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Inhomogeneous Aging of Nuclear Power Plant Electrical Cable Insulation, PNNL-31443.231379Cable Aging Degradation and Gap AnalysisInhomogeneous 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 2021.6/25/2021 8:17:29 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 Aging at the interior edge of 39https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2021-06-25T06:00:00Z
A System-Level Framework for Fatigue Life Prediction of a PWR Pressurizer-Surge-Line Nozzle under Design-basis Loading, ANL/LWRS-19/01.25257Cable Aging Degradation and Gap AnalysisA 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 2019.9/26/2019 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 160https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2019-09-05T06:00:00Z
Sequential Versus Simultaneous Aging of XLPE and EPDM Nuclear Cable Insulation Subjected to Elevated Temperature and Gamma Radiation (Final Results), PNNL-30041.97503CablesSequential 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 2020.12/11/2020 10:34:11 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 256https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2020-12-12T07:00:00Z
Potential Life Extension Strategies for In-Service Degraded Cables, PNNL-30402.200487CablesPotential Life Extension Strategies for In-Service Degraded Cables, PNNL-30402, S. Nune, M. Spencer, L. Fifield, September 2020.9/17/2020 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 273https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2020-09-21T06:00:00Z
Cable Nondestructive Examination Online Monitoring for Nuclear Power Plants, PNNL-155612.200493CablesCable Nondestructive Examination Online Monitoring for Nuclear Power Plants, PNNL-155612, S. Glass, L. Fifield, N. Bowler, September 2020.10/21/2020 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 320https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2020-09-20T06:00:00Z
Sequential Versus Simultaneous Aging of XLPE and EPDM Nuclear Cable Insulation Subjected to Elevated Temperature and Gamma Radiation, PNNL-30041.25290CablesSequential 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 2020.6/24/2020 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 279https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2020-06-16T06:00:00Z
Dielectric Spectroscopy for Bulk Condition Assessment of Cable Insulation, PNNL-29092.25436CablesDielectric Spectroscopy for Bulk Condition Assessment of Cable Insulation, PNNL-29092, S. Glass, L. Fifield, N. Bowler, A. Sriraman, C. Gifford, September 2019.9/11/2019 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 176https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2019-09-14T06:00:00Z
Evaluation of Inverse Temperature Effects on Cable Insulation Degradation in Accelerated Aging of High Priority Cable Insulation Materials, PNNL-29051.25389CablesEvaluation of Inverse Temperature Effects on Cable Insulation Degradation in Accelerated Aging of High Priority Cable Insulation Materials, PNNL-29051, L. Fifield, M. Murphy, A. Zwoster, T. Bisel, August 2019.8/30/2019 9:46:20 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 dose rate of 100 Gy/h was 93https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2019-08-18T06:00:00Z
Assessment of electrical breakdown strength relative to mechanical properities in insulations from harvested cable systems from nuclear power plants, ORNL SPR-2019/1145.24647CablesAssessment of electrical breakdown strength realtive to mechanical properities in insulations from harvested cable systems from nuclear power plants, ORNL SPR-2019/1145, R. Duckworth, April 2019.4/30/2019 4:46:08 PM57https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2019-04-12T06:00:00Z
Report on Initial Evaluations of Effects of Diffusion Limited Oxidation (DLO) Testing, PNNL-28351.25236CablesReport on Initial Evaluations of Effects of Diffusion Limited Oxidation (DLO) Testing, PNNL-28351, L. Fifield, A. Zwoster, M. Murphy, Z. Zhu, R. Subella, December 2018.12/21/2018 7:49:39 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 The DLO knowledge gap raises the 106https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2018-12-18T07:00:00Z
Investigation of Thermal Aging Behavior for Harvested Crosslinked, PNNL-27729.25240CablesInvestigation of Thermal Aging Behavior for Harvested Crosslinked Polyethylene and Ethylene-Propylene Rubber Cable Insulation, PNNL-27729, L. Fifield, M. Correa, Y. Shin, A. Zwoster, July 2018.7/30/2018 3:47:41 PMPNNL-27729 Light Water Reactor Sustainability Program Investigation of Thermal Aging Behavior for Harvested Crosslinked Polyethylene and Ethylene-Propylene Rubber Cable Insulation 124https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2018-07-29T06:00:00Z
Interdigital Capacitance Local Non-Destructive Examination of Nuclear Power Plant Cable for Aging Management Programs, PNNL-27546.25237CablesInterdigital Capacitance Local Non-Destructive Examination of Nuclear Power Plant Cable for Aging Management Programs, PNNL-27546, S. Glass, L. Fifield, N. Bowler, A. Sriraman, W. Palmer, May 2018.9/11/2018 6:26:53 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 typical test strategy is to 264https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2018-05-18T06:00:00Z
Crystal River 3 Cable Materials for Thermal and Gamma Radiation Aging September 2017 U.S., PNNL-26785.25429CablesCrystal River 3 Cable Materials for Thermal and Gamma Radiation Aging, PNNL-26785, L. Fifield, M. Correa, A. Zwoster, September 2017.9/8/2017 4:01:28 PMPNNL-26785 Light Water Reactor Sustainability Program Crystal River 3 Cable Materials for Thermal and Gamma Radiation Aging September 2017 U.S. Department of Energy Office of 175https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2017-09-20T06:00:00Z
Accelerated Thermal Aging Of Harvested Zion Electrical Cable Jacket And Insulation (Interim Report)24639CablesAccelerated Thermal Aging Of Harvested Zion Electrical Cable Jacket And Insulation (Interim Report), M3LW-17OR0404110, R. Duckworth, July 2017.8/3/2017 4:33:41 PMM3LW-17OR0404110 Revision 0 Light Water Reactor Sustainability Program ACCELERATED THERMAL AGING OF HARVESTED ZION ELECTRICAL CABLE JACKET AND INSULATION (INTERIM REPORT) July 102https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2017-07-01T06:00:00Z
Analysis of simultaneous thermal/gamma radiation aging of cross-linked polyethylene (XLPE) insulation—interim status report, PNNL-26554.24643CablesAnalysis of simultaneous thermal/gamma radiation aging of cross-linked polyethylene (XLPE) insulation—interim status report, PNNL-26554, L. Fifield, M. Correa, June 2017.6/19/2017 9:30:44 PMNeither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the 86https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2017-06-01T06:00:00Z
Physics-Based Modeling of Cable Insulation Conditions for Frequency Domain Reflectometry (FDR), PNNL-26493.25447CablesPhysics-Based Modeling of Cable Insulation Conditions for Frequency Domain Reflectometry (FDR), PNNL-26493, S. Glass, A. Jones, L. Fifield, T. Hartman, N. Bowler, May 2017.6/1/2017 3:51:35 PMPNNL-26493 Light Water Reactor Sustainability Program Physics-Based Modeling of Cable Insulation Conditions for Frequency Domain Reflectometry (FDR) May 2017 U.S. Department of 145https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2017-05-18T06:00:00Z
Update on Combined Thermal/Radiation Aging at Five Dose Rates in Chlorosulfonated Polyethylene (Hypalon)/Ethylene-Propylene Rubber (EPR) Cable Jacket Insulation System25066CablesUpdate on Combined Thermal/Radiation Aging at Five Dose Rates in Chlorosulfonated Polyethylene (Hypalon)/Ethylene-Propylene Rubber (EPR) Cable Jacket Insulation System, M3LW-17OR0404019, R. Duckworth, March 2017.3/29/2017 5:23:27 PMM3LW-17OR0404019 Revision 0 Light Water Reactor Sustainability Program UPDATE ON COMBINED THERMAL/RADIATION AGING AT FIVE DOSE RATES IN CHLOROSULFONATED POLYETHYLENE (HYPALON 113https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2017-03-18T06:00:00Z
Bulk and Distributed Electrical Cable Non-Destructive Examination Methods for Nuclear Power Plant Cable Aging Management Programs, PNNL-25634.24649CablesBulk and Distributed Electrical Cable Non-Destructive Examination Methods for Nuclear Power Plant Cable Aging Management Programs, PNNL-25634, S. Glass, A. Jones, L. Fifield, T. Hartman, September 2016.9/13/2016 10:09:06 PMNeither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the 130https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2016-09-01T06:00:00Z
Status Report and Research Plan for Cables Harvested from Crystal River Unit 3 Nuclear Generating Plant, PNNL-25833.25246CablesStatus Report and Research Plan for Cables Harvested from Crystal River Unit 3 Nuclear Generating Plant, PNNL-25833, L. Fifield, September 2016.9/22/2016 2:33:32 PMPNNL-25833 Light Water Reactor Sustainability Program Status Report and Research Plan for Cables Harvested from Crystal River Unit 3 Nuclear Generating Plant September 2016 U.S. 129https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2016-09-01T06:00:00Z
Progress in Characterizing Thermal Degradation of Ethylene-Propylene Rubber, PNNL-25713.25276CablesProgress in Characterizing Thermal Degradation of Ethylene-Propylene Rubber, PNNL-25713, L. Fifield, Q. Huang, M. Childers, M. Correa, Y. Shin, A. Zwoster, August 20168/29/2016 8:24:29 PMM3LW-16OR0404014 PNNL-25713 Light Water Reactor Sustainability Program Progress in Characterizing Thermal Degradation of Ethylene-Propylene Rubber August 2016 U.S. Department of 151https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2016-08-01T06:00:00Z
Progress in Characterizing Naturally-Aged Nuclear Power Plant Cables, PNNL-25439.25277CablesProgress in Characterizing Naturally-Aged Nuclear Power Plant Cables, PNNL-25439, L. Fifield, Q. Huang, M. Ian Childers, A. Zwoster, May 2016.5/31/2016 6:47:00 PMM3LW-16OR0404013 PNNL-25439 Light Water Reactor Sustainability Program Progress in Characterizing NaturallyAged Nuclear Power Plant Cables May 2016 U.S. Department of Energy 283https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2016-05-01T06:00:00Z
Evaluation of Localized Cable Test Methods for Nuclear Power Plant Cable Aging Management Programs, PNNL-25432.25390CablesEvaluation of Localized Cable Test Methods for Nuclear Power Plant Cable Aging Management Programs, PNNL-25432, S. Glass, L. Fifield, T. Hartman, May 2016.5/31/2016 9:24:50 PMM3LW-16OR0404022 PNNL-25432 Light Water Reactor Sustainability Program Evaluation of Localized Cable Test Methods for Nuclear Power Plant Cable Aging Management Programs May 2016 148https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2016-05-01T06:00:00Z
Characterizing oxidation of cross-linked polyethylene and ethylene propylene rubber insulation materials by differential scanning calorimeter24653CablesCharacterizing oxidation of cross-linked polyethylene and ethylene propylene rubber insulation materials by differential scanning calorimeter, L. Fifield, J. Liu, Q. Huang, A. Zwoster, PNNL-25172, January 2016.1/30/2016 4:56:48 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 DSC measures the heat flow into 320https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2016-01-03T07:00:00Z
State-of-the-Art Assessment of NDE Techniques for Aging Cable Management in Nuclear Power Plants FY2015, PNNL-24649.25245CablesState-of-the-Art Assessment of NDE Techniques for Aging Cable Management in Nuclear Power Plants FY2015, S. Glass, L. Fifield, G. Dib, J. Tedeschi, A. Jones, T. Hartman, PNNL-24649, September 2015.9/8/2015 3:31:11 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 SW Glass, LS Fifield, G Dib, JR 88https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2015-09-08T06:00:00Z
Progress on Analysis of Inverse Temperature Effects, Submerged Cables, Diffusion Limited Oxidation and Dose Rate Effects PNNL-24634 September 201525056CablesProgress on Analysis of Inverse Temperature Effects, Submerged Cables, Diffusion Limited Oxidation and Dose Rate Effects. L.S. Fifield, M. P. Westman, M. K. Murphy, A. J. Zwoster, PNNL-24634, September 2015.9/1/2015 5:55:32 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 While the research at PNNL is at 128https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2015-09-01T06:00:00Z
Assessment of Additional Key Indicators of Aging Cables in Nuclear Power Plants – Interim Status for FY 2015, PNNL-24649.25051CablesAssessment of Additional Key Indicators of Aging Cables in Nuclear Power Plants – Interim Status for FY 2015, P. Ramuhalli, L. Fifield, M. Prowant, G. Dib, J. Tedeschi, J. Suter, A. Jones, M. Good, S. Glass, A. Pardini, PNNL-24309, Pacific Northwest National Laboratory, May 2015.5/15/2015 6:09:49 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 With greater than 1000 km of 78https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2015-05-01T06:00:00Z
Thermal aging modeling and validation on the Mo containing Fe-Cr-Ni alloys, Y. Yang, L. Tan, and J. Busby, ORNL/TM-2015/93, Oak Ridge National Laboratory, March 2015.25143CablesThermal aging modeling and validation on the Mo containing Fe-Cr-Ni alloys, Y. Yang, L. Tan, and J. Busby, ORNL/TM-2015/93, Oak Ridge National Laboratory, March 2015.3/27/2015 5:35:22 PMORNL/TM-2015/93 Light Water Reactor Sustainability Program Thermal aging modeling and validation on the Mo containing FeCr-Ni alloys March 2015 U.S. Department of Energy Office of 52https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2015-03-01T07:00:00Z
New Technologies for Repairing Aging Cables in Nuclear Power Plants, K. Simmons, L. Fifield, M. Westman, and J. Roberts, Pacific Northwest National Laboratory, September 201424766CablesNew Technologies for Repairing Aging Cables in Nuclear Power Plants, K. Simmons, L. Fifield, M. Westman, and J. Roberts, Pacific Northwest National Laboratory, PNNL-XXXX, September 2014.9/3/2014 2:15:48 AMPNNL-XXXX Prepared for the U.S. Department of Energy under Contract DE-AC05-76RL01830 The goal of this project is to conceptually demonstrate techniques to repair cables that have 103https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2014-09-01T06:00:00Z
Determining Remaining Useful Life of Aging Cables in Nuclear Power Plants—Interim Status for FY 2014, K. Simmons, L. Fifield, M Westman, J. Tedeschi, A. Jones, M. Prowant, A. Pardini, and P. Ramuhalli, Pacific Northwest National Laboratory, PNNL-23624.25453CablesDetermining Remaining Useful Life of Aging Cables in Nuclear Power Plants—Interim Status for FY 2014, K. Simmons, L. Fifield, M Westman, J. Tedeschi, A. Jones, M. Prowant, A. Pardini, and P. Ramuhalli, Pacific Northwest National Laboratory, PNNL-23624, September 2014.9/17/2014 1:53:20 PMPNNL-23624 Determining Remaining Useful Life of Aging Cables in Nuclear Power Plants – Interim Status for FY2014 Milestone Report M3LW-140R04022 September 2014 KL Simmons AM Jones 658https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2014-09-01T06:00:00Z
Preliminary List of Aging Conditions and Measurement Methods to be Examined for Key Indicators of Cable Aging – Status Summary, K. Simmons, PNNL, April 201324650CablesPreliminary List of Aging Conditions and Measurement Methods to be Examined for Key Indicators of Cable Aging – Status Summary, K. Simmons, PNNL, April 2013.4/8/2013 9:30:46 PMTel: (509) 375-3651 Fax: (509) 375-2186 MSIN: K2-44 kl.simmons@pnnl.gov April 2, 2013 To Dr. Jeremy Busby Fuel Cycle and Isotopes Division Oak Ridge National Laboratory P.O. 43https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2013-05-01T06:00:00Z
Nondestructive Examination (NDE) Detection and Characterization of Degradation Precursors, PNNL-21692, P. Ramuhalli J.W. Griffin, R.M. Meyer, S.G. Pitman, J.M. Fricke, M.E. Dahl, M.S. Prowant, T.A. Kafentzis, J.B. Coble, T.J. Roosendaal, September 2012.25452CablesNondestructive Examination (NDE) Detection and Characterization of Degradation Precursors, PNNL-21692, P. Ramuhalli J.W. Griffin, R.M. Meyer, S.G. Pitman, J.M. Fricke, M.E. Dahl, M.S. Prowant, T.A. Kafentzis, J.B. Coble, T.J. Roosendaal, September 2012.9/4/2012 8:29:36 PMPNNL-21692 Prepared for the U.S. Department of Energy under Contract DE-AC05-76RL01830 Technical Progress Report for FY 2012 The overall objective of this project was to investigate 198https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2012-09-01T06:00:00Z
Assessment of Opportunities for Acquiring Plant Materials to Aid in Model Validation, G. Von White and R. Bernstein, Sandia National Laboratory, June 2012.25398CablesAssessment of Opportunities for Acquiring Plant Materials to Aid in Model Validation, G. Von White and R. Bernstein, Sandia National Laboratory, June 2012.7/2/2012 11:03:13 PMdate: Jun to: Jer from: Gre Rob subject: FY 1. Explo S accelera t manufact ultimatel (e.g., the validatin (cables w A model va sources: 2 75https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2012-06-01T06:00:00Z
Ultrasonic Model Based Iterative Reconstruction of Experimental Concrete Specimens at EPR, ORNL/SPR-2022/2318.204154ConcreteUltrasonic 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.aspxpdfFalsepdf2022-01-01T07:00:00Z
Evaluation of Stress Corrosion Cracking Behavior of Ni-base Alloys in PWR Primary Water Containing KOH vs. LiOH , M2LW-21OR0402036.221026ConcreteEvaluation 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.aspxpdfFalsepdf2021-09-21T06:00:00Z
Comparative Analysis of Nondestructive Examination Techniques of Enhanced Model Based Iterative Reconstruction (MBIR) and Frequency-banded Synthetic Aperture Focusing Technique (SAFT) Reconstructions, ORNL/SPR-2019/1240.24642ConcreteComparative 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 2019.9/13/2019 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 235https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2019-09-11T06:00:00Z
Two-Modulator Generalized Ellipsometry Microscope, ORNL/TM-2019/1025.24764ConcreteTwo-Modulator Generalized Ellipsometry Microscope (2-MGEM) Examination of Concrete Aggregates, ORNL/TM-2019/1025, G. Jellison Jr., L. Anovitz, and T. M. Rosseel, June 2019.12/19/2019 4:10:29 AMORNL/TM-2019/1025 Revision 0 Two-modulator Generalized Ellipsometry Microscope (2-MGEM) Examination of Concrete Aggregates MILESTONE M3LW-19OR0403047, WORK PACKAGE: LW-19OR040304 109https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2019-06-01T06:00:00Z
Microstructural characterization of the alkali-silica reaction (ASR)-induced damage in structural concrete test blocks at the University of Tennessee, Knoxville, ORNL/SPR-2019/1139.24661ConcreteMicrostructural characterization of the alkali-silica reaction (ASR)-induced damage in structural concrete test blocks at the University of Tennessee, Knoxville, ORNL/SPR-2019/1139, Y. Pape, N. Hayes, E. Rodriquez, J. Arregui-Mena, T. Rosseel, May 2019.5/1/2019 6:20:27 PMWebsite: http://www.osti.gov/scitech/ Reports produced before January 1, 1996, may be purchased by members of the public from the following source: National Technical Information 69https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2019-05-28T06:00:00Z
Identification of Mechanisms to Study Alkali-Silica Reaction Effects on Stress-Confined Concrete Nuclear Thick Structures: Interpretation of the Complete Monitoring Data and Nondestructive Evaluation of the Alkali-Silica Reaction Test Assembly25229ConcreteIdentification of Mechanisms to Study Alkali-Silica Reaction Effects on Stress-Confined Concrete Nuclear Thick Structures: Interpretation of the Complete Monitoring Data and Nondestructive Evaluation of the Alkali-Silica Reaction Test Assembly, ORNL/SPR-2018/965, N. Hayes, S. Le Pape, Z. Ma, Y. Le Pape, August 2018.11/27/2018 2:23:47 PMORNL/SPR-2018/965 Light Water Reactor Sustainability Program Identification of Mechanisms to Study AlkaliSilica Reaction Effects on Stress-Confined Concrete Nuclear Thick 250https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2018-08-27T06:00:00Z
Implementation of Concrete Creep Model in Grizzly, ORNL/TM-2017/729.25233ConcreteImplementation of Concrete Creep Model in Grizzly, ORNL/TM-2017/729, A. Giorla, November 2017.11/29/2017 10:22:40 PMORNL/TM-2017/729 Light Water Reactor Sustainability Program Implementation of Concrete Creep Model in Grizzly Alain Giorla November 2017 U.S. Department of Energy Office of Nuclear 153https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2017-11-18T07:00:00Z
IMAC Database v.0.3. – Concrete, ORNL/SPR-2017/436.25230ConcreteIMAC Database v.0.3. – Concrete, ORNL/SPR-2017/436, Y. Pape, August 2017.8/30/2017 8:01:55 PMORNL/SPR-2017/436 Light Water Reactor Sustainability Program IMAC Database v.0.3. – Concrete Yann Le Pape August 2017 U.S. Department of Energy Office of Nuclear Energy not 174https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2017-08-18T06:00:00Z
Development of Fast Fourier Transform (FFT) micro-mechanical simulations of concrete specimens characterized by micro-X-ray fluorescence Alain, ORNL/TM-2017/367.25434ConcreteDevelopment of Fast Fourier Transform (FFT) micro-mechanical simulations of concrete specimens characterized by micro-X-ray fluorescence Alain, ORNL/TM-2017/367, A. Giorla, August 2017.8/7/2017 3:51:30 PMWebsite: http://www.osti.gov/scitech/ Reports produced before January 1, 1996, may be purchased by members of the public from the following source: National Technical Information 149https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2017-08-18T06:00:00Z
Linear Array Ultrasonic Testing Of A Thick Concrete Specimen For Nondestructive Evaluation, ORNL/TM-2017/156.25132ConcreteLinear Array Ultrasonic Testing Of A Thick Concrete Specimen For Nondestructive Evaluation, ORNL/TM-2017/156, D. Clayton, N. Ezell, L. Khazanovich, M. Zammerachi, April 2017.4/27/2017 3:38:24 PMA-1 APPENDIX B. PANORAMIC IMAGES FOR HEIGHT ORIENTATION SAFT-IA reconstructions for location 4, row 9: (a) without lifting the device and (b) with lifting the device 67https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2017-05-29T06:00:00Z
IMAC Database v.0.1. – Minerals25231ConcreteIMAC Database v.0.1. – Minerals, ORNL/TM-2016/ORNL/TM-2016/753, Y. Pape, December 2016.12/19/2016 8:52:19 PMORNL/TM-2016/ORNL/TM-2016/753 Light Water Reactor Sustainability Program IMAC Database v.0.1. – Minerals Yann Le Pape December 2016 U.S. Department of Energy Office of Nuclear 156https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2016-12-02T07:00:00Z
Independent Modeling of the Alkali-Silica Reaction: Mock-up Test Block25235ConcreteIndependent Modeling of the Alkali-Silica Reaction: Mock-up Test Block, ORNL/TM-2016/537, M. Hariri-Ardebili, V. Saouma, Y. LePape, September 15, 2016.9/19/2016 9:11:33 PMORNL/TM-2016/537 Independent Modeling of the Alkali-Silica Reaction: Mock-up Test Block Mohammad A. Hariri-Ardebili Victor E. Saouma Yann LePape Date: Sept. 15, 2016DOCUMENT 96https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2016-09-15T06:00:00Z
Simulation of Concrete Members Affected by Alkali-Silica Reaction with Grizzly25242ConcreteSimulation of Concrete Members Affected by Alkali-Silica Reaction with Grizzly, ORNL/TM-2016/523, A. Giorla, September 2016.9/15/2016 10:41:58 PMORNL/TM-2016/523 Light Water Reactor Sustainability Program Simulation of Concrete Members Affected by Alkali-Silica Reaction with Grizzly Alain B Giorla September 2016 U.S. 123https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2016-09-01T06:00:00Z
Evaluation of Advanced Signal Processing Techniques to Improve Detection and Identification of Embedded Defects25388ConcreteEvaluation of Advanced Signal Processing Techniques to Improve Detection and Identification of Embedded Defects, ORNL-TM-2016-482, D. Clayton, H. Santos-Villalobos, J. Baba, September 2016.9/29/2016 3:20:00 PMORNL/TM-2016/482 Evaluation of Advanced Signal Processing Techniques to Improve Detection and Identification of Embedded Defects Dwight Clayton Hector Santos-Villalobos Justin 159https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2016-09-01T06:00:00Z
Identification of Mechanisms to Study Alkali-Silica Reaction Effects on Stressed-Confined Concrete Nuclear Thick Structures25228ConcreteIdentification of Mechanisms to Study Alkali-Silica Reaction Effects on Stressed-Confined Concrete Nuclear Thick Structures, Z. Ma, S. Pape, N. Hayes, Q. Gui, A. Elhassan, Y. Jing, August 31, 2016.9/1/2016 8:53:25 PM(!% '%('(%& Prepared by: Dr. Z. John Ma, Professor Dr. Sihem Le Pape, Research Associate Nolan Hayes, Graduate Research Assistant Qiang Gui, Graduate Research Assistant Ammar 103https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2016-08-31T06:00:00Z
LWRS contribution to the RILEM benchmark on materials modeling of ASR – Preliminary results25136ConcreteLWRS contribution to the RILEM benchmark on materials modeling of ASR – Preliminary results, ORNL/LTR-2016/395, Y. Pape, A. Gloria, August 2016.8/15/2016 9:26:50 PMORNL/LTR-2016/395 LWRS contribution to the RILEM benchmark on materials modeling of ASR – Preliminary results August 2015 Prepared by Yann Le Pape and Alain GiorlaThis report was 94https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2016-08-01T06:00:00Z
Linear Array Ultrasonic Test Results from Alkali-Silica Reaction (ASR) Specimens25131ConcreteLinear Array Ultrasonic Test Results from Alkali-Silica Reaction (ASR) Specimens, ORNL-TM-2016-159, D. Clayton, L. Khazanovich, L. Salles, April 2016.4/21/2016 2:54:09 PMORNL/TM-2016/159 Linear Array Ultrasonic Test Results from Alkali-Silica Reaction (ASR) Specimens Dwight Clayton Lev Khazanovich, University of Minnesota Lucio Salles 123https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2016-04-01T06:00:00Z
Alkali-Silica Reaction test Assembly - Report describing the procurement of materials and equipment for the ASR test assembly Identification of Mechanisms to Study Alkali-Silica Reaction Effects on Stressed-confined Concrete Nuclear Thick Structures24640ConcreteAlkali-Silica Reaction test Assembly - Report describing the procurement of materials and equipment for the ASR test assembly Identification of Mechanisms to Study Alkali-Silica Reaction Effects on Stressed-confined Concrete Nuclear Thick Structures, Z Ma, University of Tennessee, January 2016.1/19/2016 7:43:43 PM( !'$*152016 2 Introduction The first report related to this project, has been delivered November 30 2015 It has detailed the design of a first version of a 221https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2016-01-15T07:00:00Z

 
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