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Ville Tulkki

  • Phone+358401840852
20062020

Research output per year

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Research Output

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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

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)
2016

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)

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)

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)

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

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)
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)