L. Snead
Materials Chemistry · 2000–2019
A researcher in the Science corpus: 32 papers; trusts 15 researchers and is trusted by 11 researchers here, as inferred from the citation graph.
Subfields
- Materials Chemistry — 177 citations into it; #2,044 of 11,513 by trust here, #2,066 by citations
- Mechanical Engineering — 63 citations into it; #5,441 of 8,300 by trust here, #1,691 by citations
- Ceramics and Composites — 59 citations into it; #88 of 497 by trust here, #11 by citations
- Aerospace Engineering — 57 citations into it; #2,701 of 6,421 by trust here, #838 by citations
- Electrical and Electronic Engineering — 23 citations into it; #13,529 of 16,539 by trust here, #6,143 by citations
Whom L. Snead trusts overall
Their strongest outbound trust, strongest first, inferred from their citations.
- Y. Katoh
- S. Zinkle
- K. Terrani
- T. Nozawa
- G. Was
- A. Kohyama
- E. Opila
- G. Odette
- A. Hasegawa
- William J. Weber
Who trusts L. Snead overall
Papers from L. Snead's perspective
Ordered by how strongly the researchers L. Snead trusts endorse each paper. Same corpus, a different order for every researcher.
- Mechanical testing of advanced fibre composites
- American Society for Testing and Materials
- Interaction potential for silicon carbide: A molecular dynamics study of elastic constants and vibrational density of states for crystalline and amorphous silicon carbide
- Multiscale modelling of defect kinetics in irradiated iron
- High Chromium Ferritic and Martensitic Steels for Nuclear Applications
- Comparative study of radiation damage accumulation in Cu and Fe
- A dislocation dynamics study of the transition from homogeneous to heterogeneous deformation in irradiated body-centered cubic iron
- Ab initio study of Cr interactions with point defects in bcc Fe
- First-principles determination of grain boundary strengthening in tungsten: Dependence on grain boundary structure and metallic radius of solute
- Observations of suppressed retention and blistering for tungsten exposed to deuterium–helium mixture plasmas
Their papers
- Advanced Oxidation Resistant Iron-Based Alloys for LWR Fuel Cladding (2014) — 542 citations
- Material Selection for Accident Tolerant Fuel Cladding (2015) — 264 citations
- Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors (2015) — 465 citations
- Radiation tolerance of neutron-irradiated model Fe-Cr-Al alloys (2015) — 296 citations
- Accident tolerant fuels for LWRs: A perspective (2014) — 989 citations
- Silicon Carbide Oxidation in Steam up to 2 MPa (2014) — 243 citations
- Thermal conductivity degradation of ceramic materials due to low temperature, low dose neutron irradiation (2005) — 166 citations
- Designing Radiation Resistance in Materials for Fusion Energy (2014) — 737 citations
- Current status and critical issues for development of SiC composites for fusion applications (2007) — 350 citations
- Silicon carbide and its composites for nuclear applications – Historical overview (2019) — 238 citations
- Opportunities and limitations for ion beams in radiation effects studies: Bridging critical gaps between charged particle and neutron irradiations (2018) — 323 citations
- Recent progress in the development of SiC composites for nuclear fusion applications (2018) — 185 citations
- Recent advances in modeling and simulation of the exposure and response of tungsten to fusion energy conditions (2017) — 144 citations
- Irradiation hardening of pure tungsten exposed to neutron irradiation (2016) — 262 citations
- Development of new generation reduced activation ferritic-martensitic steels for advanced fusion reactors (2016) — 163 citations
- Thermo-mechanical analysis of LWR SiC/SiC composite cladding (2014) — 137 citations
- Current status and recent research achievements in SiC/SiC composites (2014) — 367 citations
- Radiation-tolerant joining technologies for silicon carbide ceramics and composites (2014) — 179 citations
- Continuous SiC fiber, CVI SiC matrix composites for nuclear applications: Properties and irradiation effects (2014) — 493 citations
- Properties of Zirconium Carbide for Nuclear Fuel Applications (2013) — 254 citations