The DIF3D Nodal Kinetics Capability in Hex-Z Geometry: Formulation and Preliminary Tests

Conference · Sun Apr 28 04:00:00 EDT 1991

OSTI ID:6081713

Taiwo, T. A. ^[1]; Khalil, H. S. ^[1]

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1. Argonne National Laboratory (ANL), Argonne, IL (United States)

The development of a 3-D space- and energy-dependent neutron kinetics capability in Hexagonal-Z geometry is described. The code makes use of the nodal Hex-Z spatial differencing technique implemented in the ANL DIF3D code and, at present, the theta method for time integration. Results of numerical test problems are presented to verify the formulation of the kinetics code and to demonstrate its accuracy. The nodal differencing scheme is shown to yield more accurate transient results than does the standard (six triangle per hexagon) finite-difference scheme, which is considerably less efficient. Kinetics experiments conducted at the Savannah River Site have also been successfully analyzed using the nodal kinetics code. The time evolution and the asymptotic magnitudes of the flux tilts induced and measured in these experiments were predicted with good accuracy using the published cross section data and kinetics parameters.

• Research Organization: Argonne National Laboratory (ANL), Argonne, IL (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 6081713
• Report Number(s): ANL/CP--71385; CONF-910414--34; ON: DE91010796
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
654003 -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
COMPUTER CODES
D CODES
DIFFERENTIAL EQUATIONS
EQUATIONS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON DIFFUSION EQUATION
NEUTRON TRANSPORT
NODAL EXPANSION METHOD
RADIATION TRANSPORT
TESTING
TRANSIENTS