Published April 1998 | Version v1
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New probability table treatment in MCNP for unresolved resonances

  • 1. Carter M.C. Analysis, Richland, WA (United States)
  • 2. Los Alamos National Lab., NM (United States)

Description

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

Availability note (English)

Available from INIS in electronic form; ALSO AVAILABLE FROM OSTI AS DE98005277; NTIS; US GOVT. PRINTING OFFICE DEP.

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Additional details

Publishing Information

Imprint Pagination
10 p.
Report number
LA-UR--98-26

Conference

Title
technologies for the new century
Acronym
Radiation protection and shielding topical meeting
Dates
19-23 Apr 1998
Place
Nashville, TN (United States)

Optional Information