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Jacob W McMurray
Jacob W McMurray
Kairos Power
在 ornl.gov 的电子邮件经过验证
标题
引用次数
引用次数
年份
Cation–Eutectic Transition via Sublattice Melting in CuInP2S6/In4/3P2S6 van der Waals Layered Crystals
MA Susner, M Chyasnavichyus, AA Puretzky, Q He, BS Conner, Y Ren, ...
ACS nano 11 (7), 7060-7073, 2017
582017
Reestablishing the paradigm for evaluating halide salt compatibility to study commercial chloride salts at 600 C–800 C
BA Pint, JW McMurray, AW Willoughby, JM Kurley, SR Pearson, MJ Lance, ...
Materials and Corrosion 70 (8), 1439-1449, 2019
482019
Solidstate synthesis of multicomponent equiatomic rareearth oxides
M Pianassola, M Loveday, JW McMurray, M Koschan, CL Melcher, ...
Journal of the American Ceramic Society 103 (4), 2908-2918, 2020
442020
Development of the molten salt thermal properties database− thermochemical (MSTDB− TC), example applications, and LiCl− RbCl and UF3− UF4 system assessments
JC Ard, JA Yingling, KE Johnson, J Schorne-Pinto, M Aziziha, CM Dixon, ...
Journal of Nuclear Materials 563, 153631, 2022
382022
Multi-physics simulations for molten salt reactor evaluation: Chemistry modeling and database development
JW Mcmurray, TM Besmann, J Ard, B FItzpatrick, M Piro, J Jerden, ...
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2018
382018
Quantification of process variables for carbothermic synthesis of UC1-xNx fuel microspheres
TB Lindemer, CM Silva, JJ Henry, JW McMurray, SL Voit, JL Collins, ...
Journal of Nuclear Materials 483, 176-191, 2017
342017
Solid-liquid phase equilibria of Fe-Cr-Al alloys and spinels
JW Mcmurray, R Hu, SV Ushakov, D Shin, BA Pint, KA Terrani, ...
Journal of Nuclear Materials 492, 128-133, 2017
322017
Uranium nitride-silicide advanced nuclear fuel: higher efficiency and greater safety
TL Wilson, EE Moore, D Adorno Lopes, V Kocevski, E Sooby Wood, ...
Advances in Applied Ceramics 117 (1_suppl), 76-81, 2018
312018
Roadmap for thermal property measurements of Molten Salt Reactor systems
JW Mcmurray, K Johnson, C Agca, BR Betzler, DJ Kropaczek, ...
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2021
302021
Determining the minimum required uranium carbide content for HTGR UCO fuel kernels
JW McMurray, TB Lindemer, NR Brown, TJ Reif, RN Morris, JD Hunn
Annals of Nuclear Energy 104, 237-242, 2017
282017
Thermodynamic reassessment of U–Gd–O system
JW McMurray, D Shin, BW Slone, TM Besmann
Journal of Nuclear Materials 452 (1-3), 397-406, 2014
282014
Brittle nature and the related effects of zirconium hydrides in Zircaloy-4
CM Silva, F Ibrahim, EG Lindquist, JW McMurray, CD Bryan
Materials Science and Engineering: A 767, 138396, 2019
252019
Reaction-bond composite synthesis of SiC-TiB2 by spark plasma sintering/field-assisted sintering technology (SPS/FAST)
CL Cramer, JW McMurray, MJ Lance, RA Lowden
Journal of the European Ceramic Society 40 (4), 988-995, 2020
212020
Ceramic encapsulated metal phase change material for high temperature thermal energy storage
JW McMurray, BC Jolly, SS Raiman, AT Schumacher, KM Cooley, ...
Applied Thermal Engineering 170, 115003, 2020
182020
Production of nearfull density uranium nitride microspheres with a hot isostatic press
JW McMurray, JO Kiggans, GW Helmreich, KA Terrani
Journal of the American Ceramic Society 101 (10), 4492-4497, 2018
182018
Application of thermochemical modeling to assessment/evaluation of nuclear fuel behavior
TM Besmann, JW McMurray, S Simunovic
Calphad 55, 47-51, 2016
182016
Thermochemical modeling of the U1− yGdyO2±x phase
JW McMurray, D Shin, BW Slone, TM Besmann
Journal of nuclear materials 443 (1-3), 588-595, 2013
182013
Thermodynamic assessment of the U–La–O system
JW McMurray, D Shin, TM Besmann
Journal of Nuclear Materials 456, 142-150, 2015
172015
Phase transformations in oxides above 2000 C: experimental technique development
SV Ushakov, PS Maram, D Kapush, AJ Pavlik III, M Fyhrie, LC Gallington, ...
Advances in Applied Ceramics 117 (1_suppl), 82-89, 2018
162018
Measurement of the oxygen partial pressure and thermodynamic modeling of the U–Nd–O system
SM Lee, TW Knight, JW McMurray, TM Besmann
Journal of Nuclear Materials 473, 272-282, 2016
162016
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