New probability table treatment in MCNP for unresolved resonances
- Carter M.C. Analysis, Richland, WA (United States)
- Los Alamos National Lab., NM (United States)
An upgrade for MCNP has been implemented to sample the neutron cross sections in the unresolved resonance range using probability tables. These probability tables are generated with the cross section processor code NJOY, by using the evaluated statistical information about the resonances to calculate cumulative probability distribution functions for the microscopic total cross section. The elastic, fission, and radiative capture cross sections are also tabulated as the average values of each of these partials conditional upon the value of the total. This paper summarizes how the probability tables are utilized in this MCNP upgrade and compares this treatment with the approximate smooth treatment for some example problems.
- Research Organization:
- Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
- Sponsoring Organization:
- USDOE Office of Environmental Restoration and Waste Management, Washington, DC (United States)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 658394
- Report Number(s):
- LA-UR-98-26; CONF-980403-; ON: DE98005277; TRN: 98:011284
- Resource Relation:
- Conference: Radiation protection and shielding topical meeting: technologies for the new century, Nashville, TN (United States), 19-23 Apr 1998; Other Information: PBD: Apr 1998
- Country of Publication:
- United States
- Language:
- English
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