Zobrazeno 1 - 10
of 11
pro vyhledávání: '"Ilona Lindholm"'
Autor:
Pavel Kudinov, Matjaž Leskovar, Giancarlo Albrecht, Bruno Raverdy, Renaud Meignen, Michael Buck, Georg Pohlner, Claude Brayer, Mitja Uršič, Weimin Ma, Ilona Lindholm, Pascal Piluso, Seong-Wan Hong, Ivan B. Ivanov
Publikováno v:
Annals of Nuclear Energy
Annals of Nuclear Energy, Elsevier Masson, 2014, 74 (C), pp.125-133. ⟨10.1016/j.anucene.2014.07.008⟩
Annals of Nuclear Energy, 2014, 74 (C), pp.125-133. ⟨10.1016/j.anucene.2014.07.008⟩
Meignen, R, Raverdy, B, Buck, M, Pohlner, G, Kudinov, P, Ma, W, Brayer, C, Piluso, P, Hong, S-W, Leskovar, M, Uršič, M, Albrecht, G, Lindholm, I & Ivanov, I 2014, ' Status of steam explosion understanding and modelling ', Annals of Nuclear Energy, vol. 74, pp. 125-133 . https://doi.org/10.1016/j.anucene.2014.07.008
Annals of Nuclear Energy, Elsevier Masson, 2014, 74 (C), pp.125-133. ⟨10.1016/j.anucene.2014.07.008⟩
Annals of Nuclear Energy, 2014, 74 (C), pp.125-133. ⟨10.1016/j.anucene.2014.07.008⟩
Meignen, R, Raverdy, B, Buck, M, Pohlner, G, Kudinov, P, Ma, W, Brayer, C, Piluso, P, Hong, S-W, Leskovar, M, Uršič, M, Albrecht, G, Lindholm, I & Ivanov, I 2014, ' Status of steam explosion understanding and modelling ', Annals of Nuclear Energy, vol. 74, pp. 125-133 . https://doi.org/10.1016/j.anucene.2014.07.008
International audience; The main results of the major international activities related to fuel-coolant interactions (FCI) of the last 4-year period are presented and a summary of the knowledge gained regarding understanding and the improvements of mo
Autor:
Jaakko Miettinen, Heikki Sjövall, Stefan Holmström, Ilona Lindholm, Juhani Hyvärinen, Ville Lestinen, Pekka H. Pankakoski
Publikováno v:
Lindholm, I, Holmström, S, Miettinen, J, Lestinen, V, Hyvärinen, J, Pankakoski, P & Sjövall, H 2006, ' Dryout heat flux experiments with deep heterogeneous particle bed ', Nuclear Engineering and Design, vol. 236, no. 19-21, pp. 2060-2074 . https://doi.org/10.1016/j.nucengdes.2006.03.036
A test facility has been constructed at Technical Research Centre of Finland (VTT) to simulate as accurately as possible the ex-vessel core particle bed in the conditions of Olkiluoto nuclear power plant. The STYX particle bed reproduces the anticipa
Autor:
Ilona Lindholm, L. E. Herranz Puebla, B. Clément, Didier Jacquemain, Marco K. Koch, G. Ducros, Ivo Kljenak, A. Miassoedov, G. Pascal, Sevostian Bechta, W. Klein-Heßling, E. Raimond, G. Azarian, Ivan B. Ivanov, H. Dimmelmeier, Christophe Journeau, Ari Auvinen, Andreas Schumm, M. Sonnenkalb, S. Güntay
Publikováno v:
Annals of Nuclear Energy
Annals of Nuclear Energy, Elsevier Masson, 2014, 74 (C), pp.4-11. ⟨10.1016/j.anucene.2014.07.015⟩
Klein-Heßling, W, Sonnenkalb, M, Jacquemain, D, Clement, B, Raimond, E, Dimmelmeier, H, Auvinen, A, Lindholm, I & al, E 2014, ' Conclusions on severe accident research priorities ', Annals of Nuclear Energy, vol. 74, pp. 4-11 . https://doi.org/10.1016/j.anucene.2014.07.015
Annals of Nuclear Energy, Elsevier Masson, 2014, 74 (C), pp.4-11. ⟨10.1016/j.anucene.2014.07.015⟩
Klein-Heßling, W, Sonnenkalb, M, Jacquemain, D, Clement, B, Raimond, E, Dimmelmeier, H, Auvinen, A, Lindholm, I & al, E 2014, ' Conclusions on severe accident research priorities ', Annals of Nuclear Energy, vol. 74, pp. 4-11 . https://doi.org/10.1016/j.anucene.2014.07.015
International audience; The objectives of the SARNET network of excellence are to define and work on common research programs in the field of severe accidents in Gen. II-III nuclear power plants and to further develop common tools and methodologies f
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::f0556e31b7c82f6e716155b351ef5e31
https://hal.archives-ouvertes.fr/hal-02641708
https://hal.archives-ouvertes.fr/hal-02641708
Autor:
A. Kaliatka, J. Duspiva, M. Steinbrueck, J. Fleurot, N. Kononen, T. Hollands, Ilona Lindholm, S. Ederli, B. Jaeckel
Publikováno v:
Annals of Nuclear Energy
Annals of Nuclear Energy, Elsevier Masson, 2014, 74 (C), pp.58-71. ⟨10.1016/j.anucene.2014.07.011⟩
Fleurot, J, Lindholm, I, Könönen, N, Ederli, S, Jaeckel, B, Kaliatka, A, Duspiva, J, Steinbrück, M & Hollands, T 2014, ' Synthesis of spent fuel pool accident assessments using severe accident codes ', Annals of Nuclear Energy, vol. 74, pp. 58-71 . https://doi.org/10.1016/j.anucene.2014.07.011
Annals of Nuclear Energy, Elsevier Masson, 2014, 74 (C), pp.58-71. ⟨10.1016/j.anucene.2014.07.011⟩
Fleurot, J, Lindholm, I, Könönen, N, Ederli, S, Jaeckel, B, Kaliatka, A, Duspiva, J, Steinbrück, M & Hollands, T 2014, ' Synthesis of spent fuel pool accident assessments using severe accident codes ', Annals of Nuclear Energy, vol. 74, pp. 58-71 . https://doi.org/10.1016/j.anucene.2014.07.011
International audience; The accident at the Fukushima Dai-ichi Nuclear Power Plant has highlighted the vulnerability of nuclear fuels that are stored in spent fuel pools (SFP) before their evacuation and final disposal or possible reprocessing. This
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::c4b4bbbe7f5f6106c1a19a05c7d070c5
https://hal.archives-ouvertes.fr/hal-02641699
https://hal.archives-ouvertes.fr/hal-02641699
Autor:
J. Miettinen, S. Rahman, Ilona Lindholm, Michael Buck, Weimin Ma, Rudi Kulenovic, K. Atkhen, Georg Pohlner, Florian Fichot, M. Bürger
Publikováno v:
Bürger, M, Buck, M, Rahman, S, Kulenovic, R, Fichot, F, Ma, W M, Miettinen, J, Lindholm, I & Atkhen, K 2010, ' Coolability of particulate beds in severe accidents : Status and remaining uncertainties ', Progress in Nuclear Energy, vol. 52, no. 1, pp. 61-75 . https://doi.org/10.1016/j.pnucene.2009.09.015
Progress in Nuclear Energy
Progress in Nuclear Energy, 2010, 52 (1), pp.61-75. ⟨10.1016/j.pnucene.2009.09.015⟩
Progress in Nuclear Energy
Progress in Nuclear Energy, 2010, 52 (1), pp.61-75. ⟨10.1016/j.pnucene.2009.09.015⟩
Particulate debris beds may form during different stages of a severe core melt accident; e.g. in the degrading hot core, due to thermal stresses during reflooding, in the lower plenum, by melt flow from the core into water in the lower head, and in t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::acb1d18ef5678dcd5eee8980fbade68d
https://cris.vtt.fi/en/publications/a3a954ac-a3e9-4aee-9b1d-16050438b881
https://cris.vtt.fi/en/publications/a3a954ac-a3e9-4aee-9b1d-16050438b881
Publikováno v:
Sevón, T, Kinnunen, T, Virta, J, Holmström, S, Kekki, T & Lindholm, I 2010, ' HECLA experiments on interaction between metallic melt and hematite-containing concrete ', Nuclear Engineering and Design, vol. 240, no. 10, pp. 3586-3593 . https://doi.org/10.1016/j.nucengdes.2010.04.039
In a hypothetical severe accident in a nuclear power plant, molten materials may come into contact with concrete, causing concrete ablation. In five HECLA experiments the interaction between metallic melt and concrete was investigated by pouring molt
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::de7e040a5e3519f2a7ce2abbd9d86f97
https://cris.vtt.fi/en/publications/943ba62a-61d6-47dc-bb3b-29ed510d33a0
https://cris.vtt.fi/en/publications/943ba62a-61d6-47dc-bb3b-29ed510d33a0
Autor:
Ilona Lindholm, Stefan Holmström, Jaakko Miettinen, Tommi Kekki, Pekka Pankakoski, Tuomo Sevón, Eveliina Takasuo, Jouko Virta, Riitta Zilliacus
Publikováno v:
Lindholm, I, Holmström, S, Miettinen, J, Kekki, T, Pankakoski, P, Sevon, T, Takasuo, E, Virta, J & Zilliacus, R 2006, SANCY / CAPHORN summary report . in SAFIR: The Finnish Research Programme on Nuclear Power Plant Safety 2003-2006 : Final Report . VTT Technical Research Centre of Finland, Espoo, VTT Tiedotteita-Research Notes, no. 2363, pp. 225-236 . < https://publications.vtt.fi/pdf/tiedotteet/2006/T2363.pdf >
VTT Technical Research Centre of Finland-PURE
VTT Technical Research Centre of Finland-PURE
SANCY and CAPHORN projects investigated 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
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::54800d4801f794d3efff58c8ca9dd6c7
https://cris.vtt.fi/en/publications/beb86913-365e-4ed5-b4ee-c8e382d75477
https://cris.vtt.fi/en/publications/beb86913-365e-4ed5-b4ee-c8e382d75477
Publikováno v:
Manninen, M, Silde, A, Lindholm, I, Huhtanen, R & Sjövall, H 2002, ' Simulation of hydrogen deflagration and detonation in a BWR reactor building ', Nuclear Engineering and Design, vol. 211, no. 1, pp. 27-50 . https://doi.org/10.1016/S0029-5493(01)00443-5
A systematic study was carried out to investigate the hydrogen behaviour in a BWR reactor building during a severe accident. BWR core contains a large amount of Zircaloy and the containment is relatively small. Because containment leakage cannot be t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::24faaa439bd7e68066be1062d4e4f467
https://cris.vtt.fi/en/publications/9b0a9726-5cf6-46e8-a45f-ff333d13b5e4
https://cris.vtt.fi/en/publications/9b0a9726-5cf6-46e8-a45f-ff333d13b5e4
Publikováno v:
Miettinen, J, Holmström, S, Sairanen, R & Lindholm, I 2002, Experimental study and analytical methods for particle bed dryout with heterogeneous particles and pressure variation . in 10th International Conference on Nuclear Engineering : Safety, Reliability and Plant Evaluations . vol. 2, American Society of Mechanical Engineers (ASME), pp. 255-269, 10th International Conference on Nuclear Engineering, ICONE 10, Arlington, Virginia, United States, 14/04/02 . https://doi.org/10.1115/ICONE10-22420
The interest to study the dryout heat flux in particle beds is related to interest of quantify the debris coolability margins during a hypothetical severe reactor accident. When the molten core has relocated to the containment floor, one accident man
Autor:
Ilona Lindholm, Jaakko Miettinen, E.K. Puska, F. Höjerup, Heikki Sjövall, W. Frid, L. Nilsson
Publikováno v:
Frid, W, Höjerup, F, Lindholm, I, Miettinen, J, Nilsson, K, Puska, E K & Sjövall, H 2001, ' Severe accident recriticality analyses (SARA) ', Nuclear Engineering and Design, vol. 209, no. 1-3, pp. 97-106 . https://doi.org/10.1016/S0029-5493(01)00392-2
Recriticality in a BWR during reflooding of an overheated partly degraded core, i.e. with relocated control rods, has been studied for a total loss of electric power accident scenario. In order to assess the impact of recriticality on reactor safety,
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::eeef2c97b79ce634678df4d5388af8a2
https://cris.vtt.fi/en/publications/137b5c37-5d84-4d68-a246-c54d7ecb5714
https://cris.vtt.fi/en/publications/137b5c37-5d84-4d68-a246-c54d7ecb5714