Developments in nodal reactor analysis tools for hexagonal geometry

A new nodal method for the solution of multigroup multidimensional diffusion problems in hexagonal geometry is developed and implemented into the FORTRAN code HEXPEDITE. The algorithm is adapted for modern computer features including vector and concurrent computations and demonstrates high efficiency and accuracy on many 2-D and 3-D problems. Two procedures consistent with the HEXPEDITE formalism to allow the modeling of mild intranodal heterogeneities due to depletion are outlined.

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

2011

Author dc:creator

• Fitzpatrick, William Edward

Contributors dc:contributor

• Ougouag, Abderrafi M.

• Engineering, Nuclear
• Computer Science

Statement dc:rights

• Copyright 1995 Fitzpatrick, William Edward

Language dc:language

eng

Identifier

AAI9522109
(UMI)AAI9522109

OAI identifier oai:identifier

oai:www.ideals.illinois.edu:2142/20083