Monte Carlo N-Particle Transport Code (MCNP) is the code of choice for doing complex neutron/photon/electron transport calculations for the nuclear industry and research institutions. The Visual Editor for Monte Carlo N-Particle is internationally recognized as the best code for visually creating and graphically displaying input files for MCNP. The work performed in this grant was used to enhance the capabilities of the MCNP Visual Editor to allow it to read in both 2D and 3D Computer Aided Design (CAD) files, allowing the user to electronically generate a valid MCNP input geometry
The program McCad provides a CAD interface for the Monte Carlo transport code MCNP. It is able to co...
The latest version of MCNP, the Los Alamos Monte Carlo transport code, has now been officially relea...
The question of Monte Carlo simulation of radiation transport in voxel geometries is addressed. Patc...
Monte Carlo N-Particle Transport Code (MCNP) (Reference 1) is the code of choice for doing complex n...
Monte Carlo N-Particle (MCNP) is a Monte Carlo code package allowing coupled neutron, photon, and el...
MCNP{trademark} is a general purpose three-dimensional time-dependent neutron, photon, and electron ...
MCNPX is a Fortran 90 Monte Carlo radiation transport computer code that transports all particles at...
The Los Alamos National Laboratory (LANL) Monte Carlo N-Particle radiation transport code, MCNP, has...
MCNP is a general-purpose Monte Carlo code that can be used for neutron, photon, or coupled neutron/...
The general-purpose Monte Carlo code MCNP can be used for neutron, photon, or coupled neutron-photon...
The MCNPX Monte Carlo particle transport code is rapidly developing into a significant computational...
MCNP is a general-purpose Monte Carlo code that can be used for neutron, photon, or coupled neutron/...
The Monte Carlo particle transport code MCNPX and its associated data have been the focus of a major...
The program McCad provides a CAD interface for the Monte Carlo transport code MCNP. It is able to co...
MCNP, a 3D coupled neutron/photon/electron Monte Carlo radiation transport code, is currently used i...
The program McCad provides a CAD interface for the Monte Carlo transport code MCNP. It is able to co...
The latest version of MCNP, the Los Alamos Monte Carlo transport code, has now been officially relea...
The question of Monte Carlo simulation of radiation transport in voxel geometries is addressed. Patc...
Monte Carlo N-Particle Transport Code (MCNP) (Reference 1) is the code of choice for doing complex n...
Monte Carlo N-Particle (MCNP) is a Monte Carlo code package allowing coupled neutron, photon, and el...
MCNP{trademark} is a general purpose three-dimensional time-dependent neutron, photon, and electron ...
MCNPX is a Fortran 90 Monte Carlo radiation transport computer code that transports all particles at...
The Los Alamos National Laboratory (LANL) Monte Carlo N-Particle radiation transport code, MCNP, has...
MCNP is a general-purpose Monte Carlo code that can be used for neutron, photon, or coupled neutron/...
The general-purpose Monte Carlo code MCNP can be used for neutron, photon, or coupled neutron-photon...
The MCNPX Monte Carlo particle transport code is rapidly developing into a significant computational...
MCNP is a general-purpose Monte Carlo code that can be used for neutron, photon, or coupled neutron/...
The Monte Carlo particle transport code MCNPX and its associated data have been the focus of a major...
The program McCad provides a CAD interface for the Monte Carlo transport code MCNP. It is able to co...
MCNP, a 3D coupled neutron/photon/electron Monte Carlo radiation transport code, is currently used i...
The program McCad provides a CAD interface for the Monte Carlo transport code MCNP. It is able to co...
The latest version of MCNP, the Los Alamos Monte Carlo transport code, has now been officially relea...
The question of Monte Carlo simulation of radiation transport in voxel geometries is addressed. Patc...