16 citations · 25 across the 18 of their papers we have counts for
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Compressed Sensing Methods for Memory Reduction in Monte Carlo Simulations
Ethan Lame, Camille Palmer, Todd Palmer +1
Monte Carlo simulations of neutronic systems are computationally intensive and demand significant memory resources for high-fidelity modeling. Compressed sensing enables accurate r…
Hybrid Delta Tracking Schemes Using a Track-Length Estimator
Joanna Piper Morgan, Ilham Variansyah, Kayla B. Clements +2
In Monte Carlo radiation transport calculations, Woodcock-delta tracking is a common alternative to the more popular surface tracking technique. In this work we introduce a delta-t…
Interplay of Variance Reduction and Population Control in Monte Carlo Neutron Transport
Jordan Northrop, Ilham Variansyah, Todd Palmer +1
Monte Carlo methods are widely used for neutron transport simulations at least partly because of the accuracy they bring to the modeling of these problems. However, the computation…
Comparing the Performance of MC/DC's on-GPU Event-based Processing Methods in Multigroup and Continuous-energy Problems
Braxton Cuneo, Joanna Piper Morgan, Ilham Variansyah +1
Monte Carlo / Dynamic Code (MC/DC) is a portable Monte Carlo neutron transport package for rapid numerical methods exploration in heterogeneous and HPC contexts, developed under th…
One-Cell Inversion for Solving Higher-Order Time-Dependent Radiation Transport on GPUs
Joanna Piper Morgan, Ilham Variansyah, Todd S. Palmer +1
To find deterministic solutions to the transient discrete-ordinates neutron-transport equation, source iterations (SI) are typically used to lag the scattering (and fission) source…
Derivative Source Method for Monte Carlo Transport Calculation of Sensitivities to Material Densities and Dimensions
Ilham Variansyah, Ryan G. McClarren, Todd S. Palmer
The Derivative Source Method (DSM) takes derivatives of a particle transport equation with respect to selected parameters and solves them via the standard Monte Carlo random walk s…
Implicit Collision Multiplicity Adjustment for Efficient Monte Carlo Transport Simulation of Reactivity Excursion
Ilham Variansyah, Ryan G. McClarren, Todd S. Palmer
We present an implicit collision method with on-the-fly multiplicity adjustment based on the forward weight window methodology for efficient Dynamic Monte Carlo (MC) simulation of…
A Batch Power Iteration Approach for the Iterative Quasi-Monte Carlo Method Using a Randomized-Halton Sequence
Samuel Pasmann, Ilham Variansyah, C. T. Kelley +1
The Iterative Quasi-Monte Carlo (iQMC) method is a recently developed hybrid method for neutron transport simulations. iQMC replaces standard quadrature techniques used in determin…
Enabling GPU Portability into the Numba-JITed Monte Carlo Particle Transport Code MC/DC
Joanna Piper Morgan, Braxton Cuneo, Ilham Variansyah +1
The Center for Exascale Monte Carlo Neutron Transport is developing Monte Carlo / Dynamic Code (MC/DC) as a portable Monte Carlo neutron transport package for rapid numerical metho…
Performance Portable Monte Carlo Neutron Transport in MCDC via Numba
Joanna Piper Morgan, Ilham Variansyah, Braxton Cuneo +2
Finding a software engineering approach that allows for portability, rapid development, and open collaboration for high-performance computing on GPUs and CPUs is a challenge. We im…
An Alternative to Stride-Based RNG for Monte Carlo Transport
Braxton S. Cuneo, Ilham Variansyah
The techniques used to generate pseudo-random numbers for Monte Carlo (MC) applications bear many implications on the quality and speed of that programs work. As a random number ge…
Mitigating Spatial Error in the iterative-Quasi-Monte Carlo (iQMC) Method for Neutron Transport Simulations with Linear Discontinuous Source Tilting and Effective Scattering and Fission Rate Tallies
Samuel Pasmann, Ilham Variansyah, C. T. Kelley +1
The iterative Quasi-Monte Carlo (iQMC) method is a recently proposed method for multigroup neutron transport simulations. iQMC can be viewed as a hybrid between deterministic itera…
Reducing Spatial Discretization Error with Linear Discontinuous Source Tilting in Iterative Quasi-Monte Carlo for Neutron Transport
Samuel Pasmann, Ilham Variansyah, C. T. Kelley +1
Recently, iterative Quasi-Monte Carlo (iQMC) was introduced as a new method of neutron transport which combines deterministic iterative methods and quasi-Monte Carlo simulation for…
iQMC: Iterative Quasi-Monte Carlo for k-Eigenvalue Neutron Transport Simulations
Samuel Pasmann, Ilham Variansyah, C. T. Kelley +1
The Iterative Quasi-Monte Carlo method, or iQMC, replaces standard quadrature techniques used in deterministic linear solvers with Quasi-Monte Carlo simulation for more accurate an…
An effective initial particle sampling technique for Monte Carlo reactor transient simulations
Ilham Variansyah, Ryan G. McClarren
We propose a technique to effectively sample initial neutron and delayed neutron precursor particles for Monte Carlo (MC) simulations of typical off-critical reactor transients. Th…
High-fidelity treatment for object movement in time-dependent Monte Carlo transport simulations
Ilham Variansyah, Ryan G. McClarren
We investigate the use of time-dependent surfaces in Monte Carlo transport simulation to accurately model prescribed, continuous object movements. The performance of the continuous…
Development of MC/DC: a performant, scalable, and portable Python-based Monte Carlo neutron transport code
Ilham Variansyah, J. P. Morgan, Jordan Northrop +2
We discuss the current development of MC/DC (Monte Carlo Dynamic Code). MC/DC is primarily designed to serve as an exploratory Python-based MC transport code. However, it seeks to…
Exploring One-Cell Inversion Method for Transient Transport on GPU
J. P. Morgan, Ilham Variansyah, Todd S. Palmer +1
To find deterministic solutions to the transient neutron transport equation, iterative schemes are typically used to treat the scattering (and fission) source terms. We explo…
A Quasi-Monte Carlo Method with Krylov Linear Solvers for Multigroup Neutron Transport Simulations
Sam Pasmann, Ilham Variansyah, C. T. Kelley +1
In this work we investigate replacing standard quadrature techniques used in deterministic linear solvers with a fixed-seed Quasi-Monte Carlo calculation to obtain more accurate an…
Variable Dynamic Mode Decomposition for Estimating Time Eigenvalues in Nuclear Systems
Ethan Smith, Ilham Variansyah, Ryan McClarren
We present a new approach to calculating time eigenvalues of the neutron transport operator (also known as eigenvalues) by extending the dynamic mode decomposition (DMD) to all…
Analysis of Population Control Techniques for Time-Dependent and Eigenvalue Monte Carlo Neutron Transport Calculations
Ilham Variansyah, Ryan G. McClarren
An extensive study of population control techniques (PCTs) for time-dependent and eigenvalue Monte Carlo (MC) neutron transport calculations is presented. We define PCT as a techni…