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Development and Monte Carlo Validati...

Brewster, Wayne J.

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Development and Monte Carlo Validation of a Finite Element Reactor Analysis Framework.

Record Type:	Electronic resources : Monograph/item
Title/Author:	Development and Monte Carlo Validation of a Finite Element Reactor Analysis Framework./
Author:	Brewster, Wayne J.
Published:	Ann Arbor : ProQuest Dissertations & Theses, : 2018,
Description:	169 p.
Notes:	Source: Masters Abstracts International, Volume: 57-06.
Contained By:	Masters Abstracts International57-06(E).
Subject:	Nuclear engineering. -
Online resource:	http://pqdd.sinica.edu.tw/twdaoapp/servlet/advanced?query=10792933
ISBN:	9780438114135

Development and Monte Carlo Validation of a Finite Element Reactor Analysis Framework.
Brewster, Wayne J.

Development and Monte Carlo Validation of a Finite Element Reactor Analysis Framework. - Ann Arbor : ProQuest Dissertations & Theses, 2018 - 169 p.

Source: Masters Abstracts International, Volume: 57-06.

Thesis (M.S.)--Missouri University of Science and Technology, 2018.

This study presents the development and Monte Carlo validation of a continuous Galerkin finite element reactor analysis framework. In its current state, the framework acts as an interface between the mesh preparation software GMSH and the sparse linear solvers in MATLAB, for the discretization and approximation of 1-D, 2-D, and 3-D linear partial differential equations. Validity of the framework is assessed from the following two benchmarking activities: the 2-D IAEA PWR benchmark; and the 2-D Missouri Science and Technology Reactor benchmark proposed within this study. The 2-D IAEA PWR multi-group diffusion benchmark is conducted with the following discretization schemes: linear, quadratic, and cubic triangular elements; linear and quadratic rectangular elements of mesh sizes 10, 5, 2, 1, 0.5 cm. Convergence to the reference criticality eigenvalue of 1.02985 is observed for all cases.

ISBN: 9780438114135Subjects--Topical Terms:

595435
Nuclear engineering.

Development and Monte Carlo Validation of a Finite Element Reactor Analysis Framework.
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100 1 $a Brewster, Wayne J. $3 3429475
245 1 0 $a Development and Monte Carlo Validation of a Finite Element Reactor Analysis Framework.
260 1 $a Ann Arbor : $b ProQuest Dissertations & Theses, $c 2018
300 $a 169 p.
500 $a Source: Masters Abstracts International, Volume: 57-06.
500 $a Adviser: Ayodeji B. Alajo.
502 $a Thesis (M.S.)--Missouri University of Science and Technology, 2018.
520 $a This study presents the development and Monte Carlo validation of a continuous Galerkin finite element reactor analysis framework. In its current state, the framework acts as an interface between the mesh preparation software GMSH and the sparse linear solvers in MATLAB, for the discretization and approximation of 1-D, 2-D, and 3-D linear partial differential equations. Validity of the framework is assessed from the following two benchmarking activities: the 2-D IAEA PWR benchmark; and the 2-D Missouri Science and Technology Reactor benchmark proposed within this study. The 2-D IAEA PWR multi-group diffusion benchmark is conducted with the following discretization schemes: linear, quadratic, and cubic triangular elements; linear and quadratic rectangular elements of mesh sizes 10, 5, 2, 1, 0.5 cm. Convergence to the reference criticality eigenvalue of 1.02985 is observed for all cases.
520 $a The proposed 2-D MSTR benchmark is prepared through translation of an experimentally validated 120w core configuration MCNP model into Serpent 2. Validation of the Serpent 2 model is attained from the comparison of criticality eigenvalues, flux traverses, and two 70-group energy spectrums within fuel elements D5 and D9. Then, a two-group 2-D MSTR benchmark of the 120w core configuration is prepared with the spatial homogenization methodology implemented within Serpent 2. Final validation of the framework is assessed from the comparison of criticality eigenvalues and spatial flux solutions of the diffusion and simplified spherical harmonics SP3 models. The diffusion model resulted in a difference in reactivity of Deltarho = --1673.93 pcm and the SP3 model resulted in a difference of Deltarho = --777.60 pcm with respect to the Serpent 2 criticality eigenvalues.
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650 4 $a Nuclear engineering. $3 595435
650 4 $a Mathematics. $3 515831
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710 2 $a Missouri University of Science and Technology. $b Nuclear Engineering. $3 2099536
773 0 $t Masters Abstracts International $g 57-06(E).
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792 $a 2018
793 $a English
856 4 0 $u http://pqdd.sinica.edu.tw/twdaoapp/servlet/advanced?query=10792933