Advances in the Development and Verification of MCNP5 and MCNP6

Conference · Mon Sep 19 00:00:00 EDT 2011

OSTI ID:1083866

Brown, Forrest B. ^[1]; Kiedrowski, Brian C. ^[1]; Bull, Jeffrey S. ^[1]; Goorley, John T. ^[1]; Hughes, H. Grady ^[1]; James, Michael R. ^[1]

---

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

The MCNP Monte Carlo code has been used for high-fidelity analyses of criticality safety problems since the 1970s. This paper reviews recent advances in the development and verification of MCNP, including the current production release of MCNP5 and the beta release of MCNP6. End-users in all application areas need to be aware of the forthcoming MCNP6 release and begin planning for the transition to the new code in 2012 and beyond.

• 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: AC52-06NA25396
• OSTI ID: 1083866
• Report Number(s): LA-UR-11-04211; LA-UR-11-4211
• Resource Relation: Conference: 9. International Conference on Nuclear Criticality Safety (ICNC2011), Criticality Codes and Nuclear Data, Edinburgh, Scotland (United Kingdom), 19-22 Sep 2011; Related Information: https://www.ans.org/meetings/view-120/
• Country of Publication: United States
• Language: English

Related Subjects

97 MATHEMATICS AND COMPUTING
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
Nuclear Criticality Safety Program (NCSP)
MCNP
Monte Carlo
criticality safety