Výsledky vyhledávání - "Jaakko Miettinen"

Dryout heat flux experiments with deep heterogeneous particle bed

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

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::95e789382c9a877190f52aa29874f614
https://doi.org/10.1016/j.nucengdes.2006.03.036

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SANCY / CAPHORN summary report

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

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

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Analysis of the critical heat flux in round vertical tubes under low pressure and flow oscillation conditions:Applications of artificial neural network

Autor: Jaakko Miettinen, Kenji Fukuda, Koji Morita, Su Guanghui, Jia Dounan, Mark Pidduck

Publikováno v: Guanghui, S, Morita, K, Fukuda, K, Pidduck, M, Dounan, J & Miettinen, J 2003, ' Analysis of the critical heat flux in round vertical tubes under low pressure and flow oscillation conditions : Applications of artificial neural network ', Nuclear Engineering and Design, vol. 220, no. 1, pp. 17-35 . https://doi.org/10.1016/S0029-5493(02)00304-7

Artificial neural networks (ANNs) for predicting critical heat flux (CHF) under low pressure and oscillation conditions have been trained successfully for either natural circulation or forced circulation (FC) in the present study. The input parameter

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::33ac1f16e814350a5fa37b1fc9c3c25f
https://cris.vtt.fi/en/publications/593a73c0-df95-425c-8d54-0eb487b5e540

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Generalized thermohydraulics module GENFLO for combining with the PWR core melting model, BWR recriticality neutronics model and fuel performance model

Autor: Jaakko Miettinen, Esko Pekkarinen, Anitta Hämäläinen

Publikováno v: Miettinen, J, Hämäläinen, A & Pekkarinen, E 2002, Generalized thermohydraulics module GENFLO for combining with the PWR core melting model, BWR recriticality neutronics model and fuel performance model . in 10th International Conference on Nuclear Engineering : Thermal Hydraulics . vol. 3, American Society of Mechanical Engineers (ASME), New York, pp. 665-678, 10th International Conference on Nuclear Engineering, ICONE 10, Arlington, Virginia, United States, 14/04/02 . https://doi.org/10.1115/ICONE10-22421

Thermal hydraulic simulation capability for accident conditions is needed at present in VTT in several programs. Traditional thermal hydraulic models are too heavy for simulation in the analysis tasks, where the main emphasis is the rapid neutron dyn

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::dda218bde6b8dd5a23e20653249b6917
https://cris.vtt.fi/en/publications/c2b95a0f-b730-4e7f-ab4b-c7d6080b5e4e

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CFD analyses for water-air flow with the euler-euler two-phase model in the fluent4 CFD code

Autor: Jaakko Miettinen, Holger Schmidt

Publikováno v: Miettinen, J & Schmidt, H 2002, CFD analyses for water-air flow with the euler-euler two-phase model in the fluent4 CFD code . in 10th International Conference on Nuclear Engineering (ICONE 10) : Thermal Hydraulics . vol. 3, ICONE10-22419, American Society of Mechanical Engineers (ASME), New York, pp. 653-663, 10th International Conference on Nuclear Engineering, ICONE 10, Arlington, Virginia, United States, 14/04/02 . https://doi.org/10.1115/ICONE10-22419

Framatome ANP develops a new boiling water reactor called SWR 1000. For the case of a hypothetical core melt accident it is designed in such a way that the core melt is retained in the Reactor Pressure Vessel (RPV) at low pressure owing to cooling of

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::433b161b92297a64b07d8614b8ce24b8
https://doi.org/10.1115/ICONE10-22419

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Experimental Study and Analytical Methods for Particle Bed Dryout With Heterogeneous Particles and Pressure Variation

Autor: Risto Sairanen, Stefan Holmström, Ilona Lindholm, Jaakko Miettinen

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

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::4ab3bd83130c961b4b6baed7140023d9
https://doi.org/10.1115/icone10-22420

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Severe accident recriticality analyses (SARA)

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

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