Publications

Goldmann, A., Humphries, L.L., Cardoni, J., Gauntt, R.O., & Gauntt, R.O. (2012). Fukushima Accident Spent Fuel Pool Model in MELCOR V2.1 [Conference]. https://www.osti.gov/biblio/1140685

Goldmann, A., Humphries, L.L., Cardoni, J., Gauntt, R.O., & Gauntt, R.O. (2012). MELCOR Source Term Calculation [Conference]. https://www.osti.gov/biblio/1063352

Goldmann, A., Humphries, L.L., Cardoni, J., Gauntt, R.O., & Gauntt, R.O. (2012). Modeling of Off-Site Consequences [Conference]. https://www.osti.gov/biblio/1063496

Gauntt, R.O. (2012). Fukushima Daiichi Accident StudyMELCOR Analyses Results and Insights [Conference]. https://www.osti.gov/biblio/1073259

Gauntt, R.O. (2012). Severe Accident Characterization of Fukushima Reactors and Experiences During Real-World Emergency Response [Conference]. https://www.osti.gov/biblio/1116463

Gauntt, R.O., Kalinich, D., Cardoni, J., Phillips, J., & Phillips, J. (2012). MELCOR Simulations of the Severe Accident at the Fukushima 1F1 Reactor [Conference]. https://www.osti.gov/biblio/1073343

Gauntt, R.O., Kalinich, D., Cardoni, J., Phillips, J., & Phillips, J. (2012). MELCOR Simulations of the Severe Accident at the Fukushima 1F2 Reactor [Conference]. https://www.osti.gov/biblio/1073366

Gauntt, R.O., Kalinich, D., Cardoni, J., Phillips, J., Goldmann, A., Pickering, S.Y., & Pickering, S.Y. (2012). Fukushima Daiichi accident study : status as of April 2012. 10.2172/1055601

Louie, D., Humphries, L.L., Gauntt, R.O., & Gauntt, R.O. (2012). MELCOR 2.1 Leak Path Factor Assessments and Guidance [Conference]. https://www.osti.gov/biblio/1068384

Humphries, L.L., Gauntt, R.O., & Gauntt, R.O. (2012). MELCOR 2.1 Leak Path Factor Assessment and Guidance [Conference]. https://www.osti.gov/biblio/1117388

Gauntt, R.O., Cardoni, J., Goldmann, A., Phillips, J., Pickering, S.Y., & Pickering, S.Y. (2012). Fukushima Daiichi Accident StudyPreliminary MELCOR Analyses and Results [Conference]. https://www.osti.gov/biblio/1117764

Gauntt, R.O., Weiner, R.F., Mattie, P., Ammerman, D., & Ammerman, D. (2012). NEST Fact Sheets- Part 1 [Presentation]. https://www.osti.gov/biblio/1660654

Gauntt, R.O. (2012). Severe Accident Tasks IVR [Conference]. https://www.osti.gov/biblio/1118159

Gauntt, R.O. (2012). Fukushima Lessons Learned [Conference]. https://www.osti.gov/biblio/1078741

Gauntt, R.O. (2011). Contemporary MELCOR Applications in Severe Accidents and Observations from Fukushima [Conference]. https://www.osti.gov/biblio/1143446

Gauntt, R.O. (2011). Phenomenological Uncertainties in SOARCA Study [Conference]. https://www.osti.gov/biblio/1108631

Powers, D.A., Gauntt, R.O., & Gauntt, R.O. (2010). Accident source terms for light-water nuclear power plants using high-burnup or MOX fuel. 10.2172/1010412

Young, M.F., Esmaili, H., Gauntt, R.O., Basu, S., Lee, R., Rubin, S., & Rubin, S. (2010). MELCOR fission product release model for HTGRs [Conference]. International Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010. https://www.scopus.com/inward/record.uri?partnerID=HzOxMe3b&scp=77956199912&origin=inward

Kalinich, D., Walton, F., Gauntt, R.O., & Gauntt, R.O. (2010). Application of the DG-1199 methodology to the ESBWR and ABWR. 10.2172/992320

Ashbaugh, S.G., Longmire, P., Gauntt, R.O., Powers, D.A., & Powers, D.A. (2010). Accident source terms for pressurized water reactors with high-burnup cores calculated using MELCOR 1.8.5. 10.2172/984120

Ashbaugh, S.G., Wagner, K.C., Longmire, P., Gauntt, R.O., Powers, D.A., & Powers, D.A. (2010). 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. 10.2172/984119

Longmire, P., Gauntt, R.O., Smith, J.D., & Smith, J.D. (2010). Radionuclide inventories : ORIGEN2.2 isotopic depletion calculation for high burnup low-enriched uranium and weapons-grade mixed-oxide pressurized-water reactor fuel assemblies. 10.2172/984118

Gauntt, R.O. (2010). Synthesis of VERCORS and Phebus data in severe accident codes and applications. 10.2172/983685

Gauntt, R.O. (2010). MELCOR 1.8.5 modeling aspects of fission product release, transport and deposition an assessment with recommendations. 10.2172/991532

Hessheimer, M.F., Gauntt, R.O., & Gauntt, R.O. (2009). Sandia National Laboratories Capabilities to Support the HSE/Nuclear Installations Inspectorate Generic Design Assessment [Presentation]. https://www.osti.gov/biblio/1695630