Zobrazeno 1 - 10
of 28
pro vyhledávání: '"Katrien van Tichelen"'
Autor:
Ben De Pauw, Graham Kennedy, Katrien Van Tichelen, Thomas Geernaert, Hugo Thienpont, Francis Berghmans
Publikováno v:
Applied Sciences, Vol 7, Iss 8, p 864 (2017)
Excessive vibration of nuclear reactor components, such as the heat exchanger or the fuel assembly should be avoided as these can compromise the lifetime of these components and potentially lead to safety hazards. This issue is particularly relevant
Externí odkaz:
https://doaj.org/article/7dc294404e8b41cfbe62c5b356179e29
Autor:
Ben De Pauw, Alfredo Lamberti, Julien Ertveldt, Ali Rezayat, Katrien van Tichelen, Steve Vanlanduit, Francis Berghmans
Publikováno v:
Sensors, Vol 16, Iss 4, p 571 (2016)
Excessive fuel assembly vibrations in nuclear reactor cores should be avoided in order not to compromise the lifetime of the assembly and in order to prevent the occurrence of safety hazards. This issue is particularly relevant to new reactor designs
Externí odkaz:
https://doaj.org/article/4457596d2ff7494e960b05ecea6b44ce
Publikováno v:
Frontiers in Energy. 15:842-853
A significant role for a future nuclear carbon-free energy production is attributed to fast reactors, mostly employing a liquid metal as a coolant. This paper summarizes the efforts that have been undertaken in collaborative projects sponsored by the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::429c5e7773f63ee004dd3523a702b376
https://doi.org/10.1007/s11708-021-0743-2
https://doi.org/10.1007/s11708-021-0743-2
Autor:
Julio Pacio, Katrien Van Tichelen, Sven Eckert, Thomas Wondrak, Ivan Di Piazza, Pierdomenico Lorusso, Mariano Tarantino, Markus Daubner, Karsten Litfin, Gen Ariyoshi, Hironari Obayashi, Toshinobu Sasa
Publikováno v:
Nuclear Engineering and Design 399(2022), 112010
Heavy-liquid metals (HLMs), such as lead and lead–bismuth eutectic (LBE), are proposed as primary coolants in accelerator driven systems and next-generation fast reactors. In Europe, the reference systems using HLMs are MYRRHA (LBE) and ALFRED (lea
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::329e3a7ed725649dce10c6ef63d5389d
https://www.hzdr.de/publications/Publ-35532-1
https://www.hzdr.de/publications/Publ-35532-1
Autor:
Katrien Van Tichelen, Sophia Buckingham, Giacomo Alessi, Philippe Planquart, Chiara Spaccapaniccia
Publikováno v:
Nuclear Technology. 206:231-241
The thermal-hydraulic challenges of a nuclear reactor are numerous and mastering them is crucial for the design and safety of new reactors. Numerical simulation through computational fluid dynamics...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::44329dda0d2d42a056b4f979d46921f8
https://doi.org/10.1080/00295450.2019.1637240
https://doi.org/10.1080/00295450.2019.1637240
Autor:
Henri Dolfen, Jeroen De Ridder, Landon Brockmeyer, Elia Merzari, Graham Kennedy, Katrien Van Tichelen, Joris Degroote
Publikováno v:
JOURNAL OF FLUIDS AND STRUCTURES
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::9d6694ec74fea35c79940bafe7620496
https://doi.org/10.1016/j.jfluidstructs.2021.103460
https://doi.org/10.1016/j.jfluidstructs.2021.103460
Publikováno v:
Nuclear Engineering and Design. 312:137-146
This work on fuel dispersion aims at quantifying the design and safety of the MYRRHA nuclear reactor. A number of accidents leading to the release of a secondary phase into the primary coolant loop are investigated. Among these scenarios, an incident
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2432cf820386b1f029574dbea7cb6849
https://doi.org/10.1016/j.nucengdes.2016.06.019
https://doi.org/10.1016/j.nucengdes.2016.06.019
Publikováno v:
Nuclear Engineering and Design. 358:110436
The European Scaled Pool Experiment (E-SCAPE) is a 1/6th-scale thermal hydraulic model of the MYRRHA reactor and has been developed within the European framework programs THINS and MYRTE. MYRRHA is a multi-purpose hybrid pool-type research reactor co
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::428aaec0740551f8c6776f61876b082f
https://doi.org/10.1016/j.nucengdes.2019.110436
https://doi.org/10.1016/j.nucengdes.2019.110436
Publikováno v:
Nuclear Engineering and Design. 290:65-77
MYRRHA (Multi-purpose hYbrid Research Reactor for High-tech Applications) is a flexible fast-spectrum research reactor under design at SCK·CEN. MYRRHA is a pool-type reactor with lead bismuth eutectic (LBE) as primary coolant. The proper understandi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::660144962dc36799b74a7ca003dc7d07
https://doi.org/10.1016/j.nucengdes.2014.11.011
https://doi.org/10.1016/j.nucengdes.2014.11.011
Autor:
Julien Ertveldt, Francis Berghmans, Ali Rezayat, Ben De Pauw, Thomas Geernaert, Alfredo Lamberti, Katrien Van Tichelen, Steve Vanlanduit
Publikováno v:
Journal of Lightwave Technology. 33:2378-2385
Vibration measurements of the fuel assembly of a nuclear reactor are a very useful tool to determine the health and lifetime of the reactor core. The importance of these measurements is exacerbated in the new generation of heavy liquid metal reactors
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::318c9b6f4b24aa83b56f437c4b9aa237
https://doi.org/10.1109/jlt.2014.2377371
https://doi.org/10.1109/jlt.2014.2377371