openmc
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OpenMC Monte Carlo Code
## Bug Description ``` -- Building xtensor v0.25.0 CMake Error at vendor/xtensor/CMakeLists.txt:42 (find_package): By not providing "Findxtl.cmake" in CMAKE_MODULE_PATH this project has asked CMake to find a package configuration file...
## Description Implementation of specific gamma-ray dose constants in OpenMC. Tabulated and available in a library. Then accessible in the Python API, so that analysts can take a Depletion calculated...
# Description This adds support for python 3.14 and drops support for python 3.11 per SPEC 0. Note: per SPEC 0 this should only be shipped with a minor release...
The `openmc.deplete` module relies on calls to the OpenMC shared library via `openmc.lib` in order to perform neutron transport, update material compositions, etc., which means parallel execution has to be...
## Description Python 3.14 is out, and I do love adding support for a new version of Python ASAP (#3164). As I learned last year though our dependencies do not...
# Description Depletion chain validation could be useful for users who want to provide a custom chain file. Additionally, the validation step could be applied before OpenMC parses the file,...
## Description We can currently export mesh data to an asci format vtk file using mesh.write_data_to_vtk(). This makes use of an optional dependency vtk to write the asci vtk format...
# Description This PR changes the behaviour of material.add_nuclide so that if a nuclide with the same name and percentage type exists in the material then the new nuclide will...
# Description This PR introduces a "virtual lattice" method, an acceleration technique designed to improve the performance and reduce the memory footprint of MC simulations for systems containing a large...
# Description This pull request is a continuation of #3516 . The original PR by @liangjg introduced a valuable new module, but it had merge conflicts with the latest main...