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Anitta Hämäläinen

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1983 …2017

Research output per year

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Research Output

2017

Safety analyses for dynamical events (SADE)

Sahlberg, V., Räty, H., Hovi, V., Hämäläinen, A., Ilvonen, M., Syrjälahti, E. & Taivassalo, V., 2017, SAFIR2018 - The Finnish Research Programme on Nuclear Power Plant Safety 2015-2018: Interim Report. VTT Technical Research Centre of Finland, p. 203-214 (VTT Technology, Vol. 294).

Research output: Chapter in Book/Report/Conference proceedingChapter or book articleProfessional

Open Access

Start-up of a cold loop in a VVER-440, the 7th AER benchmark calculation with HEXTRAN-SMABRE-PORFLO

Hovi, V., Taivassalo, V., Hämäläinen, A., Räty, H. & Syrjälahti, E., 1 Sep 2017, In : Kerntechnik. 82, 4, p. 426-435 10 p.

Research output: Contribution to journalArticleScientificpeer-review

2015

Statistical analysis of fuel failures in large break loss-of-coolant accident (LBLOCA) in EPR type nuclear power plant

Arkoma, A., Hänninen, M., Rantamäki, K., Kurki, J. & Hämäläinen, A., 2015, In : Nuclear Engineering and Design. 285, p. 1-14

Research output: Contribution to journalArticleScientificpeer-review

Open Access
16 Citations (Scopus)
2013

Extensive fuel modelling (PALAMA)

Arffman, A., Hämäläinen, A., Ikonen, T., Kelppe, S., Kättö, J., Nieminen, A., Stengård, J-O., Syrjälahti, E., Tulkki, V. & Tuomas, V., 2013, SAFIR2014: The Finnish Research Programme on Nuclear Power Plant Safety 2011-2014: Interim Report. Espoo: VTT Technical Research Centre of Finland, p. 124-135 (VTT Technology; No. 80).

Research output: Chapter in Book/Report/Conference proceedingChapter or book articleProfessional

Three-dimensional reactor analyses (KOURA)

Hovi, V., Hämäläinen, A., Ilvonen, M., Manninen, M., Rintala, J., Räty, H., Syrjälahti, E. & Taivassalo, V., 2013, SAFIR2014: The Finnish Research Programme on Nuclear Power Plant Safety 2011-2014: Interim Report. Espoo: VTT Technical Research Centre of Finland, p. 95-108 (VTT Technology; No. 80).

Research output: Chapter in Book/Report/Conference proceedingChapter or book articleProfessional

2011

Tridimensional Core Transient Analysis Methods (TRICOT): TRICOT summary report

Syrjälahti, E., Hämäläinen, A. & Räty, H., 2011, SAFIR2010: The Finnish Research Programme on Safety 2007-2010: Final Report. Espoo: VTT Technical Research Centre of Finland, p. 145-159 (VTT Tiedotteita - Research Notes; No. 2571).

Research output: Chapter in Book/Report/Conference proceedingChapter or book articleProfessional

Open Access
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

2009

Tridimensional core transient analysis methods (TRICOT): TRICOT summary report

Räty, H., Daavittila, A. & Hämäläinen, A., 2009, SAFIR2010: The Finnish Research Programme on Nuclear Power Plant Safety 2007-2010: Interim Report . Espoo: VTT Technical Research Centre of Finland, p. 120-130 (VTT Tiedotteita - Research Notes; No. 2466).

Research output: Chapter in Book/Report/Conference proceedingChapter or book articleProfessional

Open Access
2007

Qualification of coupled 3-D neutron-kinetic/thermal-hydraulic code systems by the calculation of main-steam-line-break benchmarks in an NPP with VVER-440 reactor

Kliem, S., Danilin, S., Hämäläinen, A., Hádek, J., Keresztúri, A. & Siltanen, P., 2007, In : Nuclear Science and Engineering. 157, 3, p. 280-298

Research output: Contribution to journalArticleScientificpeer-review

19 Citations (Scopus)
2006

HEXTRAN-SMABRE calculation of the VVER-1000 coolant transient-1 benchmark

Syrjälahti, E. & Hämäläinen, A., 2006, In : Progress in Nuclear Energy. 48, 8, p. 849-864 16 p.

Research output: Contribution to journalArticleScientificpeer-review

2005
Open Access

Comprehensive uncertainty and sensitivity analysis for coupled code calculations of VVER plant transients

Langenbuch, S., Krzykacz-Hausmann, B., Schmidt, K-D., Hegyi, G., Keresztúri, A., Kliem, S., Hadek, J., Danilin, S., Nikonov, S., Kuchin, A., Khalimanchuk, V. & Hämäläinen, A., 2005, In : Nuclear Engineering and Design. 235, 2-4, p. 521 - 540 20 p.

Research output: Contribution to journalArticleScientificpeer-review

16 Citations (Scopus)

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

Validation of coupled codes using VVER plant measurements

Vanttola, T., Hämäläinen, A., Kliem, S., Kozmenkov, Y., Weiss, F-P., Keresztúri, A., Hádek, J., Strmensky, C., Stefanova, S., Kuchin, A., Hlbocky, P., Siko, D. & Danilin, S., 2005, In : Nuclear Engineering and Design. 235, 2-4, p. 507 - 519 13 p.

Research output: Contribution to journalArticleScientificpeer-review

22 Citations (Scopus)
2004

APROS models beyond DBA

Hämäläinen, A., 2004, YK1: Basic Professional Training Course on Nuclear Safety, Finland. Kyrki-Rajamäki, R. (ed.). Lappeenranta University of Technology, Vol. 2. p. 1-4 (Lappeenrannan teknillinen yliopisto: Energia- ja ympäristötekniikan osasto. Julkaisu D; No. EN D 80).

Research output: Chapter in Book/Report/Conference proceedingChapter or book articleProfessional

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

3D methodology in VVER transient with uncertainty analyses

Hämäläinen, A., 2003.

Research output: Contribution to conferenceConference articleScientific

Effects of secondary circuit modeling on results of pressurized water reactor main steam line break benchmark calculations with new coupled code TRAB-3D/SMABRE

Daavittila, A., Hämäläinen, A. & Kyrki-Rajamäki, R., 2003, In : Nuclear Technology. 142, 2, p. 116-123 8 p.

Research output: Contribution to journalArticleScientificpeer-review

8 Citations (Scopus)

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)

GENFLO: A general thermal hydraulic solution for accident simulation

Miettinen, J. & Hämäläinen, A., 2002, Espoo: VTT Technical Research Centre of Finland. 82 p. (VTT Tiedotteita - Research Notes; No. 2163).

Research output: Book/ReportReport

Open Access

Transient behaviour of high burnup fuel (KOTO): Coupling of FRAPTRAN Fuel Rod for Transient Analysis with GENFLO Thermal Hydraulic Code (KOTO & READY)

Stengård, J-O., Hämäläinen, A. & Miettinen, J., 2002, FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002: Final Report. Espoo: VTT Technical Research Centre of Finland, p. 104-111 (VTT Tiedotteita - Research Notes; No. 2164).

Research output: Chapter in Book/Report/Conference proceedingChapter or book articleProfessional

Open Access

Validation of coupled neutron kinetic/thermal-hydraulic codes: Part 2: Analysis of a VVER-440 transient (Loviisa-1)

Hämäläinen, A., Kyrki-Rajamäki, R., Mittag, R., Kliem, S., Weiss, F., Langenbuch, S., Danilin, S., Hadek, J. & Hegyi, G., 2002, In : Annals of Nuclear Energy. 29, 3, p. 255-269

Research output: Contribution to journalArticleScientificpeer-review

24 Citations (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

TRAB-3D/SMABRE calculation of the OECD/NRC PWR MSLB benchmark

Daavittila, A., Hämäläinen, A. & Kyrki-Rajamäki, R., 2001, ANS Annual Meeting 2001. American Nuclear Society ANS, p. 31-31 1 p. (Transactions of the American Nuclear Society, Vol. 84).

Research output: Chapter in Book/Report/Conference proceedingConference abstract 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

Validation of coupled neutron kinetic/thermal-hydraulic codes. Part 1: Analysis of a VVER-1000 transient (Balakovo-4)

Mittag, R., Kliem, S., Weiss, F., Kyrki-Rajamäki, R., Hämäläinen, A., Langenbuch, S., Danilin, S., Hadek, J., Hegyi, G., Kuchin, A. & Panayotov, D., 2001, In : Annals of Nuclear Energy. 28, 9, p. 857-873 7 p.

Research output: Contribution to journalArticleScientificpeer-review

26 Citations (Scopus)
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

READY special report 1: Application of TRAB-3D to BWR and PWR transient calculations

Daavittila, A., Hämäläinen, A. & Kyrki-Rajamäki, R., 2000, FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety: Interim Report 1999 - August 2000. Espoo: VTT Technical Research Centre of Finland, p. 150-160 (VTT Tiedotteita - Research Notes; No. 2057).

Research output: Chapter in Book/Report/Conference proceedingChapter or book articleProfessional

Open Access
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

1984

Simulation of two-phase flow systems using system pressure approximation

Hämäläinen, A. & Miettinen, J., 1984. 14 p.

Research output: Contribution to conferenceConference articleScientific

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)