Zobrazeno 1 - 10
of 22
pro vyhledávání: '"Patricie Halodová"'
Autor:
Petr Červenka, Jakub Krejčí, Ladislav Cvrček, František Manoch, Adéla Chalupová, Patricie Halodová, Petra Gávelová
Publikováno v:
Acta Polytechnica CTU Proceedings, Vol 37, Pp 16-23 (2022)
The present study focuses on the evaluation of the mechanical properties degradation of Cr-coated Zr-alloy fuel cladding. The main objective of the work is to find a suitable methodology to evaluate the mechanical properties degradation of coated cla
Externí odkaz:
https://doaj.org/article/7c912df292fc487ca5b7d2bb1297796c
Publikováno v:
Acta Polytechnica CTU Proceedings, Vol 27, Iss 0, Pp 155-159 (2020)
Zirconium alloys are being commonly used as a material of choice for nuclear fuel claddings in water cooled nuclear reactors for decades due to their good corrosion resistance and low neutron absorption. However, the increasing operation conditions o
Externí odkaz:
https://doaj.org/article/a1b78dd633e442d3894c4852f1d62784
Autor:
Jakub Krejčí, Jitka Kabátová, František Manoch, Jan Kočí, Ladislav Cvrček, Jaroslav Málek, Stanislav Krum, Pavel Šutta, Petra Bublíková, Patricie Halodová, Hygreeva Kiran Namburi, Martin Ševeček
Publikováno v:
Nuclear Engineering and Technology, Vol 52, Iss 3, Pp 597-609 (2020)
Accident Tolerant Fuels have been widely studied since the Fukushima-Daiichi accident in 2011 as one of the options on how to further enhance the safety of nuclear power plants. Deposition of protective coatings on nuclear fuel claddings has been con
Externí odkaz:
https://doaj.org/article/57322a29ab504f3ba9c30d85fc0a362b
Autor:
Adéla Chalupová, Jakub Krejčí, Ladislav Cvrček, Martin Ševeček, Vojtěch Rozkošný, Antonín Přibyl, Patricie Halodová, Petra Gávelová
Publikováno v:
Acta Polytechnica CTU Proceedings, Vol 24, Iss 0 (2019)
The concept of accident-tolerant fuels has been proposed and widely investigated over the past decade. The contribution is focused on one of the near-term approaches - the modification of the surface of existing Zr-alloy claddings by protective coati
Externí odkaz:
https://doaj.org/article/f9adefe0994f4c7a9cfa57841abf8656
Publikováno v:
Acta Metallurgica Slovaca, Vol 24, Iss 1 (2018)
For the safe development of GenIV nuclear reactors, it is necessary to study the compatibility of structural materials with new coolants. Current work describes the behavior of ferritic-martensitic steel T91 in a Heavy Liquid Metal environment. Speci
Externí odkaz:
https://doaj.org/article/c678479a6b544191add39157ed46479a
Autor:
Kateřina Chrbolková, Patricie Halodová, Tomáš Kohout, Josef Ďurech, Kenichiro Mizohata, Petr Malý, Václav Dědič, Antti Penttilä, František Trojánek, Rajesh Jarugula
One of the main complications for the interpretation of reflectance spectra of airless planetary bodies is surface alteration by space weathering caused by irradiation by solar wind and micrometeoroid particles. We aim to evaluate the damage to the s
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::3518609169659eb8bbce9e73a22a85f4
http://hdl.handle.net/10138/348335
http://hdl.handle.net/10138/348335
Autor:
Vít Rosnecký, Martin Ševeček, Cinthia Antunes Corrêa, Petra Gávelová, Jakub Krejčí, Patricie Halodová, Barbora Křivská
Publikováno v:
Manufacturing Technology. 20:720-727
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::cf6b865f15a5e443a53a3dfcd2b90f87
https://doi.org/10.21062/mft.2020.088
https://doi.org/10.21062/mft.2020.088
Autor:
Věra Vrtílková, Ondřej Libera, Iveta Adéla Prokůpková, Patricie Halodová, Petra Gávelová, Jakub Krejčí
Publikováno v:
Defect and Diffusion Forum. 405:351-356
Zirconium-based alloys are commonly used as a material for nuclear fuel claddings in the light water reactors. The cladding material must function to fix a huge number of pellets, while conducting heat into the coolant that flows turbulently around t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5f97ac3266c25a69ad29485c99246051
https://doi.org/10.4028/www.scientific.net/ddf.405.351
https://doi.org/10.4028/www.scientific.net/ddf.405.351
Publikováno v:
Acta Polytechnica CTU Proceedings, Vol 27, Iss 0, Pp 155-159 (2020)
Zirconium alloys are being commonly used as a material of choice for nuclear fuel claddings in water cooled nuclear reactors for decades due to their good corrosion resistance and low neutron absorption. However, the increasing operation conditions o
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::03a1bd198feaf4d447415a2026b8a703
https://ojs.cvut.cz/ojs/index.php/APP/article/view/6713
https://ojs.cvut.cz/ojs/index.php/APP/article/view/6713
Publikováno v:
Corrosion Reviews. 38:183-194
In order to advance material development for future nuclear systems, an insight into the cracking conditions of T91 ferritic-martensitic steel in heavy liquid metals (HLM) is provided. The paper critically reviews previous experimental data and summa
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ca583692204d75da7fe7414b72038985
https://doi.org/10.1515/corrrev-2019-0035
https://doi.org/10.1515/corrrev-2019-0035