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Kevin R. Robb
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Year
Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions
LJ Ott, KR Robb, D Wang
Journal of Nuclear Materials 448 (1-3), 520-533, 2014
3082014
Fukushima Daiichi accident study: status as of April 2012.
RO Gauntt, DA Kalinich, JN Cardoni, J Phillips, AS Goldmann, ...
Sandia National Laboratories (SNL), Albuquerque, NM, and Livermore, CA …, 2012
2042012
Fluoride salt-cooled high-temperature reactor technology development and demonstration roadmap
DE Holcomb, GF Flanagan, GT Mays, WD Pointer, KR Robb, GL Yoder Jr
ORNL/TM-2013/401, ORNL, Oak Ridge, TN, 2013
932013
Scoping assessments of ATF impact on late-stage accident progression including molten core–concrete interaction
MT Farmer, L Leibowitz, KA Terrani, KR Robb
Journal of nuclear materials 448 (1-3), 534-540, 2014
502014
An experimental test facility to support development of the fluoride-salt-cooled high-temperature reactor
GL Yoder Jr, A Aaron, B Cunningham, D Fugate, D Holcomb, R Kisner, ...
Annals of Nuclear Energy 64, 511-517, 2014
472014
Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Motivation and overview
AL Qualls, BR Betzler, NR Brown, JJ Carbajo, MS Greenwood, R Hale, ...
Annals of Nuclear Energy 107, 144-155, 2017
402017
Analysis of the FeCrAl accident tolerant fuel concept benefits during BWR station blackout accidents
KR Robb
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2015
342015
Enhanced Ex-Vessel Analysis for Fukushima Daiichi Unit 1: Melt Spreading and Core-Concrete Interaction
KR Robb, MW Francis, MT Farmer
Oak Ridge National Laboratory, Oak Ridge, TN, Report No. ORNL/TM-2012/455, 2013
292013
Insight From Fukushima Daiichi Unit 3 Investigations Using MELCOR
KR Robb, MW Francis, LJ Ott
Nuclear Technology 168 (2), 145-160, 2014
282014
Validating modern methods for impurity analysis in fluoride salts
D Sulejmanovic, JM Kurley, K Robb, S Raiman
Journal of Nuclear Materials 553, 152972, 2021
272021
Ex-Vessel Core Melt Modeling Comparison between MELTSPREAD-CORQUENCH and MELCOR 2.1
KR Robb, MT Farmer, MW Francis
ORNL/TM-2014/1, March, 2014
272014
Reactor Safety Gap Evaluation of Accident-Tolerant Components and Severe Accident Analysis
MT Farmer, R Bunt, M Corradini, P Ellison, M Francis, J Gabor, R Gauntt, ...
Nuclear Science and Engineering 184 (3), 293-304, 2016
24*2016
Estimation of inherent safety margins in loaded commercial spent nuclear fuel casks
K Banerjee, KR Robb, G Radulescu, JM Scaglione, JC Wagner, JB Clarity, ...
Nuclear Technology 195 (2), 124-142, 2016
242016
Advanced fuels campaign: enhanced LWR accident tolerant fuel performance metrics
S Bragg-Sitton, B Merrill, M Teague, L Ott, K Robb, M Farmer, M Billone, ...
Idaho National Laboratory Report INL/EXT, 13-29957, 2014
242014
Parametric and experimentally informed BWR Severe Accident Analysis Utilizing FeCrAl-M3FT-17OR020205041
LJ Ott, M Howell, KR Robb
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2017
23*2017
Technology Implementation Plan ATF FeCrAl Cladding for LWR Application
M Snead, LL Snead, KA Terrani, KG Field, A Worrall, KR Robb, ...
ORNL/TM-2014-353, Oak Ridge National Laboratory (May 2014), 2014
232014
Integrated Data And Analysis System For Commercial Used Nuclear Fuel Safety Assessments–14657
JM Scaglione, JL Peterson, K Banerjee, KR Robb, RA LeFebvre
222013
Facility to alleviate salt technology risks (fastr): Preliminary design report with failure modes and effects analysis
KR Robb, PL Mulligan, GL Yoder Jr, K Smith, J Massengale
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2019
192019
Advanced fuels campaign light water reactor accident tolerant fuel performance metrics
S Bragg-Sitton, B Merrill, M Teague, L Ott, K Rob, M Farmer, M Billone, ...
INL/EXT-13-29957, 2014
172014
Safety insights from forensics evaluations at Daiichi
J Rempe, M Corradini, M Farmer, J Gabor, R Gauntt, T Hara, ...
Nuclear Materials and Energy 10, 18-34, 2017
162017
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