imronuke / ADPRESLinks
An Open Nuclear Reactor Simulator and Reactor Core Analysis Tool
☆26Updated 4 years ago
Alternatives and similar repositories for ADPRES
Users that are interested in ADPRES are comparing it to the libraries listed below
Sorting:
- Open Nuclear Reactor Simulator☆61Updated 3 months ago
- Stochastic Calculator Of Neutron transport Equation☆47Updated last week
- Collection of scripts for managing data for OpenMC☆33Updated 6 months ago
- Machine learning and artificial intelligence benchmarking library for nuclear engineering applications.☆30Updated 2 months ago
- THOR is a radiation transport code for unstructured meshes.☆14Updated 10 months ago
- Framework for REsearch in Nuclear ScIence and Engineering☆15Updated 3 years ago
- Native plotting GUI for model design and verification☆60Updated 6 months ago
- ENRICO: Exascale Nuclear Reactor Investigative COde☆65Updated 2 years ago
- XSPlot - Neutron cross section plotter for isotopes☆14Updated 2 years ago
- High-Fidelity Multiphysics☆116Updated this week
- Sampling nuclear data and uncertainty☆52Updated last month
- Direct Accelerated Geometry Monte Carlo Toolkit☆112Updated 5 months ago
- Repository for Moltres, a code for simulating Molten Salt Reactors☆70Updated this week
- A deterministic finite-element-based solver for the neutron transport equation designed for the evaluation of acceleration methods.☆27Updated 4 years ago
- Papillon Nuclear Data Library☆17Updated 3 weeks ago
- This repository holds codes from the book Computational Nuclear Engineering and Radiological Science with Python☆15Updated 5 years ago
- In this project we develop an OpenNTP package to solve the multi-group neutron transport equation.☆13Updated 4 years ago
- A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…☆156Updated last week
- MC/DC: Monte Carlo Dynamic Code☆43Updated 3 months ago
- Python ENDF Parser☆34Updated last year
- OpenMC wrapped as a Moose App☆16Updated 2 years ago
- The National Reactor Innovation Center's (NRIC) Virtual Test Bed Repository☆58Updated this week
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆42Updated last year
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆61Updated 3 months ago
- continuous energy monte carlo neutron transport in general geometries on GPUs☆43Updated 8 years ago
- Collection of validation scripts, notebooks, results☆11Updated last year
- Helios - A C++ Monte Carlo Neutron Transport Code☆19Updated 5 years ago
- Create parametric 3D fusion reactor CAD and neutronics models☆86Updated this week
- Example Jupyter notebooks for OpenMC☆37Updated 5 months ago
- Workflow and Template Toolkit for Simulation (WATTS)☆32Updated last month