Research output per year
Research output per year
Research output
- 10 results
Search results
-
2021
A Finnish district heating reactor: Thermal-Hydraulic Design and Transient Analyses
Komu, R., Hillberg, S., Hovi, V., Leppänen, J. & Leskinen, J., 2021, Proceedings of the 2021 28th International Conference on Nuclear Engineering: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications. American Society of Mechanical Engineers (ASME), Vol. 1. 7 p. V001T04A006. (International Conference on Nuclear Engineering (ICONE), Vol. 28).Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review
7 Citations (Scopus) -
A Finnish District Heating Reactor: Background and General Overview
Leppänen, J., Hillberg, S., Hovi, V., Komu, R., Kurki, J., Lauranto, U., Oinonen, A., Peltonen, J., Rintala, A., Tulkki, V., Tuominen, R. & Valtavirta, V., 2021, Proceedings of the 2021 28th International Conference on Nuclear Engineering: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications. American Society of Mechanical Engineers (ASME), Vol. 1. 8 p. V001T04A009. (International Conference on Nuclear Engineering (ICONE), Vol. 28).Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review
9 Citations (Scopus) -
2019
CFD simulations of direct-contact condensation of horizontal vapor jets
Pättikangas, T., Peltola, J., Hovi, V., Puustinen, M., Räsänen, A. & Kotro, E., 1 Jan 2019, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019. cd-rom ed. American Nuclear Society (ANS), p. 1583-1596Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review
3 Citations (Scopus) -
Coupled APROS-CFD simulation of generic VVER-440 loss of feedwater transient
Rämä, T., Toppila, T., Kättö, J., Hovi, V. & Pättikangas, T., 1 Jan 2019, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019. cd-rom ed. American Nuclear Society (ANS), p. 5652-5666 15 p.Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review
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Kraken: An upcoming Finnish reactor analysis framework
Valtavirta, V., Hovi, V., Loukusa, H., Rintala, A., Sahlberg, V., Tuominen, R. & Leppänen, J., 2019, International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019. American Nuclear Society (ANS), p. 786-795 10 p.Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review
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2014
3D core thermal hydraulics with the PORFLO code: Turbulence modelling and porous medium with porosity steps
Ilvonen, M., Hovi, V. & Taivassalo, V., 2014, Proceedings of the 22th International Conference on Nuclear Engineering, ICONE22: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory. American Society of Mechanical Engineers (ASME), Vol. 4. 11 p.Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review
1 Citation (Scopus) -
2012
Applications and development of the PORFLO 3D code in nuclear power plant thermal hydraulics
Takasuo, E., Hovi, V. & Ilvonen, M., 2012, Proceedings: 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference. New York, NY, USA: American Society of Mechanical Engineers (ASME), Vol. 4. p. 393-402Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review
8 Citations (Scopus) -
Experimental and computational studies of the coolability of heap-like and cylindrical debris beds
Takasuo, E., Holmström, S., Kinnunen, T., Pankakoski, P. H., Hovi, V., Ilvonen, M., Rahman, S., Bürger, M., Buck, M. & Pohlner, G., 2012, ERMSAR 2012 Papers (CD). GRS Gesellschaft für Anlagen- und ReaktorsicherheitResearch output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific
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Modeling of dryout in core debris beds of conical and cylindrical geometries
Takasuo, E., Hovi, V., Ilvonen, M. & Holmström, S., 2012, Proceedings: 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference. New York, NY, USA: American Society of Mechanical Engineers (ASME), p. 291-300Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review
3 Citations (Scopus) -
2010
CFD-simulation of the VVER-440 steam generator with porous media model
Rämä, T., Toppila, T., Pättikangas, T., Niemi, J. & Hovi, V., 2010, The Eighth International Seminar on Horizontal Steam Generators: OKB GIDROPRESS, Podolsk, Russia, 19-21 May 2010. 19 p.Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific
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