MCNP is a general-purpose, continuous-energy, generalized geometry, time-dependent, coupled neutron-photon-electron Monte Carlo transport code system. MCNP4C is the first major release of MCNP since version 4B (February 4, 1997). The major new features of MCNP4C include: Unresolved resonance range probability tables; Perturbation enhancements; Superimposed mesh weight window generator; Alpha eigenvalues; Macrobodies; ENDF/B-VI improvements; PC Enhancements; Electron Physics Enhancements; Parallelization enhancements; Delayed Neutrons.
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References in zbMATH (referenced in 2 articles )
Showing results 1 to 2 of 2.
- Sharifzadeh, Mohsen; Afarideh, Hosein; Khalafi, Hosein; Gholipour, Reza: A Matlab-based Monte Carlo algorithm for transport of gamma-rays in matter (2015)
- Kong, Rong; Ambrose, Martin; Spanier, Jerome: Efficient, automated Monte Carlo methods for radiation transport (2008)