Status of Monte Carlo at Los Alamos

Technical Report · Thu May 01 00:00:00 EDT 1980

DOI:https://doi.org/10.2172/5361246· OSTI ID:5361246

Thompson, W L; Cashwell, E D; Godfrey, T N.K.; Schrandt, R G; Deutsch, O L; Booth, T E

Four papers were presented by Group X-6 on April 22, 1980, at the Oak Ridge Radiation Shielding Information Center (RSIC) Seminar-Workshop on Theory and Applications of Monte Carlo Methods. These papers are combined into one report for convenience and because they are related to each other. The first paper (by Thompson and Cashwell) is a general survey about X-6 and MCNP and is an introduction to the other three papers. It can also serve as a resume of X-6. The second paper (by Godfrey) explains some of the details of geometry specification in MCNP. The third paper (by Cashwell and Schrandt) illustrates calculating flux at a point with MCNP; in particular, the once-more-collided flux estimator is demonstrated. Finally, the fourth paper (by Thompson, Deutsch, and Booth) is a tutorial on some variance-reduction techniques. It should be required for a fledging Monte Carlo practitioner.

• Research Organization: Los Alamos Scientific Lab., NM (USA)
• Sponsoring Organization: Not Available; USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 5361246
• Report Number(s): LA-8353-MS
• Country of Publication: United States
• Language: English

Related Subjects

654003* -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
COMPUTER CALCULATIONS
GEOMETRY
LASL
MATHEMATICS
MONTE CARLO METHOD
NATIONAL ORGANIZATIONS
NEUTRON FLUX
NEUTRON TRANSPORT THEORY
Nuclear Criticality Safety Program (NCSP)
RADIATION FLUX
THREE-DIMENSIONAL CALCULATIONS
TRANSPORT THEORY
US AEC
US DOE
US ERDA
US ORGANIZATIONS