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openmc-validator-mcp

MCP serverCommunity

Pre-flight checks for OpenMC models over MCP: 14 tools that catch material, geometry, tally and data errors before a run. By zxkjack123.

0 starsUpdated 2 months agoGitHub data from 5 Nov 2026

At a glance

Type
MCP server
Works with
OpenMC
How it connects
Reads and writes files; the tool isn't needed
Access
Read-only
Tool versions
openmc-validator 0.4.0; Python 3.10 to 3.12
Operating systems
Not stated in its documentation
Needs a OpenMC licence
No
Transport
Local (stdio)
AI clients documented
VS Code (GitHub Copilot)
Licence
MIT
Language
Python

What it can do

  • Validates materials, geometry, settings and tallies, flagging nuclide typos, unclosed surface references, bad batch settings and mis-ordered energy bins.
  • Cross-checks requested nuclides and temperatures against cross_sections.xml, and tally filters against geometry cells and mesh extents.
  • Converts an OpenMC energy tally to a FISPACT-II spectrum file and summarises statepoint.h5 tallies as JSON.
  • Returns structured error codes with severity and a suggested fix for each finding.

Limitations

  • Deeper checks, such as material round-trips and geometry-debug, need OpenMC installed from conda-forge; without it they degrade to warnings.
  • The template and material catalogue tools need a separate openmc-templates checkout.
  • Validates and post-processes only; it doesn't launch transport runs itself.

Install

pip install openmc-validator

Source: github.com/zxkjack123/openmc-validator-mcp#installation

MCP servers and skills run code on your computer. Review the source before installing.

AI-generated models, drawings and results must be checked by a qualified engineer before use.