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Petra Gávelová
Observed names:
Gávelová P.,
Gávelová, Petra,
P Gavelova
Institution:
Research Centre Rez
Observed institution:
Research Centre Rez
ORCID:
0000-0002-3789-3805
Observed ORCID:
0000-0002-3789-3805
OpenAlex ID:
A5005770061
Coated Cladding Behavior During High-temperature Transients
2019
·
Adéla Chalupová
, Jakub Krejčí
, et al.
·
Acta Polytechnica CTU Proceedings
·
20
PDF
Study hydrogen embrittlement and determination of E110 fuel cladding mechanical properties by ring compression testing
2018
·
H K Namburi
, L Ottazzi
, et al.
·
IOP Conference Series Materials Science and Engineering
·
10
PDF
The Influence of High-Temperature Helium and the Amount of Revert Material on the Material Properties of Inconel 738
2022
·
Daniela Marušáková
, Cinthia Corrêa
, et al.
·
Coatings
·
6
PDF
Degradation of Cr-coated cladding under the simulated Loss-of-Coolant Accident phenomena
2022
·
Petr Červenka
, Jakub Krejčí
, et al.
·
Acta Polytechnica CTU Proceedings
·
5
PDF
Microstructure of zirconium fuel claddings: TEM and EBSD studies of as-received and ne-utron-irradiated materials
2020
·
Petra Gávelová
, Patricie Halodová
, et al.
·
MANUFACTURING TECHNOLOGY
·
4
PDF
Experimental Verification of Phase Diagram Calculations of Zr-Based Alloys after High-Temperature Oxidation
2020
·
Petra Gávelová
, Patricie Halodová
, et al.
·
Defect and diffusion forum/Diffusion and defect data, solid state data. Part A, Defect and diffusion forum
·
2
From Micro to Nano: Material Characterization Methods for Testing of Nuclear Core and Structural Materials
2019
·
Petra Gávelová
, Patricie Halodová
, et al.
·
Journal of Nuclear Engineering and Radiation Science
·
2
Development and Testing of an Irradiation Rig for Accident-Tolerant Fuel Cladding Materials: Lessons Learned From Irradiation of SiC/SiC Tubes and Small-Scale FeCrAl Specimens
2026
·
Petra Gávelová
, Martina Malá
, et al.
·
Journal of Nuclear Engineering and Radiation Science
·
1
Preparation of Thin and Powdered Radioactive Samples for Electron Microscopy and X-Ray Diffraction Analysis of Radiation-Induced Damage
2025
·
Vít Rosnecký
, Claudia Aparicio
, et al.
·
Key engineering materials
·
1
ATF Claddings after High-Temperature Steam Oxidation: WDS and Nanoindentation Studies to Characterize in-depth Material Changes
2022
·
Jitka Klaisnerová
, Leoš Křivský
, et al.
·
MANUFACTURING TECHNOLOGY
·
1
PDF
NANOINDENTATION OF HYDROGEN ENRICHED Zr-1Nb ZIRCONIUM ALLOY NUCLEAR FUEL CLADDINGS
2020
·
Ondřej Libera
, Patricie Halodová
, et al.
·
Acta Polytechnica CTU Proceedings
·
1
PDF
Corrosion Resistance and High-Temperature Behavior of Chrome-Nickel Alloy Cladding Material
2022
·
Jakub Krejci
, Adéla Chalupová
, et al.
·
TopFuel Light Water Reactor Fuel Performance Conference (TopFuel)
Corrosion Resistance and High-temperature Behaviour of Zr-based Cladding Materials With Chromium-based Pvd Coatings
2021
·
Chalupová A.
, Krejčí J.
, et al.
·
Czech Technical University Digital Library (Czech Technical University in Prague)
Microstructure and Nanoindentation Studies of Hydridated Zircaloy-4 Claddings After High Temperature Oxidation
2020
·
Petra Gávelová
, Patricie Halodová
, et al.
·
Journal of Nuclear Engineering and Radiation Science
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Works count:
15
Citation count:
53
H-index:
4
I10-index:
2
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