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collapse High-Level Research Category : Accident Tolerant Components ‎(5)
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
  
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.
  
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.
  
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
  
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.
  
9/1/2015
collapse High-Level Research Category : Enabling Methods and Tools ‎(2)
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.
  
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.
  
11/1/2014
collapse High-Level Research Category : Fukushima Forensics Examinations ‎(1)
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.
  
8/1/2016
collapse High-Level Research Category : Reactor Safety Technical Support ‎(2)
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.
  
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.
  
3/31/2015
collapse High-Level Research Category : RISMC Framework ‎(1)
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.
  
4/1/2012
collapse High-Level Research Category : Severe Accident Analysis ‎(4)
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.
  
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.
  
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.
  
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.
  
8/1/2015