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MCNP

MCNP

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What is MCNP?

MCNP (Monte Carlo N-Particle) is a general-purpose Monte Carlo radiation transport code developed by Los Alamos National Laboratory. It is used to simulate the interaction of neutrons, photons, electrons, and other particles with matter. Its common uses include nuclear reactor design, radiation shielding, medical physics, and nuclear criticality safety analysis.

What other technologies are related to MCNP?

MCNP Competitor Technologies

Serpent is a Monte Carlo particle transport code, like MCNP, and therefore a direct competitor.
mentioned alongside MCNP in 89% (265) of relevant job posts
TRIPOLI is another Monte Carlo particle transport code, similar to MCNP, making it a competitor.
mentioned alongside MCNP in 88% (216) of relevant job posts
GEANT4 is a Monte Carlo simulation toolkit used in various fields including high energy physics, and is another particle transport code that can perform similar simulations to MCNP.
mentioned alongside MCNP in 44% (349) of relevant job posts
OpenMC is a Monte Carlo particle transport code focusing on reactor physics calculations, directly competing with MCNP for some applications.
mentioned alongside MCNP in 84% (174) of relevant job posts
MONK is a Monte Carlo criticality code, making it a direct competitor for criticality calculations.
mentioned alongside MCNP in 98% (102) of relevant job posts
FLUKA is a Monte Carlo particle transport code used for shielding and dosimetry calculations, competing with MCNP.
mentioned alongside MCNP in 62% (123) of relevant job posts
Attila is a discrete ordinates radiation transport code, offering an alternative approach to MCNP's Monte Carlo method, but for similar applications.
mentioned alongside MCNP in 89% (81) of relevant job posts
Older version of Geant4, which is a Monte Carlo simulation toolkit used in various fields and is another particle transport code that can perform similar simulations to MCNP.
mentioned alongside MCNP in 62% (96) of relevant job posts

MCNP Complementary Technologies

MicroShield is a point kernel code used for shielding calculations, offering a different approach than MCNP, but for similar applications.
mentioned alongside MCNP in 72% (293) of relevant job posts
SCALE includes radiation transport capabilities and criticality safety analysis tools. While parts compete, SCALE provides comprehensive nuclear safety analysis capabilities and nuclear data libraries and preprocessing tools which can complement MCNP.
mentioned alongside MCNP in 32% (608) of relevant job posts
ORIGEN is a code for calculating the buildup, decay, and processing of radioactive materials, which can provide source terms for MCNP simulations.
mentioned alongside MCNP in 72% (96) of relevant job posts

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