skip to main content

Title: Geometry creation for MCNP by Sabrina and XSM

The Monte Carlo N-Particle transport code MCNP is based on a surface description of 3-dimensional geometry. Cells are defined in terms of boolean operations on signed quadratic surfaces. MCNP geometry is entered as a card image file containing coefficients of the surface equations and a list of surfaces and operators describing cells. Several programs are available to assist in creation of the geometry specification, among them Sabrina and the new ``Smart Editor`` code XSM. We briefly describe geometry creation in Sabrina and then discuss XSM in detail. XSM is under development; our discussion is based on the state of XSM as of January 1, 1994.
Authors:
Publication Date:
OSTI Identifier:
10129600
Report Number(s):
LA-UR--94-157; CONF-940424--17
ON: DE94006272;
DOE Contract Number:
W-7405-ENG-36
Resource Type:
Conference
Resource Relation:
Conference: 8. international conference on radiation shielding,Arlington, TX (United States),24-27 Apr 1994; Other Information: PBD: [1994]
Research Org:
Los Alamos National Lab., NM (United States)
Sponsoring Org:
USDOE, Washington, DC (United States)
Country of Publication:
United States
Language:
English
Subject:
73 NUCLEAR PHYSICS AND RADIATION PHYSICS; 63 RADIATION, THERMAL, AND OTHER ENVIRON. POLLUTANT EFFECTS ON LIVING ORGS. AND BIOL. MAT.; 99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; RADIATION TRANSPORT; M CODES; MONTE CARLO METHOD; S CODES; X CODES; GEOMETRY; SHIELDING; RADIATION PROTECTION 663600; 560161; 990200; RADIATION PHYSICS; MAN; MATHEMATICS AND COMPUTERS