Han Gyu Joo
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View article: Tracing the Formation History of Intrahalo Light with Horizon Run 5
Tracing the Formation History of Intrahalo Light with Horizon Run 5 Open
We investigate the formation history of intrahalo light (IHL) using the high-resolution (~1 kpc), large-scale (~Gpc) cosmological hydrodynamical simulation, Horizon Run 5 (HR5). IHL particles are identified by carefully considering both th…
View article: Stabilization and Optimization of High-Fidelity Multiphysics Simulations for Extended Applications
Stabilization and Optimization of High-Fidelity Multiphysics Simulations for Extended Applications Open
View article: Nodal method for handling irregularly deformed geometries in hexagonal lattice cores
Nodal method for handling irregularly deformed geometries in hexagonal lattice cores Open
The hexagonal nodal code RENUS has been enhanced to handle irregularly deformed hexagonal assemblies. The underlying RENUS methods involving triangle-based polynomial expansion nodal (T-PEN) and corner point balance (CPB) were extended in …
View article: Practical methods for GPU-based whole-core Monte Carlo depletion calculation
Practical methods for GPU-based whole-core Monte Carlo depletion calculation Open
Several practical methods for accelerating the depletion calculation in a GPU-based Monte Carlo (MC) code PRAGMA are presented including the multilevel spectral collapse method and the vectorized Chebyshev rational approximation method (CR…
View article: Development of Scalable Gpu-Based Direct Whole-Core Depletion Calculation Methods
Development of Scalable Gpu-Based Direct Whole-Core Depletion Calculation Methods Open
View article: Analyses of on-the-fly generation of spectral superhomogenization factors for multigroup whole core calculation employing pin-wise slowing-down solutions
Analyses of on-the-fly generation of spectral superhomogenization factors for multigroup whole core calculation employing pin-wise slowing-down solutions Open
On-the-fly(OTF) generation of Spectral Superhomogenization(SSPH) factors is analyzed in the multigroup(MG) whole core calculation employing pin-wise continuous energy(CE) slowing-down solutions. The motivation for the work is to avoid the …
View article: Validation of the novel core solver nTRACER/COBRA-TF for full core high fidelity cycle analysis of VVERs
Validation of the novel core solver nTRACER/COBRA-TF for full core high fidelity cycle analysis of VVERs Open
This work is focused on the expansion of the Laboratory of Reactor Physics and Thermal-Hydraulics (LRT) of PSI multi-physics high-resolution core solver nTF/CTF to full core cycle analysis for VVERs. The development and code modifications …
View article: Verification and validation of the high-resolution code nTF with VVER-1000 hot zero power monte carlo calculations and experimental data
Verification and validation of the high-resolution code nTF with VVER-1000 hot zero power monte carlo calculations and experimental data Open
Novel codes allow the prediction of parameters with increased resolution, in comparison to the conventional approach, sometimes using meshing smaller than the size of the fuel pin. Optimally, complex geometric struc-tures, like the ones in…
View article: Methods and Performance of a GPU-Based Pinwise Two-Step Nodal Code VANGARD
Methods and Performance of a GPU-Based Pinwise Two-Step Nodal Code VANGARD Open
View article: Convergence analysis of fixed-point iteration with Anderson Acceleration on a simplified neutronics/thermal-hydraulics system
Convergence analysis of fixed-point iteration with Anderson Acceleration on a simplified neutronics/thermal-hydraulics system Open
In-depth convergence analyses for neutronics/thermal-hydraulics (T/H) coupled calculations are performed to investigate the performance of nonlinear methods based on the Fixed-Point Iteration (FPI). A simplified neutronics-T/H coupled syst…
View article: High performance 3D pin-by-pin neutron diffusion calculation based on 2D/1D decoupling method for accurate pin power estimation
High performance 3D pin-by-pin neutron diffusion calculation based on 2D/1D decoupling method for accurate pin power estimation Open
View article: RECENT CAPABILITY AND PERFORMANCE ENHANCEMENTS OF THE WHOLE-CORE TRANSPORT CODE nTRACER
RECENT CAPABILITY AND PERFORMANCE ENHANCEMENTS OF THE WHOLE-CORE TRANSPORT CODE nTRACER Open
The whole-core transport code nTRACER has made many advances in recent years. Several innovative cross section treatment methods were developed, a new axial transport solver was introduced for stabilizing the 2D/1D scheme, and substantial …
View article: Analysis of C5G7-TD benchmark with a multi-group pin homogenized SP3 code SPHINCS
Analysis of C5G7-TD benchmark with a multi-group pin homogenized SP3 code SPHINCS Open
View article: Domain decomposition for GPU-Based continuous energy Monte Carlo power reactor calculation
Domain decomposition for GPU-Based continuous energy Monte Carlo power reactor calculation Open
A domain decomposition (DD) scheme for GPU-based Monte Carlo (MC) calculation which is essential for whole-core depletion is introduced within the framework of the modified history-based tracking algorithm. Since GPU-offloaded MC calculati…
View article: Development of a drift-flux model based core thermal-hydraulics code for efficient high-fidelity multiphysics calculation
Development of a drift-flux model based core thermal-hydraulics code for efficient high-fidelity multiphysics calculation Open
The methods and performance of a pin-level nuclear reactor core thermal-hydraulics (T/H) code ESCOT employing the drift-flux model are presented. This code aims at providing an accurate yet fast core thermal-hydraulics solution capability …
View article: Development of a fast reactor multigroup cross section generation code EXUS-F capable of direct processing of evaluated nuclear data files
Development of a fast reactor multigroup cross section generation code EXUS-F capable of direct processing of evaluated nuclear data files Open
The methods and performance of a fast reactor multigroup cross section (XS) generation code EXUS-F are described that is capable of directly processing Evaluated Nuclear Data File format nuclear data files. RECONR of NJOY is used to genera…
View article: Special issue on International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering 2017 (M&C 2017)
Special issue on International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering 2017 (M&C 2017) Open
View article: Practical resolution of angle dependency of multigroup resonance cross sections using parametrized spectral superhomogenization factors
Practical resolution of angle dependency of multigroup resonance cross sections using parametrized spectral superhomogenization factors Open
Based on the observation that ignoring the angle dependency of multigroup resonance cross sections within a fuel pellet would result in nontrivial underestimation of the spatial self-shielding of flux, a parametrized spectral superhomogeni…
View article: Analysis of alpha modes in multigroup diffusion
Analysis of alpha modes in multigroup diffusion Open
The alpha eigenvalue problem in multigroup neutron diffusion is studied with particular attention to the theoretical analysis of the model. Contrary to previous literature results, the existence of eigenvalue and eigenflux clustering is in…
View article: An Offline Electronic Payment System Based on an Untraceable Blind Signature Scheme
An Offline Electronic Payment System Based on an Untraceable Blind Signature Scheme Open
This paper proposes a new offline electronic payment (e-payment) system that satisfies the major security requirements of e-payment, i.e. anonymity, unlinkability, unforgeability, double spending control, conditional traceability, and frau…
View article: Subgroup Benchmark Calculations for the Intra-Pellet Nonuniform Temperature Cases
Subgroup Benchmark Calculations for the Intra-Pellet Nonuniform Temperature Cases Open
A benchmark suite has been developed by Seoul National University (SNU) for intrapellet nonuniform temperature distribution cases based on the practical temperature profiles according to the thermal power levels. Though a new subgroup capa…
View article: Pointwise cross-section-based on-the-fly resonance interference treatment with intermediate resonance approximation
Pointwise cross-section-based on-the-fly resonance interference treatment with intermediate resonance approximation Open
This is an Open Access article distributed under the terms of the Creative Commons Attribution Non-Commercial License (http://creativecommons.org/licenses/by-nc/3.0) which permits unrestricted non-commercial use, distribution, and reproduc…
View article: Solution of the BEAVRS benchmark using the nTRACER direct whole core calculation code
Solution of the BEAVRS benchmark using the nTRACER direct whole core calculation code Open
The BEAVRS (Benchmark for Evaluation and Validation of Reactor Simulation) benchmark is solved by the nTRACER direct whole core calculation code to assess its accuracy and to examine the solution dependence on modeling parameters. A sophis…