Zobrazeno 1 - 10
of 20
pro vyhledávání: '"Purhonen, Heikki"'
Autor:
Kouhia, Virpi, Riikonen, Vesa, Kauppinen, Otso-Pekka, Purhonen, Heikki, Austregesilo, Henrique, Bánáti, József, Cherubini, Marco, D’Auria, Francesco, Inkinen, Pasi, Karppinen, Ismo, Kral, Pavel, Peltokorpi, Lauri, Peltonen, Joanna, Weber, Sebastian
Publikováno v:
In Annals of Nuclear Energy September 2013 59:149-156
Autor:
Kouhia, Virpi1, Purhonen, Heikki1 heikki.purhonen@lut.fi, Riikonen, Vesa1, Puustinen, Markku1, Kyrki-Rajamäki, Riitta1, Vihavainen, Juhani1
Publikováno v:
Science & Technology of Nuclear Installations. 2012, p1-8. 8p.
Publikováno v:
Science & Technology of Nuclear Installations. 2010, Vol. 2010, Special section p1-8. 8p. 1 Color Photograph, 2 Diagrams, 1 Chart, 11 Graphs.
Publikováno v:
Pättikangas, T, Niemi, J, Laine, J, Puustinen, M & Purhonen, H 2010, ' CFD modelling of condensation of vapour in the pressurized PPOOLEX facility ', Paper presented at CFD for Nuclear Reactor Safety Applications Workshop, CFD4NRS-3, Bethesda, United States, 14/09/10-16/09/10 . < https://www.oecd-nea.org/nsd/csni/cfd/workshops/CFD4NRS-3/technical-papers/2/2.3%20_Containment_1.pdf >
The behaviour of a pressure suppression containment is studied experimentally and by performing CFD calculations. The experiments have been performed with the PPOOLEX test facility, which is a scaled-down two-compartment model of a pressure suppressi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::586938f93123f286c153f5ef123563e6
https://cris.vtt.fi/en/publications/8772b9c5-1b9e-4b64-8869-e090c48e5fd6
https://cris.vtt.fi/en/publications/8772b9c5-1b9e-4b64-8869-e090c48e5fd6
Autor:
Puustinen, Markku, Räsänen, Antti, Laine, Jani, Purhonen, Heikki, Pättikangas, Timo, Timperi, Antti
Publikováno v:
Puustinen, M, Räsänen, A, Laine, J, Purhonen, H, Pättikangas, T & Timperi, A 2009, Condensation pool experiments at LUT supporting CFD and structural analysis tool development . in S Vuori & R Rintamaa (eds), 20th International Conference on Structural Mechanics in Reactor Technology, SMiRT 20 : Book of abstracts . vol. 1, VTT Technical Research Centre of Finland, Espoo, VTT Symposium, no. 256, pp. 107-109, 20th International Conference on Structural Mechanics in Reactor Technology, SMiRT 20, Espoo, Finland, 9/08/09 . < https://publications.vtt.fi/pdf/symposiums/2009/S256.pdf >
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::5d70e36f859b0ddd98e2a3514960d8ce
https://cris.vtt.fi/en/publications/5887f00d-000c-4e66-a2c8-56a68a4e9fa9
https://cris.vtt.fi/en/publications/5887f00d-000c-4e66-a2c8-56a68a4e9fa9
Publikováno v:
Pättikangas, T, Puustinen, M, Purhonen, H, Calonius, K & Saarenheimo, A 2000, STIN special report 1 : Loading to structures due to thermal stratification in a T-joint of hot and cold pipes . in FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety : Interim Report 1999-August 2000 . VTT Technical Research Centre of Finland, Espoo, VTT Tiedotteita-Research Notes, no. 2057, pp. 113-122 . < https://publications.vtt.fi/pdf/tiedotteet/2000/T2057.pdf >
Thermal stratification of hot and cold water may cause damages in pipes of power plants. The main aims of this study are to improve the knowledge of the effects of thermal loads on the structures and to develop and verify a computational tool for num
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::b1c6d4d96fe7e64de79109cb727780e9
https://cris.vtt.fi/en/publications/05dce9f4-bcb6-4211-b572-9c687b3f4a28
https://cris.vtt.fi/en/publications/05dce9f4-bcb6-4211-b572-9c687b3f4a28
Autor:
Tuunanen, Jari, Kouhia, Jyrki, Purhonen, Heikki, Riikonen, Vesa, Puustinen, Markku, Semken, Scott, Partanen, Harri, Saure, Ilkka, Pylkkö, Hannu
Publikováno v:
Tuunanen, J, Kouhia, J, Purhonen, H, Riikonen, V, Puustinen, M, Semken, S, Partanen, H, Saure, I & Pylkkö, H 1998, General description of the PACTEL test facility . VTT Tiedotteita-Meddelanden-Research Notes, no. 1929, VTT Technical Research Centre of Finland, Espoo . < https://publications.vtt.fi/pdf/tiedotteet/1998/T1929.pdf >
The PACTEL is a test facility designed to model the thermal-hydraulic behaviours of the Soviet-designed VVER-440 pressurized water reactors currently in use in Finland. These reactors have unique features that differ from other PWR designs. The PACTE
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::787f03581f1fda56fdaefd7fccf79b63
https://cris.vtt.fi/en/publications/cc2e7e2e-d789-4427-b0fa-51d0fb891071
https://cris.vtt.fi/en/publications/cc2e7e2e-d789-4427-b0fa-51d0fb891071
Publikováno v:
Purhonen, H, Lundström, P & Kymäläinen, O 1995, ' Experimental support for Loviisa VVER-440 accident management development ', Nuclear Europe Worldscan, vol. 25, no. 9-10, pp. 52-53 .
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::95003cfdaf034965e7b1740f05d7740c
https://cris.vtt.fi/en/publications/a2438001-15fb-4ed7-8851-15591e9afec4
https://cris.vtt.fi/en/publications/a2438001-15fb-4ed7-8851-15591e9afec4
Publikováno v:
Ritonummi, T, Kalli, H, Purhonen, H & Kouhia, J 1995, ' Ydinvoimalaitosten turvallisuustutkimus etenee ', Fysiikka tänään, no. 1, pp. 8-10 .
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::3d2beed3ae34ea34f5fab2fdd5a3c64e
https://cris.vtt.fi/en/publications/dc561a8e-d026-42b5-97d6-a1bc0f046ffa
https://cris.vtt.fi/en/publications/dc561a8e-d026-42b5-97d6-a1bc0f046ffa
Akademický článek
Tento výsledek nelze pro nepřihlášené uživatele zobrazit.
K zobrazení výsledku je třeba se přihlásit.
K zobrazení výsledku je třeba se přihlásit.