Jaakko Leppänen

20062019
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Research Output 2006 2019

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Article
2019
1 Citation (Scopus)
Spatial distribution
Monte Carlo simulation

New energy deposition treatment in the Serpent 2 Monte Carlo transport code

Tuominen, R., Valtavirta, V. & Leppänen, J., 2019, In : Annals of Nuclear Energy. 129, p. 224-232 9 p.

Research output: Contribution to journalArticleScientificpeer-review

Neutrons
Photons
Detectors

Response Matrix Method–Based Importance Solver and Variance Reduction Scheme in the Serpent 2 Monte Carlo Code

Leppänen, J., 30 Apr 2019, In : Nuclear Technology. 18 p.

Research output: Contribution to journalArticleScientificpeer-review

Photons
mesh
Neutron sources
Subroutines
matrices

Serpent/SCF pin-level multiphysics solutions for the VERA Fuel Assembly benchmark

Ferraro, D., Garcia, M., Imke, U., Valtavirta, V., Leppänen, J. & Sanchez-Espinoza, V., 9 Jan 2019, In : Annals of Nuclear Energy. 128, p. 102-114 13 p.

Research output: Contribution to journalArticleScientificpeer-review

Nuclear industry
Nuclear reactors
Coolants
Physics
Innovation
2018
3 Citations (Scopus)

Advancement of functional expansion capabilities: Implementation and optimization in Serpent 2

Wendt, B., Kerby, L., Tumulak, A. & Leppänen, J., 1 Aug 2018, In : Nuclear Engineering and Design. 334, p. 138-153 16 p.

Research output: Contribution to journalArticleScientificpeer-review

optimization
Astronomical Netherlands Satellite
expansion
evaluation
mesh

Applications of Serpent 2 Monte Carlo Code to ITER Neutronics Analysis

Turner, A., Burns, A., Colling, B. & Leppänen, J., 17 Nov 2018, In : Fusion Science and Technology. 74, 4, p. 315-320 6 p.

Research output: Contribution to journalArticleScientificpeer-review

Geometry
blankets
geometry
requirements
vessels
2 Citations (Scopus)

Calculation chain for the analysis of spent nuclear fuel in long-term interim dry storage

Arkoma, A., Huhtanen, R., Leppänen, J., Peltola, J. & Pättikangas, T., 22 Apr 2018, In : Annals of Nuclear Energy. 119, p. 129–138 10 p.

Research output: Contribution to journalArticleScientificpeer-review

Spent fuels
Nuclear fuels
Computational fluid dynamics
Physics
Unloading
1 Citation (Scopus)

SERPENT validation and optimization with mesh adaptive search on stereolithography geometry models

Talamo, A., Gohar, Y. & Leppänen, J., 1 May 2018, In : Annals of Nuclear Energy. 115, p. 619-632 14 p.

Research output: Contribution to journalArticleScientificpeer-review

Stereolithography
Geometry
3D printers
Research reactors
Computer programming languages
2017
5 Citations (Scopus)

Coupled neutronics-fuel behavior calculations in steady state using the Serpent 2 Monte Carlo code

Valtavirta, V., Leppänen, J. & Viitanen, T., 2017, In : Annals of Nuclear Energy. 100, Part 2, p. 50-64 15 p.

Research output: Contribution to journalArticleScientificpeer-review

Physics
Temperature distribution
Feedback
Temperature
Geometry

Estimating the effects of homogenized fuel temperature in group constant generation using Serpent 2

Valtavirta, V. & Leppänen, J., 1 Jul 2017, In : Annals of Nuclear Energy. 105, p. 79-94 16 p.

Research output: Contribution to journalArticleScientificpeer-review

Isotopes
Paramagnetic resonance
Physics
Temperature
Gadolinium
3 Citations (Scopus)

On the use of delta-tracking and the collision flux estimator in the Serpent 2 Monte Carlo particle transport code

Leppänen, J., 1 Jul 2017, In : Annals of Nuclear Energy. 105, p. 161-167 7 p.

Research output: Contribution to journalArticleScientificpeer-review

Fluxes
Physics
Reaction rates
Fusion reactions
Radiation
2016

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
Physics
Control rods
Accidents
Hydraulics
Feedback
28 Citations (Scopus)

Overview of methodology for spatial homogenization in the Serpent 2 Monte Carlo code

Leppänen, J., Pusa, M. & Fridman, E., 2016, In : Annals of Nuclear Energy. 96, p. 126-136

Research output: Contribution to journalArticleScientificpeer-review

Parameterization
Neutrons
Simulators
Scattering
Defects

Serpent Monte Carlo -reaktorifysiikkakoodin kehitys

Leppänen, J., 2016, In : ATS Ydintekniikka. 45, 3, p. 65-69

Research output: Contribution to journalArticleProfessional

1 Citation (Scopus)

Validating the Serpent Model of FiR 1 Triga Mk-II Reactor by Means of Reactor Dosimetry

Viitanen, T. & Leppänen, J., 2016, In : EPJ Web of Conferences. p. 8

Research output: Contribution to journalArticleScientificpeer-review

Open Access
estimators
dosimeters
reactors
reaction kinetics
reactor physics
10 Citations (Scopus)

Validation of the Serpent-ARES code sequence using the MIT BEAVRS benchmark: HFP conditions and fuel cycle 1 simulations

Leppänen, J. & Mattila, R., 2016, In : Annals of Nuclear Energy. 96, p. 324-331

Research output: Contribution to journalArticleScientificpeer-review

Monte Carlo methods
Simulators
Specifications
2015
51 Citations (Scopus)

A collision history-based approach to sensitivity/perturbation calculations in the continuous energy Monte Carlo code SERPENT

Aufiero, M., Bidaud, A., Hursin, M., Leppänen, J., Palmiotti, G., Pelloni, S. & Rubiolo, P., 2015, In : Annals of Nuclear Energy. 85, p. 245-258

Research output: Contribution to journalArticleScientificpeer-review

Kinetic parameters
Reaction rates
Scattering
1 Citation (Scopus)

Effect of the Target Motion Sampling temperature treatment method on the statistics and performance

Viitanen, T. & Leppänen, J., 2015, In : Annals of Nuclear Energy. 82, p. 217-225

Research output: Contribution to journalArticleScientificpeer-review

Statistics
Sampling
Reaction rates
Temperature
Program processors
8 Citations (Scopus)

Modeling of realistic pebble bed reactor geometries using the Serpent Monte Carlo code

Rintala, V., Suikkanen, H., Leppänen, J. & Kyrki-Rajamäki, R., 2015, In : Annals of Nuclear Energy. 77, p. 223-230

Research output: Contribution to journalArticleScientificpeer-review

Pebble bed reactors
Geometry
Finite difference method
Neutrons
High temperature reactors
6 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

Hydraulics
Steam piping systems
Coolants
Heat flux
Temperature distribution
8 Citations (Scopus)

Monte Carlo current-based diffusion coefficients: Application to few-group constants generation in Serpent

Dorval, E. & Leppänen, J., 2015, In : Annals of Nuclear Energy. 78, p. 104-116

Research output: Contribution to journalArticleScientificpeer-review

Sodium
Reactor cores
Fast reactors
Neutrons
Monte Carlo methods
3 Citations (Scopus)

Study on computational performance in generation of cross sections for nodal simulators using continuous-energy Monte Carlo calculations

Leppänen, J. & Mattila, R., 2015, In : Journal of Nuclear Science and Technology. 52, 7-8, p. 945-952 8 p.

Research output: Contribution to journalArticleScientificpeer-review

Advanced Reconn Electric Spacecraft
simulators
Simulators
cross sections
Neutrons
2 Citations (Scopus)

Temperature majorant cross sections in Monte Carlo neutron tracking

Viitanen, T. & Leppänen, J., 2015, In : Nuclear Science and Engineering. 180, 2, p. 209-223

Research output: Contribution to journalArticleScientificpeer-review

Neutrons
Sampling
Temperature
Program processors
Hot Temperature
13 Citations (Scopus)

The Numerical Multi-Physics project (NUMPS) at VTT Technical Research Centre of Finland

Leppänen, J., Hovi, V., Ikonen, T., Kurki, J., Pusa, M., Valtavirta, V. & Viitanen, T., 28 Jul 2015, In : Annals of Nuclear Energy. 84, p. 55-62 8 p.

Research output: Contribution to journalArticleScientificpeer-review

Nuclear reactors
Physics
Computational methods
Computational fluid dynamics
Hydraulics
2014
46 Citations (Scopus)

Calculation of effective point kinetics parameters in the Serpent 2 Monte Carlo code

Leppänen, J., Aufiero, M., Fridman, E., Rachamin, R. & Van Der Marck, S., 2014, In : Annals of Nuclear Energy. 65, p. 272-279

Research output: Contribution to journalArticleScientificpeer-review

Kinetic parameters
Research reactors
Reactor cores
Neutrons
8 Citations (Scopus)

Internal neutronics-temperature coupling in Serpent 2

Valtavirta, V., Viitanen, T. & Leppänen, J., 2014, In : Nuclear Science and Engineering. 177, 2, p. 193-202 10 p.

Research output: Contribution to journalArticleScientificpeer-review

Materials properties
Nuclear fuel elements
Temperature
Isotopes
Temperature distribution
12 Citations (Scopus)

Target Motion Sampling Temperature Treatment Technique with Elevated Basis Cross-Section Temperatures

Viitanen, T. & Leppänen, J., 2014, In : Nuclear Science and Engineering. 177, 1, p. 77-89 13 p.

Research output: Contribution to journalArticleScientificpeer-review

Sampling
Temperature
Reaction rates
Isotopes
Program processors
27 Citations (Scopus)

Validation of the Serpent-ARES code sequence using the MIT BEAVRS benchmark: Initial core at HZP conditions

Leppänen, J., Mattila, R. & Pusa, M., 2014, In : Annals of Nuclear Energy. 69, p. 212-225 14 p.

Research output: Contribution to journalArticleScientificpeer-review

2013
40 Citations (Scopus)

An extended version of the SERPENT-2 code to investigate fuel burn-up and core material evolution of the Molten Salt Fast Reactor

Aufiero, M., Cammi, A., Fiorina, C., Leppänen, J., Luzzi, L. & Ricotti, M. E., 2013, In : Journal of Nuclear Materials. 441, 1-3, p. 473-486 13 p.

Research output: Contribution to journalArticleScientificpeer-review

Fast reactors
molten salts
Molten materials
Salts
reactors
19 Citations (Scopus)

Modeling of nonuniform density distributions in the serpent 2 Monte Carlo code

Leppänen, J., 2013, In : Nuclear Science and Engineering. 174, 3, p. 318-325 7 p.

Research output: Contribution to journalArticleScientificpeer-review

Boiling water reactors
Coolants
Hydraulics
Sampling
Hot Temperature
35 Citations (Scopus)

Numerical stability of the predictor-corrector method in Monte Carlo burnup calculations of critical reactors

Dufek, J., Kotlyar, D., Shwageraus, E. & Leppänen, J., 2013, In : Annals of Nuclear Energy. 56, p. 34-38 5 p.

Research output: Contribution to journalArticleScientificpeer-review

Convergence of numerical methods
Fluxes
24 Citations (Scopus)

Preventing xenon oscillations in Monte Carlo burnup calculations by enforcing equilibrium xenon distribution

Isotalo, A. E., Leppänen, J. & Dufek, J., 2013, In : Annals of Nuclear Energy. 60, p. 78-85 10 p.

Research output: Contribution to journalArticleScientificpeer-review

Xenon
Neutron flux
Physics
13 Citations (Scopus)

Solving linear systems with sparse Gaussian elimination in the chebyshev rational approximation method

Pusa, M. & Leppänen, J., 2013, In : Nuclear Science and Engineering. 175, 3, p. 250-258 8 p.

Research output: Contribution to journalArticleScientificpeer-review

Linear systems
Isotopes
Factorization
2012
53 Citations (Scopus)

Explicit treatment of thermal motion in continuous-energy Monte Carlo tracking routines

Viitanen, T. & Leppänen, J., 2012, In : Nuclear Science and Engineering. 171, 2, p. 165-173 9 p.

Research output: Contribution to journalArticleScientificpeer-review

Neutrons
Temperature distribution
Physics
Sampling
Temperature
2011
56 Citations (Scopus)

On the use of the Serpent Monte Carlo code for few-group cross section generation

Fridman, E. & Leppänen, J., 2011, In : Annals of Nuclear Energy. 38, 6, p. 1399-1405 7 p.

Research output: Contribution to journalArticleScientificpeer-review

Feedback
Physics
Reactor cores
Pressurized water reactors
Boron
2010
101 Citations (Scopus)

Computing the Matrix Exponential in Burnup Calculations

Pusa, M. & Leppänen, J., 2010, In : Nuclear Science and Engineering. 164, 2, p. 140-150 11 p.

Research output: Contribution to journalArticleScientificpeer-review

Pressurized water reactors
59 Citations (Scopus)

Performance of Woodcock delta-tracking in lattice physics applications using the Serpent Monte Carlo reactor physics burnup calculation code

Leppänen, J., 2010, In : Annals of Nuclear Energy. 37, 5, p. 715-722 8 p.

Research output: Contribution to journalArticleScientificpeer-review

Physics
Ray tracing
Geometry
2009
2 Citations (Scopus)

A Comparison of Deterministic and Monte Carlo Depletion Methods for HTGR Fuel Elements

DeHart, M. & Leppänen, J., 2009, In : Transactions of the American Nuclear Society. 101, p. 778-781 4 p.

Research output: Contribution to journalArticleScientificpeer-review

high temperature gas cooled reactors
nuclear fuel elements
depletion
spent fuels
particle interactions
19 Citations (Scopus)

HTGR Reactor Physics and Burnup Calculations Using the Serpent Monte Carlo Code

Leppänen, J. & DeHart, M., 2009, In : Transactions of the American Nuclear Society. 101, p. 782-784 3 p.

Research output: Contribution to journalArticleScientificpeer-review

reactor physics
high temperature gas cooled reactors
light water reactors
reactor design
Finland
59 Citations (Scopus)

Two practical methods for unionized energy grid construction in continuous-energy Monte Carlo neutron transport calculation

Leppänen, J., 2009, In : Annals of Nuclear Energy. 36, 7, p. 878-885 8 p.

Research output: Contribution to journalArticleScientificpeer-review

Neutrons
Data storage equipment
Isotopes
Fission products
Actinides
2007

Uuden Monte Carlo -reaktorifysiikkakoodin kehittäminen

Leppänen, J., 2007, In : ATS Ydintekniikka. 36, 3, p. 46-47

Research output: Contribution to journalArticleProfessional