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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 151https://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-beta55210The 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.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 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 159https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/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 127https://lwrs.inl.gov/Reactor Safety Technologies/Forms/AllItems.aspxpdfFalsepdf
Status Report on Ex-Vessel Coolability and Water Management90684Status 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 137https://lwrs.inl.gov/Reactor Safety Technologies/Forms/AllItems.aspxpdfFalsepdf
Development and Implementation of Mechanistic Terry Turbine Models in RELAP-7 to Simulate RCIC Normal Operation Conditions 90676Development and Implementation of Mechanistic Terry Turbine Models in RELAP-7 to Simulate RCIC Normal Operation Conditions, INL/EXT-16-39857, H. Zhao, L. Zou, H. Zhang, J. O'Brien, September 2016.1/23/2017 9:54:02 PMINL/EXT-16-39857 Development and Implementation of Mechanistic Terry Turbine Models in RELAP-7 to Simulate RCIC Normal Operation Conditions Haihua Zhao Ling Zou Hongbin Zhang 241https://lwrs.inl.gov/Reactor Safety Technologies/Forms/AllItems.aspxpdfFalsepdf
US Efforts in Support of Examinations at Fukushima Daiichi – 2016 Evaluations90686US 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 114https://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 I90679Fukushima 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 144https://lwrs.inl.gov/Reactor Safety Technologies/Forms/AllItems.aspxpdfFalsepdf
Modeling of the Reactor Core Isolation Cooling Response to Beyond Design Basis Operations – Phase 190682Modeling of the Reactor Core Isolation Cooling Response to Beyond Design Basis Operations – Phase 1, K. Ross, J. Cardoni, C. Wilson, C. Morrow, D. Osborn, R. Gauntt, SAND2015-10662, December 2015.12/8/2015 2:48:19 PMKyle Ross, Jeff Cardoni, Chisom Wilson, Charles Morrow, Douglas Osborn, and Randall Gauntt Prepared by Sandia National Laboratories Albuquerque, New Mexico 87185-0748 159https://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 Plants90674Application 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 132https://lwrs.inl.gov/Reactor Safety Technologies/Forms/AllItems.aspxpdfFalsepdf
Scoping Study Investigating PWR Instrumentation during a Severe Accident Scenario90677Scoping 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 208https://lwrs.inl.gov/Reactor Safety Technologies/Forms/AllItems.aspxpdfFalsepdf

 
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