Abstract
Montepy is an object-oriented Python interface for MCNP input files. It excels at reading, editing, creating, and writing MCNP input files. The Monte Carlo N Particle (MCNP) code is a Monte Carlo transport solver for simulating many different types of radiation problems and is developed by Los Alamos National Laboratory. Montepy creates an object-oriented interface for the MCNP input file to allow for efficient automated modifications to large, complex simulations.
- Developers:
-
.png "ORCID")
[1]
;
[1]
;
[1]
;
Carbno, Brenna
[1]
- Idaho National Laboratory (INL), Idaho Falls, ID (United States)
- Release Date:
- 2024-01-08
- Project Type:
- Open Source, Publicly Available Repository
- Software Type:
- Scientific
- Programming Languages:
-
python3.8
- Licenses:
-
MIT License
- Sponsoring Org.:
-
USDOE Office of Nuclear Energy (NE)Primary Award/Contract Number:AC07-05ID14517
- Code ID:
- 117498
- Research Org.:
- Idaho National Laboratory (INL), Idaho Falls, ID (United States)
- Country of Origin:
- United States
- Keywords:
- mcnpy; OpenMCNPy; python; object oriented; mcnp; input files; lexer; syntax parser; semantic parser
Citation Formats
Gale, Micah, L., Travis, Bascom, Andrew J., and Carbno, Brenna A.
Montepy.
Computer Software.
https://github.com/idaholab/MontePy.
USDOE Office of Nuclear Energy (NE).
08 Jan. 2024.
Web.
doi:10.11578/dc.20240115.1.
Gale, Micah, L., Travis, Bascom, Andrew J., & Carbno, Brenna A.
(2024, January 08).
Montepy.
[Computer software].
https://github.com/idaholab/MontePy.
https://doi.org/10.11578/dc.20240115.1.
Gale, Micah, L., Travis, Bascom, Andrew J., and Carbno, Brenna A.
"Montepy." Computer software.
January 08, 2024.
https://github.com/idaholab/MontePy.
https://doi.org/10.11578/dc.20240115.1.
@misc{
doecode_117498,
title = {Montepy},
author = {Gale, Micah and L., Travis and Bascom, Andrew J. and Carbno, Brenna A.},
abstractNote = {Montepy is an object-oriented Python interface for MCNP input files. It excels at reading, editing, creating, and writing MCNP input files. The Monte Carlo N Particle (MCNP) code is a Monte Carlo transport solver for simulating many different types of radiation problems and is developed by Los Alamos National Laboratory. Montepy creates an object-oriented interface for the MCNP input file to allow for efficient automated modifications to large, complex simulations.},
doi = {10.11578/dc.20240115.1},
url = {https://doi.org/10.11578/dc.20240115.1},
howpublished = {[Computer Software] \url{https://doi.org/10.11578/dc.20240115.1}},
year = {2024},
month = {jan}
}