Terry Turbopump Expanded Operating Band Full-Scale Integral Long-Term Low-Pressure Experiments – Preliminary Test Plan | 90685 | | | Terry Turbopump Expanded Operating Band Full-Scale Integral Long-Term Low-Pressure Experiments – Preliminary Test Plan, SAND2018-12965, D. OSborn, M. Solom, January 2019 | | 1/9/2019 2:52:02 PM | SANDIA REPORT SAND2018-12965 Unlimited Release January 2019 Terry Turbopump Expanded Operating Band Full-Scale Integral Long-Term Low-Pressure Experiments – Preliminary Test Plan | 482 | https://lwrs.inl.gov/Reactor Safety Technologies/Forms/AllItems.aspx | pdf | False | pdf | | 2019-01-13T07:00:00Z | |
The CORQUENCH Code for Modeling of Ex-Vessel Corium Coolability under Top Flooding Conditions Code Manual – Version4.1-beta | 221993 | | | The CORQUENCH Code for Modeling of Ex-Vessel Corium Coolability under Top Flooding Conditions Code Manual – Version4.1-beta, ANL-18/22, M. Farmer, August 2018. | | 10/15/2018 4:53:00 PM | ANL -18/22 The CORQUENCH Code for Modeling of Ex-Vessel Corium Coolability under Top Flooding Conditions Code Manual – Version4.1-beta Nuclear Science and | 202 | https://lwrs.inl.gov/Reactor Safety Technologies/Forms/AllItems.aspx | pdf | False | pdf | | 2018-08-06T06:00:00Z | |
Improvements in the reactor core isolation cooling (RCIC) pump model | 90681 | | | Improvements in the reactor core isolation cooling (RCIC) pump model, INL/EXT-18-44739, H. Zhang, J. O'Brtien, February 2018. | | 3/1/2018 5:22:31 PM | INL/EXT-18-44739 Improvements in the reactor core isolation cooling (RCIC) pump model Hongbin Zhang James O'Brien February 2018 U.S. Department of Energy Office of Nuclear | 281 | https://lwrs.inl.gov/Reactor Safety Technologies/Forms/AllItems.aspx | pdf | False | pdf | | 2018-02-18T07:00:00Z | |
Enhancements to Engineering-scale Reactor Pressure Vessel Fracture Capabilities in Grizzly, INL/EXT-17-43427 | 221997 | | | Enhancements to Engineering-scale Reactor Pressure Vessel Fracture Capabilities in Grizzly, INL/EXT-17-43427, B. Spencer, W. Hoffman, W. Jiang, September 2017. | | 9/28/2017 8:27:11 PM | INL/EXT-17-43427 Light Water Reactor Sustainability Program Enhancements to Engineering-scale Reactor Pressure Vessel Fracture Capabilities in Grizzly Benjamin W. Spencer | 104 | https://lwrs.inl.gov/Reactor Safety Technologies/Forms/AllItems.aspx | pdf | False | pdf | | 2017-09-18T06:00:00Z | |
Status Report on Ex-Vessel Coolability and Water Management, ANL/NE-16/18 | 90684 | | | Status Report on Ex-Vessel Coolability and Water Management, ANL/NE-16/18, M. Farmer, K. Robb, September 15, 2016. | | 9/16/2016 2:32:14 AM | ANL/NE-16/18 Status Report on Ex-Vessel Coolability and Water Management NE Division About Argonne National Laboratory Argonne is a U.S. Department of | 296 | https://lwrs.inl.gov/Reactor Safety Technologies/Forms/AllItems.aspx | pdf | False | pdf | | 2016-09-15T06:00:00Z | |
US Efforts in Support of Examinations at Fukushima Daiichi – 2016 Evaluations, ANL/LWRS-16/02 | 90686 | | | US Efforts in Support of Examinations at Fukushima Daiichi – 2016 Evaluations, ANL/LWRS-16/02, P. Amway, N. Andrews, W. Bixby, R. Bunt, M. Corradini, P. Ellison, M. Farmer, T. Farthing, M. Francis, J. Gabor, R. Gauntt, C. Henry, P. Humrickhouse, S. Kraft, R. Linthicum, W. Luangdilok, R. Lutz, D. Luxat, J. Maddox, C. Negin, c. Paik, M. Plys, J. Rempe, K. Robb, R. Sanders, R. Warchowiak, B. Williamson, August 2016. | | 9/7/2016 3:01:01 PM | ANL/LWRS-16/02 Light Water Reactor Sustainability Program US Efforts in Support of Examinations at Fukushima Daiichi – 2016 Evaluations August 2016 U.S. Department of Energy | 287 | https://lwrs.inl.gov/Reactor Safety Technologies/Forms/AllItems.aspx | pdf | False | pdf | | 2016-08-01T06:00:00Z | |
Development of Three-Field Poromechanics Capability in MOOSE, INL/EXT-16-38931 | 222013 | | | Development of Three-Field Poromechanics Capability in MOOSE, M. Sivaselvan, N. Oliveto, A. Whittaker, INL/EXT-16-38931, April 2016. | | 6/2/2016 3:02:48 PM | This information was prepared as an account of work sponsored by an agency of the U.S. Government Neither the U.S. Government nor any agency thereof, nor any of their employees | 137 | https://lwrs.inl.gov/Reactor Safety Technologies/Forms/AllItems.aspx | pdf | False | pdf | | 2016-04-01T06:00:00Z | |
Fukushima Daiichi Unit 1 Accident Progression Uncertainty Analysis and Implications for Decommissioning of Fukushima Reactors – Volume I, SAND2016-0232 | 90679 | | | Fukushima Daiichi Unit 1 Accident Progression Uncertainty Analysis and Implications for Decommissioning of Fukushima Reactors – Volume I, Sandia National Laboratories, SAND2016-0232, January 2106. | | 1/13/2016 1:20:49 PM | Severe Accident Analysis Department - 06232 Sandia National Laboratories Albuquerque, New Mexico 87185 and Livermore, California 94550 NOTICE: This report was prepared as an | 346 | https://lwrs.inl.gov/Reactor Safety Technologies/Forms/AllItems.aspx | pdf | False | pdf | | 2016-01-19T07:00:00Z | |
Application of Nonlinear Seismic Soil-Structure Interaction Analysis for Identification of Seismic Margins at Nuclear Power Plants, INL/EXT-15-37382 | 90674 | | | Application of Nonlinear Seismic Soil-Structure Interaction Analysis for Identification of Seismic Margins at Nuclear Power Plants, A. Varma, J. Seo, J. Coleman, INL/EXT-15-37382, November 2015 | | 11/30/2015 6:15:59 PM | Amit H. Varma, Jungil Seo, and Justin Coleman This information was prepared as an account of work sponsored by an agency of the U.S. Government Neither the U.S. Government nor any | 323 | https://lwrs.inl.gov/Reactor Safety Technologies/Forms/AllItems.aspx | pdf | False | pdf | | 2015-11-03T07:00:00Z | |
Scoping Study Investigating PWR Instrumentation during a Severe Accident Scenario, INL/EXT-15-35940 | 90677 | | | Scoping Study Investigating PWR Instrumentation during a Severe; Accident Scenario, J. Rempe, D. Knudson, R. Lutz, INL/EXT-15-35940, September 2015. | | 9/17/2015 5:22:16 PM | INL/EXT-15-35940 Scoping Study Investigating PWR Instrumentation during a Severe Accident Scenario Joy L. Rempe, Rempe and Associates, LLC Darrell L. Knudson, Idaho National | 152 | https://lwrs.inl.gov/Reactor Safety Technologies/Forms/AllItems.aspx | pdf | False | pdf | | 2015-09-01T06:00:00Z | |