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DOE OSTI · 2510796

A Practical guide to Parsing MCNP Inputs: Lessons Learned from Implementing Context-Free Parsing in MontePy

Gale, Micah D. [Idaho National Laboratory (INL), Idaho Falls, ID (United States). Reactor Physics Analysis and Design] (ORCID:0000000164514818)·Labossiere-Hickman, Travis J. [Idaho National Laboratory (INL), Idaho Falls, ID (United States)] (ORCID:0000000307423404)·Carbno, Brenna Anne [Idaho National Laboratory (INL), Idaho Falls, ID (United States)]
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Abstract

Monte Carlo N-Particle (MCNP) is a widely used Monte Carlo transport solver that began development in the 1960’s. Due to this MCNP input files uses a custom input syntax, for which there are no off-the-shelf parsing libraries available. For MontePy to create an effective Object-Oriented interface for MCNP input files, an context-free parser was implemented to be able to fully parse the files. MontePy uses a number of shortcuts and optimizations to avoid creating a single universal input file parser. . These lessons can be applied to working with the many other custom input syntax languages persistent throughout the nuclear industry.

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97 MATHEMATICS AND COMPUTINGContext-free parserMCNPMontePy

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BibTeXRIS

Gale, Micah D. [Idaho National Laboratory (INL), Idaho Falls, ID (United States). Reactor Physics Analysis and Design] (ORCID:0000000164514818), Labossiere-Hickman, Travis J. [Idaho National Laboratory (INL), Idaho Falls, ID (United States)] (ORCID:0000000307423404), Carbno, Brenna Anne [Idaho National Laboratory (INL), Idaho Falls, ID (United States)]. 2025-04-30. A Practical guide to Parsing MCNP Inputs: Lessons Learned from Implementing Context-Free Parsing in MontePy. https://www.osti.gov/biblio/2510796

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