Variational nodal transport methods for hexagonal and three-dimensional geometries

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

DOI:https://doi.org/10.2172/7152709· OSTI ID:7152709

Lewis, E E

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). Dept. of Mechanical Engineering
• Sponsoring Organization: DOE; USDOE, Washington, DC (United States)
• DOE Contract Number: FG02-88ER12810
• OSTI ID: 7152709
• Report Number(s): DOE/ER/12810-1; ON: DE93002131
• Country of Publication: United States
• Language: English

Related Subjects

663610 -- Neutron Physics-- (1992-)
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
99 GENERAL AND MISCELLANEOUS
990200* -- Mathematics & Computers
CALCULATION METHODS
COMPUTER CODES
CONFIGURATION
CRITICALITY
D CODES
DOCUMENT TYPES
HEXAGONAL CONFIGURATION
MULTIGROUP THEORY
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
NEUTRON TRANSPORT THEORY
PROGRESS REPORT
RADIATION TRANSPORT
THREE-DIMENSIONAL CALCULATIONS
TRANSPORT THEORY