dassh-dev / dasshLinks
Ducted Assembly Steady State Heat Transfer Software (DASSH)
☆18Updated last week
Alternatives and similar repositories for dassh
Users that are interested in dassh are comparing it to the libraries listed below
Sorting:
- Stochastic Calculator Of Neutron transport Equation☆45Updated this week
- ENRICO: Exascale Nuclear Reactor Investigative COde☆65Updated last year
- The National Reactor Innovation Center's (NRIC) Virtual Test Bed Repository☆57Updated this week
- ☆31Updated 3 weeks ago
- OpenMC wrapped as a Moose App☆16Updated 2 years ago
- A deterministic finite-element-based solver for the neutron transport equation designed for the evaluation of acceleration methods.☆27Updated 4 years ago
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆41Updated last year
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆59Updated 3 months ago
- open-source Sn software☆36Updated last week
- High-Fidelity Multiphysics☆114Updated this week
- Format description for ACE nuclear data files☆21Updated 3 years ago
- Python ENDF Parser☆34Updated 11 months ago
- The Advanced Dimensional Depletion for Engineering of Reactors (ADDER) Software☆18Updated last year
- Tools to translate between different CSG geometry types☆39Updated last month
- In this project we develop an OpenNTP package to solve the multi-group neutron transport equation.☆13Updated 4 years ago
- Nuclear data processing with legacy NJOY☆111Updated last month
- Workflow and Template Toolkit for Simulation (WATTS)☆32Updated 2 weeks ago
- List of open source projects related to OpenMC☆26Updated last month
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated 3 weeks ago
- Openmc-FEnicsx for muLtiphysics tutorIAl☆16Updated last month
- NJOY for the 21st Century☆79Updated last year
- ONIX is an open-source depletion software for nuclear reactor simulations and nuclear archaeology. It is written in Python 3 and offers c…☆40Updated 7 months ago
- API for parsing and post-processing many MC simulations related files☆17Updated 3 weeks ago
- Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.☆22Updated 2 months ago
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆38Updated this week
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆47Updated last week
- Convert OpenMC Geometry Components to CAD☆18Updated 7 months ago
- TRUST is a thermohydraulic software package for CFD simulations. It was originally designed for incompressible single-phase and Low Mach …☆59Updated this week
- Native plotting GUI for model design and verification☆59Updated 5 months ago