Modification to the Monte Carlo N-Particle (MCNP) Visual Editor (MCNPVised) to Read in Computer Aided Design (CAD) Files [electronic resource]
Mcnp; Monte Carlo; Cad; Computer Aided Design; Nuclear; Particle Transport.
Saved in:
| Online Access: |
Online Access (via OSTI) |
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| Format: | Government Document Electronic eBook |
| Language: | English |
| Published: |
Washington, D.C. : Oak Ridge, Tenn. :
United States. Office of the Assistant Secretary for Nuclear Energy ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,
2005.
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| Subjects: |
| Summary: | Mcnp; Monte Carlo; Cad; Computer Aided Design; Nuclear; Particle Transport. |
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| Abstract: | 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. |
| Item Description: | Published through SciTech Connect. 08/23/2005. "doe/er/83844-1" Randolph Schwarz; Leland L. Carter; Alysia Schwarz. Visual Editor Consultants. |
| Physical Description: | 4.4 Megabytes : digital, PDF file. |
| Type of Report and Period Covered Note: | Final; |