Un-collided-flux preconditioning for the first order transport equation

Conference · Mon Jul 01 00:00:00 EDT 2013

OSTI ID:22212736

Rigley, M.; Koebbe, J. ^[1]; Drumm, C. ^[2]

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1. Utah State University, 3900 Old Main Hill, Logan, UT 84322 (United States)
2. Sandia National Laboratories, MS 1166, PO Box 5800, Albuquerque, NM 87185 (United States)

Two codes were tested for the first order neutron transport equation using finite element methods. The un-collided-flux solution is used as a preconditioner for each of these methods. These codes include a least squares finite element method and a discontinuous finite element method. The performance of each code is shown on problems in one and two dimensions. The un-collided-flux preconditioner shows good speedup on each of the given methods. The un-collided-flux preconditioner has been used on the second-order equation, and here we extend those results to the first order equation. (authors)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 22212736
• Resource Relation: Conference: M and C 2013: 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Sun Valley, ID (United States), 5-9 May 2013; Other Information: Country of input: France; 10 refs.; Related Information: In: Proceedings of the 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering - M and C 2013| 3016 p.
• Country of Publication: United States
• Language: English

Related Subjects

97 MATHEMATICAL METHODS AND COMPUTING
EQUATIONS
FINITE ELEMENT METHOD
LEAST SQUARE FIT
NEUTRON FLUX
NEUTRON TRANSPORT
NEUTRON TRANSPORT THEORY
PERFORMANCE