Jaakko Leppänen

20062019
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Research Output 2006 2019

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Conference article in proceedings
2018

Application of the Serpent–OpenFOAM Coupled Code System to the SEALER Reactor Core

Tuominen, R., Valtavirta, V. & Leppänen, J., 2018, Proceedings of PHYSOR 2018.

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

reactor cores
charge flow devices
physics
liquid metals
files

Assessment of Serpent Cross Sections of the Second Generation Fuel of TVEL for Loviisa NPP

Kuopanportti, J., Leppänen, J. & Saarinen, S., 2018, (Accepted/In press) Proceedings of the PHYSOR 2018, Cancun, Mexico. American Nuclear Society ANS

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

Development of a spatial domain decomposition scheme for Monte Carlo neutron transport

García, M., Ferraro, D., Sanchez-Espinoza, V. H., Mercatali, L., Leppänen, J. & Valtavirta, V., Nov 2018, 26th International Conference on Nuclear Engineering: Nuclear Fuel and Material, Reactor Physics, and Transport Theory. American Society of Mechanical Engineers ASME, Vol. 3. 7 p. ICONE26-82144

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

Neutrons
Decomposition
Data storage equipment
Scalability
Geometry

Effects of fuel temperature history approximations on neutronics properties of a BWR assembly

Valtavirta, V. & Leppänen, J., 2018, (Accepted/In press) Proceedings of the PHYSOR 2018, Cancun, Mexico. American Nuclear Society ANS, p. 2215-2226 12 p.

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

Boiling water reactors
Actinides
Temperature
Gadolinium
Isotopes
1 Citation (Scopus)

Foreseen capabilities, bottlenecks identification and potential limitations of serpent MC transport code in large-scale full 3-D burnup calculations

Ferraro, D., Garcia, M., Mercatali, L., Sanchez Espinoza, V. H., Leppänen, J. & Valtavirta, V., Nov 2018, 26th International Conference on Nuclear Engineering: Nuclear Fuel and Material, Reactor Physics, and Transport Theory. American Society of Mechanical Engineers ASME, Vol. 3. 9 p. ICONE26-82305

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

Nuclear reactors
Nuclear industry
Parallel architectures
Reactor cores
Screening

New stochastic substep based burnup scheme for Serpent 2

Valtavirta, V. & Leppänen, J., 2018, (Accepted/In press) Proceedings of PHYSOR 2018, Cancun, Mexico. American Nuclear Society ANS, p. 523-534

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

Gadolinium
Feedback
2017

Implementation of weighted delta-tracking with scattering in the serpent 2 monte carlo code

Rehak, J. S., Kerby, L. M., Dehart, M. D., Slaybaugh, R. N. & Leppänen, J., 1 Jan 2017, 2017 Annual Meeting. American Nuclear Society ANS, Vol. 116. p. 548-551 4 p. (Transactions of the American Nuclear Society, Vol. 116).

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

Open Access
2016

Calculating neutron dosimeter activation in VVER-440 surveillance chains with Serpent

Viitanen, T. & Leppänen, J., 2016, 26th Symposium of AER on VVER Reactor Physics and Reactor Safety : Book of Abstracts. p. 181-188

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

surveillance
dosimeters
pressure vessels
activation
reactors
5 Citations (Scopus)

Coupling Serpent and OpenFOAM for neutronics - CFD multi-physics calculations

Tuominen, R., Valtavirta, V., Peltola, J. & Leppänen, J., 2016, PHYSOR 2016: Unifying Theory and Experiments in the 21st Century. American Nuclear Society ANS, p. 255-269

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

Open Access
charge flow devices
boiling
physics
density distribution
temperature distribution
5 Citations (Scopus)

Expanding the Use of Serpent 2 to Fusion Applications: Shut-down Dose Rate Calculations

Leppänen, J. & Kaltiaisenaho, T., 2016, Proceedings of PHYSOR 2016. American Nuclear Society ANS

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

5 Citations (Scopus)

Expanding the use of Serpent 2 to Fusion Applications: Development of a Plasma Neutron Source

Sirén, P. & Leppänen, J., 2016, PHYSOR 2016: Unifying Theory and Experiments in the 21st Century. American Nuclear Society ANS

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

Neutronic Assessment of TRISO Particle Fuels in a Small Fluoride Salt-cooled High-temperature Reactor

Mohamed, H., Lindley, B., Parks, G. & Leppänen, J., 2016, Proceedings of PHYSOR 2016. American Nuclear Society ANS

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

5 Citations (Scopus)

New Interpolation Capabilities for Thermal Scattering Data in Serpent 2

Viitanen, T. & Leppänen, J., 2016, PHYSOR 2016: Unifying Theory and Experiments in the 21st Century. cd-rom ed. American Nuclear Society ANS

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

2015

Analyzing the statistics of group constants generated by Serpent 2 Monte Carlo code

Kaltiaisenaho, T. & Leppänen, J., 2015, Proceedings of the International Conference on the Physics of Reactors: PHYSOR 2014. Vol. JAEA-Conf 2014-003. 9 p. 1106126

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

Open Access
5 Citations (Scopus)

CAD-based geometry type in serpent 2-application in fusion neutronics

Leppänen, J., 2015, Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference . Curran Associates Inc., p. 1635-1646

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

Computer aided design
Fusion reactions
Geometry
Fusion reactors
Demonstrations

Development of an unstructured mesh based geometry model in the Serpent 2 Monte Carlo code

Leppänen, J. & Aufiero, M., 2015, Proceedings of the international conference on physics of reactors: PHYSOR2014. Vol. JAEA-Conf 2014-003. p. 10 1101586

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-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., 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
Physics
Control rods
Accidents
Hydraulics
Feedback

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
Physics
Control rods
Accidents
Hydraulics
Feedback

Simulating fast transients with fuel behavior feedback with the Serpent 2 Monte Carlo Code

Valtavirta, V., Ikonen, T., Viitanen, T. & Leppänen, J., 2015, Proceedings of the international conference on physics of reactors: PHYSOR2014. Vol. JAEA-Conf 2014-003. 12 p. 1105897

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

Open Access

Target motion sampling temperature treatment technique with track-length estimators in OpenMC - preliminary results

Viitanen, T., Leppänen, J. & Forget, B., 2015, Proceedings of the international conference on physics of reactors: PHYSOR 2014. Vol. JAEA-Conf 2014-003. 11 p. 1106078

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

Open Access

Unstructured mesh based multi-physics interface for CFD code coupling in the Serpent 2 Monte Carlo code

Leppänen, J., Valtavirta, V., Viitanen, T. & Aufiero, M., 2015, Proceedings of the international conference on physics of reactors: PHYSOR2014. Vol. JAEA-Conf 2014-003. 10 p. 1103981

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

Open Access
2014
2 Citations (Scopus)

Development of a CAD based geometry model in serpent 2 Monte Carlo code

Leppänen, J., 2014, ANS Winter Meeting and Nuclear Technology Expo, 2014. American Nuclear Society ANS, p. 663-667 (Transactions of the American Nuclear Society, Vol. 111).

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

2013
14 Citations (Scopus)

Comparison of serpent and HELIOS-2 as applied for the PWR few-group cross section generation

Fridman, E., Leppänen, J. & Wemple, C., 2013, Proceedings: International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M&C 2013. p. 693-703

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

cross sections
reflectors
discontinuity
diffusion coefficient
methodology
6 Citations (Scopus)

Development of a dynamic simulation mode in serpent 2 Monte Carlo code

Leppänen, J., 2013, Proceedings: International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M&C 2013. p. 117-127

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

reactivity
accidents
simulation
modules
neutrons
6 Citations (Scopus)

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

Physics
Nuclear fuels
Hydraulics
Hot Temperature
1 Citation (Scopus)

Optimizing the implementation of the target motion sampling temperature treatment technique: How fast can it get?

Viitanen, T. & Leppänen, J., 2013, Proceedings: International Conference on Mathematics and Computational Methods Applied to Nuclear Science & Engineering, M&C 2013. p. 950-961

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

Sampling
Temperature
Program processors
Neutrons
Physics
4 Citations (Scopus)

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

Physics
Temperature
Neutrons
Feedback
Hot Temperature
2012
6 Citations (Scopus)

An efficient implementation of the Chebyshev Rational Approximation Method (CRAM) for solving the burnup equations

Pusa, M. & Leppänen, J., 2012, Proceedings: International Conference on the Physics of Reactors 2012: Advances in Reactor Physics, PHYSOR 2012. American Nuclear Society ANS, Vol. 2. p. 952-963

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

Isotopes
Factorization
Linear systems
19 Citations (Scopus)

Burnup calculation methodology in the serpent 2 Monte Carlo code

Leppänen, J. & Isotalo, A., 2012, Proceedings: International Conference on the Physics of Reactors 2012: Advances in Reactor Physics, PHYSOR 2012. American Nuclear Society ANS, Vol. 2. p. 924-935

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

methodology
assembly
reactors
optimization

Explicit Temperature Treatment in Monte Carlo Neutron Tracking Routines: First Results

Viitanen, T. & Leppänen, J., 2012, Proceedings: International Conference on the Physics of Reactors 2012: Advances in Reactor Physics, PHYSOR 2012. American Nuclear Society ANS, Vol. 2. p. 995-1006

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

neutrons
reactor physics
high temperature gas cooled reactors
temperature
rejection
15 Citations (Scopus)

Multi-physics coupling scheme in the serpent 2 Monte Carlo code

Leppänen, J., Viitanen, T. & Valtavirta, V., 2012, ANS Annual Winter Meeting 2012. American Nuclear Society ANS, p. 1165-1168 (Transactions of the American Nuclear Society, Vol. 107).

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

Open Access
10 Citations (Scopus)

Revised methods for few-group cross sections generation in the Serpent Monte Carlo code

Fridman, E. & Leppänen, J., 2012, Proceedings: International Conference on the Physics of Reactors 2012: Advances in Reactor Physics, PHYSOR 2012. American Nuclear Society ANS, Vol. 1. p. 842-853

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

cross sections
methodology
homogenizing
reflectors
neutron scattering