关注
Ilham Variansyah
Ilham Variansyah
Assistant Professor, Senior Research, Oregon State University
在 oregonstate.edu 的电子邮件经过验证
标题
引用次数
引用次数
年份
Analysis of population control techniques for time-dependent and eigenvalue Monte Carlo neutron transport calculations
I Variansyah, RG McClarren
Nuclear Science and Engineering 196 (11), 1280-1305, 2022
15*2022
Multigroup constant calculation with static α-eigenvalue Monte Carlo for time-dependent neutron transport simulations
I Variansyah, BR Betzler, WR Martin
Nuclear Science and Engineering 194 (11), 1025-1043, 2020
132020
Variable dynamic mode decomposition for estimating time eigenvalues in nuclear systems
E Smith, I Variansyah, R McClarren
Nuclear Science and Engineering 197 (8), 1769-1778, 2023
112023
Development of MC/DC: a performant, scalable, and portable Python-based Monte Carlo neutron transport code
I Variansyah, JP Morgan, J Northrop, KE Niemeyer, RG McClarren
arXiv preprint arXiv:2305.07636, 2023
112023
Metaheuristic Optimization Tool
I Variansyah, JW Bae, BR Betzler, G Ilas
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2020
72020
A Quasi–Monte Carlo Method With Krylov Linear Solvers for Multigroup Neutron Transport Simulations
S Pasmann, I Variansyah, CT Kelley, R McClarren
Nuclear Science and Engineering 197 (6), 1159-1173, 2023
62023
An effective initial particle sampling technique for Monte Carlo reactor transient simulations
I Variansyah, RG McClarren
arXiv preprint arXiv:2305.07646, 2023
52023
iQMC: Iterative Quasi-Monte Carlo for k-Eigenvalue Neutron Transport Simulations
S Pasmann, I Variansyah, CT Kelley, RG McClarren
arXiv preprint arXiv:2306.11600, 2023
32023
High-fidelity treatment for object movement in time-dependent Monte Carlo transport simulations
I Variansyah, RG McClarren
arXiv preprint arXiv:2305.07641, 2023
32023
Performance of Population Control Techniques in Monte Carlo Reactor Criticality Simulations
I Variansyah, RG McClarren
Proc. PHYSOR, 2022
32022
A Robust Second-Order Multiple Balance Method for Time-Dependent Neutron Transport Simulations
I Variansyah, EW Larsen, WR Martin
EPJ Web of Conferences 247, 03024, 2021
32021
α-weighted Transition Rate Matrix Method
I Variansyah, BR Betzler, WR Martin
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2019
32019
Reducing Spatial Discretization Error with Linear Discontinuous Source Tilting in Iterative Quasi-Monte Carlo for Neutron Transport
S Pasmann, I Variansyah, CT Kelley, RG McClarren
arXiv preprint arXiv:2306.14877, 2023
22023
A metaheuristic optimization tool for high flux isotope reactor low-enriched uranium core design
I Variansyah, B Betzler, D Chandler, G Ilas, WR Martin
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2019
22019
Mitigating Spatial Error in the Iterative Quasi–Monte Carlo (iQMC) Method for Neutron Transport Simulations with Linear Discontinuous Source Tilting and Effective Scattering …
S Pasmann, I Variansyah, CT Kelley, RG McClarren
Nuclear Science and Engineering, 1-16, 2024
12024
An Alternative to Stride-Based RNG for Monte Carlo Transport
BS Cuneo, I Variansyah
arXiv preprint arXiv:2403.06362, 2024
12024
Monte Carlo/Dynamic Code (MC/DC): An accelerated Python package for fully transient neutron transport and rapid methods development
JP Morgan, I Variansyah, SL Pasmann, KB Clements, B Cuneo, A Mote, ...
Journal of Open Source Software 9 (96), 6415, 2024
2024
Development of Machine Learning Model for Neutron Clustering Classification in Monte Carlo Criticality Simulation
AR Hakim, I Variansyah, DA Fynan
Canadian Nuclear Society, American Nuclear Society, 2023
2023
Exploring One-Cell Inversion Method for Transient Transport on GPU
JP Morgan, I Variansyah, TS Palmer, KE Niemeyer
arXiv preprint arXiv:2305.13555, 2023
2023
A Robust Second-Order Multiple Balance Method and Alpha-Weighted Multigroup Constants for Time-Dependent Nuclear Reactor Simulations
I Variansyah
2021
系统目前无法执行此操作,请稍后再试。
文章 1–20