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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 22https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf
Long-Term Crack Initiation Behavior of Alloy 690 and Its Weld Metals in PWR Primary Water251344/1/2020 6:59:50 PMLight Water Reactor Sustainability Program Long-Term Crack Initiation Behavior of Alloy 690 and Its Weld Metals in PWR Primary Water March 2020 U.S. Department of Energy Office of 21https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf
Progress on Grizzly Development for Reactor Pressure Vessels and Reinforced Concrete Structures252789/30/2019 9:21:36 PMINL/EXT-19-56012 Light Water Reactor Sustainability Program Progress on Grizzly Development for Reactor Pressure Vessels and Reinforced Concrete Structures Benjamin W. Spencer 15https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf
Dielectric Spectroscopy for Bulk Condition Assessment of Cable Insulation254369/11/2019 4:50:40 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 A. Sriraman 2 , C. Gifford 2 15https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf
Steam Oxidation of Alloy 718a and Tensile Properties of Select Advanced Replacement Alloys for LWR Core Internals252479/13/2019 9:27:05 PMORNL/TM-2019/1308 Steam Oxidation of Alloy 718A and Tensile Properties of Select Advanced Replacement Alloys for LWR Core Internals Lizhen Tan Bruce Pint 16https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf
Comparative Analysis of Nondestructive Examination Techniques of Enhanced Model Based Iterative Reconstruction (MBIR) and Frequency-banded Synthetic Aperture Focusing Technique (SAFT) Reconstructions246429/13/2019 1:12:59 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 11https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf
A System-Level Framework for Fatigue Life Prediction of a PWR Pressurizer-Surge-Line Nozzle under Design-basis Loading252579/26/2019 11:32:39 PMA Complete Tensile Test Based Material Properties Database and Preliminary Results on Weld Process Modeling, Thermal-Mechanical Stress Analysis and Environmental Fatigue Testing 12https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf
Elucidating The Grain-Orientation Dependent Oxidation Rates Of Austenitic Stainless Steels 253869/20/2019 8:04:06 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 13https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf
Grain Boundary Microstructure Effects On Stress Corrosion Crack Initiation Mechanisms In Alloy 600 And Alloy 690253998/30/2019 5:53:53 PMThe focus of the work is to investigate important material (composition, processing, microstructure, strength) and environmental (temperature, water chemistry, electrochemical 11https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf
Recent Technological Advances In Welding Irradiated Austenitic Steel With Helium,250599/26/2019 11:35:01 PMLight Water Reactor Sustainability Program Recent Technological Advances in Welding Irradiated Austenitic Steel with Helium M3LW-19OR0406015 Neither the U.S. Government nor any 15https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf