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U.S. Department of Energy
Office of Scientific and Technical Information

Features of MCNP6 Relevant to Medical Radiation Physics

Conference ·
OSTI ID:1050009
MCNP (Monte Carlo N-Particle) is a general-purpose Monte Carlo code for simulating the transport of neutrons, photons, electrons, positrons, and more recently other fundamental particles and heavy ions. Over many years MCNP has found a wide range of applications in many different fields, including medical radiation physics. In this presentation we will describe and illustrate a number of significant recently-developed features in the current version of the code, MCNP6, having particular utility for medical physics. Among these are major extensions of the ability to simulate large, complex geometries, improvement in memory requirements and speed for large lattices, introduction of mesh-based isotopic reaction tallies, advances in radiography simulation, expanded variance-reduction capabilities, especially for pulse-height tallies, and a large number of enhancements in photon/electron transport.
Research Organization:
Los Alamos National Laboratory (LANL)
Sponsoring Organization:
DOE/LANL
DOE Contract Number:
AC52-06NA25396
OSTI ID:
1050009
Report Number(s):
LA-UR-12-24401
Country of Publication:
United States
Language:
English