MCNP4A: Features and Philosophy

Conference · Thu May 27 00:00:00 EDT 1993

OSTI ID:10157073

Hendricks, John S. ^[1]

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1. Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)

This paper describes MCNP, states its philosophy, introduces a number of new features becoming available with version MCNP4A, and answers a number of questions asked by participants in the workshop. MCNP is a general-purpose three-dimensional neutron, photon and electron transport code. Its philosophy is "Quality, Value and New Features." Quality is exemplified by new software quality assurance practices and a program of benchmarking against experiments. Value includes a strong emphasis on documentation and code portability. New features are the third priority. MCNP4A is now available at Los Alamos. New features in MCNP4A include enhanced statistical analysis, distributed processor multitasking, new photon libraries, ENDF/B-VI capabilities, X-Windows graphics, dynamic memory allocation, expanded criticality output, periodic boundaries, plotting of particle tracks via SABRINA, and many other improvements.

• Research Organization: Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 10157073
• Report Number(s): LA-UR-93-1475; CONF-9304137-1; ON: DE93012749; TRN: 93:015204
• Resource Relation: Conference: Centre d`Etudes Meeting, Saclay (France), 27-29 Apr 1993; Other Information: PBD: [1993]
• Country of Publication: United States
• Language: English

Related Subjects

73 NUCLEAR PHYSICS AND RADIATION PHYSICS
97 MATHEMATICS AND COMPUTING
NEUTRON TRANSPORT
M CODES
CHARGED-PARTICLE TRANSPORT
PHOTON TRANSPORT
THREE-DIMENSIONAL CALCULATIONS
MONTE CARLO METHOD
CRITICALITY
FORTRAN
Nuclear Criticality Safety Program (NCSP)
MCNP
MCNP4A
New Features
663610
663620
NEUTRON PHYSICS
PHYSICS OF RADIATIONS OTHER THAN NEUTRONS