Jaakko Leppänen
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View article: Status of Serpent Monte Carlo code in 2024
Status of Serpent Monte Carlo code in 2024 Open
The Serpent Monte Carlo code has been in public distribution for 15 years, and has a large international user basis with both research and commercial applications. Serpent is currently developed as part of the Kraken multi-physics framewor…
View article: Improved polynomial rates of memory loss for nonstationary intermittent dynamical systems
Improved polynomial rates of memory loss for nonstationary intermittent dynamical systems Open
We study nonstationary dynamical systems formed by sequential concatenation of nonuniformly expanding maps with a uniformly expanding first return map. Assuming a polynomially decaying upper bound on the tails of first return times that is…
View article: Evaluation of Life Cycle CO2 Emissions for the LDR-50 Nuclear District Heating Reactor
Evaluation of Life Cycle CO2 Emissions for the LDR-50 Nuclear District Heating Reactor Open
The LDR-50 low-temperature nuclear reactor is designed for the Finnish and European district heating markets, as an environmentally sustainable heating option for the 2030s. While the carbon footprint of conventional electricity-producing …
View article: Advancement of functional expansion tallies capabilities in serpent 2
Advancement of functional expansion tallies capabilities in serpent 2 Open
View article: An introduction to Spent Nuclear Fuel decay heat for Light Water Reactors: a review from the NEA WPNCS
An introduction to Spent Nuclear Fuel decay heat for Light Water Reactors: a review from the NEA WPNCS Open
This paper summarized the efforts performed to understand decay heat estimation from existing spent nuclear fuel (SNF), under the auspices of the Working Party on Nuclear Criticality Safety (WPNCS) of the OECD Nuclear Energy Agency. Needs …
View article: Methodology, applications and performance of the CAD-based geometry type in the serpent 2 Monte Carlo code
Methodology, applications and performance of the CAD-based geometry type in the serpent 2 Monte Carlo code Open
The Serpent 2 Monte Carlo code features a CAD-based geometry option for the modeling of complicated and irregular systems. The methodology is based on the STL data format, which is commonly used for computer graphics and 3D printing, and s…
View article: Blind Benchmark Exercise for Spent Nuclear Fuel Decay Heat
Blind Benchmark Exercise for Spent Nuclear Fuel Decay Heat Open
The decay heat rate of five spent nuclear fuel assemblies of the pressurized water reactor type were measured by calorimetry at the interim storage for spent nuclear fuel in Sweden. Calculations of the decay heat rate of the five assemblie…
View article: Investigation of novel weight window methods in Serpent 2 for fusion neutronics applications
Investigation of novel weight window methods in Serpent 2 for fusion neutronics applications Open
Released in 2009, the Serpent Monte Carlo code has established itself as a highly efficient and powerful simulation code for nuclear systems analysis. Originally developed for reactor physics applications, the scope of the code now extends…
View article: Current Status and On-Going Development of VTT’s Kraken Core Physics Computational Framework
Current Status and On-Going Development of VTT’s Kraken Core Physics Computational Framework Open
The Kraken computational framework is a new modular calculation system designed for coupled core physics calculations. The development started at VTT Technical Research Centre of Finland in 2017, with the aim to replace VTT’s outdated lega…
View article: Methodology, Applications and Performance of the Cad-Based Geometry Type in the Serpent 2 Monte Carlo Code
Methodology, Applications and Performance of the Cad-Based Geometry Type in the Serpent 2 Monte Carlo Code Open
View article: Serpent transient analyses of GIACINT geometrical change experiments
Serpent transient analyses of GIACINT geometrical change experiments Open
View article: Microscopic cross section calculation methodology in the Serpent 2 Monte Carlo code
Microscopic cross section calculation methodology in the Serpent 2 Monte Carlo code Open
This paper describes the methodology used by the Monte Carlo particle transport code Serpent to produce homogenized microscopic cross sections. The microscopic cross sections can be used for multiple purposes for example in nodal programs.…
View article: Loss of Memory and Moment Bounds for Nonstationary Intermittent Dynamical Systems
Loss of Memory and Moment Bounds for Nonstationary Intermittent Dynamical Systems Open
View article: SERPENT2-SUBCHANFLOW-TRANSURANUS PIN-BY-PIN DEPLETION CALCULATIONS FOR A PWR FUEL ASSEMBLY
SERPENT2-SUBCHANFLOW-TRANSURANUS PIN-BY-PIN DEPLETION CALCULATIONS FOR A PWR FUEL ASSEMBLY Open
This work presents the results for a coupled neutronic-thermalhydraulic-thermomechanic pin-level depletion calculation of a PWR fuel assembly using Serpent2-SUBCHANFLOW-TRANSURANUS. This tool is based on a semi-implicit depletion scheme wi…
View article: EFFECT OF ENERGY DEPOSITION MODELLING IN COUPLED STEADY STATE MONTE CARLO NEUTRONICS/THERMAL HYDRAULICS CALCULATIONS
EFFECT OF ENERGY DEPOSITION MODELLING IN COUPLED STEADY STATE MONTE CARLO NEUTRONICS/THERMAL HYDRAULICS CALCULATIONS Open
In coupled calculations with Monte Carlo neutronics and thermal hydraulics the Monte Carlo code is used to produce a power distribution which in practice means tallying the energy deposition. Usually the energy deposition is estimated by m…
View article: A SUBCHANNEL COARSENING METHOD FOR Serpent2-SUBCHANFLOW APPLIED TO A FULL-CORE VVER PROBLEM
A SUBCHANNEL COARSENING METHOD FOR Serpent2-SUBCHANFLOW APPLIED TO A FULL-CORE VVER PROBLEM Open
This work presents a methodology to coarsen subchannel models to accelerate largescale Serpent2-SUBCHANFLOW calculations. The method is based on first building a fully detailed subchannel model and then combining subchannels into larger ch…
View article: ENHANCING THE PERFORMANCE OF FISSION SOURCE CONVERGENCE WITH FUNCTIONAL EXPANSION TALLIES IN SERPENT 2 MONTE CARLO CODE
ENHANCING THE PERFORMANCE OF FISSION SOURCE CONVERGENCE WITH FUNCTIONAL EXPANSION TALLIES IN SERPENT 2 MONTE CARLO CODE Open
This paper presents an upgrade to the built-in response matrix based solver implemented in Serpent 2 Monte Carlo code aiming to improve the fission source convergence when obtaining the forward solution to the k -eigenvalue criticality sou…
View article: THE McSAFE PROJECT - HIGH-PERFORMANCE MONTE CARLO BASED METHODS FOR SAFETY DEMONSTRATION: FROM PROOF OF CONCEPT TO INDUSTRY APPLICATIONS
THE McSAFE PROJECT - HIGH-PERFORMANCE MONTE CARLO BASED METHODS FOR SAFETY DEMONSTRATION: FROM PROOF OF CONCEPT TO INDUSTRY APPLICATIONS Open
The increasing use of Monte Carlo methods for core analysis is fostered by the huge and cheap computer power available nowadays e.g. in large HPC. Apart from the classical criticality calculations, the application of Monte Carlo methods fo…
View article: SERPENT/SUBCHANFLOW COUPLED CALCULATIONS FOR A VVER CORE AT HOT FULL POWER
SERPENT/SUBCHANFLOW COUPLED CALCULATIONS FOR A VVER CORE AT HOT FULL POWER Open
An increasing interest on the development of highly accurate methodologies in reactor physics is nowadays observed, mainly stimulated by the availability of vast computational resources. As a result, an on-going development of a wide range…
View article: SERPENT/SUBCHANFLOW COUPLED BURNUP CALCULATIONS FOR VVER FUEL ASSEMBLIES
SERPENT/SUBCHANFLOW COUPLED BURNUP CALCULATIONS FOR VVER FUEL ASSEMBLIES Open
The continuous improvement in nuclear industry safety standards and reactor designers’ and operators’ commercial goals represent a push for the development of highly accurate methodologies in reactor physics. This fact, combined with the a…
View article: HIGH FIDELITY AND REDUCED ORDER SOLUTIONS TO AN SMR-LEVEL PROGRESSION PROBLEM WITH THE KRAKEN COMPUTATIONAL FRAMEWORK
HIGH FIDELITY AND REDUCED ORDER SOLUTIONS TO AN SMR-LEVEL PROGRESSION PROBLEM WITH THE KRAKEN COMPUTATIONAL FRAMEWORK Open
Kraken is a new computational reactor analysis framework under development at VTT Technical Research Center of Finland Ltd. The framework builds heavily on the new generation of Finnish simulation codes such as the Serpent Monte Carlo code…
View article: EFFECT OF THE UNIFORM FISSION SOURCE METHOD ON LOCAL POWER VARIANCE IN FULL CORE SERPENT CALCULATION
EFFECT OF THE UNIFORM FISSION SOURCE METHOD ON LOCAL POWER VARIANCE IN FULL CORE SERPENT CALCULATION Open
One of challenges of the Monte Carlo full core simulations is to obtain acceptable statistical variance of local parameters throughout the whole reactor core at a reasonable computation cost. The statistical variance tends to be larger in …
View article: BENCHMARKING OF THE SERPENT 2 MONTE CARLO CODE FOR FUSION NEUTRONICS APPLICATIONS
BENCHMARKING OF THE SERPENT 2 MONTE CARLO CODE FOR FUSION NEUTRONICS APPLICATIONS Open
Analyses of radiation fields resulting from a deuterium-tritium (DT) plasma in fusion devices is a critical input to the design and validation of many aspects of the reactor design, including, shielding, material lifetime and remote mainte…
View article: Serpent/SUBCHANFLOW pin-by-pin coupled transient calculations for the SPERT-IIIE hot full power tests
Serpent/SUBCHANFLOW pin-by-pin coupled transient calculations for the SPERT-IIIE hot full power tests Open
View article: EU FP7 Project: HPMC-High Performance Monte Carlo (HPMC) Rector Core Analysis (Proof of Concept)
EU FP7 Project: HPMC-High Performance Monte Carlo (HPMC) Rector Core Analysis (Proof of Concept) Open
View article: McSAFE- High performance monte Carlo Methods for SAFETy Demonstration
McSAFE- High performance monte Carlo Methods for SAFETy Demonstration Open
View article: Benchmark of Serpent-2 with MCNP: application to EU fusion DEMO HCPB breeding blanket
Benchmark of Serpent-2 with MCNP: application to EU fusion DEMO HCPB breeding blanket Open
View article: Serpent and TRIPOLI-4® transient calculations comparisons for several reactivity insertion scenarios in a 3D PWR minicore benchmark
Serpent and TRIPOLI-4® transient calculations comparisons for several reactivity insertion scenarios in a 3D PWR minicore benchmark Open
View article: High-fidelity multiphysics simulations for Light Water Reactors in the McSAFE H2020 project
High-fidelity multiphysics simulations for Light Water Reactors in the McSAFE H2020 project Open
View article: Development of a Spatial Domain Decomposition Scheme for Monte Carlo Neutron Transport
Development of a Spatial Domain Decomposition Scheme for Monte Carlo Neutron Transport Open
The computing power available nowadays to the average Monte-Carlo-code user is sufficient to perform large-scale neutron transport simulations, such as full-core burnup or high-fidelity multiphysics. In practice however, software limitatio…