MCNP capabilities for nuclear well logging calculations
- Los Alamos National Lab., NM (USA). Applied Theoretical Physics Div.
The Los Alamos Radiation Transport Code System (LARTCS) consists of state-of-the-art Monte Carlo and discrete ordinates transport codes and data libraries. This paper discusses how the general-purpose continuous-energy Monte Carlo code MCNP ({und M}onte {und C}arlo {und n}eutron {und p}hoton), part of the LARTCS, provides a computational predictive capability for many applications of interest to the nuclear well logging community. The generalized three-dimensional geometry of MCNP is well suited for borehole-tool models. SABRINA, another component of the LARTCS, is a graphics code that can be used to interactively create a complex MCNP geometry. Users can define many source and tally characteristics with standard MCNP features. The time-dependent capability of the code is essential when modeling pulsed sources. Problems with neutrons, photons, and electrons as either single particle or coupled particles can be calculated with MCNP. The physics of neutron and photon transport and interactions is modeled in detail using the latest available cross-section data.
- OSTI ID:
- 6871281
- Report Number(s):
- CONF-900143-; CODEN: IETNA; TRN: 90-031801
- Journal Information:
- IEEE Transactions on Nuclear Science (Institute of Electrical and Electronics Engineers); (USA), Vol. 37:3; Conference: Institute for Electronic and Electrical Engineers (IEEE) nuclear science symposium, San Francisco, CA (USA), 15-19 Jan 1990; ISSN 0018-9499
- Country of Publication:
- United States
- Language:
- English
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LANL
MONTE CARLO METHOD
NEUTRON TRANSPORT
WELL LOGGING
GEOLOGIC DEPOSITS
MINERAL RESOURCES
NATIONAL ORGANIZATIONS
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