Published October 1978 | Version v1
Report Open

New resonance cross section calculational algorithms

Creators

  • 1. General Atomic Co., San Diego, CA

Description

Improved resonance cross section calculational algorithms were developed and tested for inclusion in a fast reactor version of the MICROX code. The resonance energy portion of the MICROX code solves the neutron slowing-down equations for a two-region lattice cell on a very detailed energy grid (about 14,500 energies). In the MICROX algorithms, the exact P0 elastic scattering kernels are replaced by synthetic (approximate) elastic scattering kernels which permit the use of an efficient and numerically stable recursion relation solution of the slowing-down equation. In the work described here, the MICROX algorithms were modified as follows: an additional delta function term was included in the P0 synthetic scattering kernel. The additional delta function term allows one more moments of the exact elastic scattering kernel to be preserved without much extra computational effort. With the improved synthetic scattering kernel, the flux returns more closely to the exact flux below a resonance than with the original MICROX kernel. The slowing-down calculation was extended to a true B1 hyperfine energy grid calculatn in each region by using P1 synthetic scattering kernels and tranport-corrected P0 collision probabilities to couple the two regions. 1 figure, 6 tables

Files

10453917.pdf

Files (509.4 kB)

Name Size Download all
md5:4b6dc31fad69048f6cfe6610ef8920d0
509.4 kB Preview Download

Additional details

Additional titles

Augmented title (English)
For MICROX code

Publishing Information

Imprint Title
Review of multigroup nuclear cross-section processing
Journal Page Range
p. 59-82.
Report number
ORNL/RSIC--41

Conference

Title
Radiation shielding information center seminar.
Dates
14 - 16 Mar 1978.
Place
Oak Ridge, TN, USA.