Παρακολούθηση
Kevin R. Robb
Kevin R. Robb
Η διεύθυνση ηλεκτρονικού ταχυδρομείου έχει επαληθευτεί στον τομέα ornl.gov - Αρχική σελίδα
Τίτλος
Παρατίθεται από
Παρατίθεται από
Έτος
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
3472014
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
2132012
Fluoride salt-cooled high-temperature reactor technology development and demonstration roadmap
DE Holcomb, GF Flanagan, GT Mays, WD Pointer, KR Robb, GL Yoder Jr
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 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
542014
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
522014
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
452017
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
412015
Validating modern methods for impurity analysis in fluoride salts
D Sulejmanovic, JM Kurley, K Robb, S Raiman
Journal of Nuclear Materials 553, 152972, 2021
382021
Insight From Fukushima Daiichi Unit 3 Investigations Using MELCOR
KR Robb, MW Francis, LJ Ott
Nuclear Technology 168 (2), 145-160, 2014
322014
Ex-Vessel Core Melt Modeling Comparison between MELTSPREAD-CORQUENCH and MELCOR 2.1
KR Robb, M Farmer, MW Francis
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2014
292014
Enhanced Ex-Vessel Analysis for Fukushima Daiichi Unit 1: Melt Spreading and Core-Concrete Interaction Analyses with MELTSPREAD & CORQUENCH
KR Robb, M Farmer, MW Francis
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2013
292013
Technology Implementation Plan. Fully Ceramic Microencapsulated Fuel for Commercial Light Water Reactor Application
LL Snead, KA Terrani, JJ Powers, A Worrall, KR Robb, MA Snead
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2015
27*2015
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
272014
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
262016
Parametric and experimentally informed BWR Severe Accident Analysis Utilizing FeCrAl-M3FT-17OR020205041
LJ Ott, M Howell, KR Robb
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2017
23*2017
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
23*2016
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 Laboratory (ORNL), Oak Ridge, TN (United States), 2019
202019
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
192017
Fluoride Salt-Cooled High-Temperature Demonstration Reactor Point Design
AL Qualls, NR Brown, BR Betzler, J Carbajo, RE Hale, TJ Harrison, ...
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2016
182016
Δεν είναι δυνατή η εκτέλεση της ενέργειας από το σύστημα αυτή τη στιγμή. Προσπαθήστε ξανά αργότερα.
Άρθρα 1–20