Improvement of SCALEXSPROC Multigroup Cross Section Processing Based on the CENTRM Pointwise Slowing Down Calculation
Abstract
The SCALEXSProc multigroup (MG) cross section processing procedure based on the CENTRM pointwise slowing down calculation is the primary procedure to process problemdependent selfshielded MG cross sections and scattering matrices for neutron transport calculations.This procedure supports various cellbased geometries including slab, 1D cylindrical, 1D spherical and 2D rectangular configurations and doubly heterogeneous particulate fuels. Recently, this procedure has been significantly improved to be applied to any advanced reactor analysis covering thermal and fast reactor systems, and to be comparable to continuous energy (CE) Monte Carlo calculations. Some reactivity bias and reaction rate differences have been observed compared with CE Monte Carlo calculations, and several areas for improvement have been identified in the SCALEXSProc MG cross section processing: (1) resonance selfshielding calculations within the unresolved resonance range, (2) 10 eV thermal cutoff energy for the free gas model, (3) onthefly adjustments to the thermal scattering matrix, (4) normalization of the pointwise neutron flux, and (5) fine MG energy structure. This procedure ensures very accurate MG cross section processing for highfidelity deterministic reactor physics analysis for various advanced reactor systems.
 Authors:

 ORNL
 Publication Date:
 Research Org.:
 Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
 Sponsoring Org.:
 USDOE
 OSTI Identifier:
 1649469
 DOE Contract Number:
 AC0500OR22725
 Resource Type:
 Conference
 Resource Relation:
 Conference: PHYSOR 2020: Transition to a Scalable Nuclear Future  Cambridge, , United Kingdom  3/29/2020 4:00:00 AM4/2/2020 4:00:00 AM
 Country of Publication:
 United States
 Language:
 English
Citation Formats
Kim, Kang Seog, Holcomb, Andrew M., Bostelmann, Rike, Wiarda, Dorothea, and Wieselquist, William. Improvement of SCALEXSPROC Multigroup Cross Section Processing Based on the CENTRM Pointwise Slowing Down Calculation. United States: N. p., 2020.
Web.
Kim, Kang Seog, Holcomb, Andrew M., Bostelmann, Rike, Wiarda, Dorothea, & Wieselquist, William. Improvement of SCALEXSPROC Multigroup Cross Section Processing Based on the CENTRM Pointwise Slowing Down Calculation. United States.
Kim, Kang Seog, Holcomb, Andrew M., Bostelmann, Rike, Wiarda, Dorothea, and Wieselquist, William. Sun .
"Improvement of SCALEXSPROC Multigroup Cross Section Processing Based on the CENTRM Pointwise Slowing Down Calculation". United States. https://www.osti.gov/servlets/purl/1649469.
@article{osti_1649469,
title = {Improvement of SCALEXSPROC Multigroup Cross Section Processing Based on the CENTRM Pointwise Slowing Down Calculation},
author = {Kim, Kang Seog and Holcomb, Andrew M. and Bostelmann, Rike and Wiarda, Dorothea and Wieselquist, William},
abstractNote = {The SCALEXSProc multigroup (MG) cross section processing procedure based on the CENTRM pointwise slowing down calculation is the primary procedure to process problemdependent selfshielded MG cross sections and scattering matrices for neutron transport calculations.This procedure supports various cellbased geometries including slab, 1D cylindrical, 1D spherical and 2D rectangular configurations and doubly heterogeneous particulate fuels. Recently, this procedure has been significantly improved to be applied to any advanced reactor analysis covering thermal and fast reactor systems, and to be comparable to continuous energy (CE) Monte Carlo calculations. Some reactivity bias and reaction rate differences have been observed compared with CE Monte Carlo calculations, and several areas for improvement have been identified in the SCALEXSProc MG cross section processing: (1) resonance selfshielding calculations within the unresolved resonance range, (2) 10 eV thermal cutoff energy for the free gas model, (3) onthefly adjustments to the thermal scattering matrix, (4) normalization of the pointwise neutron flux, and (5) fine MG energy structure. This procedure ensures very accurate MG cross section processing for highfidelity deterministic reactor physics analysis for various advanced reactor systems.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2020},
month = {3}
}