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Title: Control rod treatment for FEM based radiation transport methods

Abstract

This paper presents a novel control rod treatment for finite element method (FEM) based reactor physics simulations. The new method falls into the class of homogenization methods which treat material interfaces within mesh elements by defining a representative, homogenized nuclear cross section set. In contrast to existing homogenization based cusping treatments that attempt to approximate flux-volume weighting of the cross sections, we propose to exactly integrate terms appearing in the variational form of the transport or diffusion equation over mixed material elements. This goal is achieved by defining smoothly varying cross sections in elements that straddle material boundaries. It is shown that the smoothly varying cross sections can be obtained by projecting the piecewise set of cross sections onto the set of Legendre polynomials up to a finite order. Implementation of smoothly varying cross sections is supported within the Rattlesnake radiation multiphysics code that is currently under development at the Idaho National Laboratory. Homogenization methods traditionally suffer from cusping effects that originate from overestimation of absorption cross sections in strongly neutron-absorbing materials as found in control rods. We demonstrate that the presented method is (1) highly effective in removing cusping effects and (2) provides accurate results based on the C5G7-TDmore » benchmark, a time-dependent version of the C5G7 benchmark.« less

Authors:
ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1542606
Report Number(s):
[INL/JOU-18-45608-Rev000]
[Journal ID: ISSN 0306-4549]
Grant/Contract Number:  
[AC07-05ID14517]
Resource Type:
Accepted Manuscript
Journal Name:
Annals of Nuclear Energy (Oxford)
Additional Journal Information:
[Journal Name: Annals of Nuclear Energy (Oxford); Journal Volume: 127; Journal Issue: C]; Journal ID: ISSN 0306-4549
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; Finite Element Method; Control Rod Cusping; Reactor Physics; Radiation Transport; Rattlesnake Transport Code; Multiphysics Object Oriented Simulation Environment

Citation Formats

Schunert, Sebastian, Wang, Yaqi, Ortensi, Javier, Laboure, Vincent, Gleicher, Frederick, DeHart, Mark, and Martineau, Richard. Control rod treatment for FEM based radiation transport methods. United States: N. p., 2018. Web. doi:10.1016/j.anucene.2018.11.054.
Schunert, Sebastian, Wang, Yaqi, Ortensi, Javier, Laboure, Vincent, Gleicher, Frederick, DeHart, Mark, & Martineau, Richard. Control rod treatment for FEM based radiation transport methods. United States. doi:10.1016/j.anucene.2018.11.054.
Schunert, Sebastian, Wang, Yaqi, Ortensi, Javier, Laboure, Vincent, Gleicher, Frederick, DeHart, Mark, and Martineau, Richard. Thu . "Control rod treatment for FEM based radiation transport methods". United States. doi:10.1016/j.anucene.2018.11.054. https://www.osti.gov/servlets/purl/1542606.
@article{osti_1542606,
title = {Control rod treatment for FEM based radiation transport methods},
author = {Schunert, Sebastian and Wang, Yaqi and Ortensi, Javier and Laboure, Vincent and Gleicher, Frederick and DeHart, Mark and Martineau, Richard},
abstractNote = {This paper presents a novel control rod treatment for finite element method (FEM) based reactor physics simulations. The new method falls into the class of homogenization methods which treat material interfaces within mesh elements by defining a representative, homogenized nuclear cross section set. In contrast to existing homogenization based cusping treatments that attempt to approximate flux-volume weighting of the cross sections, we propose to exactly integrate terms appearing in the variational form of the transport or diffusion equation over mixed material elements. This goal is achieved by defining smoothly varying cross sections in elements that straddle material boundaries. It is shown that the smoothly varying cross sections can be obtained by projecting the piecewise set of cross sections onto the set of Legendre polynomials up to a finite order. Implementation of smoothly varying cross sections is supported within the Rattlesnake radiation multiphysics code that is currently under development at the Idaho National Laboratory. Homogenization methods traditionally suffer from cusping effects that originate from overestimation of absorption cross sections in strongly neutron-absorbing materials as found in control rods. We demonstrate that the presented method is (1) highly effective in removing cusping effects and (2) provides accurate results based on the C5G7-TD benchmark, a time-dependent version of the C5G7 benchmark.},
doi = {10.1016/j.anucene.2018.11.054},
journal = {Annals of Nuclear Energy (Oxford)},
number = [C],
volume = [127],
place = {United States},
year = {2018},
month = {12}
}

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