Certification of MCNP Version 4A for WHC computer platforms. Revision 7

Technical Report · Wed May 03 00:00:00 EDT 1995

DOI:https://doi.org/10.2172/71572· OSTI ID:71572

Carter, L L

MCNP is a general-purpose Monte Carlo code that can be used for neutron, photon, or coupled neutron/photon transport, including the capability to calculate eigenvalues for critical systems. The code treats an arbitrary three-dimensional configuration of materials in geometric cells bounded by first- and second-degree surfaces, and some special fourth-degree surfaces (elliptical tori).

• Research Organization: Westinghouse Hanford Co., Richland, WA (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC06-87RL10930
• OSTI ID: 71572
• Report Number(s): WHC-SD-MP-SWD-30001-Rev.7; ON: DE95011546; TRN: 95:015321
• Resource Relation: Other Information: PBD: 3 May 1995
• Country of Publication: United States
• Language: English

Related Subjects

66 PHYSICS
99 MATHEMATICS
COMPUTERS
INFORMATION SCIENCE
MANAGEMENT
LAW
MISCELLANEOUS
NEUTRAL-PARTICLE TRANSPORT
M CODES
MONTE CARLO METHOD
NEUTRON TRANSPORT
PHOTON TRANSPORT
EIGENVALUES
THREE-DIMENSIONAL CALCULATIONS
MANUALS
COMPUTER ARCHITECTURE
TORI