Zobrazeno 1 - 7
of 7
pro vyhledávání: '"Veikko, Taivassalo"'
Publikováno v:
Hovi, V, Taivassalo, V, Hämäläinen, A, Räty, H & Syrjälahti, E 2017, ' Start-up of a cold loop in a VVER-440, the 7th AER benchmark calculation with HEXTRAN-SMABRE-PORFLO ', Kerntechnik, vol. 82, no. 4, pp. 426-435 . https://doi.org/10.3139/124.110820
The 7th dynamic AER benchmark is the first in which three-dimensional thermal hydraulics codes are supposed to be applied. The aim is to get a more precise core inlet temperature profile than the sector temperatures available typically with system co
Autor:
Bentaïb, Ahmed, Chaumeix, Nabiha, Grosseuvres, Romain, alexandre, bleyer, Gastaldo, Laura, Ludovic, MAAS, Jallais, Simon, Vyazmina, Elena, Kudriakov, Sergey, Studer, Etienne, Dehbi, Abdelouahab, Berthold, Schramm, Veikko, Taivassalo, m, Frankova, Tadej, Höller, Ivo, Kljenak, Yu, maruyama, Trianti, Nuri, Sato, Masatoshi, Murgatroyd, Julian, Povilaitis, Mantas
Publikováno v:
12th International Topical Meeting on Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-12)
12th International Topical Meeting on Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-12), Oct 2018, Qingdao City, Shandong Province, China
12th International Topical Meeting on Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-12), Oct 2018, Qingdao City, Shandong Province, China
International audience
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::0d7c197e3c82f1ee0d0b271da996629b
https://hal.archives-ouvertes.fr/hal-02413712
https://hal.archives-ouvertes.fr/hal-02413712
Autor:
Eckart Laurien, Weimin Ma, Liangxing Li, Eveliina Takasuo, Veikko Taivassalo, S. Leininger, Rudi Kulenovic, Nourdine Chikhi, Olivia Coindreau
Publikováno v:
Annals of Nuclear Energy
Annals of Nuclear Energy, Elsevier Masson, 2014, 74 (C), pp.24-41. ⟨10.1016/j.anucene.2014.05.009⟩
Chikhi, N, Coindreau, O, Li, L X, Ma, W M, Taivassalo, V, Takasuo, E, Leininger, S, Kulenovic, R & Laurien, E 2014, ' Evaluation of an effective diameter to study quenching and dry-out of complex debris bed ', Annals of Nuclear Energy, vol. 74, pp. 24-41 . https://doi.org/10.1016/j.anucene.2014.05.009
Annals of Nuclear Energy, Elsevier Masson, 2014, 74 (C), pp.24-41. ⟨10.1016/j.anucene.2014.05.009⟩
Chikhi, N, Coindreau, O, Li, L X, Ma, W M, Taivassalo, V, Takasuo, E, Leininger, S, Kulenovic, R & Laurien, E 2014, ' Evaluation of an effective diameter to study quenching and dry-out of complex debris bed ', Annals of Nuclear Energy, vol. 74, pp. 24-41 . https://doi.org/10.1016/j.anucene.2014.05.009
International audience; Many of the current research works performed in the SARNET-2 WP5 deal with the study of the coolability of debris beds in case of severe nuclear power plant accidents. One of the difficulties for modeling and transposition of
Publikováno v:
Taivassalo, V, Kallio, S & Peltola, J 2012, ' On time-averaged CFD modeling of circulating fluidized beds ', International Journal of Nonlinear Sciences and Numerical Simulation, vol. 13, no. 6, pp. 363-373 . https://doi.org/10.1515/ijnsns-2012-0025
CFD simulations of single-phase flows are regularly performed as steady-state utilizing closure models of varying complexity. On the contrary, dense gas-solid flows are usually computed as time dependent. These simulations commonly require a small ti
Publikováno v:
Ilvonen, M, Hovi, V & Taivassalo, V 2014, 3D core thermal hydraulics with the PORFLO code : Turbulence modelling and porous medium with porosity steps . in Proceedings of the 22th International Conference on Nuclear Engineering, ICONE22 : Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory . vol. 4, American Society of Mechanical Engineers (ASME), 22nd International Conference on Nuclear Engineering, ICONE 22, Prague, Czech Republic, 7/07/14 . https://doi.org/10.1115/ICONE22-30731
VTT is developing a 3D two-phase flow solver code called PORFLO with the objective of enabling coupled reactor dynamics simulations through a parallel computation and porous medium description of complex geometries. The current features include unstr
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::8882a91b439d741decf37cf15e508c1e
https://cris.vtt.fi/en/publications/073469b1-c00a-4b53-9f08-35e9bf8a072e
https://cris.vtt.fi/en/publications/073469b1-c00a-4b53-9f08-35e9bf8a072e
Autor:
Anna Nieminen, Tuomo Sevón, Magnus Strandberg, Eveliina Takasuo, Veikko Taivassalo, Mikko Ilvonen, Jukka Rossi
Publikováno v:
VTT Technical Research Centre of Finland-PURE
Nieminen, A, Sevón, T, Strandberg, M, Takasuo, E, Taivassalo, V, Ilvonen, M & Rossi, J 2017, Comprehensive analysis of severe accidents (CASA) . in J Hämäläinen & V Suolanen (eds), SAFIR2018-The Finnish Research Programme on Nuclear Power Plant Safety 2015-2018 : Interim Report . VTT Technical Research Centre of Finland, Espoo, VTT Technology, vol. 294, pp. 66-77 .
Nieminen, A, Sevón, T, Strandberg, M, Takasuo, E, Taivassalo, V, Ilvonen, M & Rossi, J 2017, Comprehensive analysis of severe accidents (CASA) . in J Hämäläinen & V Suolanen (eds), SAFIR2018-The Finnish Research Programme on Nuclear Power Plant Safety 2015-2018 : Interim Report . VTT Technical Research Centre of Finland, Espoo, VTT Technology, vol. 294, pp. 66-77 .
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::591d50072e45902bef8746164bf3e88c
https://cris.vtt.fi/en/publications/1d7485f2-9c2f-426d-afe0-c261791edd26
https://cris.vtt.fi/en/publications/1d7485f2-9c2f-426d-afe0-c261791edd26
Conference
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