Inhomogeneous Aging of Nuclear Power Plant Electrical Cable Insulation, PNNL-31443. | 231379 | | Cable Aging Degradation and Gap Analysis | | Inhomogeneous Aging of Nuclear Power Plant Electrical Cable Insulation, PNNL-31443, L. L. Fifield, W. Fuchs, Y. Ni, D. Li, M. Pallaka, A. Arteaga, M. Spencer, A. Zwoster, June 2021. | | 6/25/2021 8:17:29 PM | U.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 | 39 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2021-06-25T06:00:00Z | |
A System-Level Framework for Fatigue Life Prediction of a PWR Pressurizer-Surge-Line Nozzle under Design-basis Loading, ANL/LWRS-19/01. | 25257 | | Cable Aging Degradation and Gap Analysis | | A System-Level Framework for Fatigue Life Prediction of a PWR Pressurizer-Surge-Line Nozzle under Design-basis Loading Cycles, ANL/LWRS-19/01, S. Mohanty, J. Listwan, J. Phil Park, September 2019. | | 9/26/2019 11:32:39 PM | A Complete Tensile Test Based Material Properties Database and Preliminary Results on Weld Process Modeling, Thermal-Mechanical Stress Analysis and Environmental Fatigue Testing | 160 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2019-09-05T06:00:00Z | |
Sequential Versus Simultaneous Aging of XLPE and EPDM Nuclear Cable Insulation Subjected to Elevated Temperature and Gamma Radiation (Final Results), PNNL-30041. | 97503 | | Cables | | Sequential Versus Simultaneous Aging of XLPE and EPDM Nuclear Cable Insulation Subjected to Elevated Temperature and Gamma Radiation (Final Results), PNNL-30041 Rev. 1, L. Fifield, M. Spencer, Y. Ni, D. Li, M. Pallaka, T. Bisel, A. Zwoster, M. Murphy, December 2020. | | 12/11/2020 10:34:11 PM | U.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 | 256 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2020-12-12T07:00:00Z | |
Potential Life Extension Strategies for In-Service Degraded Cables, PNNL-30402. | 200487 | | Cables | | Potential Life Extension Strategies for In-Service Degraded Cables, PNNL-30402, S. Nune, M. Spencer, L. Fifield, September 2020. | | 9/17/2020 12:42:36 AM | U.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 | 273 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2020-09-21T06:00:00Z | |
Cable Nondestructive Examination Online Monitoring for Nuclear Power Plants, PNNL-155612. | 200493 | | Cables | | Cable Nondestructive Examination Online Monitoring for Nuclear Power Plants, PNNL-155612, S. Glass, L. Fifield, N. Bowler, September 2020. | | 10/21/2020 9:11:48 PM | U.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 | 320 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2020-09-20T06:00:00Z | |
Sequential Versus Simultaneous Aging of XLPE and EPDM Nuclear Cable Insulation Subjected to Elevated Temperature and Gamma Radiation, PNNL-30041. | 25290 | | Cables | | Sequential Versus Simultaneous Aging of XLPE and EPDM Nuclear Cable Insulation Subjected to Elevated Temperature and Gamma Radiation, PNNL-30041, L.S. Fifield, M.P. Spencer, A. Zwoster, T.T. Bisel, M.K. Murphy, June 2020. | | 6/24/2020 5:59:37 PM | U.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 | 279 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2020-06-16T06:00:00Z | |
Dielectric Spectroscopy for Bulk Condition Assessment of Cable Insulation, PNNL-29092. | 25436 | | Cables | | Dielectric 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 PM | U.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 | 176 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2019-09-14T06:00:00Z | |
Evaluation of Inverse Temperature Effects on Cable Insulation Degradation in Accelerated Aging of High Priority Cable Insulation Materials, PNNL-29051. | 25389 | | Cables | | Evaluation 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 PM | U.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 | 93 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2019-08-18T06:00:00Z | |
Assessment of electrical breakdown strength relative to mechanical properities in insulations from harvested cable systems from nuclear power plants, ORNL SPR-2019/1145. | 24647 | | Cables | | Assessment 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 PM | | 57 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2019-04-12T06:00:00Z | |
Report on Initial Evaluations of Effects of Diffusion Limited Oxidation (DLO) Testing, PNNL-28351. | 25236 | | Cables | | Report 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 PM | U.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 | 106 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2018-12-18T07:00:00Z | |
Investigation of Thermal Aging Behavior for Harvested Crosslinked, PNNL-27729. | 25240 | | Cables | | Investigation 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 PM | PNNL-27729 Light Water Reactor Sustainability Program Investigation of Thermal Aging Behavior for Harvested Crosslinked Polyethylene and Ethylene-Propylene Rubber Cable Insulation | 124 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2018-07-29T06:00:00Z | |
Interdigital Capacitance Local Non-Destructive Examination of Nuclear Power Plant Cable for Aging Management Programs, PNNL-27546. | 25237 | | Cables | | Interdigital 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 PM | U.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 | 264 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2018-05-18T06:00:00Z | |
Crystal River 3 Cable Materials for Thermal and Gamma Radiation Aging September 2017 U.S., PNNL-26785. | 25429 | | Cables | | Crystal 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 PM | PNNL-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 | 175 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2017-09-20T06:00:00Z | |
Accelerated Thermal Aging Of Harvested Zion Electrical Cable Jacket And Insulation (Interim Report) | 24639 | | Cables | | Accelerated Thermal Aging Of Harvested Zion Electrical Cable Jacket And Insulation (Interim Report), M3LW-17OR0404110, R. Duckworth, July 2017. | | 8/3/2017 4:33:41 PM | M3LW-17OR0404110 Revision 0 Light Water Reactor Sustainability Program ACCELERATED THERMAL AGING OF HARVESTED ZION ELECTRICAL CABLE JACKET AND INSULATION (INTERIM REPORT) July | 102 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2017-07-01T06:00:00Z | |
Analysis of simultaneous thermal/gamma radiation aging of cross-linked polyethylene (XLPE) insulation—interim status report, PNNL-26554. | 24643 | | Cables | | Analysis 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 PM | Neither 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 | 86 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2017-06-01T06:00:00Z | |
Physics-Based Modeling of Cable Insulation Conditions for Frequency Domain Reflectometry (FDR), PNNL-26493. | 25447 | | Cables | | Physics-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 PM | PNNL-26493 Light Water Reactor Sustainability Program Physics-Based Modeling of Cable Insulation Conditions for Frequency Domain Reflectometry (FDR) May 2017 U.S. Department of | 145 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2017-05-18T06:00:00Z | |
Update on Combined Thermal/Radiation Aging at Five Dose Rates in Chlorosulfonated Polyethylene (Hypalon)/Ethylene-Propylene Rubber (EPR) Cable Jacket Insulation System | 25066 | | Cables | | Update 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 PM | M3LW-17OR0404019 Revision 0 Light Water Reactor Sustainability Program UPDATE ON COMBINED THERMAL/RADIATION AGING AT FIVE DOSE RATES IN CHLOROSULFONATED POLYETHYLENE (HYPALON | 113 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2017-03-18T06:00:00Z | |
Bulk and Distributed Electrical Cable Non-Destructive Examination Methods for Nuclear Power Plant Cable Aging Management Programs, PNNL-25634. | 24649 | | Cables | | Bulk 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 PM | Neither 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 | 130 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2016-09-01T06:00:00Z | |
Status Report and Research Plan for Cables Harvested from Crystal River Unit 3 Nuclear Generating Plant, PNNL-25833. | 25246 | | Cables | | Status 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 PM | PNNL-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. | 129 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2016-09-01T06:00:00Z | |
Progress in Characterizing Thermal Degradation of Ethylene-Propylene Rubber, PNNL-25713. | 25276 | | Cables | | Progress in Characterizing Thermal Degradation of Ethylene-Propylene Rubber, PNNL-25713, L. Fifield, Q. Huang, M. Childers, M. Correa, Y. Shin, A. Zwoster, August 2016 | | 8/29/2016 8:24:29 PM | M3LW-16OR0404014 PNNL-25713 Light Water Reactor Sustainability Program Progress in Characterizing Thermal Degradation of Ethylene-Propylene Rubber August 2016 U.S. Department of | 151 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2016-08-01T06:00:00Z | |
Progress in Characterizing Naturally-Aged Nuclear Power Plant Cables, PNNL-25439. | 25277 | | Cables | | Progress 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 PM | M3LW-16OR0404013 PNNL-25439 Light Water Reactor Sustainability Program Progress in Characterizing NaturallyAged Nuclear Power Plant Cables May 2016 U.S. Department of Energy | 283 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2016-05-01T06:00:00Z | |
Evaluation of Localized Cable Test Methods for Nuclear Power Plant Cable Aging Management Programs, PNNL-25432. | 25390 | | Cables | | Evaluation 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 PM | M3LW-16OR0404022 PNNL-25432 Light Water Reactor Sustainability Program Evaluation of Localized Cable Test Methods for Nuclear Power Plant Cable Aging Management Programs May 2016 | 148 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2016-05-01T06:00:00Z | |
Characterizing oxidation of cross-linked polyethylene and ethylene propylene rubber insulation materials by differential scanning calorimeter | 24653 | | Cables | | Characterizing 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 AM | U.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 | 320 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2016-01-03T07:00:00Z | |
State-of-the-Art Assessment of NDE Techniques for Aging Cable Management in Nuclear Power Plants FY2015, PNNL-24649. | 25245 | | Cables | | State-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 PM | U.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 | 88 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2015-09-08T06:00:00Z | |
Progress on Analysis of Inverse Temperature Effects, Submerged Cables, Diffusion Limited Oxidation and Dose Rate Effects PNNL-24634 September 2015 | 25056 | | Cables | | Progress 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 PM | U.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 | 128 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2015-09-01T06:00:00Z | |
Assessment of Additional Key Indicators of Aging Cables in Nuclear Power Plants – Interim Status for FY 2015, PNNL-24649. | 25051 | | Cables | | Assessment 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 PM | U.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 | 78 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2015-05-01T06:00:00Z | |
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. | 25143 | | Cables | | 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. | | 3/27/2015 5:35:22 PM | ORNL/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 | 52 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2015-03-01T07:00:00Z | |
New Technologies for Repairing Aging Cables in Nuclear Power Plants, K. Simmons, L. Fifield, M. Westman, and J. Roberts, Pacific Northwest National Laboratory, September 2014 | 24766 | | Cables | | New 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 AM | PNNL-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 | 103 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2014-09-01T06:00:00Z | |
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. | 25453 | | Cables | | 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, September 2014. | | 9/17/2014 1:53:20 PM | PNNL-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 | 658 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2014-09-01T06:00:00Z | |
Preliminary List of Aging Conditions and Measurement Methods to be Examined for Key Indicators of Cable Aging – Status Summary, K. Simmons, PNNL, April 2013 | 24650 | | Cables | | Preliminary 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 PM | Tel: (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. | 43 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2013-05-01T06:00:00Z | |
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. | 25452 | | Cables | | 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. | | 9/4/2012 8:29:36 PM | PNNL-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 | 198 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2012-09-01T06:00:00Z | |
Assessment of Opportunities for Acquiring Plant Materials to Aid in Model Validation, G. Von White and R. Bernstein, Sandia National Laboratory, June 2012. | 25398 | | Cables | | Assessment 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 PM | date: 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 | 75 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2012-06-01T06:00:00Z | |
Ultrasonic Model Based Iterative Reconstruction of Experimental Concrete Specimens at EPR, ORNL/SPR-2022/2318. | 204154 | | Concrete | | Ultrasonic Model Based Iterative Reconstruction of Experimental Concrete Specimens at EPRI, ORNL/SPR-2022/2318, N. Ezell, H. Sun, S. Venkatakrishnan, S. Sabatino, January 2022 | | 3/31/2022 10:03:14 PM | ORNL/SPR-2022/2318 Ultrasonic Model Based Iterative Reconstruction of Experimental Concrete Specimens at EPRI N. Dianne Bull Ezell Hongbin Sun Singanallur Venkatakrishnan Sam | 56 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2022-01-01T07:00:00Z | |
Evaluation of Stress Corrosion Cracking Behavior of Ni-base Alloys in PWR Primary Water Containing KOH vs. LiOH , M2LW-21OR0402036. | 221026 | | Concrete | | Evaluation of Stress Corrosion Cracking Behavior of Ni-base Alloys in PWR Primary Water Containing KOH vs. LiOH, M2LW-21OR0402036, Z. Zhai, M. Toloczko, F. Colon, R. Bouffious, September 2021. | | 9/21/2021 8:23:26 PM | U.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 | 58 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2021-09-21T06:00:00Z | |
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. | 24642 | | Concrete | | Comparative Analysis of Nondestructive Examination Techniques of Enhanced Model Based Iterative Reconstruction (MBIR) and Frequency-banded Synthetic Aperture Focusing Technique (SAFT) Reconstructions, ORNL/SPR-2019/1240, N. Ezell, S. Venkatakrishnan, H. Santos-Villalobos, A. Albright, September 2019. | | 9/13/2019 1:12:59 PM | Reports 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 | 235 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2019-09-11T06:00:00Z | |
Two-Modulator Generalized Ellipsometry Microscope, ORNL/TM-2019/1025. | 24764 | | Concrete | | Two-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 AM | ORNL/TM-2019/1025 Revision 0 Two-modulator Generalized Ellipsometry Microscope (2-MGEM) Examination of Concrete Aggregates MILESTONE M3LW-19OR0403047, WORK PACKAGE: LW-19OR040304 | 109 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2019-06-01T06:00:00Z | |
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. | 24661 | | Concrete | | 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, Y. Pape, N. Hayes, E. Rodriquez, J. Arregui-Mena, T. Rosseel, May 2019. | | 5/1/2019 6:20:27 PM | Website: 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 | 69 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2019-05-28T06:00:00Z | |
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 | 25229 | | Concrete | | 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-2018/965, N. Hayes, S. Le Pape, Z. Ma, Y. Le Pape, August 2018. | | 11/27/2018 2:23:47 PM | ORNL/SPR-2018/965 Light Water Reactor Sustainability Program Identification of Mechanisms to Study AlkaliSilica Reaction Effects on Stress-Confined Concrete Nuclear Thick | 250 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2018-08-27T06:00:00Z | |
Implementation of Concrete Creep Model in Grizzly, ORNL/TM-2017/729. | 25233 | | Concrete | | Implementation of Concrete Creep Model in Grizzly, ORNL/TM-2017/729, A. Giorla, November 2017. | | 11/29/2017 10:22:40 PM | ORNL/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 | 153 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2017-11-18T07:00:00Z | |
IMAC Database v.0.3. – Concrete, ORNL/SPR-2017/436. | 25230 | | Concrete | | IMAC Database v.0.3. – Concrete, ORNL/SPR-2017/436, Y. Pape, August 2017. | | 8/30/2017 8:01:55 PM | ORNL/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 | 174 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2017-08-18T06:00:00Z | |
Development of Fast Fourier Transform (FFT) micro-mechanical simulations of concrete specimens characterized by micro-X-ray fluorescence Alain, ORNL/TM-2017/367. | 25434 | | Concrete | | Development 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 PM | Website: 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 | 149 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2017-08-18T06:00:00Z | |
Linear Array Ultrasonic Testing Of A Thick Concrete Specimen For Nondestructive Evaluation, ORNL/TM-2017/156. | 25132 | | Concrete | | Linear 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 PM | A-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 | 67 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2017-05-29T06:00:00Z | |
IMAC Database v.0.1. – Minerals | 25231 | | Concrete | | IMAC Database v.0.1. – Minerals, ORNL/TM-2016/ORNL/TM-2016/753, Y. Pape, December 2016. | | 12/19/2016 8:52:19 PM | ORNL/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 | 156 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2016-12-02T07:00:00Z | |
Independent Modeling of the Alkali-Silica Reaction: Mock-up Test Block | 25235 | | Concrete | | Independent 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 PM | ORNL/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 | 96 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2016-09-15T06:00:00Z | |
Simulation of Concrete Members Affected by Alkali-Silica Reaction with Grizzly | 25242 | | Concrete | | Simulation of Concrete Members Affected by Alkali-Silica Reaction with Grizzly, ORNL/TM-2016/523, A. Giorla, September 2016. | | 9/15/2016 10:41:58 PM | ORNL/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. | 123 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2016-09-01T06:00:00Z | |
Evaluation of Advanced Signal Processing Techniques to Improve Detection and Identification of Embedded Defects | 25388 | | Concrete | | Evaluation 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 PM | ORNL/TM-2016/482 Evaluation of Advanced Signal Processing Techniques to Improve Detection and Identification of Embedded Defects Dwight Clayton Hector Santos-Villalobos Justin | 159 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2016-09-01T06:00:00Z | |
Identification of Mechanisms to Study Alkali-Silica Reaction Effects on Stressed-Confined Concrete Nuclear Thick Structures | 25228 | | Concrete | | Identification 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 | 103 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2016-08-31T06:00:00Z | |
LWRS contribution to the RILEM benchmark on materials modeling of ASR – Preliminary results | 25136 | | Concrete | | LWRS 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 PM | ORNL/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 | 94 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2016-08-01T06:00:00Z | |
Linear Array Ultrasonic Test Results from Alkali-Silica Reaction (ASR) Specimens | 25131 | | Concrete | | Linear 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 PM | ORNL/TM-2016/159 Linear Array Ultrasonic Test Results from Alkali-Silica Reaction (ASR) Specimens Dwight Clayton Lev Khazanovich, University of Minnesota Lucio Salles | 123 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2016-04-01T06:00:00Z | |
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 Structures | 24640 | | Concrete | | 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 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 | 221 | https://lwrs.inl.gov/Materials Aging and Degradation/Forms/AllItems.aspx | pdf | False | pdf | | 2016-01-15T07:00:00Z | |