Martin Ševeček

523 total citations
30 papers, 370 citations indexed

About

Martin Ševeček is a scholar working on Materials Chemistry, Aerospace Engineering and Mechanical Engineering. According to data from OpenAlex, Martin Ševeček has authored 30 papers receiving a total of 370 indexed citations (citations by other indexed papers that have themselves been cited), including 29 papers in Materials Chemistry, 20 papers in Aerospace Engineering and 8 papers in Mechanical Engineering. Recurrent topics in Martin Ševeček's work include Nuclear Materials and Properties (29 papers), Nuclear reactor physics and engineering (18 papers) and Fusion materials and technologies (13 papers). Martin Ševeček is often cited by papers focused on Nuclear Materials and Properties (29 papers), Nuclear reactor physics and engineering (18 papers) and Fusion materials and technologies (13 papers). Martin Ševeček collaborates with scholars based in Czechia, South Korea and United States. Martin Ševeček's co-authors include Koroush Shirvan, Yifeng Che, Bren Phillips, Malik Wagih, Victor K. Champagne, Ladislav Cvrček, Youho Lee, Patricie Halodová, Pavol Šutta and Jan Kočí and has published in prestigious journals such as SHILAP Revista de lepidopterología, Surface and Coatings Technology and Journal of Nuclear Materials.

In The Last Decade

Martin Ševeček

26 papers receiving 347 citations

Peers — A (Enhanced Table)

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

Name h Career Trend Papers Cites
Martin Ševeček Czechia 9 354 262 81 36 12 30 370
Valérie Vandenberghe France 8 439 1.2× 312 1.2× 102 1.3× 47 1.3× 8 0.7× 11 461
Evrard Lacroix United States 5 322 0.9× 151 0.6× 93 1.1× 34 0.9× 13 1.1× 9 343
A. V. Nikulina Russia 7 267 0.8× 88 0.3× 113 1.4× 31 0.9× 13 1.1× 16 301
Philippe Bossis France 9 266 0.8× 152 0.6× 39 0.5× 21 0.6× 7 0.6× 16 281
D. Hamon France 12 430 1.2× 200 0.8× 168 2.1× 40 1.1× 7 0.6× 23 475
Jean-Paul Mardon France 14 416 1.2× 213 0.8× 81 1.0× 41 1.1× 15 1.3× 26 440
Jong Hyuk Baek South Korea 10 314 0.9× 179 0.7× 91 1.1× 24 0.7× 8 0.7× 17 328
Tomoyuki Uwaba Japan 11 290 0.8× 159 0.6× 98 1.2× 38 1.1× 28 2.3× 36 321
Martine Blat France 7 351 1.0× 161 0.6× 102 1.3× 31 0.9× 4 0.3× 12 372
M. Blat-Yrieix France 8 240 0.7× 81 0.3× 80 1.0× 35 1.0× 3 0.3× 16 279

Countries citing papers authored by Martin Ševeček

Since Specialization
Citations

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

Fields of papers citing papers by Martin Ševeček

Since Specialization
Physical SciencesHealth SciencesLife SciencesSocial Sciences

This network shows the impact of papers produced by Martin Ševeček. 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 Martin Ševeček. The network helps show where Martin Ševeček may publish in the future.

Co-authorship network of co-authors of Martin Ševeček

This figure shows the co-authorship network connecting the top 25 collaborators of Martin Ševeček. A scholar is included among the top collaborators of Martin Ševeček 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 Martin Ševeček. Martin Ševeček 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.
Ševeček, Martin, et al.. (2025). Qualification of L-DED 316L for nuclear reactor core applications – Material characteristics before and after neutron irradiation. Nuclear Engineering and Technology. 57(11). 103765–103765.
2.
Kang, Hyun-Goo, et al.. (2025). Parabolic oxidation for various chromium-coated Zr-Nb Alloy Claddings. Journal of Nuclear Materials. 615. 155946–155946. 2 indexed citations
3.
Ševeček, Martin, et al.. (2025). High-temperature creep behavior of Cr-coated optimized ZIRLO™ cladding via inverse analysis based on finite element method. Nuclear Engineering and Design. 444. 114383–114383.
5.
Ševeček, Martin, et al.. (2024). Post-quench ductility limits of coated ATF with various zirconium-based alloys and coating designs. Journal of Nuclear Materials. 591. 154915–154915. 8 indexed citations
6.
Halodová, Patricie, et al.. (2024). Effect of neutron irradiation on microstructural evolution and deformation behavior of Zirconium (Zr-1Nb) alloy. Journal of Nuclear Materials. 605. 155596–155596. 1 indexed citations
7.
Zhang, Jinzhao, Michel Havet, Junlin Zheng, et al.. (2024). Analyses of design extension conditions without significant fuel degradation for operating nuclear power plants: An OECD/NEA review. Nuclear Engineering and Design. 425. 113320–113320. 1 indexed citations
8.
Jang, Dongchan, et al.. (2024). Micro-mechanical evaluations of adhesion properties for Cr-coated accident tolerant fuel cladding. Nuclear Materials and Energy. 41. 101799–101799. 1 indexed citations
9.
Zhang, Jinzhao, et al.. (2024). Contribution of IAEA coordinated research projects to light water reactors advanced technology fuel testing and simulation. Nuclear Engineering and Design. 418. 112910–112910. 3 indexed citations
10.
Lomonaco, Guglielmo, et al.. (2023). Assessment of Accident-Tolerant Fuel with FeCrAl Cladding Behavior Using MELCOR 2.2 Based on the Results of the QUENCH-19 Experiment. Energies. 16(6). 2763–2763. 2 indexed citations
11.
Ševeček, Martin, et al.. (2023). Characterization of eutectic reaction of Cr and Cr/CrN coated zircaloy accident tolerant fuel cladding. Nuclear Engineering and Technology. 55(10). 3535–3542. 17 indexed citations
12.
Ševeček, Martin, et al.. (2022). Utilization of Additive Manufacturing in Nuclear Power Industry. 1–6. 1 indexed citations
13.
Ševeček, Martin, et al.. (2022). Modelling of fission gas release in UO2 doped fuel using transuranus code. SHILAP Revista de lepidopterología. 37. 24–30.
14.
Cappia, Fabiola, et al.. (2022). Development of axial and ring hoop tension testing methods for nuclear fuel cladding tubes. Nuclear Materials and Energy. 31. 101175–101175. 15 indexed citations
15.
Ševeček, Martin, et al.. (2020). THERMAL ANALYSIS OF DRY STORAGE AND TRANSPORTATION CASKS CASTOR USING COBRA-SFS. SHILAP Revista de lepidopterología. 28. 32–41. 1 indexed citations
16.
Pastore, Giovanni, Sami Penttilä, Martin Ševeček, et al.. (2020). Analysis of Options and Experimental Examination of Fuels for Water Cooled Reactors with Increased Accident Tolerance (ACTOF). 1 indexed citations
17.
Hózer, Zoltán, M. Horváth, Péter Szabó, et al.. (2020). Development of new cladding types for nuclear fuel. IOP Conference Series Materials Science and Engineering. 903(1). 12004–12004. 3 indexed citations
18.
Ševeček, Martin, et al.. (2018). Development of high thermal conductivity UO2–Th heterogeneous fuel. Progress in Nuclear Energy. 108. 489–496. 4 indexed citations
19.
Ševeček, Martin, et al.. (2016). Measurements of the thermal conductivity of uranium dioxide by the flashing method. 1–6. 1 indexed citations
20.
Ševeček, Martin, et al.. (2016). EVALUATION METRICS APPLIED TO ACCIDENT TOLERANT FUEL CLADDING CONCEPTS FOR VVER REACTORS. SHILAP Revista de lepidopterología. 4. 89–89. 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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