Published 1972 | Version v1
Miscellaneous Open

Finite-difference solution of the space-angle-lethargy-dependent slowing-down transport equation

  • 1. Boris Kidric Vinca Institute of Nuclear Sciences, Vinca, Belgrade (Yugoslavia)

Description

A procedure has been developed for solving the slowing-down transport equation for a cylindrically symmetric reactor system. The anisotropy of the resonance neutron flux is treated by the spherical harmonics formalism, which reduces the space-angle-Iethargy-dependent transport equation to a matrix integro-differential equation in space and lethargy. Replacing further the lethargy transfer integral by a finite-difference form, a set of matrix ordinary differential equations is obtained, with lethargy-and space dependent coefficients. If the lethargy pivotal points are chosen dense enough so that the difference correction term can be ignored, this set assumes a lower block triangular form and can be solved directly by forward block substitution. As in each step of the finite-difference procedure a boundary value problem has to be solved for a non-homogeneous system of ordinary differential equations with space-dependent coefficients, application of any standard numerical procedure, for example, the finite-difference method or the method of adjoint equations, is too cumbersome and would make the whole procedure practically inapplicable. A simple and efficient approximation is proposed here, allowing analytical solution for the space dependence of the spherical-harmonics flux moments, and hence the derivation of the recurrence relations between the flux moments at successive lethargy pivotal points. According to the procedure indicated above a computer code has been developed for the CDC -3600 computer, which uses the KEDAK nuclear data file. The space and lethargy distribution of the resonance neutrons can be computed in such a detailed fashion as the neutron cross-sections are known for the reactor materials considered. The computing time is relatively short so that the code can be efficiently used, either autonomously, or as part of some complex modular scheme. Typical results will be presented and discussed in order to prove and illustrate the applicability of the method proposed. (author)

Availability note (English)

Available from INIS in electronic form; Also available from the Institute of nuclear sciences Vinca

Files

39110552.pdf

Files (317.3 kB)

Name Size Download all
md5:e01a7988ff0225f941bf45b6f0d53dcd
317.3 kB Preview Download

Additional details

Publishing Information

Publisher
International Atomic Energy Agency, IAEA
Imprint Pagination
11 p.
Report number
INIS-RS--1475

Conference

Title
Seminar on numerical reactor calculations
Dates
17-21 Jan 1972
Place
Vienna (Austria)

Optional Information

Notes
10 refs., 4 figs., 2 tabs.
Secondary number(s)
IAEA-SM--154/63