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Radiation-induced segregation and void swelling in 304 stainless steel.

DE2001757550

Publication Date	2000
Personal Author	Allen, T. R.; Cole, J. I.; Kenik, E. A.
Page Count	20
Abstract	Void swelling and radiation-induced segregation have been measured in 304 stainless steel. Samples were irradiated in the outer regions of the EBR-II reactor where displacement rates of 2.0x10(sup -8) and 6.6 x 10 (sup -8) dpa/s are comparable to those in pressurized water reactor components. Samples were irradiated at temperatures from 371-390 deg C to total doses of up to 20 dpa. Void swelling reached a maximum of 2% at 20 dpa. Nickel enrichment and chromium depletion of up to 20 at% and 12 at% respectively were measured. Both void swelling and radiation-induced segregation were dependent on dose rate, increased as the dose rate decreased. Grain boundary compositions were measured both near and in areas of free precipitates. The presence of a precipitate significantly changes the grain boundary compositions near the precipitate.
Keywords	Radiation Stainless steels Segregation Swelling Stainless steel-304 Grain boundaries Temperature effects Reactor components Irradiation
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Argonne National Lab., IL.; Department of Energy, Washington, DC.
Document Type	Conference Proceedings
NTIS Issue Number	200123
Contract Number	W-31109-ENG-38

Radiation-induced segregation and void swelling in 304 stainless steel.

Radiation-induced segregation and void swelling in 304 stainless steel.
DE2001757550

Publication Date	2000
Personal Author	Allen, T. R.; Cole, J. I.; Kenik, E. A.
Page Count	20
Abstract	Void swelling and radiation-induced segregation have been measured in 304 stainless steel. Samples were irradiated in the outer regions of the EBR-II reactor where displacement rates of 2.0x10(sup -8) and 6.6 x 10 (sup -8) dpa/s are comparable to those in pressurized water reactor components. Samples were irradiated at temperatures from 371-390 deg C to total doses of up to 20 dpa. Void swelling reached a maximum of 2% at 20 dpa. Nickel enrichment and chromium depletion of up to 20 at% and 12 at% respectively were measured. Both void swelling and radiation-induced segregation were dependent on dose rate, increased as the dose rate decreased. Grain boundary compositions were measured both near and in areas of free precipitates. The presence of a precipitate significantly changes the grain boundary compositions near the precipitate.
Keywords	Radiation Stainless steels Segregation Swelling Stainless steel-304 Grain boundaries Temperature effects Reactor components Irradiation
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Argonne National Lab., IL.; Department of Energy, Washington, DC.
Document Type	Conference Proceedings
NTIS Issue Number	200123
Contract Number	W-31109-ENG-38