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Title: Anisotropic Elastic Resonance Scattering model for the Neutron Transport equation

The resonance scattering transfer cross-section has been reformulated to account for anisotropic scattering in the center-of-mass of the neutron-nucleus system. The main innovation over previous implementations is the relaxation of the ubiquitous assumption of isotropic scattering in the center-of-mass and the actual effective use of scattering angle distributions from evaluated nuclear data files in the computation of the angular moments of the resonant scattering kernels. The formulas for the high order anisotropic moments in the laboratory system are also derived. A multi-group numerical formulation is derived and implemented into a module incorporated within the NJOY nuclear data processing code. An ultra-fine energy mesh cross section library was generated using these new theoretical models and then was used for fuel assembly calculations with the PARAGON lattice physics code. The results obtained indicate a strong effect of this new model on reactivity, multi-group fluxes and isotopic inventory during depletion.
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Publication Date:
OSTI Identifier:
Report Number(s):
Journal ID: ISSN 0029-5639
DOE Contract Number:
Resource Type:
Journal Article
Resource Relation:
Journal Name: Nuclear Science and Engineering; Journal Volume: 179; Journal Issue: 1
Academic Press
Research Org:
Idaho National Laboratory (INL)
Sponsoring Org:
Country of Publication:
United States
22 GENERAL STUDIES OF NUCLEAR REACTORS; 97 MATHEMATICS AND COMPUTING Anisotropy; Multi-group formulation; Resonance Scattering; Scattering kernels; Temperature broadening