arfc / saltprocLinks
Online reprocessing for molten salt reactors
☆20Updated 2 months ago
Alternatives and similar repositories for saltproc
Users that are interested in saltproc are comparing it to the libraries listed below
Sorting:
- Simulation of transmutation and decay in nuclear systems☆28Updated 5 months ago
- detailed cad model of the msre☆37Updated 4 months ago
- Repository for Moltres, a code for simulating Molten Salt Reactors☆69Updated 3 weeks ago
- Framework for REsearch in Nuclear ScIence and Engineering☆15Updated 3 years ago
- Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.☆22Updated last month
- Collection of scripts for managing data for OpenMC☆33Updated 5 months ago
- Native plotting GUI for model design and verification☆59Updated 5 months ago
- Monte Carlo Particle Lists☆32Updated last week
- Sampling nuclear data and uncertainty☆51Updated last week
- Workflow and Template Toolkit for Simulation (WATTS)☆32Updated last month
- Stochastic Calculator Of Neutron transport Equation☆44Updated 2 weeks ago
- ERSN-OpenMC is a Graphical User Interface for OpenMC Monte Carlo particle transport simulation code, originally developed by Jaafar EL Ba…☆30Updated last year
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆58Updated 2 months ago
- List of open source projects related to OpenMC☆26Updated 3 weeks ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆47Updated this week
- THOR is a radiation transport code for unstructured meshes.☆14Updated 9 months ago
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆32Updated this week
- MC/DC: Monte Carlo Dynamic Code☆41Updated 2 months ago
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆41Updated last year
- The Advanced Dimensional Depletion for Engineering of Reactors (ADDER) Software☆18Updated 11 months ago
- Format description for ACE nuclear data files☆21Updated 3 years ago
- open-source Sn software☆35Updated last week
- OpenMC Monte Carlo Code☆18Updated 4 months ago
- Tools to translate between different CSG geometry types☆38Updated last month
- ENRICO: Exascale Nuclear Reactor Investigative COde☆65Updated last year
- A tool for making reproducible materials and standardizing use across several neutronics codes☆24Updated 8 months ago
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆11Updated 2 years ago
- Tool for converting MCNP input files to OpenMC classes/XML☆42Updated last month
- An Open Nuclear Reactor Simulator and Reactor Core Analysis Tool☆24Updated 4 years ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆16Updated last month