Whole-core neutron transport calculations without fuel-coolant homogenization

Whole-core neutron transport calculations without fuel-coolant homogenization [electronic resource]

The variational nodal method implemented in the VARIANT code is generalized to perform full core transport calculations without spatial homogenization of cross sections at either the fuel-pin cell or fuel assembly level. The node size is chosen to correspond to one fuel-pin cell in the radial plane....

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Bibliographic Details
Online Access: Online Access
Corporate Author: Argonne National Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Washington, D.C : Oak Ridge, Tenn. : United States. Dept. of Energy ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 2000.
Subjects:
Reactor Cores.
Nodal Expansion Method.
Water Cooled Reactors.
Mixed Oxide Fuels.
Reactor Kinetics.
V Codes.
Homogenization Methods.
Neutron Transport.
Variational Methods.
Specific Nuclear Reactors And Associated Plants.

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Call Number: E 1.99:anl/ra/cp-100240
E 1.99:anl/ra/cp-100240 Available

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