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Evaluation of Critical Parameters to Model Stress Corrosion Crack Initiation in Alloy 600 and Alloy 182 in PWR Primary Water2004859/15/2020 6:13:28 PMU.S. Department of Energy Office of Nuclear Energy This information was prepared as an account of work sponsored by an agency of the U.S. Government In this report, a brief summary 45https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf
Evaluation of the stress and fluence dependence of irradiation assisted stress corrosion crack initiation in high fluence austenitic stainless steels under pressurized water reactor relevant conditions, 2004869/28/2020 7:16:42 PMM2LW-20OR0402023 Light Water Reactor Sustainability Program Evaluation of the stress and fluence dependence of irradiation assisted stress corrosion crack initiation in high 43https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf
Potential Life Extension Strategies for In-Service Degraded Cables2004879/17/2020 12:42:36 AMU.S. Department of Energy Office of Nuclear Energy This information was prepared as an account of work sponsored by an agency of the U.S. Government As cable materials age over time 46https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf
Intermediate-Term Thermal Aging Effect Evaluation for Grade 92 and 316L at the LWR Relevant Temperature2004889/27/2020 3:05:21 PMReports produced after January 1, 1996, are generally available free via US Department of Energy (DOE) SciTech Connect Reports produced before January 1, 1996, may be purchased by 53https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf
A Hybrid AI/ML and Computational Mechanics Based Approach for Time-Series State and Fatigue Life Estimation of Nuclear Reactor Components2004899/22/2020 12:17:05 AMArgonne is a U.S. Department of Energy laboratory managed by UChicago Argonne, LLC under contract DE-AC02-06CH11357 The Laboratory’s main facility is outside Chicago, at 9700 56https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf
Analysis of Deformation Localization Mechanisms in Highly Irradiated Austenitic Stainless Steel via In Situ Techniques2004909/24/2020 3:01:38 AMReports produced after January 1, 1996, are generally available free via US Department of Energy (DOE) SciTech Connect Reports produced before January 1, 1996, may be purchased by 67https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf
Quantifying micro-galvanic corrosion in stainless steels activated by post-yielding microstructures2004919/15/2020 5:11:01 PMU.S. Department of Energy Office of Nuclear Energy This information was prepared as an account of work sponsored by an agency of the U.S. Government This research was carried out in 40https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf
Assessment of Grizzly Capabilities for Reactor Pressure Vessels and Reinforced Concrete Structures2004929/15/2020 3:24:29 PMINL/EXT-20-00617 Light Water Reactor Sustainability Program Assessment of Grizzly Capabilities for Reactor Pressure Vessels and Reinforced Concrete Structures Benjamin W 40https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf
Cable Nondestructive Examination Online Monitoring for Nuclear Power Plants20049310/21/2020 9:11:48 PMU.S. Department of Energy Office of Nuclear Energy This information was prepared as an account of work sponsored by an agency of the U.S. Government To date, there are few examples 58https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf
Sequential Versus Simultaneous Aging of XLPE and EPDM Nuclear Cable Insulation Subjected to Elevated Temperature and Gamma Radiation252906/24/2020 5:59:37 PMU.S. Department of Energy Office of Nuclear Energy This information was prepared as an account of work sponsored by an agency of the U.S. Government This report addresses one of the 72https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf