated true stress-strain curves for these materials at various strain rates and temperatures were generated. By incorporating the strain rate elevated true stress-strain material curves into an inelastic finite element computer program as the defined material input, significant improvement in the accuracy of the computer analyses was attained.
Keywords	Stainless steels Tensile properties Nuclear fuels Radioactive materials Containers Accuracy Computer codes Computers Construction Dynamic loads Energy analysis Impact tests Strain rates Testing
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Idaho National Laboratory, Idaho Falls, ID.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200826

Impact Tensile Testing of Stainless Steels at Various Temperatures.

Impact Tensile Testing of Stainless Steels at Various Temperatures.
DE2008933178

Publication Date	2008
Personal Author	Morton, D. K.; Bladnford, R. K.
Page Count	162
Abstract	Stainless steels are used for the construction of numerous spent nuclear fuel or radioactive material containers that may be subjected to high strains and moderate strain rates during accidental drop events. Mechanical characteristics of these base materials and their welds under dynamic loads in the strain rate range of concern (1 to 300 per second) are not well documented. However, research is being performed at the Idaho National Laboratory to quantify these characteristics. The work presented herein discusses tensile impact testing of dual-marked 304/304L and 316/316L stainless steel material specimens. Both base material and welded material specimens were tested at -20 degrees F, room temperature, 300 degrees F, and 600 degrees F conditions. Utilizing a drop weight impact test machine and 1/4-inch and 1/2-inch thick dog bone-shaped test specimens, a strain rate range of approximately 4 to 40 per second (depending on initial temperature conditions) was achieved. Factors were determined that reflect the amount of increased strain energy the material can absorb due to strain rate effects. Using the factors, elevated true stress-strain curves for these materials at various strain rates and temperatures were generated. By incorporating the strain rate elevated true stress-strain material curves into an inelastic finite element computer program as the defined material input, significant improvement in the accuracy of the computer analyses was attained.
Keywords	Stainless steels Tensile properties Nuclear fuels Radioactive materials Containers Accuracy Computer codes Computers Construction Dynamic loads Energy analysis Impact tests Strain rates Testing
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Idaho National Laboratory, Idaho Falls, ID.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200826