Stress corrosion cracking behavior of irradiated model austenitic stainless steel alloys.

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Slow-strain-rate tensile tests (SSRTs) and posttest fractographic analyses by scanning electron microscopy were conducted on 16 austenitic stainless steel (SS) alloys that were irradiated at 289 C in He. After irradiation to {approx}0.3 x 10{sup 21} n{center_dot}cm{sup {minus}2} and {approx}0.9 x 10{sup 21} n{center_dot}cm{sup {minus}2} (E >1 MeV), significant heat-to-heat variations in the degree of intergranular and transgranular stress corrosion cracking (IGSCC and TGSCC) were observed. Following irradiation to a fluence of {approx}0.3 x 10{sup 21} n{center_dot}cm{sup {minus}2}, a high-purity laboratory heat of Type 316L SS (Si {approx} 0.024 wt%) exhibited the highest susceptibility to IGSCC. The other 15 alloys ... continued below

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18 p.

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Chung, H. M.; Karlsen, T. M.; Ruther, W. E.; Shack, W. J. & Strain, R. V. July 16, 1999.

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Slow-strain-rate tensile tests (SSRTs) and posttest fractographic analyses by scanning electron microscopy were conducted on 16 austenitic stainless steel (SS) alloys that were irradiated at 289 C in He. After irradiation to {approx}0.3 x 10{sup 21} n{center_dot}cm{sup {minus}2} and {approx}0.9 x 10{sup 21} n{center_dot}cm{sup {minus}2} (E >1 MeV), significant heat-to-heat variations in the degree of intergranular and transgranular stress corrosion cracking (IGSCC and TGSCC) were observed. Following irradiation to a fluence of {approx}0.3 x 10{sup 21} n{center_dot}cm{sup {minus}2}, a high-purity laboratory heat of Type 316L SS (Si {approx} 0.024 wt%) exhibited the highest susceptibility to IGSCC. The other 15 alloys exhibited negligible susceptibility to IGSCC at this low fluence. The percentage of TGSCC on the fracture surfaces of SSRT specimens of the 16 alloys at {approx}0.3 x 10{sup 21} n{center_dot}cm{sup {minus}2} (E > 1 MeV) could be correlated well with N and Si concentrations; all alloys that contained <0.01 wt.% N and <1.0 wt. % Si were susceptible, whereas all alloys that contained >0.01 wt.% N or >1.0 wt.% Si were relatively resistant. High concentrations of Cr were beneficial. Alloys that contain <15.5 wt.% Cr exhibited greater percentages of TGSCC and IGSCC than those alloys with {approx}18 wt.% Cr, whereas an alloy that contains >21 wt.% Cr exhibited less susceptibility than the lower-Cr alloys under similar conditions.

Physical Description

18 p.

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OSTI as DE00011896

Medium: P; Size: 18 pages

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  • Enlarged Halden Reactor Project Annual Meeting, Loen (NO), 05/24/1999--05/29/1999

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  • Report No.: ANL/ET/CP-99539
  • Grant Number: W-31109-ENG-38
  • Office of Scientific & Technical Information Report Number: 11896
  • Archival Resource Key: ark:/67531/metadc627658

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  • July 16, 1999

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  • June 16, 2015, 7:43 a.m.

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  • April 7, 2017, 4:21 p.m.

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Chung, H. M.; Karlsen, T. M.; Ruther, W. E.; Shack, W. J. & Strain, R. V. Stress corrosion cracking behavior of irradiated model austenitic stainless steel alloys., article, July 16, 1999; Illinois. (digital.library.unt.edu/ark:/67531/metadc627658/: accessed October 18, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.