V.E. Shestak

505 total citations
26 papers, 419 citations indexed

About

V.E. Shestak is a scholar working on Materials Chemistry, Aerospace Engineering and Mechanical Engineering. According to data from OpenAlex, V.E. Shestak has authored 26 papers receiving a total of 419 indexed citations (citations by other indexed papers that have themselves been cited), including 25 papers in Materials Chemistry, 21 papers in Aerospace Engineering and 7 papers in Mechanical Engineering. Recurrent topics in V.E. Shestak's work include Nuclear Materials and Properties (24 papers), Nuclear reactor physics and engineering (20 papers) and Fusion materials and technologies (6 papers). V.E. Shestak is often cited by papers focused on Nuclear Materials and Properties (24 papers), Nuclear reactor physics and engineering (20 papers) and Fusion materials and technologies (6 papers). V.E. Shestak collaborates with scholars based in Russia, France and Netherlands. V.E. Shestak's co-authors include M.S. Veshchunov, V. D. Ozrin, V. I. Tarasov, R. Dubourg, Grégory Nicaise, M. Steinbrück, Daria Smirnova, A. Yu. Kuksin, А. В. Палагин and A. V. Yanilkin 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

V.E. Shestak

25 papers receiving 405 citations

Peers — A (Enhanced Table)

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

Name h Career Trend Papers Cites
V.E. Shestak Russia 11 400 315 134 60 27 26 419
Pavel Medvedev United States 14 594 1.5× 414 1.3× 162 1.2× 82 1.4× 33 1.2× 60 615
Kyle Johnson Sweden 13 374 0.9× 185 0.6× 236 1.8× 44 0.7× 6 0.2× 27 435
T. Barani Italy 13 508 1.3× 428 1.4× 128 1.0× 63 1.1× 37 1.4× 29 532
Fabiola Cappia United States 14 407 1.0× 301 1.0× 150 1.1× 50 0.8× 19 0.7× 44 444
Masahiko Osaka Japan 14 562 1.4× 294 0.9× 306 2.3× 78 1.3× 43 1.6× 87 640
Suresh Yagnik United States 12 335 0.8× 205 0.7× 73 0.5× 63 1.1× 58 2.1× 38 404
Shinji KASHIBE Japan 13 598 1.5× 450 1.4× 366 2.7× 36 0.6× 33 1.2× 25 612
Mutsumi Hirai Japan 13 428 1.1× 310 1.0× 166 1.2× 73 1.2× 11 0.4× 39 471
S. Guilbert France 10 259 0.6× 133 0.4× 136 1.0× 29 0.5× 21 0.8× 26 304
S. Chatain France 11 321 0.8× 198 0.6× 159 1.2× 121 2.0× 6 0.2× 29 371

Countries citing papers authored by V.E. Shestak

Since Specialization
Citations

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

Fields of papers citing papers by V.E. Shestak

Since Specialization
Physical SciencesHealth SciencesLife SciencesSocial Sciences

This network shows the impact of papers produced by V.E. Shestak. 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 V.E. Shestak. The network helps show where V.E. Shestak may publish in the future.

Co-authorship network of co-authors of V.E. Shestak

This figure shows the co-authorship network connecting the top 25 collaborators of V.E. Shestak. A scholar is included among the top collaborators of V.E. Shestak 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 V.E. Shestak. V.E. Shestak 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.
Ozrin, V. D., et al.. (2024). Fuel performance code BERKUT-U to simulate the in-pile behavior of a single oxide or nitride fuel rod for fast reactors. Journal of Nuclear Materials. 603. 155417–155417.
2.
Veshchunov, M.S., et al.. (2022). LOCA advanced failure criteria: Implementation in the mechanistic fuel performance code and practical applications. Nuclear Engineering and Design. 399. 112039–112039. 3 indexed citations
3.
Tarasov, V. I., et al.. (2019). Development of the MFPR/R code for characterization of the rim zone and high burnup structure evolution in UO2 fuel pellets. Journal of Nuclear Materials. 517. 214–224. 6 indexed citations
4.
Veshchunov, M.S., et al.. (2017). Model for oxidized corium melt interactions with vessel steel. Nuclear Engineering and Design. 320. 153–164. 2 indexed citations
5.
Veshchunov, M.S., V.E. Shestak, & V. D. Ozrin. (2016). A new model of hydrogen redistribution in Zr alloy claddings during waterside corrosion in a temperature gradient. Journal of Nuclear Materials. 472. 65–75. 8 indexed citations
6.
Veshchunov, M.S., et al.. (2013). Modelling the formation and oxidation of molten pools. Annals of Nuclear Energy. 61. 54–62. 5 indexed citations
7.
Veshchunov, M.S. & V.E. Shestak. (2012). Modelling of fission gas release from irradiated UO2 fuel under high-temperature annealing conditions. Journal of Nuclear Materials. 430(1-3). 82–89. 10 indexed citations
8.
Veshchunov, M.S., et al.. (2011). A new mechanistic code SFPR for modeling of single fuel rod performance under various regimes of LWR operation. Nuclear Engineering and Design. 241(8). 2822–2830. 20 indexed citations
9.
Veshchunov, M.S., et al.. (2008). Analysis of molten pool physico-chemical interactions and interpretation of the Phebus FP tests observations. Nuclear Engineering and Design. 238(7). 1728–1742. 11 indexed citations
10.
Veshchunov, M.S. & V.E. Shestak. (2008). An advanced model for intragranular bubble diffusivity in irradiated UO2 fuel. Journal of Nuclear Materials. 376(2). 174–180. 32 indexed citations
11.
Veshchunov, M.S., R. Dubourg, V. D. Ozrin, V.E. Shestak, & V. I. Tarasov. (2007). Mechanistic modelling of urania fuel evolution and fission product migration during irradiation and heating. Journal of Nuclear Materials. 362(2-3). 327–335. 56 indexed citations
12.
Steinbrück, M., et al.. (2006). Oxidation of B4C by steam at high temperatures: New experiments and modelling. Nuclear Engineering and Design. 237(2). 161–181. 18 indexed citations
13.
14.
Veshchunov, M.S., V. D. Ozrin, V.E. Shestak, et al.. (2005). Development of the mechanistic code MFPR for modelling fission-product release from irradiated UO2 fuel. Nuclear Engineering and Design. 236(2). 179–200. 113 indexed citations
15.
Stuckert, J., A. Miassoedov, А. В. Палагин, et al.. (2005). Experimental and computational results of the QUENCH-08 experiment. (Reference to QUENCH-07). KITopen. 6970. 3 indexed citations
16.
17.
Палагин, А. В., et al.. (2001). Development of SVECHA/QUENCH Code for Modeling Fuel Cladding Degradation in QUENCH Tests. NCSU Libraries Repository (North Carolina State University Libraries). 4 indexed citations
18.
19.
Shestak, V.E., et al.. (1992). Iodine induced SCC of Zr alloys at constant strain rate. Journal of Nuclear Materials. 199(1). 50–60. 11 indexed citations
20.
Shestak, V.E., et al.. (1990). Anisotropy of the elastic modulus and thermal-expansion coefficient of textured zirconium alloys N-1 and N-2.5. Atomic Energy. 68(2). 113–118. 4 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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