anl-rtr / adderLinks
The Advanced Dimensional Depletion for Engineering of Reactors (ADDER) Software
☆17Updated 11 months ago
Alternatives and similar repositories for adder
Users that are interested in adder are comparing it to the libraries listed below
Sorting:
- Stochastic Calculator Of Neutron transport Equation☆43Updated 3 weeks ago
- Ducted Assembly Steady State Heat Transfer Software (DASSH)☆17Updated 2 years ago
- Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.☆22Updated 3 weeks ago
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆57Updated last month
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated this week
- List of open source projects related to OpenMC☆26Updated last week
- open-source Sn software☆34Updated this week
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- API for parsing and post-processing many MC simulations related files☆17Updated last week
- Format description for ACE nuclear data files☆21Updated 3 years ago
- Tool for converting MCNP input files to OpenMC classes/XML☆42Updated 2 weeks ago
- Tools to translate between different CSG geometry types☆37Updated last week
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆70Updated 3 weeks ago
- Accelerated Discretized Geometry☆17Updated this week
- Python ENDF Parser☆33Updated 10 months ago
- A deterministic finite-element-based solver for the neutron transport equation designed for the evaluation of acceleration methods.☆26Updated 4 years ago
- Sampling nuclear data and uncertainty☆51Updated last month
- Framework for REsearch in Nuclear ScIence and Engineering☆15Updated 3 years ago
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆40Updated 11 months ago
- Computational inputs, reference outputs and experimental data for V&V systems☆13Updated last month
- Native plotting GUI for model design and verification☆58Updated 4 months ago
- Convert OpenMC Geometry Components to CAD☆18Updated 6 months ago
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆34Updated 2 months ago
- JADE, a novel nuclear data libraries V&V tool☆29Updated this week
- ☆30Updated 3 months ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆16Updated 3 weeks ago
- The National Reactor Innovation Center's (NRIC) Virtual Test Bed Repository☆53Updated last week
- A Python package for parsing FISPACT-II output☆28Updated last week
- NJOY for the 21st Century☆79Updated last year
- ☆79Updated last year