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Inhomogeneous Aging of Nuclear Power Plant Electrical Cable Insulation, PNNL-31443231379Cable Aging Degradation and Gap AnalysisNuclear cable insulation samples of the two most common types, EPR and XPLE, from three of the most sourced manufacturers, Anaconda, Rockbestos, and Brand-Rex, were subjected to thermal aging at temperatures like those used in historic environmental qualification, 121, 136, 150, and 165°C. The aged materials were characterized for effects of aging using the conventional tensile EAB for all three and the indenter modulus for the EPR.Nuclear cable insulation samples of the two most common types, EPR and XPLE, from three of the most sourced manufacturers, Anaconda, Rockbestos, and Brand-Rex, were subjected to thermal aging at temperatures like those used in historic environmental qualification, 121, 136, 150, and 165°C. The aged materials were characterized for effects of aging using the conventional tensile EAB for all three and the indenter modulus for the EPR.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 105https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2021-06-25T06:00:00Z
Inverse Temperature Effects in Nuclear Power Plant Electrical Cable Insulation, PNNL-33296267590Cable Aging and Gap AnalysisThe results described in this report do not support the conclusion that ITE in cable qualification necessarily excludes safe continued use of existing cables. Inverse temperature effects were found to differ based on insulation material and on property measured. The current industry practice of subjecting cables to thermal aging followed by radiation aging at room temperature in qualification appears to be a conservative scenario for materials exhibiting ITE. Ongoing non-destructive cable system condition monitoring is encouraged to support repair and replace decisions for continued safe and effective use of electrical cables in long term operation.9/9/2022 3:55:14 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 One gap identified is related to 93https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2022-09-09T06:00:00Z
Sequential Versus Simultaneous Aging of XLPE and EPDM Nuclear Cable Insulation Subjected to Elevated Temperature and Gamma Radiation (Final Results), PNNL-3004197503CablesThis report addresses one of the knowledge gaps identified for the prediction of nuclear electrical cable aging: the conservatism of accelerated aging performed during historical cable qualification. If synergistic effects—degradation mechanisms unique to simultaneous exposure to thermal and gamma radiation stress—occur during cable service in an operating power plant, but not in the sequential thermal and radiation stress commonly used to simulate aging in the laboratory, then the aging case used in qualification may not be sufficiently conservative to envelope service aging.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 314https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2020-12-12T07:00:00Z
Potential Life Extension Strategies for In-Service Degraded Cables, PNNL-30402200487CablesElectrical cable systems are integral to the safe and efficient operation of nuclear power plants. As cable materials age over time in service, the performance and reliability of cables decrease and can fall to unacceptable levels. Effective techniques for assessing cable health and monitoring their condition are essential for determining cable status, predicting remaining useful life, and informing operators of the need for additional monitoring or replacement.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 346https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2020-09-21T06:00:00Z
Cable Nondestructive Examination Online Monitoring for Nuclear Power Plants, PNNL-155612200493CablesThis PNNL report describes an investigation into cable inspection and monitoring methods that may be adapted to nuclear power plant online monitoring. There are numerous NDE methods to assess the condition of power plant cables. Most of these methods, however, require the cable systems to be offline and, in many cases, separated from their load.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 414https://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-3004125290CablesThis report addresses one of the knowledge gaps identified for the prediction of nuclear electrical cable aging, accelerated aging, performed during cable qualification. Synergistic effects are defined as polymer aging mechanisms specific to simultaneous or concurrent application of thermal and gamma radiation. If these effects differ from those experienced during sequentially applied thermal and gamma radiation stressors, then qualification that relies on sequential aging, as most historically did, may not well represent actual service aging when stressors exist simultaneously.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 369https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2020-06-16T06:00:00Z
Dielectric Spectroscopy for Bulk Condition Assessment of Cable Insulation, PNNL-2909225436CablesThis report describes progress to date on the investigation of nondestructive test methods focusing on bulk cable insulation testing using a dielectric spectroscopy (DS) approach. This report addresses relevant literature coupled with a discussion of the theory of DS measurements and work on modeling to appreciate the influence of damage/defect profile on the bulk total cable measurement.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 228https://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-2905125389CablesElectrical cable insulation may degrade over time in service as a result of exposure to elevated temperature and gamma irradiation if the cable is at a location in the plant, such as inside containment, where both stresses occur. Cable polymer insulation generally degrades faster at higher temperatures. The extent of degradation is also generally proportional to the absorbed radiation dose. Accelerated aging at high temperatures and high doses has been used in the laboratory to simulate cable material aging that occurs in the milder temperatures and lower doses experienced by cables in service over the 40-year or longer life of the reactor.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 129https://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-2019/114524647CablesAssessment 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 PM91https://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-2835125236CablesReport 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 145https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2018-12-18T07:00:00Z
Investigation of Thermal Aging Behavior for Harvested Crosslinked, PNNL-2772925240CablesInvestigation 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 154https://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-2754625237CablesInterdigital 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 305https://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, PNNL-2678525429CablesCrystal 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 234https://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), M3LW-17OR040411024639CablesAccelerated 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 127https://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-2655424643CablesAnalysis 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 117https://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-2649325447CablesPhysics-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 243https://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 System, M3LW-17OR040401925066CablesUpdate 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 140https://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-2563424649CablesBulk 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 159https://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-2583325246CablesStatus 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. 164https://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 186https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2016-08-01T06:00:00Z
Progress in Characterizing Naturally-Aged Nuclear Power Plant Cables, PNNL-2543925277CablesProgress 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 395https://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-2543225390CablesEvaluation 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 206https://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 calorimeter, PNNL-2517224653CablesCharacterizing 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 379https://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-2464925245CablesState-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 109https://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-2463425056CablesProgress 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 184https://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-2464925051CablesAssessment 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 106https://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, ORNL/TM-2015/9325143CablesThermal 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 76https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2015-03-01T07:00:00Z
New Technologies for Repairing Aging Cables in Nuclear Power Plants24766CablesNew Technologies for Repairing Aging Cables in Nuclear Power Plants, K. Simmons, L. Fifield, M. Westman, and J. Roberts, Pacific Northwest National Laboratory, 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 148https://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, PNNL-2362425453CablesDetermining 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 851https://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 Summary24650CablesPreliminary 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. 61https://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 232https://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 96https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2012-06-01T06:00:00Z
Stress Corrosion Cracking of Ni-base Alloys in PWR Primary Water Containing KOH vs. LiOH, M3LW-22OR0402033267589ConcreteThe U.S. nuclear industry is considering replacing LiOH with potassium hydroxide (KOH) for pH control in PWR primary water for economic reasons. Among the many aspects of reactor operation that need to be assessed before switching to KOH, it is necessary to evaluate the SCC response of Ni-base alloys in a KOH environment to ensure that SCC susceptibility is not increased by KOH water chemistry.11/11/2022 2:43:20 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 Dr. John Jackson and Mr. Michael 48https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2022-07-11T06:00:00Z
Ultrasonic Model Based Iterative Reconstruction of Experimental Concrete Specimens at EPR, ORNL/SPR-2022/2318204154ConcreteConcrete is a critical component of NPPs for both safety and reliability issues. The original plant designers could not have anticipated the extended lifespan these facilities may reach. Continuous monitoring of the concrete for signs of degradation through NDE may be applied to many levels of NPP infrastructure.3/31/2022 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 148https://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-21OR0402036221026ConcreteThe U.S. nuclear industry is considering replacing LiOH with potassium hydroxide (KOH) for pH control in PWR primary water for economic reasons. Among the many aspects of reactor operation that need to be assessed before switching to KOH, it is necessary to evaluate the SCC response of Ni-base alloys in a KOH environment to ensure that SCC susceptibility is not increased by KOH water chemistry.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 150https://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-2019/124024642ConcreteAs the existing US fleet of NPPs approach their expected lifetimes and only a few new reactors are coming online, the industry is looking to extend their licenses beyond 60 years and improve efficiencies through research-informed aging management programs. Reinforced concrete is an inexpensive, strong material widely used in the nuclear industry.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 343https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2019-09-11T06:00:00Z
Two-Modulator Generalized Ellipsometry Microscope, ORNL/TM-2019/102524764ConcreteTwo-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 136https://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-2019/113924661ConcreteMicrostructural 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 106https://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 Assembly, ORNL/SPR-225229ConcreteIdentification 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 317https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2018-08-27T06:00:00Z
Implementation of Concrete Creep Model in Grizzly, ORNL/TM-2017/72925233ConcreteImplementation 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 187https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2017-11-18T07:00:00Z
IMAC Database v.0.3. – Concrete, ORNL/SPR-2017/43625230ConcreteIMAC 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 245https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2017-08-18T06:00:00Z
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Linear Array Ultrasonic Testing Of A Thick Concrete Specimen For Nondestructive Evaluation, ORNL/TM-2017/15625132ConcreteLinear 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 92https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2017-05-29T06:00:00Z
IMAC Database v.0.1. Minerals, ORNL/TM-2016/ORNL/TM-2016/75325231ConcreteIMAC 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 205https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2016-12-02T07:00:00Z
Independent Modeling of the Alkali-Silica Reaction: Mock-up Test Block, ORNL/TM-2016/53725235ConcreteIndependent 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 124https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2016-09-15T06:00:00Z
Simulation of Concrete Members Affected by Alkali-Silica Reaction with Grizzly, ORNL/TM-2016/52325242ConcreteSimulation 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. 165https://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 Defects, ORNL-TM-2016-48225388ConcreteEvaluation 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 186https://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 132https://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 results, ORNL/LTR-2016/39525136ConcreteLWRS 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 123https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2016-08-01T06:00:00Z
Linear Array Ultrasonic Test Results from Alkali-Silica Reaction (ASR) Specimens, ORNL-TM-2016-15925131ConcreteLinear 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 147https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2016-04-01T06:00:00Z

 
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