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Reactor Safety Technologies - Reports

Report TitleBrief NarrativeLinkDate
Terry Turbopump Expanded Operating Band Full-Scale Integral Long-Term Low-Pressure Experiments – Preliminary Test PlanTerry Turbopump Expanded Operating Band Full-Scale Integral Long-Term Low-Pressure Experiments – Preliminary Test Plan, SAND2018-12965, D. OSborn, M. Solom, January 2019Download1/13/2019
Improvements in the reactor core isolation cooling (RCIC) pump modelImprovements in the reactor core isolation cooling (RCIC) pump model, INL-EXT-18-44739, H. Zhang, J. O’Brtien, February 2018.Download2/18/2018
Development of Three-Field Poromechanics Capability in MOOSE, INL/EXT-16-38931Development of Three-Field Poromechanics Capability in MOOSE, M. Sivaselvan, N. Oliveto, A. Whittaker, INL/EXT-16-38931, April 2016.Download4/1/2016
Application of Nonlinear Seismic Soil-Structure Interaction Analysis for Identification of Seismic Margins at Nuclear Power Plants, INL/EXT-15-37382Application 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 2015Download11/3/2015
Scoping Study Investigating PWR Instrumentation during a Severe Accident Scenario, INL/EXT-15-35940Scoping Study Investigating PWR Instrumentation during a Severe; Accident Scenario, J. Rempe, D. Knudson, R. Lutz, INL/EXT-15-35940, September 2015.Download9/1/2015

Report TitleBrief NarrativeLinkDate
Enhancements to Engineering-scale Reactor Pressure Vessel Fracture Capabilities in Grizzly, INL/EXT-17-43427Enhancements to Engineering-scale Reactor Pressure Vessel Fracture Capabilities in Grizzly, INL/EXT-17-43427, B. Spencer, W. Hoffman, W. Jiang, September 2017.Download9/18/2017
Modular Accident Analysis Program (MAAP) – MELCOR Crosswalk Phase 1 Study, 3002004449, Electric Power Research Institute, Technical Update, November 2014.Modular Accident Analysis Program (MAAP) – MELCOR Crosswalk Phase 1 Study, 3002004449, Electric Power Research Institute, Technical Update, R. Wachowiak, EPRI 3002004449, November 2014.Download11/1/2014

Report TitleBrief NarrativeLinkDate
US Efforts in Support of Examinations at Fukushima Daiichi – 2016 Evaluations, ANL/LWRS-16/02US 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.Download8/1/2016

Report TitleBrief NarrativeLinkDate
US Efforts in Support of Examinations at Fukushima Daiichi, J. Rempe, ANL/LWRS-15/2US Efforts in Support of Examinations at Fukushima Daiichi, J. Rempe, ANL/LWRS-15/2, August 2015.Download8/1/2015
Reactor Safety Gap Evaluation of Accident Tolerant Components and Severe Accident Analysis, ANL-NE-15-4.Reactor Safety Gap Evaluation of Accident Tolerant Components and Severe Accident Analysis, R. Bunt, M. Corradini, P. Ellison, M. Farmer, M. Francis, J. Gabor, R. Gauntt, C. Henry, R. Linthicum, W. Luangdilok, R. Lutz, C. Paik, M. Plys, C. Rabiti, J. Rempe, K. Robb, R. Wachowiak, ANL-NE-15-4, March 31, 2015.Download3/31/2015

Report TitleBrief NarrativeLinkDate
Report on Prevention Analysis Trial Method and Case Study ImprovementsReport on Prevention Analysis Trial Method and Case Study Improvements, D. Blanchard and R. Youngblood, M3LW-12IN0702012, April 2012.Download4/1/2012

Report TitleBrief NarrativeLinkDate
The CORQUENCH Code for Modeling of Ex-Vessel Corium Coolability under Top Flooding Conditions Code Manual – Version4.1-betaThe 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.Download8/6/2018
Status Report on Ex-Vessel Coolability and Water Management, ANL/NE-16/18Status Report on Ex-Vessel Coolability and Water Management, ANL/NE-16/18, M. Farmer, K. Robb, September 15, 2016.Download9/15/2016
Fukushima Daiichi Unit 1 Accident Progression Uncertainty Analysis and Implications for Decommissioning of Fukushima Reactors – Volume I, SAND2016-0232Fukushima Daiichi Unit 1 Accident Progression Uncertainty Analysis and Implications for Decommissioning of Fukushima Reactors – Volume I, Sandia National Laboratories, SAND2016-0232, January 2106.Download1/19/2016
Fukushima Daiichi Unit 1 Uncertainty Analysis – Exploration of Core Melt Progression Uncertain Parameters – Volume II, SAND2015-6612Fukushima Daiichi Unit 1 Uncertainty Analysis – Exploration of Core Melt Progression Uncertain Parameters – Volume II, M. Denman, D. Brooks, SAND2015-6612, August 2015.Download8/1/2015