lanl / CGMF
CGMF nuclear fission fragment de-excitation statistical code
☆25Updated 11 months ago
Alternatives and similar repositories for CGMF:
Users that are interested in CGMF are comparing it to the libraries listed below
- A deterministic finite-element-based solver for the neutron transport equation designed for the evaluation of acceleration methods.☆27Updated 3 years ago
- Collection of scripts for managing data for OpenMC☆29Updated last month
- Framework for REsearch in Nuclear ScIence and Engineering☆14Updated 3 years ago
- Workflow and Template Toolkit for Simulation (WATTS)☆25Updated 6 months ago
- ONIX is an open-source depletion software for nuclear reactor simulations and nuclear archaeology. It is written in Python 3 and offers c…☆39Updated 2 months ago
- List of open source projects related to OpenMC☆24Updated 6 months ago
- OpenMC Monte Carlo Code☆17Updated last month
- Format description for ACE nuclear data files☆20Updated 2 years ago
- Sampling nuclear data and uncertainty☆50Updated last month
- Stochastic Calculator Of Neutron transport Equation☆40Updated last month
- A tool for making reproducible materials and standardizing use across several neutronics codes☆23Updated 5 months ago
- ENRICO: Exascale Nuclear Reactor Investigative COde☆64Updated last year
- Tool for converting MCNP input files to OpenMC classes/XML☆37Updated 2 weeks ago
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆40Updated 8 months ago
- Monte Carlo Particle Lists☆30Updated last year
- Simulation of transmutation and decay in nuclear systems☆28Updated last month
- Python ENDF Parser☆28Updated 7 months ago
- The nuclear reaction model code☆35Updated last week
- JADE, a novel nuclear data libraries V&V tool☆25Updated this week
- ENDF/B pre-processing codes (PREPRO)☆17Updated last year
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆55Updated 2 weeks ago
- ☆18Updated last week
- For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data☆28Updated last month
- continuous energy monte carlo neutron transport in general geometries on GPUs☆43Updated 7 years ago
- Native plotting GUI for model design and verification☆55Updated last month
- Toolkit for reading and interacting with ENDF-6 formatted files☆37Updated last week
- open-source Sn software☆25Updated this week
- Tools to translate between different CSG geometry types☆36Updated last year
- Papillon Nuclear Data Library☆14Updated 6 months ago
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆10Updated 2 years ago