Performance Portable Monte Carlo Particle Transport on Intel, NVIDIA, and AMD GPUs [PDF]
OpenMC is an open source Monte Carlo neutral particle transport application that has recently been ported to GPU using the OpenMP target offloading model.
Tramm John +7 more
doaj +1 more source
Direct Doppler broadening in Monte Carlo simulations using the multipole representation [PDF]
A new approach for direct Doppler broadening of nuclear data in Monte Carlo simulations is proposed based on the multipole representation. The multipole representation transforms resonance parameters into a set of poles and residues only some of which ...
Forget, Benoit Robert Yves +2 more
core +1 more source
Improved cache performance in Monte Carlo transport calculations using energy banding [PDF]
We present an energy banding algorithm for Monte Carlo (MC) neutral particle transport simulations which depend on large cross section lookup tables. In MC codes, read-only cross section data tables are accessed frequently, exhibit poor locality, and are
Beckman, P. +5 more
core +1 more source
IMPACT OF NUCLEAR DATA LIBRARIES ON PREDICTED FAST REACTOR PERFORMANCE [PDF]
The nuclear data evaluation process inherently yields a nuclear data set designed to produce accurate results for the neutron energy spectra corresponding to a specific benchmark suite of experiments.
Nelson A.G., Ramey K.M., Heidet F.
doaj +1 more source
Test Results of Variance Reduction Techniques Applied to Deep Penetration Problem
Nowadays, there is a problem of a lack of computer power to conduct high-precision reactor analysis. There are several factors that increase the excessive computational load and make it difficult to calculate nuclear reactor full-scale models using Monte
E. V. Bogdanova, G. V. Tikhomirov
doaj +1 more source
Abstract Cosmic‐ray neutron sensing (CRNS) is a promising non‐invasive technique to estimate snow water equivalent (SWE) over large areas. In contrast to preliminary studies focusing on shallow snow conditions (SWE 130 mm), more recently the method was shown experimentally to be sensitive also to deeper snowpacks providing the basis for its use at ...
P. Schattan +4 more
wiley +1 more source
Development of continuous-energy sensitivity analysis capability in OpenMC [PDF]
Abstract The iterated fission probability (IFP) method and the Contributon-Linked eigenvalue sensitivity/Uncertainty estimation via Track length importance CHaracterization (CLUTCH) method have been implemented in several Monte Carlo codes to perform sensitivity calculations.
Xingjie Peng +4 more
openaire +2 more sources
Evaluation of simulated HPGe detector efficiencies in OpenMC compared to MCNP
In late 2023, the open-source radiation transport code OpenMC introduced a pulse-height tally (PHT) feature, enabling users to track the total energy deposited by individual photons in OpenMC cells.
Ethan Bauer +2 more
doaj +1 more source
Integrating ytopt and libEnsemble to autotune OpenMC
Ytopt is a Python machine-learning-based autotuning software package developed within the ECP PROTEAS-TUNE project. The ytopt software adopts an asynchronous search framework that consists of sampling a small number of input parameter configurations and progressively fitting a surrogate model over the input-output space until exhausting the user ...
Xingfu Wu +9 more
openaire +2 more sources
Efek Penambahan Protaktinium-231 (Pa-231) pada Nilai Faktor Multiplikasi Efektif Reaktor PWR Berbahan Bakar ThN-U233N [PDF]
This study aims to determine the optimum percentage of addition of protactinium-231 in a ThN-U233N fueled PWR reactor.In ThN-U233N, uranium-233 is used as the fissile material.
Afriani, Meirita Dwi +3 more
core +2 more sources

