Modification to the Monte Carlo N-Particle (MCNP) Visual Editor (MCNPVised) to Read in Computer Aided Design (CAD) Files

Technical Report · Tue Aug 23 00:00:00 EDT 2005

DOI:https://doi.org/10.2172/843024· OSTI ID:843024

Schwarz, Randolph; Carter, Leland L; Schwarz, Alysia

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.

• Research Organization: Visual Editor Consultants
• Sponsoring Organization: USDOE Office of Nuclear Energy, Science and Technology (NE)
• DOE Contract Number: FG02-03ER83844
• OSTI ID: 843024
• Report Number(s): DOE/ER/83844-1; TRN: US0701875
• Country of Publication: United States
• Language: English

Related Subjects

61 RADIATION PROTECTION AND DOSIMETRY
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
COMPUTER-AIDED DESIGN
GEOMETRY
MODIFICATIONS
NUCLEAR INDUSTRY
TRANSPORT
MCNP
Monte Carlo
CAD
Computer Aided Design
Nuclear
Particle transport