dassh-dev / dassh
Ducted Assembly Steady State Heat Transfer Software (DASSH)
☆17Updated last year
Alternatives and similar repositories for dassh:
Users that are interested in dassh are comparing it to the libraries listed below
- ☆30Updated last week
- Stochastic Calculator Of Neutron transport Equation☆40Updated last month
- ENRICO: Exascale Nuclear Reactor Investigative COde☆64Updated last year
- The National Reactor Innovation Center's (NRIC) Virtual Test Bed Repository☆52Updated this week
- OpenMC wrapped as a Moose App☆16Updated last year
- A deterministic finite-element-based solver for the neutron transport equation designed for the evaluation of acceleration methods.☆27Updated 3 years ago
- open-source Sn software☆25Updated this week
- Workflow and Template Toolkit for Simulation (WATTS)☆25Updated 6 months ago
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆55Updated 2 weeks ago
- List of open source projects related to OpenMC☆24Updated 6 months ago
- Native plotting GUI for model design and verification☆55Updated last month
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆40Updated 8 months ago
- Tools to translate between different CSG geometry types☆36Updated last year
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆33Updated 2 months ago
- ☆18Updated last week
- Format description for ACE nuclear data files☆20Updated 2 years ago
- Collection of models for reactor physics benchmarks☆51Updated 5 months ago
- curated documents pertaining to early molten salt reactor research.☆22Updated 11 months ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- Convert OpenMC Geometry Components to CAD☆16Updated 3 months ago
- Python ENDF Parser☆28Updated 7 months ago
- Vim plugin for MOOSE Framework input file format☆12Updated last year
- Framework for REsearch in Nuclear ScIence and Engineering☆14Updated 3 years ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆60Updated last week
- Tool for converting MCNP input files to OpenMC classes/XML☆37Updated 2 weeks ago
- Sampling nuclear data and uncertainty☆50Updated last month
- Papillon Nuclear Data Library☆14Updated 6 months ago
- A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.☆11Updated 9 months ago