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

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Bibliographic Details
Online Access:	Online Access
Corporate Author:	Argonne National Laboratory (Researcher)
Format:	Government Document Electronic eBook
Language:	English
Published:	Argonne, Ill. : Oak Ridge, Tenn. : Argonne National Lab ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1983.
Subjects:	Kinetics. Breeder Reactors. Transport Theory. Epithermal Reactors. Reactors. Multigroup Theory. Liquid Metal Cooled Reactors. Lmfbr Type Reactors. Neutron Flux. Neutron Transport Theory. Fbr Type Reactors. Reactor Cores. Fast Reactors. Three-dimensional Calculations. Reactor Components. Radiation Flux. Reactor Kinetics. Specific Nuclear Reactors And Associated Plants.

Description
Abstract:	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.
Item Description:	Published through the Information Bridge: DOE Scientific and Technical Information. 01/01/1983. "conf-830304-16" "DE83008875" American Nuclear Society topical conference on computational methods, Salt Lake City, UT, USA, 28 Mar 1983. Lawrence, R.D.
Physical Description:	Pages: 16 : digital, PDF file.

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