Features of MCNP6 Relevant to Medical Radiation Physics
- Los Alamos National Laboratory
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), Los Alamos, NM (United States)
- Sponsoring Organization:
- DOE/LANL
- DOE Contract Number:
- AC52-06NA25396
- OSTI ID:
- 1050009
- Report Number(s):
- LA-UR-12-24401; TRN: US1204521
- Resource Relation:
- Conference: 12th International Conference on Radiation Shielding (ICRS-12) + 17th Topical Meeting of the Radiation Protection and Shielding Division of the ANS (RPSD-2012) ; 2012-09-02 - 2012-09-07 ; Nara, Japan
- Country of Publication:
- United States
- Language:
- English
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61 RADIATION PROTECTION AND DOSIMETRY
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
74 ATOMIC AND MOLECULAR PHYSICS
97 MATHEMATICAL METHODS AND COMPUTING
ELECTRONS
ELEMENTARY PARTICLES
HEAVY IONS
NEUTRONS
PHOTONS
PHYSICS
POSITRONS
RADIATION PROTECTION
RADIATIONS
SHIELDING
SIMULATION
TRANSPORT
VELOCITY