OpenMC Insights

What is OpenMC?

OpenMC is a Monte Carlo particle transport code. It simulates the behavior of neutrons, photons, and other particles in a variety of applications, including nuclear reactor design, radiation shielding, and medical physics. It is commonly used for high-fidelity modeling of nuclear systems.

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What other technologies are related to OpenMC?

OpenMC Competitor Technologies

Serpent

Serpent is a Monte Carlo particle transport code, primarily used for reactor physics calculations. It competes directly with OpenMC for similar applications.

mentioned alongside OpenMC in 32% (97) of relevant job posts

MCNP

MCNP is a general-purpose Monte Carlo radiation transport code used for a wide variety of applications. It is a competitor to OpenMC, particularly in criticality safety and shielding.

mentioned alongside OpenMC in 8% (177) of relevant job posts

OpenMC Complementary Technologies

SCALE

SCALE is a widely-used modeling and simulation suite for nuclear safety analysis and design. While it includes radiation transport capabilities, it also provides tools for cross-section processing, criticality safety, and depletion analysis, often used in conjunction with transport codes like OpenMC.

mentioned alongside OpenMC in 3% (54) of relevant job posts

Python

Python is a programming language that is often used to interface with OpenMC through its API. It's used for pre- and post-processing, automation, and analysis. Therefore, it is complementary.

mentioned alongside OpenMC in 0% (158) of relevant job posts