Výsledky vyhledávání - "Ismo Karppinen"

Critical flow prediction by system codes – Recent analyses made within the FONESYS network

Autor: P. Gaillard, N. Aksan, D. Bestion, M. Lanfredini, Joona Kurki, Jaeseok Heo, Philippe Fillion, A. Shen, Ismo Karppinen, D. Wang, J. L. Vacher, F. D'Auria, Kwang-Rag Kim, L. Liu

Publikováno v: Lanfredini, M, Bestion, D, D'Auria, F, Aksan, N, Fillion, P, Gaillard, P, Heo, J, Karppinen, I, Kim, K D, Kurki, J, Liu, L, Shen, A, Vacher, J L & Wang, D 2020, ' Critical flow prediction by system codes – Recent analyses made within the FONESYS network ', Nuclear Engineering and Design, vol. 366, 110731 . https://doi.org/10.1016/j.nucengdes.2020.110731

A benchmark activity on Two-Phase Critical Flow (TPCF) prediction was conducted in the framework of the Forum & Network of System Thermal-Hydraulics Nuclear Reactor Thermal-Hydraulics (FONESYS). FONESYS is a network among code developers who share th

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::98c4782aad03a36190c36a1d358f1e5f
http://hdl.handle.net/11568/1064167

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Integrated transient simulation of a BFB boiler with CFD models for the BFB furnace and dynamic system models for the steam cycle and boiler operation

Autor: Hannu Niemistö, Ville Ylä-Outinen, Ville Hovi, Timo Pättikangas, Sirpa Kallio, Lassi Karvonen, Ismo Karppinen, Marko Huttunen, Sami Tuuri

Publikováno v: Hovi, V, Huttunen, M, Karppinen, I, Pättikangas, T, Niemistö, H, Karvonen, L, Kallio, S, Tuuri, S & Ylä-Outinen, V 2017, ' Integrated transient simulation of a BFB boiler with CFD models for the BFB furnace and dynamic system models for the steam cycle and boiler operation ', Energy Procedia, vol. 120, no. August, pp. 508-515 . https://doi.org/10.1016/j.egypro.2017.07.186

An approach for integrated transient simulation of a BFB boiler furnace and the coupled steam cycle is presented. The BFB furnace is simulated with in-house CFD models implemented in the ANSYS Fluent® software. The boiler steam cycle with control lo

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::f747e5c78348f8059f7bed1f9140aa8b
http://juuli.fi/Record/0284340817

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Fluid-structure interaction analysis of large-break loss of coolant accident

Autor: Timo Pättikangas, Timo Toppila, Tellervo Brandt, Antti Timperi, Ismo Karppinen, Ville Lestinen, Jukka Kähkönen

Publikováno v: Brandt, T, Lestinen, V, Toppila, T, Kähkönen, J, Timperi, A, Pättikangas, T & Karppinen, I 2010, ' Fluid-structure interaction analysis of large-break loss of coolant accident ', Nuclear Engineering and Design, vol. 240, no. 9, pp. 2365-2374 . https://doi.org/10.1016/j.nucengdes.2009.11.013
Lestinen, V, kähkönen, J, Toppila, T, Brandt, T, Timperi, A, Pättikangas, T & Karppinen, I 2008, ' Fluid-structure interaction analysis of large-break loss of coolant accident ', Experiments and CFD Code Applications to Nuclear Reactor Safety, OECD/NEA Workshop, XCFD4NRS, Grenoble, France, 10/09/08-12/10/08 . < https://publications.vtt.fi/julkaisut/muut/2008/AC-02_Lestinen.pdf >

In this article, we study a Large-Break Loss of Coolant Accident (LBLOCA) where a guillotine break of one of the main coolant pipes occurs near the reactor pressure vessel (RPV). This initiates a rarefaction wave which propagates inside the RPV. The

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::ff30381d3508af94314cb7008000be90
https://doi.org/10.1016/j.nucengdes.2009.11.013

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A benchmark exercise on the use of CFD codes for containment issues using best practice guidelines: A computational challenge

Autor: M. Heitsch, K. Haller, H. Paillere, J. Schmid, B. Hemström, I. Toth, J. Macek, Michele Andreani, Ismo Karppinen

Publikováno v: Andreani, M, Haller, K, Heitsch, M, Hemström, B, Karppinen, I, Macek, J, Schmid, J, Paillere, H & Toth, I 2008, ' A benchmark exercise on the use of CFD codes for containment issues using best practice guidelines : A computational challenge ', Nuclear Engineering and Design, vol. 238, no. 3, pp. 502-513 . https://doi.org/10.1016/j.nucengdes.2007.01.021

In the framework of the 5th EU-FWP project ECORA the capabilities of CFD software packages for simulating flows in the containment of nuclear reactors was evaluated. Four codes were assessed using two basic tests in the PANDA facility addressing the

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::2b1236836737c42c3b603abc16c9dbc9
https://doi.org/10.1016/j.nucengdes.2007.01.021

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Evaluation of computational fluid dynamic methods for reactor safety analysis (ECORA)

Publikováno v: Scheuerer, M, Heitsch, M, Menter, F, Egorov, Y, Toth, I, Bestion, D, Pigny, S, Paillere, H, Martin, A, Boucker, M, Krepper, E, Willemsen, S, Muhlbauer, P, Andreani, M, Smith, B, Karlsson, R, Henriksson, M, Hemstrom, B, Karppinen, I & Kimber, G 2005, ' Evaluation of computational fluid dynamic methods for reactor safety analysis (ECORA) ', Nuclear Engineering and Design, vol. 235, no. 2-4, pp. 359-368 . https://doi.org/10.1016/j.nucengdes.2004.08.049
Nuclear Engineering and Design 235(2005)2-4, 359-368

The objective of the ECORA project is the evaluation of computational fluid dynamics (CFD) software for reactor safety applications, resulting in best practice guidelines (BPG) for an efficient use of CFD for reactor safety problems. The project sche

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::bf793aa37b22de9bd93ba99fb9fe69e8
https://doi.org/10.1016/j.nucengdes.2004.08.049

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Benchmark exercise on SBLOCA experiment of PWR PACTEL facility

Autor: Jozsef Banati, M. Cherubini, Lauri Peltokorpi, Heikki Purhonen, Pavel Kral, Virpi Kouhia, Ismo Karppinen, Sebastian Weber, Francesco Saverio D'Auria, Henrique Austregesilo, Otso-Pekka Kauppinen, Pasi Inkinen, Vesa Riikonen, Joanna Peltonen

Publikováno v: Kouhia, V, Riikonen, V, Kauppinen, O-P, Purhonen, H, Austregesilo, H, Bánáti, J, Cherubini, M, d'Auria, F, Inkinen, P, Karppinen, I, Kral, P, Peltokorpi, L, Peltonen, J & Weber, S 2013, ' Benchmark exercise on SBLOCA experiment of PWR PACTEL facility ', Annals of Nuclear Energy, vol. 59, pp. 149-156 . https://doi.org/10.1016/j.anucene.2013.04.004

The PWR PACTEL benchmark exercise was organized in Lappeenranta, Finland by Lappeenranta University of Technology. The benchmark consisted of two phases, i.e. a blind and an open calculation task. Seven organizations from the Czech Republic, Germany,

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::67b0b5ba3f1fda271f7b0e6b3757c5dc
https://cris.vtt.fi/en/publications/7e54009e-e772-46b4-9059-968d78ac8c81

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Validation of fluid-structure interaction calculations in a large-break loss of coolant accident

Autor: Ville Lestinen, Timo Pa¨ttikangas, Antti Timperi, Ismo Karppinen, Timo Toppila, Jukka Ka¨hko¨nen

Publikováno v: Timperi, A, Pättikangas, T, Karppinen, I, Lestinen, V, Kähkönen, J & Toppila, T 2008, Validation of fluid-structure interaction calculations in a large-break loss of coolant accident . in 16th International Conference on Nuclear Engineering, ICONE16 2008 : Fuel Cycle and High Level Waste Management; Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition . vol. 2, American Society of Mechanical Engineers (ASME), pp. 245-254, 16th International Conference on Nuclear Engineering, ICONE-16, Orlando, Florida, United States, 11/05/08 . https://doi.org/10.1115/ICONE16-48206

In the hypothetical Large-Break Loss Of Coolant Accident (LBLOCA), rapid depressurization of the reactor primary circuit causes loads on the reactor internals. This paper presents numerical simulations of a HDR experiment, where LBLOCA of a pressuriz

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::7e4062a73939ec340af83f1796b6c4f5
https://cris.vtt.fi/en/publications/647cbc01-4f0c-4c21-976a-10d528e4eda5

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