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Ville Tulkki
Ville Tulkki
Unknown affiliation
Verified email at vtt.fi
Title
Cited by
Cited by
Year
The importance of input interactions in the uncertainty and sensitivity analysis of nuclear fuel behavior
T Ikonen, V Tulkki
Nuclear Engineering and Design 275, 229-241, 2014
612014
A techno-economic assessment of NuScale and DHR-400 reactors in a district heating and cooling grid
TJ Lindroos, E Pursiheimo, V Sahlberg, V Tulkki
Energy Sources, Part B: Economics, Planning, and Policy 14 (1), 13-24, 2019
332019
Module for thermomechanical modeling of LWR fuel in multiphysics simulations
T Ikonen, H Loukusa, E Syrjälahti, V Valtavirta, J Leppänen, V Tulkki
Annals of Nuclear Energy 84, 111-121, 2015
292015
Supercritical Water Reactors-A Survey on International State of Research in 2006
V Tulkki
16*2006
Thermochemical modeling of nuclear fuel and the effects of oxygen potential buffers
H Loukusa, T Ikonen, V Valtavirta, V Tulkki
Journal of Nuclear Materials 481, 101-110, 2016
152016
FINIX: Fuel behavior model and interface for multiphysics applications
T Ikonen, V Tulkki, E Syrjälahti, V Valtavirta, J Leppänen
LWR Fuel Performance Meeting, Top Fuel 2013, 726-733, 2013
152013
District heat with small modular reactors (SMR)
V Tulkki, E Pursiheimo, TJ Lindroos
VTT Technical Research Centre of Finland, 2017
122017
Optimal investment analysis for heat pumps and nuclear heat in decarbonised Helsinki metropolitan district heating system
E Pursiheimo, TJ Lindroos, D Sundell, M Rämä, V Tulkki
Energy Storage and Saving 1 (2), 80-92, 2022
112022
Multiphysics simulation of fast transients with the FINIX fuel behaviour module
T Ikonen, E Syrjälahti, V Valtavirta, H Loukusa, J Leppänen, V Tulkki
EPJ Nuclear Sciences & Technologies 2, 37, 2016
92016
Modeling of Zircaloy cladding primary creep during load drop and reversal
V Tulkki, T Ikonen
Journal of nuclear materials 445 (1-3), 98-103, 2014
92014
A Finnish District Heating Reactor: Background and General Overview
J Leppänen, S Hillberg, V Hovi, R Komu, J Kurki, U Lauranto, A Oinonen, ...
International Conference on Nuclear Engineering 85246, V001T04A009, 2021
82021
Modelling anelastic contribution to nuclear fuel cladding creep and stress relaxation
V Tulkki, T Ikonen
Journal of Nuclear Materials 465, 34-41, 2015
72015
Viscoelastic modelling of Zircaloy cladding in-pile transient creep
V Tulkki, T Ikonen
Journal of Nuclear Materials 457, 324-329, 2015
72015
Modeling burnup-induced fuel rod deformations and their effect on transient behavior of a VVER-440 reactor core
E Syrjälahti, T Ikonen, V Tulkki
Annals of Nuclear Energy 125, 121-131, 2019
62019
The universal fuel performance code interface in Serpent 2
V Valtavirta, V Tulkki, J Leppänen, T Viitanen
Proc. TopFuel, 15-19, 2013
62013
Combining reactor physics and fuel performance calculations
T Viitanen, V Tulkki
TopFuel 2012, 695-701, 2012
62012
Fusion alpha performance in advanced scenario plasmas based on reversed central magnetic shear
T Kurki-Suonio, V Tulkki, S Sipilä, R Salomaa
Plasma physics and controlled fusion 48 (9), 1413, 2006
52006
Determination of tolerance limits for fuel assembly fission gas release summary statistics
H Loukusa, V Tulkki
Nuclear Engineering and Design 358, 110438, 2020
42020
Small Modular Reactor as a Part of a District Heating System
V Tulkki, E Pursiheimo, TJ Lindroos, V Sahlberg
Transactions of the American Nuclear Society 118, 685-687, 2018
32018
Multiphysics simulation of fast transients with the FINIX fuel behaviour module
T Ikonen, E Syrjälahti, V Valtavirta, H Loukusa, J Leppänen, V Tulkki
TopFuel 2015: Reactor Fuel Performance, 572-581, 2015
32015
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