Zobrazeno 1 - 10
of 39
pro vyhledávání: '"LINDHOLM, Ilona"'
Autor:
Meignen, Renaud, Raverdy, Bruno, Buck, Michael, Pohlner, Georg, Kudinov, Pavel, Ma, Weimin, Brayer, Claude, Piluso, Pascal, Hong, Seong-Wan, Leskovar, Matjaž, Uršič, Mitja, Albrecht, Giancarlo, Lindholm, Ilona, Ivanov, Ivan
Publikováno v:
In Annals of Nuclear Energy December 2014 74:125-133
Autor:
Takasuo, Eveliina, Holmström, Stefan, Kinnunen, Tuomo, Pankakoski, Pekka H., Hosio, Ensio, Lindholm, Ilona
Publikováno v:
In Nuclear Engineering and Design 2011 241(4):1196-1205
Autor:
Sevón, Tuomo, Kinnunen, Tuomo, Virta, Jouko, Holmström, Stefan, Kekki, Tommi, Lindholm, Ilona
Publikováno v:
In Nuclear Engineering and Design 2010 240(10):3586-3593
Autor:
CENERINO, Gerard, PIGNET, Sophie, VAN ROMPUY, Thibaut, MAZZINI, Guido, MASCARI, Fulvio, SONNENKALB, Martin, CONSTANTIN, Marin, KLJENAK, Ivo, URBONAVICIUS, Egidijus, LIND, Terttaliisa, JANCOVIC, Juraj, LINDHOLM, Ilona
Publikováno v:
International Seminar “In-vessel retention: outcomes of IVMR project”, IVMR
International Seminar “In-vessel retention: outcomes of IVMR project”, IVMR, 2020, JUAN LES PINS, France
International Seminar “In-vessel retention: outcomes of IVMR project”, IVMR, 2020, JUAN LES PINS, France
International audience; In-Vessel melt Retention (IVR) is a Severe Accident (SA) mitigation measure applied in some Pressurized Water Reactors (PWRs) in order to cool down molten fuel (corium) inside the Reactor Pressure Vessel (RPV) by flooding the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::b044337a8d318b9319e5ecafa7f1a57d
https://hal.archives-ouvertes.fr/hal-03150524/file/0000163853_003.PDF
https://hal.archives-ouvertes.fr/hal-03150524/file/0000163853_003.PDF
Autor:
Sevon, Tuomo, Lindholm, Ilona
Publikováno v:
Sevon, T & Lindholm, I 2011, Core Melt Stabilization (COMESTA) : COMESTA summary report . in SAFIR2010 : The Finnish Research Programme on Safety 2007-2010: Final Report . VTT Technical Research Centre of Finland, Espoo, VTT Tiedotteita-Research Notes, no. 2571, pp. 321-328 . < https://publications.vtt.fi/pdf/tiedotteet/2011/T2571.pdf >
Sevon, T & Lindholm, I 2009, Core melt stabilization (COMESTA) : COMESTA summary report . in SAFIR2010: The Finnish Research Programme on Nuclear Power Plant Safety 2007-2010 : Interim Report . VTT Technical Research Centre of Finland, Espoo, VTT Tiedotteita-Research Notes, no. 2466, pp. 287-294 . < https://publications.vtt.fi/pdf/tiedotteet/2009/T2466.pdf >
Sevon, T & Lindholm, I 2009, Core melt stabilization (COMESTA) : COMESTA summary report . in SAFIR2010: The Finnish Research Programme on Nuclear Power Plant Safety 2007-2010 : Interim Report . VTT Technical Research Centre of Finland, Espoo, VTT Tiedotteita-Research Notes, no. 2466, pp. 287-294 . < https://publications.vtt.fi/pdf/tiedotteet/2009/T2466.pdf >
COMESTA project has investigated core melt behavior in a severe accident. Experiments have been conducted both at VTT and in international projects on the subjects of molten core - concrete interactions, melt pool coolability and steam explosions. Co
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::5c15e6a1dc69cd8cce0d6c96a632ee82
https://cris.vtt.fi/en/publications/2c29af11-0891-4990-ab31-308e09644385
https://cris.vtt.fi/en/publications/2c29af11-0891-4990-ab31-308e09644385
Publikováno v:
Takasuo, E, Holmström, S, Kyttälä, J & Lindholm, I 2009, Hydrogen risk in containments and particle bed issues (HYRICI) : HYRICI summary report . in SAFIR2010: The Finnish Research Programme on Nuclear Power Plant Safety 2007-2010 : Interim Report . VTT Technical Research Centre of Finland, Espoo, VTT Tiedotteita-Research Notes, no. 2466, pp. 304-314 . < https://publications.vtt.fi/pdf/tiedotteet/2009/T2466.pdf >
The HYRICI project conducted during 2007 and 2008 was divided in two different research topics in the field of severe accident investigations: hydrogen distribution and the pressure and thermal loads caused by hydrogen combustion in the containment,
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::80d349cf01c2400c2b06af904f2b7ea9
https://cris.vtt.fi/en/publications/6d975311-ef59-4994-a4d0-cec966b1de83
https://cris.vtt.fi/en/publications/6d975311-ef59-4994-a4d0-cec966b1de83
Publikováno v:
Zilliacus, R, Kekki, T, Lindholm, I & Suopajärvi, A 2009, Release of radioactive materials from a degrading core (RADECO) : RADECO summary report . in SAFIR2010: The Finnish Research Programme on Nuclear Power Plant Safety 2007-2010 : Interim Report . VTT Technical Research Centre of Finland, Espoo, VTT Tiedotteita-Research Notes, no. 2466, pp. 261-275 . < https://publications.vtt.fi/pdf/tiedotteet/2009/T2466.pdf >
The formation of organic iodine on painted surface in water and in N2 was studied with and without radiation. The water pH in the experiment was 9.3 or 7. In neutral solution small amount of volatile organic iodide was detected. In high pH all volati
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::ec88c35f444ebfacc8e5ff3410c01460
https://cris.vtt.fi/en/publications/cf893a91-8d2c-4e0f-8985-5fc603706d77
https://cris.vtt.fi/en/publications/cf893a91-8d2c-4e0f-8985-5fc603706d77
Publikováno v:
Lindholm, I, Athken, K, Büregr, M, Fichot, F & Park, S H 2005, In-Vessel Retention : On Going Activity on In-vessel Core and Debris Coolability . in Proceedings of the European Review Meeting on Severe Accident Research-ERMSAR 2005 . IRSN, 1st European Review Meeting on Severe Accident Research, ERMSAR 2005, Aix en Provence, France, 14/11/05 . < https://inis.iaea.org/search/search.aspx?orig_q=RN:43095181 >
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::48d61599651b824bba672264faee8f77
https://cris.vtt.fi/en/publications/2b5936dd-9559-4c73-ac45-03daf1166619
https://cris.vtt.fi/en/publications/2b5936dd-9559-4c73-ac45-03daf1166619
Autor:
Lindholm, Ilona
Publikováno v:
Lindholm, I 2004, SANCY summary report . in SAFIR, The Finnish Research Programme on Nuclear Power Plant Safety 2003-2006 : Interim Report . VTT Technical Research Centre of Finland, Espoo, VTT Tiedotteita-Research Notes, no. 2272, pp. 153-159 . < https://publications.vtt.fi/pdf/tiedotteet/2004/T2272.pdf >
SANCY project investigates physical phenomena related to severe nuclear accidents with importance to Finnish nuclear power plants. Currently the major topics are the ex-vessel coolability issues, long-term severe accident management and containment l
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::68f50e57fc4861f84e59ed02a7d105d1
https://cris.vtt.fi/en/publications/bfeb4677-7b9d-4737-8d1f-02e85f2b13dd
https://cris.vtt.fi/en/publications/bfeb4677-7b9d-4737-8d1f-02e85f2b13dd
Autor:
Lindholm, Ilona
Publikováno v:
Lindholm, I 2002, Modelling and simulant experiments of severe accident phenomena (MOSES) : MOSES summary report . in FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002 : Final Report . VTT Technical Research Centre of Finland, Espoo, VTT Tiedotteita-Research Notes, no. 2164, pp. 165-178 . < https://publications.vtt.fi/pdf/tiedotteet/2002/T2164.pdf >
MOSES project has systematically investigated phases of severe reactor accidents relevant to Finnish nuclear power plants. The specific areas of research have been pressure vessel failure mode, core debris coolability, fission product behavior, inclu
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::aa7e1b8b6e7c2f508133a71e261eced1
https://cris.vtt.fi/en/publications/b78d38de-6100-4553-ae79-942c85ed2ee5
https://cris.vtt.fi/en/publications/b78d38de-6100-4553-ae79-942c85ed2ee5