U.S. Department of EnergyOffice of Scientific and Technical Information
Features of MCNP6 Relevant to Medical Radiation Physics
Abstract
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.
- Authors:
-
- Los Alamos National Laboratory
- Publication Date:
- Research Org.:
- Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
- Sponsoring Org.:
- DOE/LANL
- OSTI Identifier:
- 1050009
- Report Number(s):
- LA-UR-12-24401
TRN: US1204521
- DOE Contract Number:
- AC52-06NA25396
- Resource Type:
- Conference
- 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
- Subject:
- 72 PHYSICS OF ELEMENTARY PARTICLES AND FIELDS; 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
Citation Formats
Hughes, III, H Grady, and Goorley, John T. Features of MCNP6 Relevant to Medical Radiation Physics. United States: N. p., 2012.
Web.
Hughes, III, H Grady, & Goorley, John T. Features of MCNP6 Relevant to Medical Radiation Physics. United States.
Hughes, III, H Grady, and Goorley, John T. 2012.
"Features of MCNP6 Relevant to Medical Radiation Physics". United States. https://www.osti.gov/servlets/purl/1050009.
@article{osti_1050009,
title = {Features of MCNP6 Relevant to Medical Radiation Physics},
author = {Hughes, III, H Grady and Goorley, John T},
abstractNote = {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.},
doi = {},
url = {https://www.osti.gov/biblio/1050009},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Wed Aug 29 00:00:00 EDT 2012},
month = {Wed Aug 29 00:00:00 EDT 2012}
}