Recent MCNP Developments

Conference · Tue Nov 05 00:00:00 EST 1991

DOI:https://doi.org/10.1109/NSSMIC.1991.259080· OSTI ID:6026434

Hendricks, J. S. ^[1]; Briesmeister, J. F. ^[1]

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

MCNP is a widely used and actively developed Monte Carlo radiation transport code. Many important features have recently been added and more are under development. Benchmark studies not only indicate that MCNP is accurate but also that modern computer codes can give answers basically as accurate as the physics data that goes in them. Even deep penetration problems can be correct to within a factor of two after 10 to 25 mean free paths of penetration. And finally, Monte Carlo calculations, once thought to be too expensive to run routinely, can now be run effectively on desktop computers which compete with the supercomputers of yesteryear.

• 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: 6026434
• Report Number(s): LA-UR-91-3456; CONF-911106-25; ON: DE92003800
• Resource Relation: Conference: IEEE Nuclear Science Symposium, Santa Fe, NM (United States), 5-9 Nov 1991
• Country of Publication: United States
• Language: English

Related Subjects

07 ISOTOPES AND RADIATION SOURCES
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
47 OTHER INSTRUMENTATION
97 MATHEMATICS AND COMPUTING
RADIATION TRANSPORT
M CODES
BENCHMARKS
BIOMEDICAL RADIOGRAPHY
MONTE CARLO METHOD
REACTOR SAFETY
WELL LOGGING
COMPUTER CODES
DIAGNOSTIC TECHNIQUES
MEDICINE
NUCLEAR MEDICINE
RADIOLOGY
SAFETY
Nuclear Criticality Safety Program (NCSP)
Monte Carlo
Monte Carlo Radiation Transport Code
990200* - Mathematics & Computers
440400 - Well Logging Instrumentation
070204 - Radiation Sources- Industrial Uses
Radiometric
663610 - Neutron Physics- (1992-)