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Terry Turbopump Expanded Operating Band Full-Scale Integral Long-Term Low-Pressure Experiments – Preliminary Test Plan90685Terry 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 PMSANDIA REPORT SAND2018-12965 Unlimited Release January 2019 Terry Turbopump Expanded Operating Band Full-Scale Integral Long-Term Low-Pressure Experiments – Preliminary Test Plan 263https://lwrs.inl.gov/Reactor Safety Technologies/Forms/AllItems.aspxpdfFalsepdf
The CORQUENCH Code for Modeling of Ex-Vessel Corium Coolability under Top Flooding Conditions Code Manual – Version4.1-beta221993The 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 PMANL -18/22 The CORQUENCH Code for Modeling of Ex-Vessel Corium Coolability under Top Flooding Conditions Code Manual – Version4.1-beta Nuclear Science and 28https://lwrs.inl.gov/Reactor Safety Technologies/Forms/AllItems.aspxpdfFalsepdf
Improvements in the reactor core isolation cooling (RCIC) pump model90681Improvements 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 PMINL/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 180https://lwrs.inl.gov/Reactor Safety Technologies/Forms/AllItems.aspxpdfFalsepdf
Enhancements to Engineering-scale Reactor Pressure Vessel Fracture Capabilities in Grizzly, INL/EXT-17-43427.221997Enhancements 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 PMINL/EXT-17-43427 Light Water Reactor Sustainability Program Enhancements to Engineering-scale Reactor Pressure Vessel Fracture Capabilities in Grizzly Benjamin W. Spencer 20https://lwrs.inl.gov/Reactor Safety Technologies/Forms/AllItems.aspxpdfFalsepdf
Status Report on Ex-Vessel Coolability and Water Management, ANL/NE-16/18.90684Status 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 AMANL/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 197https://lwrs.inl.gov/Reactor Safety Technologies/Forms/AllItems.aspxpdfFalsepdf
US Efforts in Support of Examinations at Fukushima Daiichi – 2016 Evaluations, ANL/LWRS-16/02.90686US 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 PMANL/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 175https://lwrs.inl.gov/Reactor Safety Technologies/Forms/AllItems.aspxpdfFalsepdf
Development of Three-Field Poromechanics Capability in MOOSE, INL/EXT-16-38931.222013Development 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 PMThis 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 22https://lwrs.inl.gov/Reactor Safety Technologies/Forms/AllItems.aspxpdfFalsepdf
Fukushima Daiichi Unit 1 Accident Progression Uncertainty Analysis and Implications for Decommissioning of Fukushima Reactors – Volume I, SAND2016-0232.90679Fukushima 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 PMSevere Accident Analysis Department - 06232 Sandia National Laboratories Albuquerque, New Mexico 87185 and Livermore, California 94550 NOTICE: This report was prepared as an 219https://lwrs.inl.gov/Reactor Safety Technologies/Forms/AllItems.aspxpdfFalsepdf
Application of Nonlinear Seismic Soil-Structure Interaction Analysis for Identification of Seismic Margins at Nuclear Power Plants, INL/EXT-15-37382.90674Application 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 201511/30/2015 6:15:59 PMAmit 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 229https://lwrs.inl.gov/Reactor Safety Technologies/Forms/AllItems.aspxpdfFalsepdf
Scoping Study Investigating PWR Instrumentation during a Severe  Accident Scenario, INL/EXT-15-35940.90677Scoping 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 PMINL/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 27https://lwrs.inl.gov/Reactor Safety Technologies/Forms/AllItems.aspxpdfFalsepdf

 
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