Reactor Safety Technologies - Reports
Report Title | Brief Narrative | Link | Date |
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Terry Turbopump Expanded Operating Band Full-Scale Integral Long-Term Low-Pressure Experiments – Preliminary Test Plan | Terry Turbopump Expanded Operating Band Full-Scale Integral Long-Term Low-Pressure Experiments – Preliminary Test Plan, SAND2018-12965, D. OSborn, M. Solom, January 2019 | Download | 1/13/2019 |
Improvements in the reactor core isolation cooling (RCIC) pump model | Improvements in the reactor core isolation cooling (RCIC) pump model, INL-EXT-18-44739, H. Zhang, J. O’Brtien, February 2018. | Download | 2/18/2018 |
Development of Three-Field Poromechanics Capability in MOOSE, INL/EXT-16-38931 | Development of Three-Field Poromechanics Capability in MOOSE, M. Sivaselvan, N. Oliveto, A. Whittaker, INL/EXT-16-38931, April 2016. | Download | 4/1/2016 |
Application of Nonlinear Seismic Soil-Structure Interaction Analysis for Identification of Seismic Margins at Nuclear Power Plants, INL/EXT-15-37382 | 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 | Download | 11/3/2015 |
Scoping Study Investigating PWR Instrumentation during a Severe Accident Scenario, INL/EXT-15-35940 | Scoping Study Investigating PWR Instrumentation during a Severe; Accident Scenario, J. Rempe, D. Knudson, R. Lutz, INL/EXT-15-35940, September 2015. | Download | 9/1/2015 |
Report Title | Brief Narrative | Link | Date |
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Enhancements to Engineering-scale Reactor Pressure Vessel Fracture Capabilities in Grizzly, INL/EXT-17-43427 | Enhancements to Engineering-scale Reactor Pressure Vessel Fracture Capabilities in Grizzly, INL/EXT-17-43427, B. Spencer, W. Hoffman, W. Jiang, September 2017. | Download | 9/18/2017 |
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. | Download | 11/1/2014 |
Report Title | Brief Narrative | Link | Date |
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US Efforts in Support of Examinations at Fukushima Daiichi – 2016 Evaluations, ANL/LWRS-16/02 | 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. | Download | 8/1/2016 |
Report Title | Brief Narrative | Link | Date |
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US Efforts in Support of Examinations at Fukushima Daiichi, J. Rempe, ANL/LWRS-15/2 | US Efforts in Support of Examinations at Fukushima Daiichi, J. Rempe, ANL/LWRS-15/2, August 2015. | Download | 8/1/2015 |
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. | Download | 3/31/2015 |
Report Title | Brief Narrative | Link | Date |
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Report on Prevention Analysis Trial Method and Case Study Improvements | Report on Prevention Analysis Trial Method and Case Study Improvements, D. Blanchard and R. Youngblood, M3LW-12IN0702012, April 2012. | Download | 4/1/2012 |
Report Title | Brief Narrative | Link | Date |
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The CORQUENCH Code for Modeling of Ex-Vessel Corium Coolability under Top Flooding Conditions Code Manual – Version4.1-beta | 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. | Download | 8/6/2018 |
Status Report on Ex-Vessel Coolability and Water Management, ANL/NE-16/18 | Status Report on Ex-Vessel Coolability and Water Management, ANL/NE-16/18, M. Farmer, K. Robb, September 15, 2016. | Download | 9/15/2016 |
Fukushima Daiichi Unit 1 Accident Progression Uncertainty Analysis and Implications for Decommissioning of Fukushima Reactors – Volume I, SAND2016-0232 | Fukushima Daiichi Unit 1 Accident Progression Uncertainty Analysis and Implications for Decommissioning of Fukushima Reactors – Volume I, Sandia National Laboratories, SAND2016-0232, January 2106. | Download | 1/19/2016 |
Fukushima Daiichi Unit 1 Uncertainty Analysis – Exploration of Core Melt Progression Uncertain Parameters – Volume II, SAND2015-6612 | Fukushima Daiichi Unit 1 Uncertainty Analysis – Exploration of Core Melt Progression Uncertain Parameters – Volume II, M. Denman, D. Brooks, SAND2015-6612, August 2015. | Download | 8/1/2015 |