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Ultrasonic Model Based Iterative Reconstruction of Experimental Concrete Specimens at EPR, ORNL/SPR-2022/2318.204154Ultrasonic Model Based Iterative Reconstruction of Experimental Concrete Specimens at EPRI, ORNL/SPR-2022/2318, N. Ezell, H. Sun, S. Venkatakrishnan, S. Sabatino, January 20223/31/2022 10:03:14 PMORNL/SPR-2022/2318 Ultrasonic Model Based Iterative Reconstruction of Experimental Concrete Specimens at EPRI N. Dianne Bull Ezell Hongbin Sun Singanallur Venkatakrishnan Sam 56https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf
Toward an understanding of straining mode, grain boundary oxidation and localized deformation on intergranular cracking of neutron irradiated austenitic stainless steels in pressurized water reactor relevant conditions231369Toward an understanding of straining mode, grain boundary oxidation and localized deformation on intergranular cracking of neutron irradiated austenitic stainless steels in pressurized water reactor relevant conditions, M2LW-21OR0402023, G. Was, S. Swaminathan, K. Sun, D. Du, September 2021.9/27/2021 9:01:42 PMM2LW-21OR0402023 Light Water Reactor Sustainability Program Toward an understanding of straining mode, grain boundary oxidation and localized deformation on intergranular cracking 109https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf
Fracture Toughness and Fatigue Crack Growth Rate Testing of Baffle-Former Bolts Harvested from a Westinghouse Two-Loop Downflow Type PWR, ORNL/TM-2021/2264.241224Fracture Toughness and Fatigue Crack Growth Rate Testing of Baffle-Former Bolts Harvested from a Westinghouse Two-Loop Downflow Type PWR, ORNL/TM-2021/2264, X. Chen, M. Sokolov, September 2021.11/5/2021 6:44:21 PMORNL/TM-2021/2264 ORNL IS MANAGED BY UT-BATTELLE LLC FOR THE US DEPARTMENT OF ENERGY Reports produced after January 1, 1996, are generally available free via US Department of 89https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf
Evaluation of Stress Corrosion Cracking Behavior of Ni-base Alloys in PWR Primary Water Containing KOH vs. LiOH , M2LW-21OR0402036.221026Evaluation of Stress Corrosion Cracking Behavior of Ni-base Alloys in PWR Primary Water Containing KOH vs. LiOH, M2LW-21OR0402036, Z. Zhai, M. Toloczko, F. Colon, R. Bouffious, September 2021.9/21/2021 8:23:26 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 Dr. John Jackson and Mr. Michael 58https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf
Electrochemical profiling of physical damage in nuclear core components 231148Electrochemical profiling of physical damage in nuclear core components, M2LW-21OR0402027, X. Chen, M. Gussev, G. Sant, September 2021.9/20/2021 4:01:51 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 107https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf
Development of Digital Twin Predictive Model for PWR Components: Updates on Multi Times Series Temperature Prediction Using Recurrent Neural Network, DMW Fatigue Tests, System Level Thermal-Mechanical-Stress Analysis231297Development of Digital Twin Predictive Model for PWR Components: Updates on Multi Times Series Temperature Prediction Using Recurrent Neural Network, DMW Fatigue Tests, System Level Thermal-Mechanical-Stress Analysis, M2LW-21OR0402027, X. Chen, M. Gussev, G. Sant, September 2021.9/18/2021 3:06:10 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 67https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf
Improve the design of and assess upgrades to the Friction Stir welding system to reduce defects on surrogate unirradiated materials, ORNL/TM-2021/2242.240239Improve the design of and assess upgrades to the Friction Stir welding system to reduce defects on surrogate unirradiated materials, ORNL/TM-2021/2242, R. Miller, Z. Feng, J. Chen, September 2021.10/7/2021 5:47:19 PMU.S. Department of Energy Office of Nuclear Energy This manuscript has been authored by UT-Battelle, LLC under Contract No. DE-AC05-00OR22725 with the U.S. Department of Energy 44https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf
Nondestructive Evaluation (NDE) of Cable Moisture Exposure using Frequency Domain Reflectometry (FDR), PNNL-31934.124035Nondestructive Evaluation (NDE) of Cable Moisture Exposure using Frequency Domain Reflectometry (FDR), PNNL-31934, S. Glass, M. Spencer, A. Sriraman, L. Fifield, M. Prowant, September 2021.9/17/2021 7:54:19 AMLight Water Reactor Sustainability Program Nondestructive Evaluation (NDE) of Cable Moisture Exposure using Frequency Domain Reflectometry (FDR) September 2021 U.S. Department 151https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf
Effect of thermal aging and irradiation on microstructure and crack growth response of Alloy 690, ANL/LWRS-21/1.231386Effect of thermal aging and irradiation on microstructure and crack growth response of Alloy 690, ANL/LWRS-21/1, B. Alexandreanu,, Y. Chen, x. Zhang, W. Chen, September 2021.9/9/2021 5:22:06 AMANL/LWRS-21/1 Effect of thermal aging and irradiation on microstructure and crack growth response of Alloy 690 LWRS milestone Report Number: M3LW-21OR0402039 Nuclear Science and 228https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf
Microstructure and Mechanical Performance of the Friction Stir Welds Performed on Neutron-Irradiated Steel with Helium, ORNL/TM-2021/2079.231366Microstructure and Mechanical Performance of the Friction Stir Welds Performed on Neutron-Irradiated Steel with Helium, ORNL/TM-2021/2079, M. Gussev, W. Tan, N. Bibhanshu, T. Rosseel, August 2021.8/31/2021 9:56:14 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 40https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf