Approximate solutions of the two-dimensional integral transport equation by collision probability methods

Journal Article · Sat Oct 01 00:00:00 EDT 1977 · Nucl. Sci. Eng.; (United States)

DOI:https://doi.org/10.13182/NSE64-384· OSTI ID:5311072

Sanchez, R

A set of approximate solutions for the isotropic two-dimensional neutron transport problem has been developed using the interface current formalism. The method has been applied to regular lattices of rectangular cells containing a fuel pin, cladding, and water, or homogenized structural material. The cells are divided into zones that are homogeneous. A zone-wise flux expansion is used to formulate a direct collision probability problem within a cell. The coupling of the cells is effected by making extra assumptions on the currents entering and leaving the interfaces. Two codes have been written: The first uses a cylindrical cell model and one or three terms for the flux expansion, and the second uses a two-dimensional flux representation and does a truly two-dimensional calculation inside each cell. In both codes, one or three terms can be used to make a space-independent expansion of the angular fluxes entering and leaving each side of the cell. The accuracies and computing times achieved with the different approximations are illustrated by numerical studies on two benchmark problems.

• Research Organization: CEN de Saclay, Gif-sur-Yvette, France
• OSTI ID: 5311072
• Journal Information: Nucl. Sci. Eng.; (United States), Vol. 64:2
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
NEUTRON TRANSPORT
TWO-DIMENSIONAL CALCULATIONS
REACTOR LATTICES
WATER COOLED REACTORS
CALCULATION METHODS
NEUTRON DIFFUSION EQUATION
NUMERICAL SOLUTION
NEUTRAL-PARTICLE TRANSPORT
RADIATION TRANSPORT
REACTORS
220100* - Nuclear Reactor Technology- Theory & Calculation
654003 - Radiation & Shielding Physics- Neutron Interactions with Matter