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Anitta Hämäläinen

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1983 …2017

Research output per year

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Research Output

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Conference article in proceedings
2010

High performance light water reactor transient analysis with neutr feedback using TRAB-3D and SMABRE codes

Seppälä, M., Hämäläinen, A. & Daavittila, A., 2010, Proceedings of the International Congress on Advances in Nuclear Power Plants (ICAPP 2010), June 13-17, 2010, San Diego, California, USA: Embedded International Topical Meeting at the 2010 ANS Annual Meeting. American Nuclear Society ANS, p. 48-57

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

3 Citations (Scopus)

Sensitivity studies for the main steam line break in the Loviisa NPP with the Hextran-Smabre

Syrjälahti, E. & Hämäläinen, A., 2010, Proceedings of the PHYSOR 2010. LaGrange Park, IL: American Nuclear Society ANS, p. 2358-2373

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

2005

HEXTRAN-SMABRE calculation of the VVER-1000 coolant transient benchmark

Syrjälahti, E. & Hämäläinen, A., 2005, 11th International Topical Meeting on Nuclear Thermal-Hydraulics (NURETH-11). 450

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

Transient and fuel performance analysis with VTT's coupled code system

Daavittila, A., Hämäläinen, A. & Räty, H., 2005, Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications. American Nuclear Society ANS, 12 p.

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

Open Access
2004

Validation of coupled neutrons/thermal hydraulics codes for VVER reactors (VALCO)

Weiss, F-P., Mittag, S., Langenbuch, S., Vanttola, T., Hämäläinen, A., Keresztúri, A., Hádek, J., Darilek, P., Petkov, P., Kuchin, A., Hlbocky, P., Sico, D., Danilin, S. & Powney, D., 2004, Proceedings, FISA 2003 EU research in reactor safety: Conclusion symposium on shared-cost and concerted actions. van Goethem, G., Zurita, A., Casalta, S. & Manolatos, P. (eds.). European Commission EC, p. 506-511 (EU Publications, Vol. 21026).

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

Open Access
2003

HEXTRAN-SMABRE calculation of the 6th AER benchmark, main steam line break in a VVER440 NPP

Hämäläinen, A. & Kyrki-Rajamäki, R., 2003, 13th Symposium of AER on VVER Reactor Physics and Safety. KFKI Atomic Energy Research Institute, p. 445-458

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

Validation of coupled codes in VALCO WP1 using measured VVER data

Hämäläinen, A., Vanttola, T. & et al., 2003, 13th Symposium of AER on VVER Reactor Physics and Safety. KFKI Atomic Energy Research Institute, p. 555-576

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

2002

Coupled code FRAPTRAN - GENFLO for analysing fuel behaviour during PWR and BWR transients and accidents

Hämäläinen, A., Stengård, J-O., Miettinen, J., Kyrki-Rajamäki, R. & Valtonen, K., 2002, Fuel Behaviour under Transient and LOCA Conditions: Proceedings of a Technical Committee Meeting. International Atomic Energy Agency IAEA, p. 43-54 (IAEA Technical Documents; No. IAEA-TECDOC-1320).

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientific

Open Access

FRAPTRAN fuel rod code and its coupled transient analysis with the GENFLO thermal hydraulic code

Valtonen, K., Hämäläinen, A. & Cunningham, M. E., 2002, Proceedings of the Nuclear Safety Research Conference: Washington D.C., USA, 22-24 October 2001. U.S. Nuclear Regulatory Commission, p. 381-395 (NUREG/CP; No. NUREG/CP-0176).

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

Open Access

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

Miettinen, J., Hämäläinen, A. & Pekkarinen, E., 2002, 10th International Conference on Nuclear Engineering. New York, NY: American Society of Mechanical Engineers ASME, Vol. 3. p. 665-678

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

1 Citation (Scopus)
2001

Advanced analysis of steam line break with the codes HEXTRAN and SMABRE for Loviisa NPP

Hämäläinen, A., Vanttola, T. & Siltanen, P., 2001, Advanced Thermal-hydraulic and Neutronic Codes: Current and Future Applications. Workshop Proceedings NEA/CSNI/R(2001)2/VOL1. Issy-les-Moulineaux: OECD, p. 325 - 336

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientific

Coupling of GENFLO thermohydraulic model with FRAPTRAN code for fuel transients

Hämäläinen, A., Stengård, J-O., Miettinen, J. & Kyrki-Rajamäki, R., 2001, ENS TopFuel 2001 International Topical Meeting - Nuclear Fuel: Development to Meet the Challenge of a Changing Market: Stockholm, Sweden, 28-30 May 2001. European Nuclear Society, p. 1-14

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientific

Validation of coupled codes for VVERs by analysis of plant transients

Mittag, R., Kliem, S., Weiss, F. P., Kyrki-Rajamäki, R., Hämäläinen, A., Langenbuch, S., Danilin, S., Hadek, J., Hegyi, G., Kuchin, A. & Panayotov, D., 2001, Advanced Thermal-hydraulic and Neutronic Codes: Current and Future Applications: Workshop Proceedings. OECD NEA Nuclear Energy Agency, p. 309-324 (NEA Committee on the Safety of Nuclear Installations. Report; No. NEA/CSNI/R(2001)2/VOL1).

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsProfessional

Open Access
2000

Coupled neutronics and thermal-hydraulics of PWRS and BWRS

Daavittila, A., Hämäläinen, A. & Kyrki-Rajamäki, R., 2000, Proceedings of 3rd Finnish-French colloquium on nuclear power plant safety. Virtanen, E. (ed.). Lappeenranta University of Technology, p. 40-45 (Acta Universitatis Lappeenrantaensis, Vol. 100).

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

1994

Interactive simulation and visualisation in APROS nuclear applications

Puska, E-K., Hämäläinen, A., Kontio, H. & Niemi, J., 1994, Proceedings of the SIMS'94 Simulation Conference. Langemyr, L. (ed.). Stockholm: Scandinavian Simulation Society SIMS, p. 150-155

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

1993

Three-dimensional core neutronics simulation in APROS

Puska, E-K., Hämäläinen, A., Tiihonen, O., Porkholm, K. & Kontio, H., 1993, 3rd Nuclear Simulation Symposium. Heller, M. R. (ed.). München, p. 87-98

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientific

1986

Computer codes for safety analysis in Finland

Holmström, H., Hämäläinen, A., Mattila, L., Miettinen, J., Rajamäki, M. & Vuori, S., 1986, IAEA Programme on Computer-Aided Safety Analysis: Proceedings of the Technical Committee Workshop. Vienna: International Atomic Energy Agency, p. 23-29 (IAEA Technical Documents; No. IAEA-TC-560).

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

1983

Reflood experiments in the REWET-II rod bundle facility including comparisons with computer calculations

Kervinen, T., Hämäläinen, A. & Miettinen, J., 1983, Second International Topical Meeting on Nuclear Reactor Thermal-Hydraulics. American Nuclear Society ANS, p. 638-645

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

2 Citations (Scopus)