RSICC CODE PACKAGE PSR-500

1. NAME AND TITLE
MCNP-VISED 4C2: Visual Editor for Creating MCNP4C2 Input Files.

2. CONTRIBUTOR
Visual Editor Consultants, Richland, Washington.

3. CODING LANGUAGE AND COMPUTERS
C++ and C; Pentium running Windows or Linux; HP (P00500/MNYCP/00).

4. NATURE OF PROBLEM SOLVED
MCNP-VISED 4C2 enables a visual creation of an MCNP input file which can be read by the Los Alamos National Laboratory MCNP4C2 (CCC-701) Monte Carlo transport code. The Visual Editor was developed to make the creation and debugging of MCNP geometries easier. It is a powerful visualization tool that can be used to rapidly create complex geometry models, including lattices, universes, fills, and other geometrical transformations for use with MCNP. The Visual Editor can:
Display MCNP 4C geometries in multiple plot windows.
Create surfaces and cells to build a geometry.
Create materials using the local xsdir file.
Store commonly used materials in a material library.
Sub-divide large cells into smaller cells.
Full geometry capabilities including universes and lattices.
Interactively set cell importances from the plot window.
Display source points and collision points in the plot window.
Multiple dynamic cross sectional views of the geometry can be utilized to create surfaces and build the geometry. Surfaces appear on the plots as soon as they are created before they are used in the definition of cells. Surface and cell creation are implemented with flexible menus that also allow for ease of modification and rapid creation of similar sets of surfaces and cells. Universes, fills, lattices and transformations are allowed. When creating a cell, the sense of the surfaces can be set with a click of the mouse, and complex cells can be created through a series of "cut" and "paste" operations. A cell splitting option can be used to split certain types of regions [a slab region, the region between two concentric spheres or cylinders, or a box-in-box region] into n cells with n input by the user. The user can also obtain on-line dynamic views of the source points created from the source description as a further verification of the description of the source. Helps are included to aid in the creation of rectangular and hexagonal lattices including the generation of the surfaces and tools for creating and modifying the fill matrix. Current data cards that can be created include materials, transformations and importances. An input file, or backup, can be created at any time during the visual editing session. Partially completed input files can be read in to continue with another editing session. The program uses data files containing a "standard materials" list for easy input of materials and cross section sets, and allows the user to create their own "special materials" list for the individual applications.

5. METHOD OF SOLUTION
This menu-driven graphical interface is based on C-language routines that interface with the screen and call FORTRAN subroutines which initialize the input data and prepare the information for the geometry plots. These FORTRAN routines in turn call slightly modified FORTRAN subroutines from the initiation and plot modules of MCNP. These FORTRAN subroutines constantly check the evolving input data being received from the C routines and generate the information for dynamically plotting the geometry in user-selected cross-sectional views.

6. RESTRICTIONS OR LIMITATIONS
The Windows version of the Visual Editor is compiled with an MDAS of 15,000,000, which will correspond to 60 Mbytes of memory. Data cards can be read in from an input file, but only a limited set of data cards can be created or modified with the current version. See the developer's website for workshop schedules and other information including a list of current bugs: http://www.mcnpvised.com/.

7. TYPICAL RUNNING TIME
The interactive running times depend upon the complexity of the input file being created. Plot generation is comparable to those for making MCNP plots, file initialization can be a factor of two to three times longer than for MCNP for larger problems. Typically, creation of an MCNP input file with the visual editor is a factor of two to ten faster than creating the input file with a line editor.

8. COMPUTER HARDWARE REQUIREMENTS
The Visual Editor was tested on Pentium computers and on HP workstations. It is expected to run on Sun and SGI Unix workstations but is untested on these.

9. COMPUTER SOFTWARE REQUIREMENTS
The package includes executables for Windows NT, Windows 95 and Linux. The Windows NT version, which also runs under Windows 2000, is now considered the most stable version and is fully functional. The Windows version has all of the capabilities of the Linux version except cylindrical duct creation. No source files are included for Windows. The Digital Visual Fortran and Microsoft Visual C++ compilers were used to create the Windows executable. The included Linux executable was created under RedHat Linux 5.2, and it was tested at RSICC under RH Linux 6.1 and 7.0. For Linux/UNIX computers, the package also includes the Visual Editor C code plus Fortran and C patch files for mcnp. Compilation under Linux/Unix requires both Fortran 77 and C compilers, Xlib, and Motif libraries to build executables. The widgets are created in Motif, the graphics are created using Xlib routines. MCNP4C2 Fortran and C source files are also required but are not included in this package.

10. REFERENCES
a. included in documentation:
L.L. Carter and R.A. Schwarz, "MCNP Visual Editor Computer Code Manual"
(February 2002).
b. background references:
J. F. Breismeister, Editor, "MCNP - A General Monte Carlo Code N-Particle Transport Code," LA-13709-M, Los Alamos National Laboratory, Los Alamos, New Mexico (2000).
R. A. Schwarz, L. L. Carter, and N. Shrivastava, "Creation of MCNP Input Files With a Visual Editor," Proceedings of the 8th International Conference on Radiation Shielding, pages 454-459, Arlington, Texas. Published by the American Nuclear Society. (April 24-27, 1994).
L.L. Carter, R.A. Schwarz, "Visual Creation of Lattice Geometries for MCNP Criticality Calculations," Transactions of the American Nuclear Society, 77, 223 American Nuclear Society, La Grange Park, Illinois (1997).
R. A. Schwarz, L. L. Carter, "Visual Editor to Create and Display MCNP Input Files," Trans. Am. Nucl. Soc. Vol 77, pages 311-312 (November 16-20, 1997).
R. A. Schwarz, L. L. Carter, Karl E. Hillesland, and Victor E. Roetman, "Advanced MCNP Input File Creation Using the Visual Editor," Proceedings of the 1998 Topical on Radiation Shielding, Vol. 2, pages 317-324, Nashville, Tennessee. Published by the American Nuclear Society. (April 19-23, 1998).
L.L. Carter, R.A. Schwarz, "The Visual Creation and Display of MCNP Geometries and Lattices for Criticality Problems," Trans. Amer. Nucl. Soc., American Nuclear Society, La Grange Park, Illinois (1999).
R.A. Schwarz, L.L. Carter, W Brown, "Particle Track Visualization Using the MCNP Visual Editor," Proc. Am. Nucl. Soc. Topical Radiation Protection for Our National Priorities Medicine, the Environment and, the Legacy, 324-331, Spokane, Washington (2000).

11. CONTENTS OF CODE PACKAGE
Included is the referenced document in (10.a) and a CD which contains a self-extracting Windows file and a GNU compressed Unix tar file.

12. DATE OF ABSTRACT
February 2002.

KEYWORDS: MONTE CARLO; NEUTRON; GAMMA-RAY; INTERACTIVE; ON-LINE; MICROCOMPUTER; WORKSTATION