Results 41 to 50 of about 538 (156)
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
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
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
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
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
fusion-energy/openmc-dagmc-wrapper: v0.1.1
Added support for tet mesh based ...
Jonathan Shimwell
core +1 more source
Fuel Performance Comparison of Uranium Nitride and Uranium Carbide in VVER-1200 using OpenMC [PDF]
Nuclear power is a reliable and large-scale source of GHG-free electricity. This study asses the viability of ATF fuel of uranium nitride (UN) and uranium carbide (UC) as fuel for the VVER-1200 reactor.
Jamil Meekal, Ali Majid
doaj +1 more source
openmc-dev/openmc: OpenMC 0.11.0
This release of OpenMC adds several major new features: depletion, photon transport, and support for CAD geometries through DAGMC. In addition, the core codebase has been rewritten in C++14 (it was previously written in Fortran 2008).
Isaac Meyer +29 more
core +1 more source
Penelitian bahan bakar reaktor riset saat ini mengarah pada peningkatan densitas uranium untuk menghasilkan fluks neutron yang lebih tinggi dalam rangka peningkatan produksi radioisotop serta efisiensi dan akurasi pada berbagai pengujian material ...
Saga Octadamailah +2 more
doaj +1 more source

