Randall O. Gauntt

发表

Using Uncertainty Information in Level 3 PRA Calculations (PSAM-0233)

Jocelyn Mitchell, Randall O. Gauntt, Nathan E. Bixler, 2006 .

New model improvements in MELCOR 1.8.6 to simulate the formation and behavior of molten pools in severe accidents.

Randall O. Gauntt, Jamie Eric Cash, Larry L. Humphries, 2005 .

Development of prismatic VHTR model using the MELCOR code

Karen Vierow, Salvador B. Rodriguez, Randall O. Gauntt, 2007 .

Synthesis of VERCORS and Phebus data in severe accident codes and applications.

Randall O. Gauntt, 2010 .

Severe accident analysis of a PWR station blackout with the MELCOR, MAAP4 and SCDAP/RELAP5 codes

Karen Vierow, Randall O. Gauntt, Y. Liao, 2004 .

A methodology for performing consequence analyses in support of level-3 PRAs.

Randall O. Gauntt, Nathan E. Bixler, 2005 .

In-reactor tests of the nuclear light bulb rocket concept

Randall O. Gauntt, Stephen A. Slutz, Ward C. Roman, 1992 .

MELCOR 1.8.5 benchmark for Alternative Source Term technical basis

Randall O. Gauntt, Scott G. Ashbaugh, 2006 .

Assessment of SAMPSON Severe Accident Code Modeling against MAAP-MELCOR Crosswalk.

Marco Pellegrini, Randall O. Gauntt, Ayumi Itoh, 2016 .

Methodology Development for Seamless Level 2/3 PRA Using Dynamic Event Trees

Tunc Aldemir, Randall O. Gauntt, Kyle Metzroth, 2008 .

SOARCA Peach Bottom Atomic Power Station Long-Term Station Blackout Uncertainty Analysis: Overview

Cedric Jean-Marie. Sallaberry, Patrick D. Mattie, Randall O. Gauntt, 2014 .

Overview of Reactor Safety and Severe Accident Analysis Technologies at Sandia National Laboratories.

Randall O. Gauntt, 2007 .

Application of the DG-1199 methodology to the ESBWR and ABWR.

Randall O. Gauntt, Donald A. Kalinich, Fotini Walton, 2010 .

TSG Skill Set - Ex-Vessel Accident Progression.

Randall O. Gauntt, Fotini Walton, Douglas Osborn, 2015 .

SOARCA Peach Bottom Atomic Power Station Long-Term Station Blackout Uncertainty Analysis: Knowledge Advancement

Cedric Jean-Marie. Sallaberry, Jeffrey N Cardoni, Patrick D. Mattie, 2014 .

Light Water Reactor Sustainability Program Reactor Safety Technologies Pathway Technical Program Plan

Kevin R Robb, Mitchell T. Farmer, Michael L. Corradini, 2016 .

An uncertainty analysis of the hydrogen source term for a station blackout accident in Sequoyah using MELCOR 1.8.5

Randall O. Gauntt, Nathan E. Bixler, Kenneth C. Wagner, 2014 .

TSG Executive Summary - Severe Accident Phenomena.

Randall O. Gauntt, Douglas Osborn, Fotini Walton, 2015 .

Assessment of severe accident source terms in pressurized-water reactors with a 40% mixed-oxide and 60% low-enriched uranium core using MELCOR 1.8.5.

Randall O. Gauntt, Scott G. Ashbaugh, Kenneth C. Wagner, 2010 .

Exercises in Severe Accident Analysis using MELCOR: Accident Walkthrough.

Randall O. Gauntt, 2015 .

TSG Skill Set - Spent Fuel Pool Accident Phenomena.

Randall O. Gauntt, Douglas Osborn, Fotini Walton, 2015 .

Addition of secondary system modules and a graphical user interface into MELCOR-H2--Phase 1.

Leonard A. Malczynski, Karen Vierow, Mohamed S. El-Genk, 2006 .

The MELCOR code: History, status, and plans

Randall O. Gauntt, J. N. Ridgely, R. K. Cole, 1996 .

TSG Skill Set - Containment Performance.

Randall O. Gauntt, Douglas Osborn, Fotini Walton, 2015 .

RCIC operation in Fukushima accidents as modeled by MELCOR and proposed testing

Randall O. Gauntt, 2014 .

PROPOSED FUTURE COLLABORATION.

Leonard A. Malczynski, Karen Vierow, Mohamed S. El-Genk, 2006 .

Overview of MELCOR 1.8.4: Modeling advances and assessment

Randall O. Gauntt, R. D. Gasser, R. K. Cole, 1998 .

MELCOR-H2 Benchmarking of the Sandia National Labs Transient Sulfuric Acid Decomposition Experiments.

Karen Vierow, Thomas E. Drennen, Mohamed S. El-Genk, 2007 .

Severe Accident Code Assessment Activities Supported by Sandia National Laboratories.

Randall O. Gauntt, Nathan Andrews, 2017 .

Accident source terms for light-water nuclear power plants using high-burnup or MOX fuel.

Randall O. Gauntt, Mark Thomas Leonard, Michael Salay, 2011 .

Accident Source Terms for Pressurized Water Reactors with High-Burnup Cores Calculated Using MELCOR 1.8.5

Randall O. Gauntt, Scott G. Ashbaugh, Mark Thomas Leonard, 2016 .

MELCOR Fission Product Release Model for HTGRs.

Hossein Esmaili, Randall O. Gauntt, Richard Lee, 2010 .

MELCOR Simulations of the Severe Accident at the Fukushima 1F2 Reactor.

Jeffrey N Cardoni, Jesse Phillips, Randall O. Gauntt, 2012 .

Revisiting Insights from Three Mile Island Unit 2 Postaccident Examinations and Evaluations in View of the Fukushima Daiichi Accident

Michael L. Corradini, Randall O. Gauntt, Joy L. Rempe, 2012 .

Accident source terms for boiling water reactors with high burnup cores.

Randall O. Gauntt, Mark Thomas Leonard, Dana Auburn Powers, 2007 .

Transient Analysis of Sulfur-Iodine Cycle Experiments and Very High Temperature Reactor Simulations Using MELCOR-H2

Karen Vierow, Mohamed S. El-Genk, Shripad T. Revankar, 2009 .

Fukushima Daiichi accident study : status as of April 2012.

Susan Y. Pickering, Kevin R Robb, Jeffrey N Cardoni, 2012 .

Implementation of a generalized diffusion layer model for condensation into MELCOR

Karen Vierow, Randall O. Gauntt, Bradley Beeny, 2010 .

Uncertainty Analyses Using the MELCOR Severe Accident Analysis Code

Randall O. Gauntt, 2005 .

A Butanol Olfactometer for Field Measurement of Ambient Odors

John M. Sweeten, Andrew R. McFarland, Randall O. Gauntt, 1984 .