Neutronics analysis for cylindrical assembly using Green's functions

Rivera, Jose E.

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https://hdl.handle.net/2142/24034 Copy

Description

Title

Neutronics analysis for cylindrical assembly using Green's functions

Author(s)

Rivera, Jose E.

Issue Date

2011-05-25T14:52:35Z

Director of Research (if dissertation) or Advisor (if thesis)

Axford, Roy A.

Department of Study

Nuclear, Plasma, & Rad Engr

Discipline

Nuclear, Plasma, Radiolgc Engr

Degree Granting Institution

University of Illinois at Urbana-Champaign

Degree Name

M.S.

Degree Level

Thesis

Keyword(s)

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

Abstract

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.

Graduation Semester

2011-05

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

Copyright and License Information

Copyright 2011 Jose E. Rivera

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