MIG: MCNP input generator for EFFI magnet geometries

Conference · Mon Jul 01 00:00:00 EDT 1985 · Fusion Technol.; (United States)

OSTI ID:5793740

Gohar, Y; Attaya, M

A computer code, MIG, has been developed to interface the magnet design and the three dimensional Monte Carlo code MCNP to perform neutronics design analyses. MIG prepares all the required MCNP cells and surfaces to simulate the magnets described in EFFI input. Extra zones with different materials could be added to envelop or divide the winding packs of the magnets. Examples of the input and output of MIG used by MCNP are given to illustrate the different capabilities of MIG.

• Research Organization: Fusion Technology Institute, University of Wisconsin, Madison, WI
• OSTI ID: 5793740
• Report Number(s): CONF-850310-
• Journal Information: Fusion Technol.; (United States), Journal Name: Fusion Technol.; (United States) Vol. 8:1; ISSN FUSTE
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700202* -- Fusion Power Plant Technology-- Magnet Coils & Fields
COMPUTER CODES
COMPUTER-AIDED DESIGN
COMPUTERIZED SIMULATION
E CODES
ELECTRIC COILS
ELECTRICAL EQUIPMENT
EQUIPMENT
M CODES
MAGNET COILS
MAGNETIC FIELDS
MONTE CARLO METHOD
NEUTRON FLUX
PROGRAMMING
RADIATION FLUX
SIMULATION
THREE-DIMENSIONAL CALCULATIONS