Kory Linton

662 total citations
27 papers, 284 citations indexed

About

Kory Linton is a scholar working on Materials Chemistry, Aerospace Engineering and Mechanical Engineering. According to data from OpenAlex, Kory Linton has authored 27 papers receiving a total of 284 indexed citations (citations by other indexed papers that have themselves been cited), including 26 papers in Materials Chemistry, 14 papers in Aerospace Engineering and 8 papers in Mechanical Engineering. Recurrent topics in Kory Linton's work include Nuclear Materials and Properties (22 papers), Nuclear reactor physics and engineering (14 papers) and Fusion materials and technologies (11 papers). Kory Linton is often cited by papers focused on Nuclear Materials and Properties (22 papers), Nuclear reactor physics and engineering (14 papers) and Fusion materials and technologies (11 papers). Kory Linton collaborates with scholars based in United States, China and Germany. Kory Linton's co-authors include Kurt A. Terrani, Ben Garrison, Maxim N. Gussev, Timothy G. Lach, Mahmut Nedim Cinbiz, Xiang Chen, Thak Sang Byun, Keith J. Leonard, Nathan Capps and Chinthaka M. Silva and has published in prestigious journals such as Journal of Nuclear Materials, Nuclear Engineering and Design and Annals of Nuclear Energy.

In The Last Decade

Kory Linton

24 papers receiving 278 citations

Peers — A (Enhanced Table)

Peers by citation overlap · career bar shows stage (early→late) cites · hero ref

Name h Career Trend Papers Cites
Kory Linton United States 9 224 117 86 27 22 27 284
Jesper Ejenstam Sweden 7 247 1.1× 125 1.1× 170 2.0× 5 0.2× 13 0.6× 14 306
Jingshan He China 13 99 0.4× 349 3.0× 107 1.2× 7 0.3× 44 2.0× 15 376
Z.J. Li China 7 175 0.8× 278 2.4× 104 1.2× 7 0.3× 17 0.8× 10 342
Masaya Higashi Japan 9 168 0.8× 317 2.7× 54 0.6× 65 2.4× 38 1.7× 11 348
Yunhai Su China 10 94 0.4× 315 2.7× 119 1.4× 14 0.5× 10 0.5× 39 345
Tao Wan Japan 6 202 0.9× 235 2.0× 67 0.8× 9 0.3× 8 0.4× 23 320
Calvin Parkin United States 8 158 0.7× 391 3.3× 254 3.0× 32 1.2× 7 0.3× 12 442
Grant Helmreich United States 9 166 0.7× 87 0.7× 109 1.3× 53 2.0× 22 1.0× 28 253
S. Heuer Germany 10 179 0.8× 149 1.3× 58 0.7× 7 0.3× 21 1.0× 14 263
Guangming Zhang China 12 312 1.4× 176 1.5× 101 1.2× 7 0.3× 9 0.4× 15 382

Countries citing papers authored by Kory Linton

Since Specialization
Citations

This map shows the geographic impact of Kory Linton's research. It shows the number of citations coming from papers published by authors working in each country. You can also color the map by specialization and compare the number of citations received by Kory Linton with the expected number of citations based on a country's size and research output (numbers larger than one mean the country cites Kory Linton more than expected).

Fields of papers citing papers by Kory Linton

Since Specialization
Physical SciencesHealth SciencesLife SciencesSocial Sciences

This network shows the impact of papers produced by Kory Linton. Nodes represent research fields, and links connect fields that are likely to share authors. Colored nodes show fields that tend to cite the papers produced by Kory Linton. The network helps show where Kory Linton may publish in the future.

Co-authorship network of co-authors of Kory Linton

This figure shows the co-authorship network connecting the top 25 collaborators of Kory Linton. A scholar is included among the top collaborators of Kory Linton based on the total number of citations received by their joint publications. Widths of edges represent the number of papers authors have co-authored together. Node borders signify the number of papers an author published with Kory Linton. Kory Linton is excluded from the visualization to improve readability, since they are connected to all nodes in the network.

All Works

20 of 20 papers shown
1.
Lach, Timothy G., et al.. (2025). Strength and ductility of additively manufactured 316L stainless steel: Impact of neutron irradiation and data variability. Journal of Nuclear Materials. 615. 155956–155956.
2.
Howard, Richard H., et al.. (2025). The state of the art for neutron irradiation experiments from the perspective of the High Flux Isotope Reactor (HFIR). Nuclear Engineering and Design. 444. 114401–114401.
3.
Lach, Timothy G., Weicheng Zhong, David Sprouster, et al.. (2024). Phase stability and microstructure of neutron-irradiated substoichiometric yttrium dihydrides. Journal of Nuclear Materials. 603. 155374–155374. 4 indexed citations
4.
Cakmak, Ercan, Mahmut Nedim Cinbiz, Aditya Sundar, et al.. (2024). Hydrogen motion in near stoichiometric yttrium dihydride at elevated temperatures. Journal of Nuclear Materials. 593. 154972–154972. 9 indexed citations
5.
Gallagher, Ryan, et al.. (2023). Simulation of a TRISO MiniFuel irradiation experiment with data-informed uncertainty quantification. Nuclear Engineering and Design. 404. 112177–112177. 5 indexed citations
6.
Yan, Yong, et al.. (2023). High-temperature steam oxidation study of irradiated FeCrAl defueled specimens. Journal of Nuclear Materials. 590. 154868–154868. 4 indexed citations
7.
Petrie, Christian, Kory Linton, Gokul Vasudevamurthy, et al.. (2023). Fission gas retention of densely packed uranium carbonitride tristructural-isotropic fuel particles in a 3D printed SiC matrix. Journal of Nuclear Materials. 580. 154419–154419. 6 indexed citations
8.
Cinbiz, Mahmut Nedim, et al.. (2023). Impact of nano-scale cavities on hydrogen storage and retention in yttrium hydride. Materialia. 32. 101933–101933. 7 indexed citations
9.
Schappel, Danny, et al.. (2023). Failure analysis of nuclear transient-tested UN tristructural isotropic fuel particles in a 3D printed SiC matrix. Journal of Nuclear Materials. 586. 154691–154691. 6 indexed citations
10.
Wachs, Daniel M., Colby Jensen, Fabiola Cappia, et al.. (2022). The U.S. Accident Tolerant Fuels Program -- Transforming the Future of LWR Fuels. 90–97.
11.
Woolstenhulme, Nicolas, Nikolaus L. Cordes, Austin Fleming, et al.. (2022). TREAT testing of additively manufactured SiC canisters loaded with high density TRISO fuel for the Transformational Challenge Reactor project. Journal of Nuclear Materials. 575. 154204–154204. 5 indexed citations
12.
Gussev, Maxim N., et al.. (2022). A correlation-based approach for evaluating mechanical properties of nuclear fuel cladding tubes. Journal of Nuclear Materials. 574. 154192–154192. 6 indexed citations
13.
Terrani, Kurt A., Timothy G. Lach, Hsin Wang, et al.. (2021). Irradiation stability and thermomechanical properties of 3D-printed SiC. Journal of Nuclear Materials. 551. 152980–152980. 12 indexed citations
14.
Byun, Thak Sang, Ben Garrison, Xiang Chen, et al.. (2021). Mechanical behavior of additively manufactured and wrought 316L stainless steels before and after neutron irradiation. Journal of Nuclear Materials. 548. 152849–152849. 64 indexed citations
15.
Garrison, Ben, Mahmut Nedim Cinbiz, Maxim N. Gussev, & Kory Linton. (2021). Burst characteristics of advanced accident-tolerant FeCrAl cladding under temperature transient testing. Journal of Nuclear Materials. 560. 153488–153488. 11 indexed citations
16.
Yu, Zefeng, et al.. (2020). (S)TEM/EDS study of native precipitates and irradiation induced Nb-rich platelets in high-burnup M5®. Journal of Nuclear Materials. 544. 152667–152667. 10 indexed citations
17.
Capps, Nathan, Yong Yan, Tyler Smith, et al.. (2020). Integral LOCA fragmentation test on high-burnup fuel. Nuclear Engineering and Design. 367. 110811–110811. 31 indexed citations
18.
Byun, Thak Sang, et al.. (2020). HFIR Irradiation Testing Supporting the Transformational Challenge Reactor. 242–245. 3 indexed citations
19.
Chen, Xiang, Arunodaya Bhattacharya, Mikhail A. Sokolov, et al.. (2019). Mechanical properties and microstructure characterization of Eurofer97 steel variants in EUROfusion program. Fusion Engineering and Design. 146. 2227–2232. 25 indexed citations
20.
Cinbiz, Mahmut Nedim, Maxim N. Gussev, Kory Linton, & Kurt A. Terrani. (2018). An advanced experimental design for modified burst testing of nuclear fuel cladding materials during transient loading. Annals of Nuclear Energy. 127. 30–38. 7 indexed citations

Rankless uses publication and citation data sourced from OpenAlex, an open and comprehensive bibliographic database. While OpenAlex provides broad and valuable coverage of the global research landscape, it—like all bibliographic datasets—has inherent limitations. These include incomplete records, variations in author disambiguation, differences in journal indexing, and delays in data updates. As a result, some metrics and network relationships displayed in Rankless may not fully capture the entirety of a scholar's output or impact.

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