OpenMC
Monte Carlo neutron and photon transport simulation code for particle physics
OpenMC's random ray solver has gone from new arrival to the centre of every release
◆Recent moves
- 5d ago
Surface-flux tallies and PDG particle identifiers in OpenMC 0.16.0
A broad release touching every subsystem: surface-flux tallies, secondary-particle production filters, source biasing and coupled neutron-photon pulse-height support in the core solver, and generalized particle identifiers moving to PDG numbering. The random ray solver and the depletion workflow both take another step forward, and Python 3.12 becomes the minimum.
View source ↗ - 8mo ago
R2SManager automates shutdown dose rate calculations in OpenMC 0.15.3
Packages the rigorous two-step shutdown dose workflow into a single class, which is the clearest example yet of the project turning expert multi-stage procedures into API objects. Also adds collision tracking, an uncertainty-aware criticality search and higher tally moments for normality testing, while MCPL becomes an optional runtime dependency rather than a build-time one.
View source ↗ - 1y ago
OpenMC 0.15.2 hotfixes an MPI regression
A three-fix hotfix for an MPI bug introduced in the previous release, specifically a wrongly sized displacement list in the source-site interface. Corrective only, with no new capability.
View source ↗ - 1y ago
Ray-traced material volumes and Phong-shaded plots in OpenMC 0.15.1
The first release after the random ray solver's debut, and already dominated by improvements to it. The standout elsewhere is a reimplementation of mesh material volume computation on ray tracing, which parallelizes and substantially speeds up a previously slow step, plus a 3D solid ray trace plot class and composite surfaces that widen MCNP model conversion.
View source ↗ - 2y ago
OpenMC 0.15.0 introduces a random ray transport solver
⚡ SPARKThe release that sets the agenda for everything after it: a second transport solver based on the random ray method, added alongside the Monte Carlo core rather than replacing it. Every subsequent release in this window devotes significant work to extending it, which is the clearest evidence of where the project's effort has moved.
View source ↗ - 2y ago
Weight window generation and continuous nuclide feed in OpenMC 0.14.0
The pre-random-ray baseline: projection plots, photon pulse height tallies, weight window generation, and continuous removal or feed of nuclides during depletion. It also eliminated the long-standing requirement to seed depletion calculations with dilute nuclides, and redesigned the MicroXS class — early instances of the workflow-smoothing that later becomes the project's signature.
View source ↗