Kurt A. Terrani

12.0k total citations · 5 hit papers
194 papers, 8.3k citations indexed

About

Kurt A. Terrani is a scholar working on Materials Chemistry, Aerospace Engineering and Mechanical Engineering. According to data from OpenAlex, Kurt A. Terrani has authored 194 papers receiving a total of 8.3k indexed citations (citations by other indexed papers that have themselves been cited), including 171 papers in Materials Chemistry, 116 papers in Aerospace Engineering and 38 papers in Mechanical Engineering. Recurrent topics in Kurt A. Terrani's work include Nuclear Materials and Properties (154 papers), Nuclear reactor physics and engineering (99 papers) and Fusion materials and technologies (79 papers). Kurt A. Terrani is often cited by papers focused on Nuclear Materials and Properties (154 papers), Nuclear reactor physics and engineering (99 papers) and Fusion materials and technologies (79 papers). Kurt A. Terrani collaborates with scholars based in United States, Germany and Japan. Kurt A. Terrani's co-authors include Lance L. Snead, Bruce A. Pint, S.J. Zinkle, L.L. Snead, Jess C Gehin, Yutai Katoh, L.J. Ott, Yukinori Yamamoto, Kevin G. Field and Chinthaka M. Silva and has published in prestigious journals such as SHILAP Revista de lepidopterología, Acta Materialia and Scientific Reports.

In The Last Decade

Kurt A. Terrani

188 papers receiving 8.0k citations

Hit Papers

5 papers align trajectories

What are hit papers?

Hit papers significantly outperform the citation benchmark for their cohort. A paper qualifies if it has ≥500 total citations, achieves ≥1.5× the top-1% citation threshold for papers in the same subfield and year (this is the minimum needed to enter the top 1%, not the average within it), or reaches the top citation threshold in at least one of its specific research topics.

Accident tolerant fuels for LWRs: A perspective

2013 796 citations S.J. Zinkle, Kurt A. Terrani et al. Journal of Nuclear Materials profile →
Accident tolerant fuel cladding development: Promise, status, and challenges

2018 656 citations Kurt A. Terrani Journal of Nuclear Materials profile →
Advanced oxidation-resistant iron-based alloys for LWR fuel cladding

2013 416 citations Kurt A. Terrani, S.J. Zinkle et al. Journal of Nuclear Materials profile →
Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors

2015 382 citations Yukinori Yamamoto, Bruce A. Pint et al. Journal of Nuclear Materials profile →
High temperature oxidation of fuel cladding candidate materials in steam–hydrogen environments

2013 375 citations Bruce A. Pint, Kurt A. Terrani et al. Journal of Nuclear Materials profile →

Peers

Kurt A. Terrani

Kumar Sridharan United States

Ying Yang United States

Lance L. Snead United States

Jingjie Guo China

L. Arnberg Norway

William Yi Wang China

Triplicane A. Parthasarathy United States

Patrick Wollants Belgium

Hong‐Yu Yang China

Shigeharu Ukai Japan

Kumar Sridharan United States

Kurt A. Terrani

3.4k ×0.5

2.2k ×0.5

2.4k ×0.9

404 ×0.3

613 ×1.1

Citations per year, relative to Kurt A. Terrani Kurt A. Terrani (= 1×) peers Kumar Sridharan

Countries citing papers authored by Kurt A. Terrani

Since Specialization

Citations

This map shows the geographic impact of Kurt A. Terrani'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 Kurt A. Terrani with the expected number of citations based on a country's size and research output (numbers larger than one mean the country cites Kurt A. Terrani more than expected).

Fields of papers citing papers by Kurt A. Terrani

Since Specialization

Physical SciencesHealth SciencesLife SciencesSocial Sciences

This network shows the impact of papers produced by Kurt A. Terrani. 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 Kurt A. Terrani. The network helps show where Kurt A. Terrani may publish in the future.

Co-authorship network of co-authors of Kurt A. Terrani

This figure shows the co-authorship network connecting the top 25 collaborators of Kurt A. Terrani. A scholar is included among the top collaborators of Kurt A. Terrani 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 Kurt A. Terrani. Kurt A. Terrani is excluded from the visualization to improve readability, since they are connected to all nodes in the network.

All Works

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20 of 20 papers shown

Terrani, Kurt A.. (2023). Additive manufacturing of complex objects using refractory matrix materials. OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information).

Doyle, Peter, J. Stuckert, M. Große, et al.. (2023). Analysis of iron-chromium-aluminum samples exposed to accident conditions followed by quench in the QUENCH-19 experiment. Journal of Nuclear Materials. 580. 154433–154433. 4 indexed citations

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

Schappel, Danny, et al.. (2022). Ordered Particle Packing in Dense TRISO/SiC Fuel Elements and Preliminary Assessment of Neutronic and Thermomechanical Characteristics. Nuclear Science and Engineering. 196(12). 1517–1538.

Betzler, Benjamin R., Prashant Jain, Aaron Wysocki, et al.. (2022). Conceptual Design of the Transformational Challenge Reactor. Nuclear Science and Engineering. 196(12). 1399–1424. 9 indexed citations

Schappel, Danny & Kurt A. Terrani. (2022). Stress Profile in Coating Layers of TRISO Fuel Particles in Contact with One Another. Nuclear Science and Engineering. 196(11). 1349–1360. 3 indexed citations

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

Zhong, Weicheng, Ying Yang, Kevin G. Field, et al.. (2021). Microstructure and mechanical properties of high Mn-containing ferritic-martensitic alloys exposed to cyclical thermal treatment. Materials Science and Engineering A. 813. 141143–141143. 6 indexed citations

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

10.

Terrani, Kurt A., Brian Jolly, Gokul Vasudevamurthy, et al.. (2021). Architecture and properties of TCR fuel form. Journal of Nuclear Materials. 547. 152781–152781. 34 indexed citations

11.

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

12.

Doyle, Peter, Caen Ang, L.L. Snead, et al.. (2020). Hydrothermal Corrosion of First-Generation Dual-Purpose Coatings on Silicon Carbide for Accident-Tolerant Fuel Cladding. Journal of Nuclear Materials. 544. 152695–152695. 20 indexed citations

13.

Terrani, Kurt A., et al.. (2020). Observed volatilization behavior of silicon carbide in flowing hydrogen above 2000 K. Journal of the American Ceramic Society. 103(12). 7159–7171. 2 indexed citations

14.

Zhong, Weicheng, Niyanth Sridharan, Dieter Isheim, et al.. (2020). Microstructures and mechanical properties of a modified 9Cr ferritic-martensitic steel in the as-built condition after additive manufacturing. Journal of Nuclear Materials. 545. 152742–152742. 24 indexed citations

15.

Terrani, Kurt A., et al.. (2019). 3D printing of high‐purity silicon carbide. Journal of the American Ceramic Society. 103(3). 1575–1581. 91 indexed citations

16.

Koyanagi, Takaaki, et al.. (2019). Fully Ceramic Microencapsulated fuel in prismatic high-temperature gas-cooled reactors: Sensitivity of reactor behavior during design basis accidents to fuel properties and the potential impact of the SiC defect annealing process. Nuclear Engineering and Design. 345. 125–147. 18 indexed citations

17.

Mouche, Peter & Kurt A. Terrani. (2019). Steam pressure and velocity effects on high temperature silicon carbide oxidation. Journal of the American Ceramic Society. 103(3). 2062–2075. 11 indexed citations

18.

Briggs, Samuel A., Philip D. Edmondson, Kenneth C. Littrell, et al.. (2017). A combined APT and SANS investigation of α′ phase precipitation in neutron-irradiated model FeCrAl alloys. Acta Materialia. 129. 217–228. 134 indexed citations

19.

Terrani, Kurt A., Bruce A. Pint, Y.-J. Kim, et al.. (2016). Uniform corrosion of FeCrAl alloys in LWR coolant environments. Journal of Nuclear Materials. 479. 36–47. 167 indexed citations

20.

Terrani, Kurt A., et al.. (2012). Fluoride-Salt-Cooled High-Temperature Reactor (FHR) with Silicon-Carbide-Matrix Coated-Particle Fuel. Transactions of the American Nuclear Society. 107. 907–910. 19 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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