Difference between revisions of "MCNP"
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Revision as of 18:28, 18 August 2022
Description
MCNP is a general-purpose Monte Carlo N-Particle code that can be used for neutron, photon, electron, or coupled neutron/photon/electron transport. Specific areas of application include, but are not limited to, radiation protection and dosimetry, radiation shielding, radiography, medical physics, nuclear criticality safety, Detector Design and analysis, nuclear oil well logging, Accelerator target design, Fission and fusion reactor design, decontamination and decommissioning.
Environment Modules
Run module spider mcnp to find out what environment modules are available for this application.
System Variables
- DATAPATH
Additional Information
MCNP is a restricted application. Only authorized users who have completed required training and certification can access it.