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Long-Term Aging of Cast Stainless Steels: Mechanisms and Resulting Properties.

DE88002888

Publication Date	1987
Personal Author	Chopra, O. K.; Chung, H. M.
Page Count	33
Abstract	Mechanical property data are presented from Charpy-impact, tensile, and J-R curve tests for several heats of cast stainless steel aged up to 10,000 h at 450, 400, 350, 320, and 290 deg C. The results indicate that thermal aging increases the tensile strength and decreases the impactenergy, J/sub IC/ and tearing modulus of the steels. Also, the ductile-to-brittle transition curve shifts to higher temperatures. The low-carbon CF-3 steels were the most resistant and the molybdenum-containing high-carbon CF-8M steels were the most susceptible to low-temperature embrittlement. The influence of nitrogen content and distribution of ferrite on loss of toughness are discussed. Data also indicate that existing correlations do not accurately represent the embrittlement behavior over the temperature range 280 to 450 sup 0 C, i.e., extrapolation of high-temperature data to reactor temperatures may not be valid for some compositions of cast stainless steels. 13 refs., 13 figs., 2 tabs. (ERA citation 13:011797)
Keywords	Carbon Steels Chromium Alloys Iron Base Alloys Molybdenum Alloys Nickel Alloys Silicon Alloys Stainless Steels Aging Casting Charpy Test Chemical Composition Comparative Evaluations Ductile-Brittle Transitions Embrittlement Ferrite Heat Treatments High Temperature Manganese Additions Microstructure Nitrogen Additions Phase Transformations Precipitation Hardening Temperature Effects Tensile Properties Water Cooled Reactors Reactor materials ERDA/360103 ERDA/210100 ERDA/210200
Source Agency	Technical Information Center Oak Ridge Tennessee
NTIS Subject Category	71J - Iron & Iron Alloys 77J - Reactor Materials
Corporate Authors	Argonne National Lab., IL.; Department of Energy, Washington, DC.
Supplemental Notes	15. water reactor safety information meeting, Gaithersburg, MD, USA, 26 Oct 1987.
Document Type	Conference Proceedings
NTIS Issue Number	198810
Contract Number	W-31109-ENG-38

Long-Term Aging of Cast Stainless Steels: Mechanisms and Resulting Properties.

Long-Term Aging of Cast Stainless Steels: Mechanisms and Resulting Properties.
DE88002888

Publication Date	1987
Personal Author	Chopra, O. K.; Chung, H. M.
Page Count	33
Abstract	Mechanical property data are presented from Charpy-impact, tensile, and J-R curve tests for several heats of cast stainless steel aged up to 10,000 h at 450, 400, 350, 320, and 290 deg C. The results indicate that thermal aging increases the tensile strength and decreases the impactenergy, J/sub IC/ and tearing modulus of the steels. Also, the ductile-to-brittle transition curve shifts to higher temperatures. The low-carbon CF-3 steels were the most resistant and the molybdenum-containing high-carbon CF-8M steels were the most susceptible to low-temperature embrittlement. The influence of nitrogen content and distribution of ferrite on loss of toughness are discussed. Data also indicate that existing correlations do not accurately represent the embrittlement behavior over the temperature range 280 to 450 sup 0 C, i.e., extrapolation of high-temperature data to reactor temperatures may not be valid for some compositions of cast stainless steels. 13 refs., 13 figs., 2 tabs. (ERA citation 13:011797)
Keywords	Carbon Steels Chromium Alloys Iron Base Alloys Molybdenum Alloys Nickel Alloys Silicon Alloys Stainless Steels Aging Casting Charpy Test Chemical Composition Comparative Evaluations Ductile-Brittle Transitions Embrittlement Ferrite Heat Treatments High Temperature Manganese Additions Microstructure Nitrogen Additions Phase Transformations Precipitation Hardening Temperature Effects Tensile Properties Water Cooled Reactors Reactor materials ERDA/360103 ERDA/210100 ERDA/210200
Source Agency	Technical Information Center Oak Ridge Tennessee
NTIS Subject Category	71J - Iron & Iron Alloys 77J - Reactor Materials
Corporate Authors	Argonne National Lab., IL.; Department of Energy, Washington, DC.
Supplemental Notes	15. water reactor safety information meeting, Gaithersburg, MD, USA, 26 Oct 1987.
Document Type	Conference Proceedings
NTIS Issue Number	198810
Contract Number	W-31109-ENG-38