Date of download: 11/8/2017 Copyright © ASME. All rights reserved. From: Influence of Changes in Pressure and Temperature of Supercritical Water on the Susceptibility to Stress Corrosion Cracking of 316L Austenitic Stainless Steel ASME J of Nuclear Rad Sci. 2016;3(1):011009-011009-6. doi:10.1115/1.4032780 Figure Legend: Geometry of the samples tested in SCW. (a) Samples used in the stress corrosion tests. (b) Samples used in the oxidation tests

Date of download: 11/8/2017 Copyright © ASME. All rights reserved. From: Influence of Changes in Pressure and Temperature of Supercritical Water on the Susceptibility to Stress Corrosion Cracking of 316L Austenitic Stainless Steel ASME J of Nuclear Rad Sci. 2016;3(1):011009-011009-6. doi:10.1115/1.4032780 Figure Legend: Stress–strain curves obtained after CERT tests in SCW at different pressures and temperatures

Date of download: 11/8/2017 Copyright © ASME. All rights reserved. From: Influence of Changes in Pressure and Temperature of Supercritical Water on the Susceptibility to Stress Corrosion Cracking of 316L Austenitic Stainless Steel ASME J of Nuclear Rad Sci. 2016;3(1):011009-011009-6. doi:10.1115/1.4032780 Figure Legend: Stress–strain curves for specimens strained in supercritical water up to failure at 400°C and 500°C/25  MPa/<10  ppb O2

Date of download: 11/8/2017 Copyright © ASME. All rights reserved. From: Influence of Changes in Pressure and Temperature of Supercritical Water on the Susceptibility to Stress Corrosion Cracking of 316L Austenitic Stainless Steel ASME J of Nuclear Rad Sci. 2016;3(1):011009-011009-6. doi:10.1115/1.4032780 Figure Legend: (a) Fracture surface of the specimen tested in supercritical water at 500°C/25  MPa/<10  ppb O2, granulated crack is highlighted. (b) The granulated crack at higher magnifications. (c) Fracture surface of the specimen tested in supercritical water at 400°C/25  MPa/<10  ppb O2. (d) An example of a crack found in the surface of a specimen tested in supercritical water (400°C/30  MPa/<10  ppb O2).

Date of download: 11/8/2017 Copyright © ASME. All rights reserved. From: Influence of Changes in Pressure and Temperature of Supercritical Water on the Susceptibility to Stress Corrosion Cracking of 316L Austenitic Stainless Steel ASME J of Nuclear Rad Sci. 2016;3(1):011009-011009-6. doi:10.1115/1.4032780 Figure Legend: Comparison between the microstructure obtained by EBSD before the test and the same surface after the test in supercritical water at 500°C/25  MPa/<10  ppb O2

Date of download: 11/8/2017 Copyright © ASME. All rights reserved. From: Influence of Changes in Pressure and Temperature of Supercritical Water on the Susceptibility to Stress Corrosion Cracking of 316L Austenitic Stainless Steel ASME J of Nuclear Rad Sci. 2016;3(1):011009-011009-6. doi:10.1115/1.4032780 Figure Legend: (a) Weight gains as a function of exposure time for the alloy 316L at 400°C/30  MPa with 8 ppm O2 and at 400°C/30  MPa in deaerated supercritical water. (b) SEM image of the surface of the specimen tested in supercritical water at 400°C/30  MPa/<10  ppb O2.

Date of download: 11/8/2017 Copyright © ASME. All rights reserved. From: Influence of Changes in Pressure and Temperature of Supercritical Water on the Susceptibility to Stress Corrosion Cracking of 316L Austenitic Stainless Steel ASME J of Nuclear Rad Sci. 2016;3(1):011009-011009-6. doi:10.1115/1.4032780 Figure Legend: Elemental composition profiles of oxide layers formed on the alloy 316L at (a) 400°C/30  MPa/<10  ppb O2 (528 hrs) and at (b) 400°C/30  MPa/8  ppm O2 (760 hrs)