Kory D. Linton
Title
Cited by
Cited by
Year
LAMDA: irradiated-materials microscopy at Oak Ridge National Laboratory
CM Parish, NAPK Kumar, LL Snead, PD Edmondson, KG Field, C Silva, ...
Microscopy and Microanalysis 21 (S3), 1003-1004, 2015
432015
Irradiation of miniature fuel specimens in the High Flux Isotope Reactor
CM Petrie, JR Burns, RN Morris, KR Smith, AG Le Coq, KA Terrani
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2018
15*2018
Report on Design and Failure Limits of SiC/SiC and FeCrAl ATF Cladding Concepts Under RIA
MN Cinbiz, N Brown, RR Lowden, MN Gussev, KD Linton, KA Terrani
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2018
52018
Transition fracture toughness characterization of Eurofer97 steel using pre-cracked miniature multi-notch bend bar specimens
X Chen, MA Sokolov, KD Linton, L Clowers, Y Katoh
ORNL/LTR-2017/532, November 30, 2017
42017
Mechanical properties and microstructure characterization of Eurofer97 steel variants in EUROfusion program
X Chen, A Bhattacharya, MA Sokolov, LN Clowers, Y Yamamoto, ...
Fusion Engineering and Design 146, 2227-2232, 2019
32019
Tensile Testing of Irradiated Grade 92 Ferritic-Martensitic Steels at the IMET Hot Cell Facility
AM Raftery, L Tan, H Sakasegawa, KD Linton
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2018
32018
Irradiation of Wrought FeCrAl Tubes in the High Flux Isotope Reactor
CM Petrie, KG Field, K Linton
ORNL/SR-2017/466, Oak Ridge National Laboratory, Oak Ridge, TN, 2017
32017
Hot Cell Installation and Demonstration of the Severe Accident Test Station
KD Linton, ZM Burns, KA Terrani, Y Yan
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2017
32017
Tensile Testing and Characterization of Irradiated Grade 92 Ferritic-Martensitic Steels at the IMET Hot Cell and Lambda Facilities
B Garrison, W Zhong, L Tan, K Linton
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2019
22019
Identification and shipment progress of the INL and LANL samples to be received at ORNL
L Tan, K Linton, C Knight, TA Saleh
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2019
22019
First annual progress report on the procurement and post-irradiation examination of the selected samples of alloy 800H and Grade 92 and 91 steels
L Tan, T Chen, K Linton, C Knight, TA Saleh
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2019
22019
Status of Wrought FeCrAl-UO2 Capsules Irradiated in the Advanced Test Reactor
KG Field, J Harp, G Core, K Linton
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2017
22017
Integral LOCA fragmentation test on high-burnup fuel
N Capps, Y Yan, A Raftery, Z Burns, T Smith, K Terrani, K Yueh, M Bales, ...
Nuclear Engineering and Design 367, 110811, 2020
12020
Characteristics of Fuel Articles for Irradiation Testing in TREAT and MITR
G Vasudevamurthy, N Brown, R Kile, D Schappel, K Linton
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2020
12020
An advanced experimental design for modified burst testing of nuclear fuel cladding materials during transient loading
MN Cinbiz, M Gussev, K Linton, KA Terrani
Annals of Nuclear Energy 127, 30-38, 2019
12019
Transportation Planning for Irradiated Fuel-Cladding and Integral FeCrAl Experiments
AG Le Coq, RC Martin, KD Linton
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2019
12019
Design and Thermal Analysis for Irradiation of Tensile Specimens from Wrought, Powder Metallurgy, and Additive Processed Alloys in the HFIR
AG Le Coq, RH Howard, KD Linton, KG Field
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2018
12018
Design and Thermal Analysis for Irradiation of Silicon Carbide Joint Specimens in the High Flux Isotope Reactor
CM Petrie, AG LeCoq, RC Gallagher, KD Linton, CP Deck
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2018
12018
In-cell Re-fabrication and Loss-of-coolant Accident (LOCA) Testing of High Burnup Commercial Spent Fuel
AM Raftery, Y Yan, TS Smith, ZM Burns, KA Terrani, KD Linton
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2018
12018
Assembly of Rabbit Capsules for Irradiation of Pyrolytic Carbon/Silicon Carbide Diffusion Couples in the High Flux Isotope Reactor
AG Le Coq, KD Linton, RC Gallagher, TJ Gerczak, KA Terrani, CM Petrie
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2018
12018
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