Measurement and modeling of radiation-induced grain boundary grain boundary segregation in stainless steels

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Grain boundary radiation-induced segregation (RIS) in Fe-Ni-Cr stainless alloys has been measured and modelled as a function of irradiation temperature and dose. Heavy-ion irradiation was used to produce damage levels from 1 to 20 displacements per atom (dpa) at temperatures from 175 to 550{degrees}C. Measured Fe, Ni, and Cr segregation increased sharply with irradiation dose (from 0 to 5 dpa) and temperature (from 175 to about 350{degrees}C). However, grain boundary concentrations did not change significantly as dose or temperatures were further increased. Impurity segregation (Si and P) was also measured, but only Si enrichment appeared to be radiation-induced. Grain boundary ... continued below

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20 p.

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Bruemmer, S.M.; Charlot, L.A. & Simonen, E.P. August 1, 1995.

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  • Pacific Northwest Laboratory
    Publisher Info: Pacific Northwest Lab., Richland, WA (United States)
    Place of Publication: Richland, Washington

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Grain boundary radiation-induced segregation (RIS) in Fe-Ni-Cr stainless alloys has been measured and modelled as a function of irradiation temperature and dose. Heavy-ion irradiation was used to produce damage levels from 1 to 20 displacements per atom (dpa) at temperatures from 175 to 550{degrees}C. Measured Fe, Ni, and Cr segregation increased sharply with irradiation dose (from 0 to 5 dpa) and temperature (from 175 to about 350{degrees}C). However, grain boundary concentrations did not change significantly as dose or temperatures were further increased. Impurity segregation (Si and P) was also measured, but only Si enrichment appeared to be radiation-induced. Grain boundary Si levels peaked at an intermediate temperature of {approximately}325{degrees}C reaching levels of {approximately}8 at. %. Equilibrium segregation of P was measured in the high-P alloys, but interfacial concentration did not increase with irradiation exposure. Examination of reported RIS in neutron-irradiated stainless steels revealed similar effects of irradiation dose on grain boundary compositional changes for both major alloying and impurity element`s. The Inverse Kirkendall model accurately predicted major alloying element RIS in ion- and neutron-irradiated alloys over the wide range of temperature and dose conditions. In addition, preliminary calculations indicate that the Johnson-Lam model can reasonably estimate grain boundary Si enrichment if back diffusion is enhanced.

Physical Description

20 p.

Notes

INIS; OSTI as DE96002634

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  • 7. international symposium on environmental degradation of materials in nuclear power plants: water reactors, Breckenridge, CO (United States), 6-10 Aug 1995

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  • Other: DE96002634
  • Report No.: PNL-SA--26484
  • Report No.: CONF-950816--4
  • Grant Number: AC06-76RL01830
  • Office of Scientific & Technical Information Report Number: 137153
  • Archival Resource Key: ark:/67531/metadc625010

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  • August 1, 1995

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  • June 16, 2015, 7:43 a.m.

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  • April 7, 2016, 2:53 p.m.

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Bruemmer, S.M.; Charlot, L.A. & Simonen, E.P. Measurement and modeling of radiation-induced grain boundary grain boundary segregation in stainless steels, article, August 1, 1995; Richland, Washington. (digital.library.unt.edu/ark:/67531/metadc625010/: accessed October 21, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.