Advances in the Development and Verification of MCNP5 and MCNP6
Conference
·
OSTI ID:1083866
- 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
- Country of Publication:
- United States
- Language:
- English
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