2026 Lance Lewis Snead: Materials Science Researcher – H-Index, Publications & Awards

Discipline name	D-Index	World Ranking	Current World Ranking	National Ranking	Current National Ranking	Publications	Citations
Materials Science	76	3253	3141	912	856	364	22691

Discipline name

D-Index

World Ranking

Current World Ranking

National Ranking

Current National Ranking

Publications

Citations

Materials Science

3253

3141

912

856

364

22691

Overview

Lance Lewis Snead is affiliated with the Massachusetts Institute of Technology (MIT) in the United States. Their research primarily focuses on materials science and engineering, with a particular emphasis on nuclear materials and properties.

The scientist's work covers several main fields of study:

Materials Science
Engineering

Within these fields, their subfields of study include:

Materials Chemistry
Industrial and Manufacturing Engineering
Ceramics and Composites
Electrical and Electronic Engineering
Mechanics of Materials

The main topics explored in their research involve:

Nuclear Materials and Properties
Fusion materials and technologies
Recycling and Waste Management Techniques
Graphite, nuclear technology, radiation studies
Advanced ceramic materials synthesis
Metal and Thin Film Mechanics
Nuclear reactor physics and engineering

Frequent co-authors collaborating with Lance Lewis Snead are:

David Sprouster
Yutai Katoh
Koroush Shirvan
Takaaki Koyanagi
P Neggi

The researcher has published in several venues multiple times, with frequent appearances in:

SSRN Electronic Journal
Annals of Nuclear Energy
Journal of Nuclear Materials
Scripta Materialia
Acta Materialia

Recent published papers include:

"Evaluation of the effects of neutron irradiation on first-generation corrosion mitigation coatings on SiC for accident-tolerant fuel cladding," 2020, Journal of Nuclear Materials
"X-ray characterization of anisotropic defect formation in SiC under irradiation with applied stress," 2021, Scripta Materialia
"Deuterium trapping mechanisms in reduced activation ferritic martensitic steels and their correlation with mechanical strengthening," 2025, Acta Materialia
"Low Temperature Neutron Irradiation Stability of Zirconium Hydride and Yttrium Hydride," 2025, SSRN Electronic Journal
"Nitrogen and Metal Impurities of Historic and Modern Graphite Grades," 2025, SSRN Electronic Journal

Best Publications

Handbook of SiC properties for fuel performance modeling

Lance L. Snead;Takashi Nozawa;Yutai Katoh;Thak Sang Byun

1671
Citations
Accident tolerant fuels for LWRs: A perspective

Steven J Zinkle;Steven J Zinkle;Kurt A Terrani;Jess C Gehin;Larry J Ott

1199
Citations
Designing Radiation Resistance in Materials for Fusion Energy

Steven J Zinkle;Lance Lewis Snead

764
Citations
Advanced Oxidation Resistant Iron-Based Alloys for LWR Fuel Cladding

Kurt A Terrani;Steven J Zinkle;Lance Lewis Snead

669
Citations
Continuous SiC fiber, CVI SiC matrix composites for nuclear applications: Properties and irradiation effects

Yutai Katoh;Kazumi Ozawa;Chunghao Shih;Takashi Nozawa

563
Citations
Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors

Yukinori Yamamoto;Bruce A. Pint;Kurt A. Terrani;Kevin G. Field

547
Citations
Radiation effects in SiC for nuclear structural applications

Yutai Katoh;Lance Lewis Snead;Izabela Szlufarska;William J. Weber;William J. Weber

485
Citations
Current status and critical issues for development of SiC composites for fusion applications

Yutai Katoh;Lance L. Snead;Charles H. Henager;A. Hasegawa

444
Citations
Current status and recent research achievements in SiC/SiC composites

Y. Katoh;L.L. Snead;C.H. Henager;T. Nozawa

432
Citations
Limits on irradiation-induced thermal conductivity and electrical resistivity in silicon carbide materials

L.L Snead

362
Citations
Opportunities and limitations for ion beams in radiation effects studies: Bridging critical gaps between charged particle and neutron irradiations

S.J. Zinkle;S.J. Zinkle;L.L. Snead

338
Citations
Radiation tolerance of neutron-irradiated model Fe-Cr-Al alloys

Kevin G. Field;Xunxiang Hu;Kenneth C. Littrell;Yukinori Yamamoto

336
Citations
Properties of zirconium carbide for nuclear fuel applications

Yutai Katoh;Gokul Vasudevamurthy;Takashi Nozawa;Lance Lewis Snead

324
Citations
Material Selection for Accident Tolerant Fuel Cladding

Bruce A. Pint;Kurt A. Terrani;Yukinori Yamamoto;Lance Lewis Snead

311
Citations
Silicon Carbide Oxidation in Steam up to 2 MPa

Kurt A. Terrani;Bruce A. Pint;Chad M. Parish;Chinthaka M. Silva

297
Citations
Microencapsulated fuel technology for commercial light water and advanced reactor application

Kurt A Terrani;Lance Lewis Snead;Jess C Gehin

283
Citations
Irradiation hardening of pure tungsten exposed to neutron irradiation

Xunxiang Hu;Takaaki Koyanagi;Makoto Fukuda;N.A.P. Kiran Kumar

277
Citations
Promise and challenges of SiCf/SiC composites for fusion energy applications

Russell H. Jones;L. Giancarli;Akira Hasegawa;Y. Katoh

275
Citations
Silicon carbide composites as fusion power reactor structural materials

L. L. Snead;T. Nozawa;Monica Ferraris;Y. Katoh

275
Citations
Status of silicon carbide composites for fusion

L.L Snead;R.H Jones;A Kohyama;P Fenici

249
Citations
Issues and advances in SiCf/SiC composites development for fusion reactors

B Riccardi;L Giancarli;A Hasegawa;Y Katoh

248
Citations