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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 conditions, M2LW-21OR0402023, G. Was, S. Swaminathan, K. Sun, D. Du, September 2021.
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 conditions9/27/2021
  
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, X. Chen, M. Sokolov, September 2021.
Fracture Toughness and Fatigue Crack Growth Rate Testing of Baffle-Former Bolts Harvested from a Westinghouse Two-Loop Downflow Type PWR9/22/2021
  
Reactor Pressure Vessel
Evaluation 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.
Evaluation of Stress Corrosion Cracking Behavior of Ni-base Alloys in PWR Primary Water Containing KOH vs. LiOH 9/21/2021
  
Concrete
Electrochemical profiling of physical damage in nuclear core components, M2LW-21OR0402027, X. Chen, M. Gussev, G. Sant, September 2021.
Electrochemical profiling of physical damage in nuclear core components 9/20/2021
  
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 Analysis, M2LW-21OR0402027, X. Chen, M. Gussev, G. Sant, September 2021.
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 Analysis9/17/2021
  
Improve 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.
Improve the design of and assess upgrades to the Friction Stir welding system to reduce defects on surrogate unirradiated materials9/17/2021
  
Nondestructive 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.
Nondestructive Evaluation (NDE) of Cable Moisture Exposure using Frequency Domain Reflectometry (FDR)9/16/2021
  
Effect 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.
Effect of thermal aging and irradiation on microstructure and crack growth response of Alloy 6909/9/2021
  
Microstructure 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.
Microstructure and Mechanical Performance of the Friction Stir Welds Performed on Neutron-Irradiated Steel with Helium8/31/2021
  
Development of a Reconstruction Methodology Based on X-Ray Computed Tomography to Generate Realistic 3D Concrete Microstructures in MOSAIC, ORNL/TM-2021/2156, A. Cheniour, Y. Li, Y. LePape, J. Arregui-Mena, E. Cakmak, E. Rodriquez, T. Rosseel, August 2021.
Development of a Reconstruction Methodology Based on X-Ray Computed Tomography to Generate Realistic 3D Concrete Microstructures in MOSAIC.8/26/2021
  
Conduct weld campaign (FY-21-1) on irradiated materials provided by the Canadian Nuclear Laboratory (CNL), including baseline post-weld evaluation and testing, ORNL/TM-2020/1673, J. Chen, Z. Feng, R. Miller, S. White, W. Li, L. Water, J. Tatman, G. Frederick, August 2021.
Conduct weld campaign (FY-21-1) on irradiated materials provided by the Canadian Nuclear Laboratory (CNL), including baseline post-weld evaluation and testing8/13/2021
  
Inhomogeneous Aging of Nuclear Power Plant Electrical Cable Insulation, PNNL-31443, L. L. Fifield, W. Fuchs, Y. Ni, D. Li, M. Pallaka, A. Arteaga, M. Spencer, A. Zwoster, June 2021.
Inhomogeneous Aging of Nuclear Power Plant Electrical Cable Insulation6/25/2021
  
Sequential Versus Simultaneous Aging of XLPE and EPDM Nuclear Cable Insulation Subjected to Elevated Temperature and Gamma Radiation (Final Results), PNNL-30041 Rev. 1, L. Fifield, M. Spencer, Y. Ni, D. Li, M. Pallaka, T. Bisel, A. Zwoster, M. Murphy, December 2020.
Sequential Versus Simultaneous Aging of XLPE and EPDM Nuclear Cable Insulation Subjected to Elevated Temperature and Gamma Radiation (Final Results)12/12/2020
  
Cables
Sequential Versus Simultaneous Aging of XLPE and EPDM Nuclear Cable Insulation Subjected to Elevated Temperature and Gamma Radiation (Finial Results), PNNL-30041, L. Fifield, M Spencer, Y. Ni, D. Li, M. Pallaka, T. Bisel, A. Zwoster, M. Murphy, December 2020.
Sequential Versus Simultaneous Aging of XLPE and EPDM Nuclear Cable Insulation Subjected to Elevated Temperature and Gamma Radiation (FInal Results)12/11/2020
  
Cables
Evaluation of Critical Parameters to Model Stress Corrosion Crack Initiation in Alloy 600 and Alloy 182 in PWR Primary Water, M2LW-20OR0402036, Z. Zhai, J. Wang, M. Toloczko, S. Bruemmer, September 2020.
Evaluation of Critical Parameters to Model Stress Corrosion Crack Initiation in Alloy 600 and Alloy 182 in PWR Primary Water9/21/2020
  
Reactor Core and Primary Systems
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, M2LW-20OR0402023, G. Was, D. Du, September 2020.
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, 9/21/2020
  
Reactor Core and Primary Systems
Potential Life Extension Strategies for In-Service Degraded Cables, PNNL-30402, S. Nune, M. Spencer, L. Fifield, September 2020.
Potential Life Extension Strategies for In-Service Degraded Cables9/21/2020
  
Cables
Intermediate-Term Thermal Aging Effect Evaluation for Grade 92 and 316L at the LWR Relevant Temperature, ORNL/TM-2020/1754, L. Tan, X. Chen, September 30, 2020.
Intermediate-Term Thermal Aging Effect Evaluation for Grade 92 and 316L at the LWR Relevant Temperature9/21/2020
  
Mitigation
A Hybrid AI/ML and Computational Mechanics Based Approach for Time-Series State and Fatigue Life Estimation of Nuclear Reactor Components, ANL/LWRS-20/01, S. Mohanty, J. Listwan, September 2020.
A Hybrid AI/ML and Computational Mechanics Based Approach for Time-Series State and Fatigue Life Estimation of Nuclear Reactor Components9/21/2020
  
Reactor Core and Primary Systems
Analysis of Deformation Localization Mechanisms in Highly Irradiated Austenitic Stainless Steel via In Situ Techniques,ORNL/TM-2020/1739,  M. Gussev, N. Bibhanshu, E. Cakmak, J. Dixon, September 2020.
Analysis of Deformation Localization Mechanisms in Highly Irradiated Austenitic Stainless Steel via In Situ Techniques9/21/2020
  
Reactor Core and Primary Systems
Quantifying micro-galvanic corrosion in stainless steels activated by post-yielding microstructures, M2LW-20R0402027, X. Chen, M. Gussev, G. Sant, September 2020.
Quantifying micro-galvanic corrosion in stainless steels activated by post-yielding microstructures9/21/2020
  
Reactor Core and Primary Systems
Assessment of Grizzly Capabilities for Reactor Pressure Vessels and Reinforced Concrete Structures, INL/EXT-20-00617, B. Spencer, W. Hoffman, S. Biswas, A. Jain, September 2020.
Assessment of Grizzly Capabilities for Reactor Pressure Vessels and Reinforced Concrete Structures9/21/2020
  
Reactor Pressure Vessel and Concrete
Cable Nondestructive Examination Online Monitoring for Nuclear Power Plants, PNNL-155612, S. Glass, L. Fifield, N. Bowler, September 2020.
Cable Nondestructive Examination Online Monitoring for Nuclear Power Plants9/20/2020
  
Cables
Sequential Versus Simultaneous Aging of XLPE and EPDM Nuclear Cable Insulation Subjected to Elevated Temperature and Gamma Radiation, PNNL-30041, L.S. Fifield, M.P. Spencer, A. Zwoster, T.T. Bisel, M.K. Murphy, June 2020.
Sequential Versus Simultaneous Aging of XLPE and EPDM Nuclear Cable Insulation Subjected to Elevated Temperature and Gamma Radiation6/16/2020
  
Cables
Long-Term Crack Initiation Behavior of Alloy 690 and Its Weld Metals in PWR Primary Water, Z. Zhai, M.Olszta, M. Toloczko, and S. Bruemmer, March 2020
Long-Term Crack Initiation Behavior of Alloy 690 and Its Weld Metals in PWR Primary Water3/10/2020
  
Reactor Pressure Vessel and Concrete
Progress on Grizzly Development for Reactor Pressure Vessels and Reinforced Concrete Structures, INL/EXT-19-56012, B. Spencer, W. Hoffman, D. Schwen, S. Biswas, September 2019.
Progress on Grizzly Development for Reactor Pressure Vessels and Reinforced Concrete Structures9/18/2019
  
Reactor Pressure Vessel
Dielectric Spectroscopy for Bulk Condition Assessment of Cable Insulation, PNNL-29092, S. Glass, L. Fifield, N. Bowler, A. Sriraman, C. Gifford, September 2019.
Dielectric Spectroscopy for Bulk Condition Assessment of Cable Insulation9/14/2019
  
Cables
Steam Oxidation of Alloy 718a and Tensile Properties of Select Advanced Replacement Alloys for LWR Core Internals, ORNL/TM-2019/1308, L. Tan, B. Pint, September 13, 2019.
Steam Oxidation of Alloy 718a and Tensile Properties of Select Advanced Replacement Alloys for LWR Core Internals9/12/2019
  
Mitigation
Comparative Analysis of Nondestructive Examination Techniques of Enhanced Model Based Iterative Reconstruction (MBIR) and Frequency-banded Synthetic Aperture Focusing Technique (SAFT) Reconstructions, ORNL/SPR-2019/1240, N. Ezell, S. Venkatakrishnan, H. Santos-Villalobos, A. Albright, September 2019.
Comparative Analysis of Nondestructive Examination Techniques of Enhanced Model Based Iterative Reconstruction (MBIR) and Frequency-banded Synthetic Aperture Focusing Technique (SAFT) Reconstructions9/11/2019
  
Concrete
A System-Level Framework for Fatigue Life Prediction of a PWR Pressurizer-Surge-Line Nozzle under Design-basis Loading Cycles, ANL/LWRS-19/01, S. Mohanty, J. Listwan, J. Phil Park, September 2019.
A System-Level Framework for Fatigue Life Prediction of a PWR Pressurizer-Surge-Line Nozzle under Design-basis Loading9/5/2019
  
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