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Survey of Aging and Monitoring Concerns for Cables and Splices Due to Cable Repair and Replacement, PNNL-34576280728Cable Aging and Cable NDEAs portions of existing electrical cable runs in NPPs are replaced over time due to localized events, the total number of splices in NPPs are expected to increase. Relative to electrical cables, the body of knowledge regarding aging of splices and of splices in combination with aging cables in nuclear service environments in long-term operation is low. The Nuclear Regulatory Commission Licensee Event Reports database was used to identify documented issues of electrical cable and splice failure. The trend in resultant data over time was considered to see if failures were increasing as NPPs age. From this data it can be concluded that electrical cables and splices are highly reliable. Common-cause failure of splices is primarily associated with loose connections, which may be attributed to workmanship issues, thermal cycling, and/or vibration. Replacement of electrical cables is more common than repair of cables with a failure point, leading to an increase in the proportion of new generation cables in NPPs over time. Splices on degraded electrical cables have been observed to be problematic. Condition monitoring approaches, while shown to be fruitful for electrical cables, have been shown to be insensitive to degradation of splice sleeves, which are critical to the continued performance of splices. Questions with accelerated aging in environmental qualification have not been investigated for splices as they have been for cables, but may represent similar concerns. Rejuvenation and/or mitigation techniques to renew aged cable lengths prior to splice application may improve performance of splices applied to aged cables. As with cables, aging management of splices may best be accomplished with a condition-based rather than a time-based approach. Understanding of the aging behavior of splice materials and development of effective methods to evaluate and monitor splice condition are necessary prerequisites to establishing such a condition-based aging management program with acceptance criteria that informs repair and replacement decisions based on the actual status of components in service. Development of such a program could be beneficial both for in the increasing number of splices applied in existing NPPs in long-term operation and for aging management in new reactors.7/28/2023 11:23:29 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 The purpose of this report is to 12https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2023-07-31T06:00:00Z
Frequency Domain Reflectometry (FDR) Simulation Techniques for Digital Twin Representation of an Electrical Cable, Milestone M3LW-23OR0404023265341Cable Aging and Cable NDESimulation of nuclear electric cable system response to FDR tests can be instrumental to understanding the results of these tests and the nature and influence of various cable anomalies on test signatures.4/14/2023 10:30:22 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 digital twin in this work 119https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2023-04-14T06:00:00Z
Dose Rate Effects on Degradation of Nuclear Power Plant Electrical Cable Insulation at a Common Dose. PNNL-34068265399Cable Aging and Cable NDEDose rate effects (DRE) are an identified knowledge gap in relating accelerated aging of nuclear electrical cables to service aging, and here refer to gamma radiation-induced polymer degradation being a function of dose rate in addition to total absorbed dose. In this work, cross-linked polyethylene (XLPE) and ethylene propylene diene elastomer (EPDM) materials were subjected to accelerated aging at ambient temperature (26°C) at different gamma dose rates of 100, 200 and 1800 Gy/h for select exposure durations to achieve constant total doses of 170, 210 and 300 kGy to evaluate DRE.3/24/2023 8:07:18 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 Muthu Elen 1 , Md Kamrul Hasan 1 73https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2023-03-24T06:00:00Z
Inverse Temperature Effects in Nuclear Power Plant Electrical Cable Insulation, PNNL-33296267590Cable Aging and Cable NDEThe 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 170https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2022-09-09T06:00:00Z
Nondestructive Evaluation (NDE) of Cable Moisture Exposure using Frequency Domain Reflectometry (FDR), PNNL-31934124035Cable Aging and Cable NDENuclear power facilities have experienced various electrical cable failures related to water exposure. The current industry response involves actions to de-water cable vaults, manholes, and other cable locations. These efforts require considerable expenditure of resources, which makes it desirable for the industry to have information on cable condition and history regarding their submergence and water exposure.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 292https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2021-09-16T06:00:00Z
Inhomogeneous Aging of Nuclear Power Plant Electrical Cable Insulation, PNNL-31443231379Cable Aging and Cable NDENuclear 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 166https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2021-06-25T06:00:00Z
Sequential Versus Simultaneous Aging of XLPE and EPDM Nuclear Cable Insulation Subjected to Elevated Temperature and Gamma Radiation (Final Results), PNNL-3004197503Cable Aging and Cable NDEThis 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 371https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2020-12-12T07:00:00Z
Potential Life Extension Strategies for In-Service Degraded Cables, PNNL-30402200487Cable Aging and Cable NDEElectrical 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 416https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2020-09-21T06:00:00Z
Cable Nondestructive Examination Online Monitoring for Nuclear Power Plants, PNNL-155612200493Cable Aging and Cable NDEThis 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 483https://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-3004125290Cable Aging and Cable NDEThis 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 440https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2020-06-16T06:00:00Z
Dielectric Spectroscopy for Bulk Condition Assessment of Cable Insulation, PNNL-2909225436Cable Aging and Cable NDEThis 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 276https://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-2905125389Cable Aging and Cable NDEElectrical 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 150https://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-2019/114524647Cable Aging and Cable NDEThis report summarizes the characterization of the electrical breakdown strength in harvested electrical I&C cable insulation as a function of aging and its relationship to other mechanical properties.4/30/2019 4:46:08 PM109https://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-2835125236Cable Aging and Cable NDEThe objective of this study is to experimentally determine the thresholds of significant degradation in the most common nuclear cable insulation materials used by major cable manufacturers. Specifically, the focus is on thermal aging (temperature) and gamma irradiation aging (dose rate) thresholds. The selected materials for investigation include cross-linked polyethylene (XLPE) and ethylene-propylene rubber (EPR) insulation materials from prominent suppliers. The study involves subjecting these materials to accelerated aging conditions, covering a range of temperatures and dose rates that encompass the expected thresholds for significant degradation. The research aims to provide valuable insights into the aging behavior of these insulation materials, particularly in the context of plant operation extending beyond sixty years.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 182https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2018-12-18T07:00:00Z
Investigation of Thermal Aging Behavior for Harvested Crosslinked, PNNL-2772925240Cable Aging and Cable NDEInvestigation 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 188https://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-2754625237Cable Aging and Cable NDEInterdigital 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 341https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2018-05-18T06:00:00Z
Implementation of Concrete Creep Model in Grizzly, ORNL/TM-2017/72925233Cable Aging and Cable NDEImplementation 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 218https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2017-11-18T07:00:00Z
Crystal River 3 Cable Materials for Thermal and Gamma Radiation Aging, PNNL-2678525429Cable Aging and Cable NDECrystal 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 280https://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-17OR040411024639Cable Aging and Cable NDEAccelerated 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 160https://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-2655424643Cable Aging and Cable NDEAnalysis 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 163https://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-2649325447Cable Aging and Cable NDEPhysics-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 349https://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-17OR040401925066Cable Aging and Cable NDEUpdate 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 195https://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-2563424649Cable Aging and Cable NDEBulk 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 196https://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-2583325246Cable Aging and Cable NDEStatus 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. 194https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2016-09-01T06:00:00Z
Progress in Characterizing Thermal Degradation of Ethylene-Propylene Rubber, PNNL-25713.25276Cable Aging and Cable NDEProgress 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 220https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2016-08-01T06:00:00Z
Progress in Characterizing Naturally-Aged Nuclear Power Plant Cables, PNNL-2543925277Cable Aging and Cable NDEProgress 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 482https://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-2543225390Cable Aging and Cable NDEEvaluation 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 294https://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-2517224653Cable Aging and Cable NDECharacterizing 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 442https://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-2464925245Cable Aging and Cable NDEState-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 160https://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-2463425056Cable Aging and Cable NDEProgress 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 221https://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-2464925051Cable Aging and Cable NDEAssessment 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 143https://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-2015/9325143Cable Aging and Cable NDEThermal 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 105https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2015-03-01T07:00:00Z
New Technologies for Repairing Aging Cables in Nuclear Power Plants24766Cable Aging and Cable NDENew 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 178https://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-2362425453Cable Aging and Cable NDEDetermining 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 1021https://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 Summary24650Cable Aging and Cable NDEPreliminary 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. 104https://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 2012.25452Cable Aging and Cable NDENondestructive 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 280https://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 2012.25398Cable Aging and Cable NDEAssessment 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 123https://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-2022/2318204154Concrete Aging and DegradationConcrete 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 201https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2022-01-01T07:00:00Z
Development of a Reconstruction Methodology Based on X-Ray Computed Tomography to Generate Realistic 3D Concrete Microstructures in MOSAIC, ORNL/TM-2021/2156231364Concrete Aging and DegradationDespite being passive components, concrete structures represent a major capital investment in nuclear power plants. However, some concrete components are critical for the safety and long-term operation of the reactors: the concrete containment building protects the reactors from external aggression. The concrete biological shield (CBS) contains the radiation exiting the reactor to protect equipment and personnel. Depending on the design, the CBS also has a function for supporting the reactor’s systems. This function needs to be ensured in-service and during accident scenarios.8/26/2021 11:01:48 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 121https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2021-08-26T06:00:00Z
Comparative Analysis of Nondestructive Examination Techniques of Enhanced Model Based Iterative Reconstruction (MBIR) and Frequency-banded Synthetic Aperture Focusing Technique (SAFT) Reconstructions, ORNL/SPR-2019/124024642Concrete Aging and DegradationAs 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 379https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2019-09-11T06:00:00Z
Two-Modulator Generalized Ellipsometry Microscope, ORNL/TM-2019/102524764Concrete Aging and DegradationThe examination of microstructures in geological materials, including aggregates used in concrete, is a complex task. Natural rocks contain crystals of varying sizes, ranging from submicron to centimeters, and these crystals can have different chemical compositions and orientations.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 164https://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-2019/113924661Concrete Aging and DegradationThe key findings and conclusions from phase (1) can be summarized as follows: (i) The expansion caused by alkali-silica reaction (ASR) primarily takes place in the unreinforced (unconfined) direction. (ii) Surface degradation, such as visible cracking, does not necessarily indicate the development of ASR or damage in the interior of the reactive specimens.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 140https://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-225229Concrete Aging and DegradationThe evaluation of the structural impact of alkali-silica reaction (ASR) on concrete in nuclear power plants is not directly comparable to transportation infrastructures or concrete dams due to differences in exposure, dimensions, and reinforcement ratios. Although the methodological approaches share similarities to a large extent, specific considerations must be made for nuclear power plant structures. For instance, the absence of shear reinforcement in the concrete thickness is common, which results in a lack of confinement and promotes out-of-plane expansion caused by ASR.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 362https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2018-08-27T06:00:00Z
IMAC Database v.0.3. – Concrete, ORNL/SPR-2017/43625230Concrete Aging and DegradationIMAC 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 290https://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-2017/36725434Concrete Aging and DegradationDevelopment 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 283https://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-2017/15625132Concrete Aging and DegradationLinear 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 141https://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-2016/75325231Concrete Aging and DegradationIMAC 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 336https://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-2016/53725235Concrete Aging and DegradationIndependent 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 136https://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-2016/52325242Concrete Aging and DegradationSimulation 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. 204https://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-2016-48225388Concrete Aging and DegradationEvaluation 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 230https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspxpdfFalsepdf2016-09-01T06:00:00Z

 
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