Simple benchmark for evaluating self-shielding models
Name
Forget_SIMPLE BENCHMARK FOR EVALUATING SELF.pdf
Size
264.79 KB
Format
Adobe PDF
Checksum (MD5)
875634367edec97d502e7ef540875e45
Author(s)
Gibson, Nathan Andrew
Smith, Kord S.
Forget, Benoit Robert Yves
Date Issued
April 2015
Journal
Proceedings of the Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, 2015. (M&C+SNA+MC 2015)
Publisher
American Nuclear Society
Citation
Gibson, Nathan A., Kord Smith, and Benoit Forget. "Simple Benchmark for Evaluating Self-Shielding Models." Proceedings of Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference (M&C+SNA+MC 2015), Nashville, Tennessee, USA. Vol. 1. pp. 1832-851.
Version
Author's final manuscript
Abstract
Accounting for self-shielding effects is paramount to accurate generation of multigroup cross sections for use in deterministic reactor physics neutronics calculations. Historically, equivalence in dilution and subgroup techniques have been the preeminent means of accounting for these effects, but recent work has proposed new solutions, including the Embedded Self-Shielding Method (ESSM). This paper presents a very simple benchmark problem to compare these and future self-shielding methods. The benchmark is perhaps the simplest problem in which both energy and spatial self-shielding effects are important, a two-region problem with a lumped resonant material. A single resonance in a
single energy group is considered. Scattering is approximated using the narrow resonance approximation, decoupling each energy value and allowing an easily-computed reference solution to be obtained.
Equivalence in dilution using two-term rational expansions and the subgroup method were both found to give very accurate solutions on this benchmark, with errors less than 1% in nearly all cases. One-term rational expansions and ESSM showed much larger errors.
MIT Department
Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
Terms of Use
Creative Commons Attribution-Noncommercial-Share Alike
Persistent DSpace Link
DOI of Published Version
http://www.proceedings.com/27010.html
