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Martin Ševeček

Czech Technical University in Prague

SCHOLARLY PAPERS

7

DOWNLOADS

442

TOTAL CITATIONS

3

Scholarly Papers (7)

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1.

Neutronic Performance of Vver-1200 Reactor with Advanced Fuel and Cladding Materials

Number of pages: 14 Posted: 13 Oct 2022
Pavel Suk, Martin Ševeček, Dušan Kobylka and Filip Fejt
affiliation not provided to SSRN, Czech Technical University in Prague, affiliation not provided to SSRN and affiliation not provided to SSRN
Downloads 143 (514,995)

Abstract:

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Alternative cladding, Alternative fuel, VVER-1200, Advanced Technology Fuel (ATF), Neutronics, Enrichment

2.

International Fuel Performance Study of Fresh Fuel Experiments for Pcmi Effects During Ria Experiments

Number of pages: 44 Posted: 02 Jul 2024
Seokbin Seo, Charles Folsom, Colby Jensen, David Kamerman, Luana Giaccardi, Marco Cherubini, Pavel Suk, Martin Ševeček, Jérôme Sercombe, Isabelle Guenot-Delahaie, Alessandro Scolaro, Matthieu Reymond, Katalin Kulacsy, Luis E. Herranz, Francisco Feria, Pau Aragón, Grigori Khvostov, Imran Khan, Anuj Kumar Deo, Ravva Srinivasa Rao, Rolando Calabrese, Felix Boldt, Jonathan Sappl, Florian Falk, Asko Arkoma, Georgenthum Vincent, Yudai Tasaki, Kazuo Kakiuchi, Yutaka Udagawa, Gregory Delipei, Charles Cheron, James Corson, Jinzhao Zhang, Thomas Drieu, Jan Klouzal, Martin Dostal, Vitezslav Matocha, Tereza Kinkorová and Carlo Fiorina
Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, Czech Technical University in Prague, affiliation not provided to SSRN, affiliation not provided to SSRN, École Polytechnique Fédérale de Lausanne (EPFL), École Polytechnique Fédérale de Lausanne (EPFL), affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, VTT Technical Research Centre of Finland, affiliation not provided to SSRN, Japan Atomic Energy Agency, Japan Atomic Energy Agency, Japan Atomic Energy Agency, North Carolina State University, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, Czech Technical University in Prague and Texas A&M University
Downloads 104 (669,616)

Abstract:

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HERA, Modeling and simulation, LWR fuel, Fuel behavior, RIA, Irradiation testing

3.

Experimental Investigation of CrNb Coatings for BWRs and PWRs

Number of pages: 9 Posted: 19 Nov 2025
Petr Cervenka, Andrea Fazi, Arunkumar Seshadri, Martin Ševeček and Koroush Shirvan
Massachusetts Institute of Technology (MIT), Massachusetts Institute of Technology (MIT), Massachusetts Institute of Technology (MIT), Czech Technical University in Prague and Massachusetts Institute of Technology (MIT)
Downloads 58 (1,010,164)
Citation 1

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ATF, Corrosion, BWR, Reactor Irradiation

4.

Understanding the High-Temperature Behavior and Corrosion Resistance of Cr-Nb Coated Cladding for BWRs

Number of pages: 40 Posted: 23 Jan 2026 Last Revised: 10 Jun 2026
Petr Cervenka, Andrea Fazi, Martin Ševeček, Arunkumar Seshadri, Alžběta Endrychová, Ladislav Cvrček and Koroush Shirvan
Massachusetts Institute of Technology (MIT), Massachusetts Institute of Technology (MIT), Czech Technical University in Prague, Massachusetts Institute of Technology (MIT), Czech Technical University in Prague, affiliation not provided to SSRN and Massachusetts Institute of Technology (MIT)
Downloads 40 (1,263,436)

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nuclear fuel, Cladding, coating, ATF, BWR, corrosion

5.

High-Temperature Creep Behavior of Cr-Coated Optimized Zirlo™ Cladding Via Inverse Analysis 1 Based on Finite Element Method

Number of pages: 25 Posted: 30 May 2025
Sung-Uk Lee, Hyo Chan Kim, Martin Ševeček and Márton Király
Korea Atomic Energy Research Institute, Korea Atomic Energy Research Institute, Czech Technical University in Prague and HUN-REN Centre for Energy Research
Downloads 35 (1,249,711)

Abstract:

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Accident Tolerant Fuel, Cr-Coated Cladding, High-Temperature Creep, Inverse Analysis, MERCURY, ISIGHT

6.

Side-by-Side High-Temperature Accident Performance of ATF and Conventional Claddings in the CODEX-ATF Experiment

Number of pages: 19 Posted: 28 Nov 2025
Nóra Vér, Róbert Farkas, Berta Bürger, Anna Pintér-Csordás, Tamás Novotny, Erzsébet Perez-Feró, Péter Szabó, Levente Illés, Zoltán Kovács, Dávid Cinger, Martin Ševeček and Zoltán Hózer
affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, HUN-REN Centre for Energy Research, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, Czech Technical University in Prague and HUN-REN Centre for Energy Research
Downloads 32 (1,304,549)

Abstract:

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accident tolerant fuelhigh temperature reactor accidentsCr-coated Zr alloy claddingsoxidationballooning and burst Cr-Zr eutectic

7.

Parabolic Oxidation Behavior of Various Chromium-Coated Zr-Nb Alloy Claddings

Number of pages: 61 Posted: 25 Feb 2025
Hyeongtak Kang, Dongju Kim, Martin Ševeček and Youho Lee
Seoul National University, Seoul National University, Czech Technical University in Prague and Seoul National University
Downloads 30 (1,345,526)
Citation 2

Abstract:

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Cr-coated Zr-Nb alloy, Oxide growth model, EBSD, TGA, High-temperature oxidation