GUI for ASEDRA
March 2007
Added a Swing GUI frontend for the ASEDRA spectral deconvolution algorithm
(screenshot). ASEDRA is my master's
thesis, and I am preparing it for commercial release as a supplement to
radiation detection systems.
Kinetics Code 2: Runge-Kutta-Fehlberg Solver
March 2007
Improving the Runge-Kutta solver by adding error control. Applying the
improved solver to the point kinetics equations. This is the numerical
equivalent to the symbolic work in Kinetics Code 1.
Runge-Kutta Solver
February 2007
First order differential equation solver which uses
Runge-Kutta and Euler solution methods. Written for my Reactor Kinetics class and
submitted on February 22, 2007.
Kinetics Code 1
February 2007
Point kinetics code that uses the Laplace transform, written for my Reactor Kinetics
class and submitted on February 19, 2007. This was my first Java application and
used both Apache Ant and JUnit. I learned JUnit when this kinetics code was almost
finished, so my tests cover only a small fraction of the code.
Neutron Diffusion Code 3
April 2005
Criticality search for arbitrary 3-D geometry, written for my Reactor Analysis class and
submitted on April 28, 2005. Materials vary by region, and two
energy levels are modeled. This code was used to model a cylindrical
reactor with Uranium-235 surrounding a water flux trap. As in the second diffusion code
I received a lot of help on
comp.lang.lisp,
mostly with speed tuning. For details, see the following threads:
Neutron Diffusion Code 2
April 2005
Criticality search for a homogenous 1-D slab, written for my Reactor Analysis class and
submitted on April 10, 2005. Both more advanced and cleaner than my
first diffusion code. This is partly because I know how to use arrays
now (simulated them with lists in the first code, using recursion rather
than iteration) and partly because I asked for help on
comp.lang.lisp.
Thanks to Andrew Philpot, Paul Foley, Kenny Tilton, and Kalle Olavi Niemitalo.
I skipped a few of your suggestions due to time constraints, but I am still
looking at them for the next version.
Neutron Diffusion Code 1
March 2005
Fixed source neutron diffusion in a non-multiplying, 1-D, homogenous material.
Covers 3 cases with different boundary conditions (described
by albedo factors). Written on March 24, 2005, for my Reactor
Analysis class. This is my first program written in Common
Lisp. The code performs 100 iterations
rather than checking for convergence, and 100 turns out not to be
enough. The code is also very clumsy, but I will be improving it over
the next few weeks as I continue to study Common Lisp. When I
wrote this program, I was about a third of the way through my
first Lisp book, "The Little Lisper."
Neutron Scattering Code
January 2005
A simple program written in January 2005 for my Reactor Analysis
class. Simulates a neutron scattering off of a nucleus. Input
includes initial energy of neutron, mass of target nucleus, and
center-of-mass scattering angle of the neutron. Output includes
final velocity (speed and direction) of the neutron and the
target nucleus. This is my first program written in Python. It
demonstrates use of lists, dictionaries, for loops, and the
DISLIN graphing library.
AGA Journal Article
June 2004
An description of my unique, homemade Go board. Written as an article for the Journal
of the American Go Association.
UF Go Club
Fall 2002
My first web site, created for the UF Go Club.