Nodal method for three-dimensional fast-reactor calculations in hexagonal geometry. [LMFBR]

Conference · Sat Jan 01 00:00:00 EST 1983

OSTI ID:6403642

Lawrence, R D

A nodal method is developed for the solution of the multigroup neutron-diffusion equation in three-dimensional hexagonal-z geometry. The method employs an extension to hexagonal geometry of the transverse-integration procedure used extensively in the development of nodal schemes in Cartesian geometry. The partially-integrated fluxes in the three hex-plane directions are approximated by a polynomial tailored to the unique properties of the transverse-integrated equations in hexagonal geometry. The final equations, which are cast in the form of local inhomogeneous response matrix equations for each energy group, involve spatial moments of the node-interior flux distribution plus surface-averaged partial currents across the faces of the node.

• Research Organization: Argonne National Lab., IL (USA)
• DOE Contract Number: W-31-109-ENG-38
• OSTI ID: 6403642
• Report Number(s): CONF-830304-16; ON: DE83008875
• Resource Relation: Conference: American Nuclear Society topical conference on computational methods, Salt Lake City, UT, USA, 28 Mar 1983
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LMFBR TYPE REACTORS
REACTOR CORES
REACTOR KINETICS
NEUTRON FLUX
MULTIGROUP THEORY
THREE-DIMENSIONAL CALCULATIONS
BREEDER REACTORS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
KINETICS
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NEUTRON TRANSPORT THEORY
RADIATION FLUX
REACTOR COMPONENTS
REACTORS
TRANSPORT THEORY
210500* - Power Reactors
Breeding