Neutronics analysis for cylindrical assembly using Green's functions

When designing a reactor a preliminary design is done in order to obtain a rough estimate of various reactor properties. These properties include the neutron flux, criticality condition, or distribution of material in the assembly. It is possible to obtain an analytic solution for the neutron flux for a reactor represented in cylindrical coordinates using a Green's function or Green's function matrix method for both one group and two group neutron diffusion. The analytic results for a two-dimensional cylindrical system are simplified by assuming a cosine flux shape in the horizontal direction. This assumption makes the flux in the horizontal direction a neutron sink term in the radial direction. From the neutron flux, expressions for the criticality condition and fuel distribution cross section can be obtained by specifying the form factor, which is equivalent to specifying the power shape. A specific form factor, such as a constant power shape or parabolic power shape allow for a comparision between the results obtained by using a one group diffusion model against a two group diffusion model.

Name thesis:degree_name

M.S.

Level thesis:degree_level

Thesis

Discipline thesis:degree_discipline

Nuclear, Plasma, Radiolgc Engr

Grantor

University of Illinois at Urbana-Champaign

Year dc:date

2011

Author dc:creator

• Rivera, Jose E.

Contributors dc:contributor

• Axford, Roy A.

• Neutronics
• Cylindrical Assembly
• Neutron Diffusion in Cylindrical Coordinates
• Green's Function Matrix
• Chopped Cosine

Statement dc:rights

• Copyright 2011 Jose E. Rivera

Language dc:language

en

Handle dc:identifier

http://hdl.handle.net/2142/24034

OAI identifier oai:identifier

oai:www.ideals.illinois.edu:2142/24034