Comparison of Generation of HigherOrder Neutron Scattering Cross Sections
Abstract
The generation of highorder neutron scattering cross sections consistent with highfidelity simulations remains an area of active research. Popular options include generating cross sections from continuous energy Monte Carlo calculations or generating cross sections from a deterministic neutron transport calculation with highfidelity tabulated cross sections. Both options present challenges. Monte Carlo simulations can naturally process continuous energy cross section data and allow for the general description of anisotropic neutron scattering given a scattering law. However, Monte Carlo simulations are inherently related to particle weighting and it has been suggested that this may be unacceptable for generating highorder neutron scattering cross sections. Deterministic neutron transport calculations can easily calculate highorder moments of the flux to appropriately calculate higherorder neutron scattering cross sections but are generally limited by discretization of space, energy, and angle. In this work, the tradeoffs between generation of highorder neutron scattering cross sections via Monte Carlo and deterministic neutron transport methods are investigated. The methods implemented in the Monte Carlo computer program Serpent and the deterministic fast reactor neutron cross section generator MC23 are compared. Cross sections resulting from these methods are used in Rattlesnake, a deterministic neutron transport code developed by Idaho National Laboratory (INL), and resultsmore »
 Authors:

 North Carolina State University
 Idaho National Laboratory
 Publication Date:
 Research Org.:
 Idaho National Lab. (INL), Idaho Falls, ID (United States)
 Sponsoring Org.:
 USDOE Office of Nuclear Energy (NE)
 OSTI Identifier:
 1593864
 Report Number(s):
 INL/EXT1954899Rev000
 DOE Contract Number:
 DEAC0705ID14517
 Resource Type:
 Technical Report
 Country of Publication:
 United States
 Language:
 English
 Subject:
 97  MATHEMATICS AND COMPUTING; 22  GENERAL STUDIES OF NUCLEAR REACTORS; Cross section; Fast reactor; scattering; weighting; Serpent; MCC3
Citation Formats
Dawn, William C., Ortensi, Javier, DeHart, Mark D, and Palmtag, Scott P. Comparison of Generation of HigherOrder Neutron Scattering Cross Sections. United States: N. p., 2020.
Web. doi:10.2172/1593864.
Dawn, William C., Ortensi, Javier, DeHart, Mark D, & Palmtag, Scott P. Comparison of Generation of HigherOrder Neutron Scattering Cross Sections. United States. doi:10.2172/1593864.
Dawn, William C., Ortensi, Javier, DeHart, Mark D, and Palmtag, Scott P. Mon .
"Comparison of Generation of HigherOrder Neutron Scattering Cross Sections". United States. doi:10.2172/1593864. https://www.osti.gov/servlets/purl/1593864.
@article{osti_1593864,
title = {Comparison of Generation of HigherOrder Neutron Scattering Cross Sections},
author = {Dawn, William C. and Ortensi, Javier and DeHart, Mark D and Palmtag, Scott P.},
abstractNote = {The generation of highorder neutron scattering cross sections consistent with highfidelity simulations remains an area of active research. Popular options include generating cross sections from continuous energy Monte Carlo calculations or generating cross sections from a deterministic neutron transport calculation with highfidelity tabulated cross sections. Both options present challenges. Monte Carlo simulations can naturally process continuous energy cross section data and allow for the general description of anisotropic neutron scattering given a scattering law. However, Monte Carlo simulations are inherently related to particle weighting and it has been suggested that this may be unacceptable for generating highorder neutron scattering cross sections. Deterministic neutron transport calculations can easily calculate highorder moments of the flux to appropriately calculate higherorder neutron scattering cross sections but are generally limited by discretization of space, energy, and angle. In this work, the tradeoffs between generation of highorder neutron scattering cross sections via Monte Carlo and deterministic neutron transport methods are investigated. The methods implemented in the Monte Carlo computer program Serpent and the deterministic fast reactor neutron cross section generator MC23 are compared. Cross sections resulting from these methods are used in Rattlesnake, a deterministic neutron transport code developed by Idaho National Laboratory (INL), and results are compared to a reference continuous energy Monte Carlo calculation. Whereas previous work investigating the effects of anisotropic neutron scattering has focused on light water reactor (LWR) simulations, this work focuses on highorder neutron scattering cross sections as they relate to fast reactor simulations. To investigate the consequences of the Serpent and MC23 methodologies, a test problem is developed. The test problem is a onedimensional geometry with fast reactor materials designed to demonstrate deep penetration and exacerbate the effects of highorder neutron scattering. Based on the results of the deep penetration test problem, it is concluded that P3 neutron scattering cross sections are sufficient to describe anisotropic scattering in fast reactor materials. Any neutron scattering of order higher than P3 offers negligible change in the eigenvalue of the test problem. Additionally, it is determined that the methodology as implemented in Serpent is applicable for generating highorder neutron scattering cross sections through at least P3 in fast reactor materials.},
doi = {10.2172/1593864},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2020},
month = {1}
}