Image: Derrick Coetzee from Berkeley, CA, USA · CC0 1.0 Public Domain Dedication · Wikimedia Commons
Open-source Monte Carlo neutron and photon transport code for reactor, shielding and blanket design.
What it changes
Gives fusion and fission teams a transport solver they can inspect, cite and run on their own hardware instead of licensing a closed code.
Availability
Self-hosted (global)
Access and cost
Get OpenMC — Free and open source with no licence fee or per-core charge; users supply their own compute and data.
Evidence it works
- Publishes the source code, releases and install instructions for the Monte Carlo particle transport code. — source
- Documents the project as developed at MIT and maintained by an open-source community for reactor physics work. — source
What it cannot do yet
- It is a solver, not a product: geometry, nuclear data and validation remain the user’s responsibility.
- No support contract or certification path, so licensed reactor work still depends on commercial codes.
OpenMC community · Research · Last verified 2026-09-17. Claims are re-checked on a 30-day clock; the date above is when this line was last confirmed.
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