Performance Characteristics of Specified Power Reactors in Multidimensional Neutron Diffusion Problems

The multigroup neutron diffusion equations with the constraint of specified power distributions are investigated by the application of the straight-line method which can be considered as the limiting case of zero mesh space in the finite difference method. The standard partial differential form of the diffusion equation is reduced to sets of ordinary differential equations and then converted into sets of integral equations by using Green's functions defined on the pseudo straight lines. Coupling of each straight line to the adjacent lines arises from the application of a three-point central difference formula. The interfaces encountered between two regions are taken into account by imposing the continuity conditions for the group fluxes and net currents with Taylor expansions of internal fluxes at the interface positions.

Name thesis:degree_name

Ph.D.

Level thesis:degree_level

Dissertation

Discipline thesis:degree_discipline

Nuclear Engineering

Grantor

University of Illinois at Urbana-Champaign

Year dc:date

2014

Author dc:creator

• Kim, Moon Gil

• Engineering, Nuclear
• Energy

Language dc:language

eng

Identifier

(UMI)AAI8026537

OAI identifier oai:identifier

oai:www.ideals.illinois.edu:2142/67790