L.L. Snead - Concepedia

Author

L.L. Snead

Oak Ridge National Laboratory ORCID

Also Known As

C. E. Singer, L L Snead, L SNEAD, L Snead, L. L. Snead, L. Snead, L.L Snead, L.L. SNEAD, L.L. Snead, Lance L Snead

223

Publications

7.3K

Citations

H-Index

105

Concepts

All Affiliations

Oak Ridge National Laboratory University of Tennessee at Knoxville Stony Brook University Bechtel (United States)University of California, Los Angeles

About

L.L. Snead is an author at Oak Ridge National Laboratory specializing in engineering, materials science, and microstructure.

Top Concepts

#	Concept	H-Index	Publications	Citations
1	Engineering	35	86	5.8K
2	Applied Physics	20	26	1.1K
3	Chemical Engineering	8	8	221
4	Natural Sciences	5	5	589
5	Chemistry	4	4	106

L.L. Snead

Publications

6.8K

Citations

H-Index

Page 1

	Year	Citations
Accident tolerant fuels for LWRs: A perspective S.J. Zinkle, Kurt A. Terrani, Jess C Gehin, Journal of Nuclear Materials Accident Tolerant FuelsEngineeringCombustion ScienceFuel SciencePetroleum Engineering	2013	1K
Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors Yukinori Yamamoto, Bruce A. Pint, Kurt A. Terrani, Journal of Nuclear Materials Materials ScienceEngineeringProperty EvaluationCorrosionNuclear Fuel	2015	493
Current status and critical issues for development of SiC composites for fusion applications Yutai Katoh, L.L. Snead, Charles H. Henager, Journal of Nuclear Materials Materials ScienceCeramic Matrix CompositeEngineeringCompositesComposite Technology	2007	379
Opportunities and limitations for ion beams in radiation effects studies: Bridging critical gaps between charged particle and neutron irradiations S.J. Zinkle, L.L. Snead Scripta Materialia Bridging Critical GapsNuclear PhysicsPhysicsNatural SciencesIonizing Radiation	2017	335
Radiation tolerance of neutron-irradiated model Fe–Cr–Al alloys Kevin G. Field, Xunxiang Hu, Kenneth C. Littrell, Journal of Nuclear Materials Materials ScienceRadiation ToleranceAlloy Design	2015	314
Properties of zirconium carbide for nuclear fuel applications Yutai Katoh, Gokul Vasudevamurthy, Takashi Nozawa, Journal of Nuclear Materials Materials ScienceNuclear CeramicEngineeringZirconium CarbideNuclear Materials	2013	292
Influence of irradiation spectrum and implanted ions on the amorphization of ceramics S.J. Zinkle, L.L. Snead Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms Materials ScienceCrystalline CeramicsEngineeringCeramicsCeramic Material	1996	189
Development of new generation reduced activation ferritic-martensitic steels for advanced fusion reactors Lizhen Tan, L.L. Snead, Yutai Katoh Journal of Nuclear Materials EngineeringCorrosionMechanical EngineeringFusion PowerNew Generation	2016	171
Evaluation of neutron irradiated silicon carbide and silicon carbide composites G.A. Newsome, L.L. Snead, Tatsuya Hinoki, Journal of Nuclear Materials Materials ScienceNuclear CeramicEngineeringMechanical EngineeringSilicon Carbide Composites	2007	159
Recent advances in modeling and simulation of the exposure and response of tungsten to fusion energy conditions Jaime Marian, Charlotte Becquart, Christophe Domain, Nuclear Fusion	2017	146

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