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Ville Tulkki

  • Phone+358401840852
20062020

Research output per year

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Research Output

2020

Determination of tolerance limits for fuel assembly fission gas release summary statistics

Loukusa, H. & Tulkki, V., Mar 2020, In : Nuclear Engineering and Design. 358, 110438.

Research output: Contribution to journalArticleScientificpeer-review

Implementation of burnup effects in the multiphysics fuel behavior module FINIX

Loukusa, H., Peltonen, J., Valtavirta, V. & Tulkki, V., 1 Feb 2020, In : Annals of Nuclear Energy. 136, 107022.

Research output: Contribution to journalArticleScientificpeer-review

Validation and verification of the FINIX fuel behavior module

Peltonen, J., Loukusa, H. & Tulkki, V., 2020, Global/Top Fuel 2019. American Nuclear Society ANS, p. 1164-1173

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

2019
3 Citations (Scopus)

Modeling burnup-induced fuel rod deformations and their effect on transient behavior of a VVER-440 reactor core

Syrjälahti, E., Ikonen, T. & Tulkki, V., 2019, In : Annals of Nuclear Energy. 125, p. 121-131 11 p.

Research output: Contribution to journalArticleScientificpeer-review

3 Citations (Scopus)

Physics and chemistry of nuclear fuels (PANCHO)

Arkoma, A., Heikinheimo, J., Ikonen, T., Kättö, J., Loukusa, H., Myllykylä, E., Peltonen, J., Pohja, R., Tulkki, V. & Valtavirta, V., 2019, SAFIR2018 - The Finnish Research Programme on Nuclear Power Plant Safety 2015-2018: Final Report. Hämäläinen, J. & Suolanen, V. (eds.). VTT Technical Research Centre of Finland, p. 252-268 (VTT Technology; No. 349).

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

Open Access
2018

Small modular reactor as a part of a district heating system

Tulkki, V., Pursiheimo, E., Lindroos, T. J. & Sahlberg, V., 1 Jan 2018, In : Transactions of the American Nuclear Society. 118, p. 685-687 3 p.

Research output: Contribution to journalArticle in a proceedings journalScientificpeer-review

2017
Open Access

JHR collaboration & Melodie follow-up (JHR)

Huotilainen, S., Tulkki, V. & Kinnunen, P., 2017, SAFIR2018 - The Finnish Research Programme on Nuclear Power Plant Safety 2015-2018: Interim Report. VTT Technical Research Centre of Finland, p. 354-361 (VTT Technology, Vol. 294).

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

Open Access

Physics and chemistry of nuclear fuel (PANCHO)

Arkoma, A., Ikonen, T., Kättö, J., Loukusa, H., Myllykylä, E., Pohja, R., Tulkki, V. & Valtavirta, V., 2017, SAFIR2018 - The Finnish Research Programme on Nuclear Power Plant Safety 2015-2018: Interim Report. VTT Technical Research Centre of Finland, p. 192-202 (VTT Technology, Vol. 294).

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

Open Access

Safety of new reactor technologies (GENXFIN)

Penttilä, S., Kolehmainen, J., Toivonen, A., Jäppinen, T., Nevasmaa, P., Tulkki, V., Rantakaulio, A. & Niemi, M., 2017, SAFIR2018 - The Finnish Research Programme on Nuclear Power Plant Safety 2015-2018: Interim Report. VTT Technical Research Centre of Finland, p. 135-142 (VTT Technology, Vol. 294).

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

Open Access
2016

Creep performance of fuel cladding

Pohja, R., Tulkki, V., Ikonen, T., Moilanen, P., Rantala, J., Huotilainen, S. & Ehrnstén, U., 2016, Baltica X: International Conference on Life Management and Maintenance for Power Plants. Auerkari, P. (ed.). Espoo: VTT Technical Research Centre of Finland, 8 p. (VTT Technology, Vol. 261).

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

Open Access

Multiaxial creep testing device for nuclear fuel claddings

Pohja, R., Moilanen, P., Rantala, J., Huotilainen, S., Tulkki, V., Ehrnstén, U. & Holmström, S., 2016, In : Athens Journal of Sciences. 3, 3, p. 227-240

Research output: Contribution to journalArticleScientificpeer-review

Open Access

Multiphysics simulation of fast transients with the FINIX fuel behaviour module

Ikonen, T., Syrjälahti, E., Valtavirta, V., Loukusa, H., Leppänen, J. & Tulkki, V., 8 Sep 2016, In : EPJ Nuclear Sciences & Technologies. 2, 8 p., 37.

Research output: Contribution to journalArticleScientificpeer-review

Open Access

Thermochemical modeling of nuclear fuel and the effects of oxygen potential buffers

Loukusa, H., Ikonen, T., Valtavirta, V. & Tulkki, V., 2016, In : Journal of Nuclear Materials. 481, p. 101-110

Research output: Contribution to journalArticleScientificpeer-review

4 Citations (Scopus)

Thermochemical modelling of nuclear fuel

Loukusa, H., Ikonen, T., Valtavirta, V. & Tulkki, V., 3 Nov 2016, SYP2016 Proceedings. Finnish Nuclear Society, 4 p.

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

Open Access

Ydinturvallisuustalo vihittiin käyttöön

Nieminen, A. & Tulkki, V., 2016, In : ATS Ydintekniikka. 45, 4, p. 12-13

Research output: Contribution to journalArticleProfessional

2015

Modelling anelastic contribution to nuclear fuel cladding creep and stress relaxation

Tulkki, V. & Ikonen, T., 2015, In : Journal of Nuclear Materials. 465, p. 34-41

Research output: Contribution to journalArticleScientificpeer-review

4 Citations (Scopus)

Modelling cladding response to changing conditions

Tulkki, V. & Ikonen, T., 2015, TopFuel 2015 Conference Proceedings, Part 1. European Nuclear Society, p. 212-221

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

Open Access

Module for thermomechanical modeling of LWR fuel in multiphysics simulations

Ikonen, T., Loukusa, H., Syrjälahti, E., Valtavirta, V., Leppänen, J. & Tulkki, V., 2015, In : Annals of Nuclear Energy. 84, p. 111-121

Research output: Contribution to journalArticleScientificpeer-review

9 Citations (Scopus)

Multiphysics simulation of fast transients with the FINIX fuel behaviour module

Ikonen, T., Syrjälahti, E., Valtavirta, V., Loukusa, H., Leppänen, J. & Tulkki, V., 2015, TopFuel 2015 Conference Proceedings, Part I. European Nuclear Society, p. 572-581

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

Open Access

Multiphysics simulations of fast transients in VVER-1000 and VVER-440 reactors

Syrjälahti, E., Valtavirta, V., Kättö, J., Loukusa, H., Ikonen, T., Leppänen, J. & Tulkki, V., 2015, Proceedings of the 11th International Conference on WWER Fuel Performance, Modeling and Experimental Support. State Scientific and Technical Center for Nuclear and Radiation Safety SSTC NRS, 10 p.

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

Open Access

State-of-the-art review of data on fuel cladding interaction in advanced fuels for Gen IV reactors

Dumas, J-C., Martinelli, L., Bottomley, D., Wallenius, J., Tulkki, V. & Pohja, R., 2015, European Commission EC. 91 p.

Research output: Book/ReportReport

Thermochemical modelling of the oxygen potential of uranium oxide fuel pellets under irradiation

Loukusa, H., Ikonen, T., Räty, A. & Tulkki, V., 2015, TopFuel 2015 Conference Proceedings, Poster. European Nuclear Society, p. 10-19

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

Open Access

Viscoelastic modeling of Zircaloy cladding in-pile transient creep

Tulkki, V. & Ikonen, T., 2015, In : Journal of Nuclear Materials. 457, p. 324 - 329

Research output: Contribution to journalArticleScientificpeer-review

Open Access
4 Citations (Scopus)
2014

Effect of underlying assumptions to the publication and display of creep data

Tulkki, V. & Ikonen, T., 2014.

Research output: Contribution to conferenceConference articleScientific

Fiscal year report (9/2013 - 9/2014) of the Academy of Finland project IDEA (Interactive Modelling of Fuel Cladding Degradation Mechanisms)

Anderson, T., Huotilainen, S., Loukusa, H., Penttilä, S., Pohja, R. & Tulkki, V., 2014, VTT Technical Research Centre of Finland. 10 p. (Helsinki University of Technology: Systems Analysis Laboratory. A: Research Reports; No. VTT-R-05121-14).

Research output: Book/ReportReport

Modeling of Zircaloy cladding primary creep during load drop and reversal

Tulkki, V. & Ikonen, T., 2014, In : Journal of Nuclear Materials. 445, p. 98 - 103

Research output: Contribution to journalArticleScientificpeer-review

Open Access
6 Citations (Scopus)

The importance of input interactions in the uncertainty and sensitivity analysis of nuclear fuel behavior

Ikonen, T. & Tulkki, V., 2014, In : Nuclear Engineering and Design. 275, p. 229-241 12 p.

Research output: Contribution to journalArticleScientificpeer-review

17 Citations (Scopus)
2013

Creep properties of Zircaloy-4 for nuclear fuel cladding FEA simulation

Holmström, S., Andersson, T., Tulkki, V. & Laukkanen, A., 2013, Baltica IX. International Conference on Life Management and Maintenance for Power Plants - Abstracts. Auerkari, P. & Veivo, J. (eds.). Espoo: VTT Technical Research Centre of Finland, p. 46 (VTT Technology; No. 107).

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

Open Access

Creep properties of Zircaloy-4 for nuclear fuel cladding FEA simulation

Holmström, S., Andersson, T., Tulkki, V. & Laukkanen, A., 2013, Baltica IX. International Conference on Life Management and Maintenance for Power Plants. Auerkari, P. & Veivo, J. (eds.). Espoo: VTT Technical Research Centre of Finland, p. 302- 17 (VTT Technology; No. 106).

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

Open Access

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

FINIX: Fuel behavior model and interface for multiphysics applications

Ikonen, T., Tulkki, V., Syrjälahti, E., Valtavirta, V. & Leppänen, J., 2013, Proceedings of LWR Fuel Performance Meeting TopFuel 2013. American Nuclear Society ANS, p. 726-733

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

7 Citations (Scopus)

Radionuclide source term analysis (RASTA)

Nieminen, A., Räty, A. & Tulkki, V., 2013, SAFIR2014: The Finnish Research Programme on Nuclear Power Plant Safety 2011-2014: Interim Report. Espoo: VTT Technical Research Centre of Finland, p. 136-141 (VTT Technology; No. 80).

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

Release of radioactive nuclides from spent WWER fuel

Arkoma, A. & Tulkki, V., 2013, WWER Fuel Performance, Modelling and Experimental Support: Proceedings of the 10th International Conference 2013. Bulgarian Academy of Sciences, p. 421-427 12 p.

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

The universal fuel performance code interface in serpent 2

Valtavirta, V., Tulkki, V., Leppänen, J. & Viitanen, T., 2013, Proceedings of LWR Fuel Performance Meeting TopFuel 2013. American Nuclear Society ANS, p. 195-202

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

4 Citations (Scopus)
2012

Combining Reactor Physics and Fuel Performance Calculations

Viitanen, T. & Tulkki, V., 2012, Proceedings: TopFuel 2012 Transactions. European Nuclear Society, p. 695-701

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

Open Access
2006

Fusion alpha performance in advanced scenario plasmas based on reversed central magnetic shear

Kurki-Suonio, T., Tulkki, V., Sipilä, S. & Salomaa, R., 2006, In : Plasma Physics and Controlled Fusion. 48, 9, p. 1413-1424

Research output: Contribution to journalArticleScientificpeer-review

4 Citations (Scopus)

Fusion Alpha Performance in Advanced Scenario Plasmas based on Reversed Central Magnetic Shear

Kurki-Suonio, T., Asunta, O., Tulkki, V., Tala, T., Kiviniemi, T., Sipilä, S., Salomaa, R. & JET-EFDA collaborators, 2006, In : Europhysics Conference Abstracts. 30I, 4 p.

Research output: Contribution to journalArticle in a proceedings journalScientific

Open Access