Variational Nodal Transport Methods for Hexagonal and Three-Dimensional Geometries (Final Report)

Technical Report · Sat Feb 01 04:00:00 EST 1992

DOI:https://doi.org/10.2172/10187641· OSTI ID:10187641

Lewis, Elmer E. ^[1]

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1. Northwestern Univ., Evanston, IL (United States)

The properties of the variational nodal method for neutron transport calculations are investigated. The method is generalized for three-dimensional multigroup criticality problems in both hexagonal-z and Cartesian geometries. The method is implemented as part of the Argonne National Laboratory Code DIF3D, and applied to a series of benchmark reactor calculations. Variational nodal methods are compared of nodal transport methods based on both interface-current and discrete ordinate approximations. Model problems are used to examine the effect of running each of the three classes of nodal transport methods on computers with massively parallel architectures.

• Research Organization: Northwestern Univ., Evanston, IL (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: FG02-88ER12810
• OSTI ID: 10187641
• Report Number(s): DOE/ER/12810-1; ON: DE93002131
• Country of Publication: United States
• Language: English

Related Subjects

663610
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
97 MATHEMATICS AND COMPUTING
990200
ANL
Argonne National Laboratory
CALCULATION METHODS
CRITICALITY
Calculations
Criticality
D CODES
Geometry
HEXAGONAL CONFIGURATION
MATHEMATICS AND COMPUTERS
MULTIGROUP THEORY
Multigroup Theory
NEUTRON PHYSICS
NEUTRON TRANSPORT
Nuclear Criticality Safety Program (NCSP)
PROGRESS REPORT
Properties
THREE-DIMENSIONAL CALCULATIONS