Effect of Stress Level on SCC Initiation of Stainless ... · performed following ASTM Standard...

16
Effect of Stress Level on the Stress Corrosion Cracking Initiation of Type 304L Stainless Steel Exposed to Simulated Sea Salt Larry Miller 1 , Todd S. Mintz 1 , Xihua He 1 , Roberto Pabalan 1 , Yi-Ming Pan 1 , Greg Oberson 2 , and Darrell Dunn 2 1 Southwest Research Institute ® 6220 Culebra Road San Antonio, Texas 78238 2 U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, Maryland 20852 ABSTRACT In the U.S. and elsewhere in the world, some spent nuclear fuel is maintained in dry storage in welded canisters fabricated from austenitic stainless steel. The canister is placed in an overpack or concrete module for physical protection and radiation shielding, but with external vents to allow airflow for passive cooling. If the canister is in an environment, such as near the ocean, where it is exposed to airborne chlorides, it may be susceptible to chloride-induced stress corrosion cracking (SCC). SCC could initiate from weld residual stresses or at other locations where there is tensile stress on the canister surface. The stress level at which SCC initiates may be an important factor to consider for assessing the integrity of the canister. Under contract with the Nuclear Regulatory Commission (NRC), Southwest Research Institute ® (SwRI ® ) has performed a range of SCC tests in which austenitic stainless steel U-bend specimens were exposed to chloride salts. Specimens were fabricated according to ASTM Standard G30, “Standard Practice for Making and Using U-Bend Stress Corrosion Test Specimens.” It is recognized, however, that U-bend specimens represent a relatively high stress or strain condition, with strain of approximately 13 to 14 percent at the apex. To more systematically evaluate the effects of stress or strain level on crack initiation, an additional series of tests was performed following ASTM Standard G38–01, “Standard Practice for Making and Using C-Ring Stress-Corrosion Test Specimens.” Compared to U-bend testing, C-ring testing offers the advantage of allowing the specimen strain to be manually adjusted to desired levels. C-ring specimens were fabricated from Type 304L stainless steel in the as-received and sensitized condition, deposited with 1 or 10 g/m 2 of simulated sea salt on the surface, and then set to 0.4 or 1.5 percent plastic strain. Specimens were exposed in atmospheric test chambers at a range of temperatures and humidity levels, and then examined for evidence of SCC initiation. Test results indicate that in certain conditions, SCC can initiate at a strain as low as 0.4%. This paper will present and discuss the significance of the test results. *The views expressed in this paper are not necessarily those of the U.S. Nuclear Regulatory Commission.

Transcript of Effect of Stress Level on SCC Initiation of Stainless ... · performed following ASTM Standard...

Page 1: Effect of Stress Level on SCC Initiation of Stainless ... · performed following ASTM Standard G38–01, “Standard Practice for Making and Using C-Ring Stress-Corrosion Test Specimens.”

Effect of Stress Level on the Stress Corrosion Cracking Initiation of Type 304L Stainless Steel Exposed to Simulated Sea Salt

Larry Miller1, Todd S. Mintz1, Xihua He1, Roberto Pabalan1, Yi-Ming Pan1,

Greg Oberson2, and Darrell Dunn2

1Southwest Research Institute®

6220 Culebra Road San Antonio, Texas 78238

2U.S. Nuclear Regulatory Commission

11555 Rockville Pike Rockville, Maryland 20852

ABSTRACT

In the U.S. and elsewhere in the world, some spent nuclear fuel is maintained in dry storage in welded canisters fabricated from austenitic stainless steel. The canister is placed in an overpack or concrete module for physical protection and radiation shielding, but with external vents to allow airflow for passive cooling. If the canister is in an environment, such as near the ocean, where it is exposed to airborne chlorides, it may be susceptible to chloride-induced stress corrosion cracking (SCC). SCC could initiate from weld residual stresses or at other locations where there is tensile stress on the canister surface. The stress level at which SCC initiates may be an important factor to consider for assessing the integrity of the canister. Under contract with the Nuclear Regulatory Commission (NRC), Southwest Research Institute® (SwRI®) has performed a range of SCC tests in which austenitic stainless steel U-bend specimens were exposed to chloride salts. Specimens were fabricated according to ASTM Standard G30, “Standard Practice for Making and Using U-Bend Stress Corrosion Test Specimens.” It is recognized, however, that U-bend specimens represent a relatively high stress or strain condition, with strain of approximately 13 to 14 percent at the apex. To more systematically evaluate the effects of stress or strain level on crack initiation, an additional series of tests was performed following ASTM Standard G38–01, “Standard Practice for Making and Using C-Ring Stress-Corrosion Test Specimens.” Compared to U-bend testing, C-ring testing offers the advantage of allowing the specimen strain to be manually adjusted to desired levels. C-ring specimens were fabricated from Type 304L stainless steel in the as-received and sensitized condition, deposited with 1 or 10 g/m2 of simulated sea salt on the surface, and then set to 0.4 or 1.5 percent plastic strain. Specimens were exposed in atmospheric test chambers at a range of temperatures and humidity levels, and then examined for evidence of SCC initiation. Test results indicate that in certain conditions, SCC can initiate at a strain as low as 0.4%. This paper will present and discuss the significance of the test results. *The views expressed in this paper are not necessarily those of the U.S. Nuclear Regulatory Commission.

Page 2: Effect of Stress Level on SCC Initiation of Stainless ... · performed following ASTM Standard G38–01, “Standard Practice for Making and Using C-Ring Stress-Corrosion Test Specimens.”

INTRODUCTION

Spent nuclear fuel (SNF) at a number of U.S. locations is maintained at independent spent fuel storage installations (ISFSIs). At the ISFSIs, spent fuel removed from the reactor may be placed into dry cask storage systems (DCSS) after cooling for several years in the spent fuel pool. The spent fuel is typically confined in canisters fabricated from austenitic stainless steel (SS) of the types UNS S30400 (304 SS), UNS S30403 (304L SS), or UNS S31603 (316L SS).1,2 The steel canister is in turn emplaced in a concrete or metal overpack or vault for radiation shielding and physical protection. The overpack or vault is vented to the ambient external environment to allow airflow for passive cooling. Inspections of DCSS have shown evidence of water intrusion and dust or particulate matter on the canister surfaces.3 Some ISFSI sites are located in areas where the atmosphere could contain a relatively high concentration of airborne chloride-rich salts, including coastal regions, near salted roads, or near cooling towers.4 Austenitic SS materials are susceptible to chloride-induced stress corrosion cracking (SCC) when there is a persistent tensile stress.5,6,7 Sources of stress on the canister could include weld residual stresses, as they are not post-weld heat treated, or contact points between the canister and support structures. Stress levels in canisters have not been well-characterized, but chloride-induced SCC has been identified as the cause of failure for welded austenitic SS tanks and piping systems at a number of nuclear power plant sites.8 Because SCC could affect the confinement function of dry storage canisters, NRC has undertaken research projects to better understand the conditions of SCC susceptibility. Most NRC-sponsored tests have been performed using Type 304 SS U-bend specimens fabricated according to ASTM Standard G30, “Standard Practice for Making and Using U-Bend Stress Corrosion Test Specimens.” SCC initiation has been observed on specimens deposited with simulated sea salt and exposed in an environmental test chamber at temperatures between 35 and 52 °C.9 The quantity of salt deposited on the specimen surfaces was between 0.1 and 10 g/m2. It was suggested from these tests that the SCC susceptibility of the stainless steel samples was related to the process of deliquescence, wherein dry salt absorbs moisture in humid air to form a brine. For a specific salt chemistry, there is a characteristic relative humidity above which deliquescence can occur, referred to as the deliquescence relative humidity.10 At a given absolute humidity, the relative humidity increases with decreasing temperature. Tests were performed at absolute humidity less than about 30 g/m3, which is assumed to be an upper bound for what would be expected in natural conditions. The use of U-bend specimens offers advantages in terms of cost and ease of fabrication, but this represents only a single test configuration, with strain at the apex of approximately 13 to 14 percent.9 Though residual strains in excess of 10 percent and stresses higher than the yield stress are possible for austenitic SS welds, 11,12 the stress and strain states of canister welds have not been specifically characterized. Therefore, further resolution in defining the stress and strain conditions at which SCC could initiate would be useful for assessments of canister integrity. This report describes a series of tests to systematically evaluate the effects of stress and strain on SCC initiation.

Page 3: Effect of Stress Level on SCC Initiation of Stainless ... · performed following ASTM Standard G38–01, “Standard Practice for Making and Using C-Ring Stress-Corrosion Test Specimens.”

PROCEDURE

Tests were conducted using Type 304L SS. C-ring specimens, which were cut from pipe material with a 5-cm outer diameter and 0.3-cm wall thickness. Specimens were made following ASTM Standard G38–01, “Standard Practice for Making and Using C-Ring Stress-Corrosion Test Specimens.”13 Type 304L was used rather than Type 304 because the latter could not be procured in the desired product form. The chemical composition of these specimens is shown in Table 1. The material was tested both in the as-received and sensitized condition. To achieve the sensitization of these specimens, prior to cutting of the C-rings, some of the as-received material was heated in air at a temperature of 600 °C for 48 hours then air cooled. The sensitization of these specimens was intended to simulate the condition of a weld heat affected zone. C-ring specimens were strained to either 0.4 percent, which was the strain measured at the 0.2 percent offset yield strength from tensile testing, or 1.5 percent. Strain gauges were used to determine how much to deflect the specimens to achieve the desired strain. Images of the specimens are shown in Figure 1. After straining, specimens were deposited with controlled quantities of simulated sea salt. Specimens were placed on support bars lined with heat tape in an atmospheric chamber, as shown in Figure 2, and heated to 90 °C. The chamber was fogged periodically with simulated sea water aerosols for 5 minutes followed by a 15 minutes ambient hold. The simulated sea water was prepared per ASTM D1141–98.16 Using this method, salt deposition amounts of 1 g/m2 and 10 g/m2 were produced on the surface of the C-ring specimens. The amounts were determined by measuring specimen weight gain normalized to surface area. Specimens were examined to confirm that no cracking or corrosion had taken place prior to the start of SCC testing. SCC testing involved the exposure of the C-ring specimens in atmospheric test chamber at static temperature and humidity conditions. The full test matrix for the environmental tests is shown in Table 2. The absolute humidity was selected as 30 g/m3 which, as mentioned previously, is considered to be an upper limit in natural conditions. Specimens were exposed at 35, 45, and 52 °C, where the relative humidities are 72, 44, and 32 percent, respectively. These are higher than the expected relative humidity for which sea salt would start to absorb mositure.14 Furthermore, at these temperatures and relative humidities, SCC was observed for tests with U-bend specimens.15 Once specimens were placed in the atmospheric chamber, there was no direct introduction of water by fog or spray. Therefore, any observed corrosion could be attributed to salt deliquescence. Specimens were removed from the test chambers at the intervals shown in Table 2, and examined for visual and microscopic indications of SCC initiation. The process of examination included photographing the specimens, rinsing with deionized water, and drying with acetone or isopropyl alcohol. The surface of the apex on the C-ring specimen was first examined using a stereomicroscope with 50 to 1,000 times magnification. If cracks were clearly visible on the surface, a determination was made that SCC had occurred on that specimen. If cracking was not clearly visible on the surface but extensive pitting was evident, the region around the apex was cross-sectioned into three to four pieces perpendicular to the rolling direction of the material. The cross-sections were mounted in resin and polished to 1 µm for examination of cracking under the stereomicroscope with at least 50 to 1,000 times magnification.

Page 4: Effect of Stress Level on SCC Initiation of Stainless ... · performed following ASTM Standard G38–01, “Standard Practice for Making and Using C-Ring Stress-Corrosion Test Specimens.”

RESULTS

C-Ring Specimens Tested at 35 °C and 72 Percent Relative Humidity C-ring testing was conducted at 35 °C at 0.4 percent strain for the two salt concentrations of 1 and 10 g/m2. After 2 to 3 months of exposure, pitting corrosion was visible on the specimen surfaces, as shown in Figure 3. The only specimen for which cracking was observed under microscopic examination was a sensitized specimen with 10 g/m2 salt on the surface as shown in Figure 4. C-Ring Specimens Tested at 45 °C and 44 Percent Relative Humidity C-ring testing was conducted at 45 °C at 0.4 percent strain for the two salt concentrations of 1 and 10 g/m2 and at 1.5% strain for a salt concentration of 10 g/m2. After 2 to 3 months of exposure, pitting corrosion was visible on the specimen surfaces, as shown in Figure 5. The only specimens for which cracking was observed under microscopic examination were the as-received and sensitized specimens with 10 g/m2 salt at 1.5% strain, as shown in Figure 6. No SCC was observed from examination of the 0.4% strain specimens. C-Ring Specimens Held at 52 °C and 32 Percent Relative Humidity C-ring testing was conducted at 52 °C at 0.4% strain for the two salt concentrations of 1 and 10 g/m2 and at 1.5% strain for a salt concentration of 10 g/m2. After 2 to 3 months of exposure, pitting was visible on the surface of most specimens, as shown in Figure 7. For reasons that are unknown, specimens at 0.4 percent strain and salt concentration of 10 g/m2 did not exhibit pitting, though it was observed for similar specimens with only 1 g/m2 of salt. This may be an artifact of the small number of specimens tested, but does not affect the conclusions of the study. Under microscopic examination, cracking was observed on of the specimens except for the as-received specimens with 0.4 percent strain and salt concentration of 10 g/m2. The extent of cracking appeared to be greater at this temperature compared to 35 and 45 °C, and also greater at 1.5 percent strain than 0.4 percent.

DISCUSSION

The results of the study using C-ring specimens indicates that SCC induced by deliquescence of chloride salt can occur on austenitic stainless steel when the strain is as low as 0.4 percent, which approximately corresponds to the material yield stress. This extent of stress and strain is much lower than U-bend specimens, which have been used for previously reported NRC testing. In tests where otherwise identical specimens were strained to 0.4 percent or 1.5 percent strain, the extent of cracking appeared to be greater for the specimens with higher strain. Direct comparison with the results of U-bend testing is difficult because of material differences (i.e., Type 304L C-ring specimens versus Type 304 U-bend specimens), exposure time differences, and the use of static rather than cyclic humidity. Nevertheless, the findings provide further insight into the conditions where SCC could occur. Variations were also made to the salt quantity and test temperatures to determine how these would affect the SCC susceptibility. Concerning the salt quantity, at each test temperature, specimens with 0.4 percent strain were exposed with either 1 or 10 g/m2 of salt. The results did

Page 5: Effect of Stress Level on SCC Initiation of Stainless ... · performed following ASTM Standard G38–01, “Standard Practice for Making and Using C-Ring Stress-Corrosion Test Specimens.”

not demonstrate a strong effect. At 35 °C, cracking was only observed in a specimen with 10 g/m2 of salt. At 45 °C, however, cracking was not observed in any specimens, while at 52 °C, the unexpected observation was made of more extensive cracking at the lower salt quantity. Results from U-bend testing seem to definitively support the notion of increased susceptibility with increasing salt quantity.15 It may be the case that the relatively small set of C-ring specimens used for the tests were not enough to identify the meaningful trends. The effect of temperature seems somewhat more pronounced, with clearly more cracking in otherwise similar specimens tested at 52 °C compared to 35 or 45 °C. Again, this represents a somewhat different response than for tests with U-bend specimens, where the susceptibility appeared to be higher at 35 and 45 °C than at 52 °C.

SUMMARY The objective of this work was to evaluate the effects of stress and strain level on SCC susceptibility of austenitic SS exposed to chloride salts. Simulated sea salt was deposited onto the surface of C-ring test specimens, which were then exposed for several months at temperatures of 35, 45, and 52 °C and constant absolute humidity of about 30 g/m3. The humidity was high enough to cause deliquescence of the deposited salts. Quantities of deposited salt were either 1 or 10 g/m2. The C-ring samples were strained to either 0.4 percent or 1.5 percent strain. SCC initiation was observed on some specimens with 0.4 percent strain, though at a greater extent on specimens with 1.5 percent strain. The effects of salt quantity on SCC susceptibility were not as pronounced as has been observed in testing with U-bend specimens. Finally, for otherwise similar specimens, there was more cracking at 52 °C compared to 35 or 45 °C.

ACKNOWLEDGEMENTS The authors thank B. Derby for technical support in conducting the testing presented in the paper. This paper describes work performed by the SwRI Center for Nuclear Waste Regulatory Analyses (CNWRA®) for the USNRC under Contract No. NRC–02–07–006. The activities reported here were performed on behalf of the USNRC Office of Nuclear Regulatory Research, Division of Engineering. This paper is an independent product of the CNWRA and does not necessarily reflect the view or regulatory position of the USNRC. The USNRC staff views expressed herein are preliminary and do not constitute a final judgment or determination of the matters addressed or of the acceptability of any licensing action that may be under consideration at USNRC.

Page 6: Effect of Stress Level on SCC Initiation of Stainless ... · performed following ASTM Standard G38–01, “Standard Practice for Making and Using C-Ring Stress-Corrosion Test Specimens.”

REFERENCES

1. NAC International, Inc. “Safety Analysis Report for the UMS Universal Storage System—Docket No. 72-1015,” ML003743531, U.S. Nuclear Regulatory Commission: Rockville, Maryland, 2003.

2. Transnuclear, Inc., “Transnuclear Standardized Advanced Nuhoms® Horizontal Modular

Storage System for Irradiated Nuclear Fuel Safety Evaluation Report,” ML030100468, U.S. Nuclear Regulatory Commission: Rockville, Maryland, 2003.

3. CENG, “Response to Request for Supplemental Information, RE: Calvert Cliffs Independent Spent Fuel Storage Installation License Renewal Application,” ML12212A216, Constellation Energy Nuclear Group: Baltimore, Maryland, 2012.

4. U.S. Nuclear Regulatory Commission, NUREG–1350, Vol. 23, “Information Digest,” U.S. Nuclear Regulatory Commission: Rockville, Maryland, 2003.

5. Toshima, Y. and Y. Ikeno, “Long-Term Exposure Test for External Stress Corrosion

Cracking on Austenitic Stainless Steels in Coastal Areas,” CORROSION/2000, Paper Number 597, NACE International: Houston, Texas, 2000.

6. Huizinga, S., J.G. De Jong, W.E. Like, B. McLoughlin, and S.J. Paterson, “Offshore 22Cr

Duplex Stainless Steel Cracking—Failure and Prevention,” CORROSION/2009, Paper Number 05474, NACE International: Houston, Texas, 2005.

7. NASA, “Corrosion Study of Bare and Coated Stainless Steel,” MAB 431-68, National

Aeronautics and Space Administration: Kennedy Space Center, Florida, 1971.

8. Gordon, B.M., “Outside Diameter Stress Corrosion Cracking of Stainless Steel in Light Water Reactors,” CORROSION/2013, Paper Number 02539, NACE International: Houston, Texas, 2013.

9. ASTM International, “Standard Practice for Making and Using U-Bend Stress-Corrosion Test

Specimens,” ASTM G30–97, West Conshohocken, Pennsylvania: ASTM International, 2009.

10. Mintz, T.S. and D.S. Dunn, “Atmospheric Chamber Testing to Evaluate Chloride Induced

Stress Corrosion Cracking of Type 304, 304L, and 316L Stainless Steel,” CORROSION/2009, Paper Number 09295, NACE International: Houston, Texas, 2009.

11. Andresen, P.L., T.M. Angeliu, W.R. Catlin, L.M. Young, and R.M. Horn, “Effect of

Deformation on SCC of Unsensitized Stainless Steel,” CORROSION/2000, NACE International: Houston, Texas, 2000.

12. Angeliu, T.M., P.L. Andresen, E. Hall, J.A. Sutliff, and S. Sitzman, “Strain and Microstructure Characterization of Austenitic SS Weld HAZs,” CORROSION/2000, NACE International: Houston, Texas, 2000.

Page 7: Effect of Stress Level on SCC Initiation of Stainless ... · performed following ASTM Standard G38–01, “Standard Practice for Making and Using C-Ring Stress-Corrosion Test Specimens.”

13. ASTM International, “Standard Practice for Making and Using C-Ring Stress-Corrosion Test Specimens,” ASTM G38–01, West Conshohocken, Pennsylvania: ASTM International, 2007.

14. U.S. Nuclear Regulatory Commission. “Atmospheric Stress Corrosion Cracking

Susceptibility of Welded and Unwelded 304, 304L, 316L Austenitic Stainless Steels Commonly Used for Dry Cask Storage Containers Exposed to Marine Environments.” NUREG/CR-7030, U.S. NRC: Rockville, Maryland. 2010.

15. Mintz, T.S., X. He, L. Miller, R. Pabalan, Y-M. Pan, L. Caseres, G. Oberson, and D.S. Dunn,

“Coastal Salt Effects on the Stress Corrosion Cracking of Type 304 Stainless Steel,” CORROSION/2013, Paper Number 02494, NACE International: Houston, Texas, 2013.

16. ASTM International, “Standard Practice for the Preparation of Substitute Ocean Water,” ASTM D1141–98, ASTM International: West Conshohocken, Pennsylvania, 2003.

Page 8: Effect of Stress Level on SCC Initiation of Stainless ... · performed following ASTM Standard G38–01, “Standard Practice for Making and Using C-Ring Stress-Corrosion Test Specimens.”

TABLES

Table 1. Chemical Composition of Type 304L Stainless Steels Used To Fabricate C-Rings (Wt%)

C S Mn P Si Cr Mo Ni Cu Co N Fe 0.013 0.004 1.06 0.034 0.39 18.65 0.01 8.18 0.04 0.19 0.085 BalanceC = carbon S = sulfur Mn = manganese P = phosphorus Si = silicon Cr = chromium Mo = molybdenum Ni = nickel Cu = cooper Co = cobalt N = nitrogen Fe = iron

Table 2. C-Ring Stress Corrosion Cracking Test Matrix

Tem

per

atu

re

(°C

)

Rel

ativ

e H

um

idit

y (%

)

Ab

solu

te

Hu

mid

ity

(g

/m3 )

Sal

t C

on

cen

trat

ion

(g

/m2 )

Str

ain

(%

)

Sp

ecim

ens

Max

imu

m T

est

Du

rati

on

(M

on

th)

Nu

mb

er o

f C

rack

ed

Sp

ecim

ens

35 72 29 1 0.4

3 As-Received 3 Sensitized

2 0 As-Received 0 Sensitized

10 0.4 3 As-Received 3 Sensitized

3 0 As-Received 1 Sensitized

45 44 29

1 0.4 3 As-Received 3 Sensitized

3 0 As-Received 0 Sensitized

10 0.4

3 As-Received 3 Sensitized

3 0 As-Received 0 Sensitized

1.5 3 As-Received 3 Sensitized

2 1 As-Received 1 Sensitized

52 32 29

1 0.4 3 As-Received 3 Sensitized

2 3 As-Received 2 Sensitized

10 0.4

3 As-Received 3 Sensitized

3 0 As-Received 1 Sensitized

1.5 3 As-Received 3 Sensitized

2 3 As-Received 3 Sensitized

Page 9: Effect of Stress Level on SCC Initiation of Stainless ... · performed following ASTM Standard G38–01, “Standard Practice for Making and Using C-Ring Stress-Corrosion Test Specimens.”

FIGURES

(a)

(b)

Figure 1. C-Ring Outer Diameter Changes As Stress Increased: (a) Strain at Yield Strength and (b) 1.5% Strain

Page 10: Effect of Stress Level on SCC Initiation of Stainless ... · performed following ASTM Standard G38–01, “Standard Practice for Making and Using C-Ring Stress-Corrosion Test Specimens.”

Figure 2. C-Ring Specimens Deposited With 1 g/m2 Simulated Sea Salt in a Singleton Atmospheric Chamber

Page 11: Effect of Stress Level on SCC Initiation of Stainless ... · performed following ASTM Standard G38–01, “Standard Practice for Making and Using C-Ring Stress-Corrosion Test Specimens.”

As-Received

Sensitized

(a)

Sensitized As-Received

(b)

Figure 3. Photographs of C-Ring Specimens Strained to 0.4 Percent and Exposed at 35 °C and 72 Percent Relative Humidity for (a) 10 g/m2 Salt after 3 Months and (b) 1 g/m2 Salt

after 2 Months

Page 12: Effect of Stress Level on SCC Initiation of Stainless ... · performed following ASTM Standard G38–01, “Standard Practice for Making and Using C-Ring Stress-Corrosion Test Specimens.”

Figure 4. Optical Micrograph from Surface of Sensitized Specimen With 10 g/m2 Salt, Strained to 0.4, and Exposed at 35 °C and 72 Percent Relative Humidity for

3 Months. Red Circle Highlights the Cracks.

Page 13: Effect of Stress Level on SCC Initiation of Stainless ... · performed following ASTM Standard G38–01, “Standard Practice for Making and Using C-Ring Stress-Corrosion Test Specimens.”

As-Received

Sensitized

(a) As-Received

Sensitized

(b)

As-Received

Sensitized

(c)

Figure 5. Photographs of Specimens Exposed at 45 °C and 44 Percent Relative Humidity for (a) 0.4 Percent Strain and 10 g/m2 Salt after 3 Months of Exposure, (b) 0.4 Percent Strain and 1 g/m2 Salt after 3 Months of

Exposure, and (c) 1.5 Percent Strain and 10 g/m2 Salt after 2 Months of Exposure

Page 14: Effect of Stress Level on SCC Initiation of Stainless ... · performed following ASTM Standard G38–01, “Standard Practice for Making and Using C-Ring Stress-Corrosion Test Specimens.”

(a)

(b)

Figure 6. Optical Micrographs from Cross-Sections of Specimens with 1.5 Percent Strain and 10 g/m2 Salt Exposed at 45 °C and 44 Percent Relative Humidity for 2 Months in the

(a) Sensitized and (b) As-Received Condition. Red Circles Highlight the Cracks.

Page 15: Effect of Stress Level on SCC Initiation of Stainless ... · performed following ASTM Standard G38–01, “Standard Practice for Making and Using C-Ring Stress-Corrosion Test Specimens.”

As-Received

Sensitized

(a)

As-Received

Sensitized

(b)

As-Received

Sensitized

(c)

Figure 7. Photographs of Specimens Exposed at 52 °C and 32 Percent Relative Humidity for (a) 0.4 Percent Strain and 10 g/m2 Salt after 2 Months of Exposure, (b) 0.4 Percent

Strain and 1 g/m2 Salt after 3 Months of Exposure, and (c) 1.5 Percent Strain and 10 g/m2 Salt after 2 Months of Exposure

Page 16: Effect of Stress Level on SCC Initiation of Stainless ... · performed following ASTM Standard G38–01, “Standard Practice for Making and Using C-Ring Stress-Corrosion Test Specimens.”

(a)

(b)

(c)

(d)

(e)

Figure 8. Optical Micrographs from Surfaces of Specimens Exposed at 52 °C and 32 Percent Relative Humidity. (a) Sensitized Specimen with

0.4 Percent Strain and 10 g/m2 Salt after 2 Months of Exposure, (b) Sensitized Specimen with 0.4 Percent Strain and 1 g/m2 Salt after 3 Months of Exposure, (c) As-Received

Specimen with 0.4 Percent Strain and 1 g/m2 Salt after 3 Months of Exposure, (d) Sensitized Specimen with 1.5 Percent Strain and 10 g/m2 Salt after 2 Months of Exposure, and (e) As-Received Specimen with 1.5 Percent Strain and 10 g/m2 Salt after 2 Months of

Exposure