학술논문

Data analysis and visualization in MCNP{trademark}
Document Type
Conference
Author
Source
Conference: Winter meeting of the American Nuclear Society (ANS),Washington, DC (United States),13-18 Nov 1994; Other Information: PBD: [1994]
Subject
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE RADIATION TRANSPORT
MONTE CARLO METHOD
COMPUTER GRAPHICS
NEUTRON TRANSPORT
PHOTON TRANSPORT
DATA ANALYSIS
NUCLEAR DATA COLLECTIONS 663600
RADIATION PHYSICS
MATHEMATICS AND COMPUTERS
Language
English
Abstract
There are many situations where the user may wish to go beyond current MCNP capabilities. For example, data produced by the code may need formatting for input into an external graphics package. Limitations on disk space may hinder writing out large PTRAK files. Specialized data analysis routines may be needed to model complex experimental results. One may wish to produce particle histories in a format not currently available in the code. To address these and other similar concerns a new capability in MCNP is being tested. A number of real, integer, logical and character variables describing the current and past characteristics of a particle are made available online to the user in three subroutines. The type of data passed can be controlled by cards in the INP file. The subroutines otherwise are empty, and the user may code in any desired analysis. A new MCNP executable is produced by compiling these subroutines and linking to a library which contains the object files for the rest of the code.