MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.

api mcnp mcnp6 monte-carlo neutronics radiation-transport
4 Open Issues Need Help Last updated: Sep 3, 2025

Open Issues Need Help

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AI Summary: This GitHub issue highlights that the example MCNP input file provided in the bug report template is not a valid input file. While acknowledging that full validity isn't strictly necessary for a template, the suggestion is to update the example to be syntactically correct. This is a minor cosmetic improvement to the template's quality.

Complexity: 1/5
good first issue low priority

MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.

Python
#api#mcnp#mcnp6#monte-carlo#neutronics#radiation-transport

AI Summary: This issue addresses instances of blank `TypeError` messages in `data_inputs/material.py` and `numbered_object_collection.py`. While exception messages are optional, if provided, they should not be empty. The task is to fill in descriptive messages for these specific `TypeError` instances, excluding one noted as intentional in `input_parser/syntax_node.py`.

Complexity: 1/5
good first issue code improvement low priority

MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.

Python
#api#mcnp#mcnp6#monte-carlo#neutronics#radiation-transport
good first issue bugs low priority

MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.

Python
#api#mcnp#mcnp6#monte-carlo#neutronics#radiation-transport
good first issue bugs low priority

MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.

Python
#api#mcnp#mcnp6#monte-carlo#neutronics#radiation-transport