Published 1987 | Version v1
Journal article

Legendre expansion of neutron flux over entire multilayer slab geometry

Creators

  • 1. Bhabha Atomic Research Centre, 5th floor, Central Complex, Bombay 400 085 (India)

Description

The monoenergetic integral transport equation for a multilayer slab geometry has been solved by Legendre expansion method. The method utilizes an expansion of the neutron flux over entire multilayer slab geometry in Legendre polynomials of the position co-ordinate (Single Expansion Method - SEM). This formulation is an extension of Carlvik's (1968) method for a homogeneous slab. Earlier (Raghav, 1984) the expansion of the neutron flux was done in each layer in Legendre polynomials of the position co-ordinate (Multi Expansion Method - MEM). The aim in this paper is to compare both the approaches of SEM and MEM. A few multilayer slab systems with vacuum boundary conditions have been selected for this purpose and Ksub(eff), the effective multiplication factor of the system, has been compared. SEM requires the evaluation of the integrals where the limits are not -1 to + 1 (as they are in MEM and where analytical expressions can be derived), in these cases we have derived recurrence relations (which are described in the Appendix) to evaluate such integrals. (author)

Additional details

Publishing Information

Journal Title
Ann. Nucl. Energy
Journal Volume
14
Journal Issue
5
Series
Ann. Nucl. Energy.
Journal Page Range
263-267
ISSN
0306-4549
CODEN
ANEND

INIS

Country of Publication
United Kingdom
Country of Input or Organization
United Kingdom
INIS RN
18097411
Subject category
S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
Descriptors DEI
LEGENDRE POLYNOMIALS; NEUTRON FLUX; NEUTRON TRANSPORT; NEUTRON TRANSPORT THEORY; SLABS
Descriptors DEC
FUNCTIONS; NEUTRAL-PARTICLE TRANSPORT; POLYNOMIALS; RADIATION FLUX; RADIATION TRANSPORT; TRANSPORT THEORY