Analysis of the Infrastructure That Will Support a Transition to a Hydrogen. TROY MITCHELL (Roane State Community College, Harriaman,
TN, 37748) JUAN FERRADA (Oak Ridge National Laboratory, Oak Ridge,
TN, 37831)
The transition
to a hydrogen economy is assumed to begin in 2020 with a total
of 2.5 million hydrogen cars in seven cities including: Atlanta,
Miami, San Francisco, Detroit, Houston, Chicago, and Los Angeles.
Factors that affect the transition to a hydrogen economy are production,
delivery, storage, and dispensing the hydrogen. Using data from
the Department of Energy’s Hydrogen Analysis (H2A) models, FLOW ©,
a simulation program developed at Oak Ridge National Laboratory,
can simulate the entire hydrogen economy for each one of the cities
used in the analysis. Sensitivity and uncertainty analysis are
applied to determine the affects of fluctuating feedstock prices
and demand for hydrogen. According to the results of the H2A models,
trucking of gaseous hydrogen was not a practical method of delivery.
During this research it was found that Python™ is a user friendly
object-oriented programming language. In terms of unit cost, natural
gas reforming was found to be an effective production method at
lower demands for hydrogen, and coal gasification was found to
be more effective with higher demands of hydrogen. Steam methane
reforming is an effective method of production and distribution,
in terms of unit cost. Piping is an effective method to distribute
hydrogen at low demands. Trucking is more cost effective when hydrogen
demand is higher. Results of the analysis will be used to provide
recommendations for the required infrastructure that will provide
a better transition to a hydrogen economy from the current fossil
fuel economy.
Candidates for new transitions in 254No. DAVID
GRAYSON (University of Illinois
at Urbana Champaign, Urbana, IL, 61801) TENG LEK KHOO (Argonne National Laboratory, Argonne, IL, 60439)
Several candidates
for transitions in 254No have been observed in an experiment performed
at Argonne National Laboratory. The reaction 208Pb(48Ca,2n)254No
was used at beam energies of 219 and 223 MeV. In this report, gamma-gamma
matrices were examined to find candidates that were coincident
with previously known transitions in the ground state band of 254No.
The candidates found were only evident at 223 MeV, which suggests
that they come from parent states with high energies that are not
populated at the lower 219 MeV beam energy. The strongest candidate
was 469 keV. If this transition feeds in to the top of the previously
observed ground state band, then it breaks the pattern of transition
energies, which implies a change in structure at that energy. This
would have implications for the width of a specific neutron "magic
gap", and would help test theories of nuclear structure.
Detection of Concentration Variations of Matrix Metalloproteases. CASSANDRA ARMSTEAD-WILLIAMS (Stanford University, Stanford, CA, 94305)
KARA KRUSE (Oak Ridge National Laboratory, Oak
Ridge, TN, 37831)
In recent years
the Nanoscale Science and Devices group at Oak Ridge National Laboratory
has developed and continues to study how micocantilever technology
can be used to create high-throughput, label-free tests for biological
macromolecules. The Vascular Research Laboratory at the University
Of Tennessee Medical Center of Knoxville is studying the effects
of certain drugs on the concentrations of Matrix Metalloproteases
(MMP’s) in the blood. The Vascular Research Laboratory and the
Nanoscale Devices and Sciences group are working together to create
a dependable, high-throughput, label-free system for quantitatively
measuring concentrations of MMP’s. Microcantilevers bend due to
a change in the entropy and energy on one side of the cantilevers
and not the other. This bending can be monitored optically by reflecting
a laser beam off of the cantilevers and onto a position sensitive
detector (PSD). The PSD translates the optical signal into an electronic
signal for real-time monitoring of microcantilever bending. For
this experiment, gold-coated silicon microcantilevers were immobilized
with 3,3-Dithiobis(sulfosuccinimidylpropionate) (DTSSP)-a homobifunctional,
amine reactive cross linking agent. Immobilizing the cantilevers
with a DTSSP monolayer allows selective attachment of biochemical
molecules onto the gold and silicon/silicon nitride microcantilever
substrate. MMP specific probe antibodies were then attached to
the microcantilevers via a captavidin-biotin linkage system. Surface
amine groups of captavidin were reacted with the succinimide terminals
of DTSSP. The biotin-conjugated, MMP specific probe antibodies
selectively adsorbs onto the captividin protein layer. After functionalization
(immobilization), solutions containing unknown concentrations of
MMP’s are introduced to the microcantilevers while bending is being
monitored. Using a model antibody system, current tests indicate
that DTSSP and antibodies can reliably be immobilized on the cantilever
surfaces. However, we have not been able to determine the antibodies’ range
of sensitivity for protein concentration detection. The reliability
of the DTSSP and antibody immobilization shows that this detection
system can work. We are currently modifying our detection system
and probe immobilization procedures to find the optimal working
range for this technology.
Development of a beam profile diagnostics device for the VENUS ECR ion source
beam line. CARY PINT (University
of Northern Iowa, Cedar
Falls, IA, 50614) DANIELA LEITNER (Lawrence Berkeley
National Laboratory, Berkley, CA, 94720)
This work describes
the design and development of the instrumentation for a beam profile
diagnostics unit for the low energy beam transport line of the
superconducting Electron Cyclotron Resonance (ECR) ion source VENUS
(Versatile ECR ion source for Nuclear Science). VENUS is currently
being commissioned at LBNL and serves as the prototype ECR injector
source for next generation heavy ion accelerators. In order to
enhance simulations of beam transport from extraction in VENUS,
a measurement device (called a harp) consisting of a grid of thin
conducting wires is placed into the beam line, directly downstream
from extraction, to measure the beam profile. Utilizing the diagnostics
unit developed and described in this work, the first measurements
of the beam profile for a simple helium beam are presented. By
changing the Glaser current to focus the ion beam onto the harp,
the helium beam profiles illustrate that the extracted beam has
the same symmetry as the plasma surface from which they are extracted,
and not the uniform circular symmetry that is assumed in most simulation
models. These results give quantitative insight into the enhancement
of initial conditions needed for using simulations to give a physically
accurate description of beam transport from extraction of an ECR
source.
DIRECTED LONG RANGE
THERMAL NEUTRON DETECTION SYSTEM. JEFFREY MAGEDANZ (Oregon State University, Corvallis, OR, 97333)
DR. RAYMOND KLANN (Argonne National Laboratory, Argonne, IL, 60439)
A long range
thermal neutron detection system could be useful for determining
whether a suspected location contains a neutron source. At long
ranges, the flux of neutrons from the source becomes small compared
to the flux of background neutrons. A bundle of collimator tubes
made of a neutron absorbing material could be used to minimize
the effect of background neutrons by only allowing neutrons coming
from the direction of the source to reach the detector. Monte Carlo
N-Particle transport code (MCNP) version 4c was used to simulate
a detector with such a collimator bundle in order to study its
potential and optimize the design. The simulations determined the
response to a moderated californium-252 source at several distances
as well as the response to background neutrons. It was determined
that cadmium was not an adequate shielding material while materials
containing boron, particularly enriched boron, performed well.
A 100 cm2 detector with a collimator was found to be reasonably
certain to detect a source producing 105 neutrons per second at
30 meters in less than a half hour. However, for greater distances,
the time required for detection becomes large. Further research
will compare the simulation results to experimental results.
Engineering Development of the Solid Oxide Electrolysis Cell by Computational
Fluid Dynamics: Restricted Flow. JEFFREY
SMITH (Kansas State University, Manhattan, KS, 66502) DAVID POINTER, BILGE YILDIZ (Argonne National Laboratory, Argonne, IL, 60439)
With the continuing
demand for energy supply and current desire to critical production
of green house gases, there is a call for alternative fuel development.
There is now considerable interest in research on producing alternative
fuels such as bio-fuels, wind power and H2 production. Some 50
million metric tons of H2 with an estimated worth of about $140
B was produced last year, and is expected to increase in years
to come. Several ways of H2 production are used or under conclusion
today such as thermo-chemical processing of hydrocarbons and electrolysis.
With an increased emphasis on nuclear power based technologies
and via the Global Nuclear Energy Partnership, we are considering
advanced nuclear system design that produce high enough temperatures,
to facilitate for example electrolysis to produce hydrogen. Steam
electrolysis to yield H2 and O2 is (electro-chemically) kinetically
and thermodynamically favorable at high temperatures (e.g. 800?C).
The analysis of a steam electrolysis device is the focus of this
work. Engineering analysis of a high temperature steam electrolytic
(HTE) cell is needed to better understand the factors that influence
cell design. The solid oxide fuel cell (SOEC) used to host the
electrolytic process must withstand high temperatures while equally
being reliable, economical and with a practical life cycle. The
DOE’s current goals are to realize a cell lasting a minimum of
5 years of operation with little degradation of the structural
integrity and efficiency of the cell. Via use of computational
fluid dynamic (CFD) software (STAR-CD) and ANL’s electrochemical
model for SOECs that runs coupled with STAR-CD, and experimental
data, determination of the cell’s desirable performance characteristics
were undertaken. In collaboration with Idaho National Labs (INL),
experimental data were obtained to facilitate refinement of the
CFD model of the SOEC. By using this data, ANL’s electrochemical
model of the SOEC was tailored such that further analysis on the
SOEC characteristics, such as material engineering consideration,
geometry and flow configuration (parallel versus cross), beyond
the experimental parameter range could be assessed. A model of
the SOEC was created to simulate restricted flow conditions of
the steam to model the bipolar supported TuffCell design of Argonne
National Laboratory. The TuffCell design has the advantage of overcoming
the sealing issues of SOECs, while imposing restricted flow path
on the steam/hydrogen side of the SOEC. Our analysis found that
the flow restrictions of the TuffCell design created large temperature
and current density gradients that can lead to the structural and
electrochemical degradation of the cell. In prior analysis of ANL,
it was found that the thermodynamic efficiencies of the cell do
vary slightly with parallel or cross flow, while the temperature
profile and gradients are more uniform, symmetric and smaller in
magnitude (gradients) for parallel flow. Our current analysis shows
that, in spite of the mechanical advantages of the TuffCell geometry,
the large thermal and electrical gradients it leads to at the SOEC
is not favorable. In the further design engineering of the SOEC,
we must minimize the possibility of restricted flow or reduced
flow across the cell, and the mechanical sealing advantages of
the TuffCell should be evaluated against its possible degradation
due to large thermal and electrical gradients compared to the base
parallel or counter flow.
Gamma-ray Spectroscopy of Dysprosium-152. JASON
KOZEMCZAK (Greenville College, Greenville, IL, 62246) ROBERT V.
F. JANSSENS (Argonne National Laboratory, Argonne, IL, 60439)
Nuclei at high
excitation energy and spin go through shape deformations, which
are a result of interplay between collective and single-particle
effects, as they decay to their ground states. Of particular interest
are the super-deformed (SD) bands in the A~150 region. In order
to assign correct excitation energy, spin, and parity to these
SD bands, linking transitions must be observed between the SD bands
and the lower-lying normal deformed (ND) bands. 152Dy is one of only a few nuclei where these linking transitions
have been observed. The GAMMASPHERE group at Argonne National Laboratory
wishes to map the complete decay process of this isotope so that
it can be used to develop a realistic model of this process that
will give good predictions of the spins and excitation energies
of SD bands where linking transitions have not been observed. To
correctly model the decay, the single-particle spectra in 152Dy have been analyzed to map out the yrast line to the highest
angular momentum state possible. The fusion reaction 108Pd(48Ca,4n)152Dy
with a beam energy of 191 MeV was used to populate the ND and SD
bands in 152Dy,
and the single-particle level scheme was constructed using triple
and quadruple coincidence events. Angular distribution data have
been analyzed to determine the spins of these states. The analysis
indicates that the single-particle states stay competitive with
the collective states up to very high excitation energy and spin
(at least 20 MeV and 48h, respectively). Furthermore, the coincidence
analysis has raised questions concerning the placement of a linking
transition from a triaxial band to the ND states. Further analysis
is needed to place this transition, as such linking transitions
allow proper spin and excitation assignment to the triaxial states
in question.
Investigating Applications for the Three-Dimensional Design Information Verification
System at Department of Energy Facilities in the United States. AARON
HANSON (Minnesota State University, Mankato, Mankato, MN, 56055) CAMERON COATES (Oak Ridge National Laboratory, Oak
Ridge, TN, 37831)
The current method
used for the annual verification of design information for nuclear
facilities under International Atomic Energy Agency Safeguards
can be labor intensive since this involves manually verifying that
a facility has not been altered over the period of time. This process
generally involves comparing new pictures of the facility to previous
pictures which can require a great deal of time and effort. A new
method was proposed, developed by the European Union’s Joint Research
Center, which involves using a Three-Dimensional Design Information
Verification system. This system uses a laser scanner to take panoramic
images of an environment. These two-dimensional images can be made
into three-dimensional meshes using accompanying software. The
software can automatically compare two three-dimensional images
of the same environment and find differences between them. The
first of the scans is considered to be a reference scan. The later
scan is used for verification, and the verification scan is compared
to the reference scan to determine how the environment has changed
since the reference scan was taken. In this project, three different
environments were set up in order to test the systems capabilities.
The first environment was used to determine how well the system
could detect large movements (0.5m to 1m) of objects within the
environment. The second environment was used to determine how well
the system could detect small movements (0.002m to 0.02m) of objects
within the environment. The third environment was used to determine
if the system can detect the addition of objects to a processing
environment. Different conditions were also incorporated into the
environments such as making the laser scan through glass and/or
water. An analysis of the resulting data showed that the system
was able to detect both small and large movements to an accuracy
of approximately 4mm, as well as find new objects that were added
to the environment. The system is capable of scanning through glass,
but not water. The high level of accuracy and the automatic capabilities
of the system mean that it will be a significant improvement on
the current methods of design information verification for nuclear
facilities, although the inability of the system to scan through
water might lead to difficulty in some areas that hold large amounts
of liquid. Further studies should focus on overcoming this difficulty.
Investigating Possible Economic
Sanctions Against Iran. PETER NEWMAN (Brigham Young University, Provo, UT, 84604)
GARIANN GELSTON (Pacific Northwest National Laboratory, Richland, WA, 99352)
The Economics
of Sanctions - Iran. Peter Newman (Brigham Young University, Provo,
UT, 84606) Barbara Reichmuth (Pacific Northwest National Laboratory,
Richland, WA, 99352). Iran is currently pursuing an aggressive
nuclear program with a declared goal of achieving long-term energy
independence. While this is a worthwhile and generally accepted
national planning objective, there is evidence to indicate that
Iran’s nuclear program may be driven by the desire to produce weapons.
Talks are currently underway between the United Nations (UN) and
Iran, in accordance with the Nuclear Nonproliferation Treaty, to
halt Iran’s uranium enrichment program; a precursor to nuclear
weapons production. In the event UN - Iran talks fail, the United
States Government is evaluating a sanctions package to levy against
Iran to encourage their compliance. Gasoline is one commodity being
considered for restriction. It is estimated Iran will consume 467,000
barrels per day (b/d) of gasoline in 2006, and import 182,000 b/d
(nearly 40%) of that total; thus, making Iran vulnerable to sanctions
against this commodity. In order to effectively sanction gasoline
imports current and potential suppliers must be identified. Utilizing
national and international statistical bureaus along with some
information gathered from private firms a partial portrayal of
gasoline imports into Iran can be illuminated. Measurement (unit)
differences, accounting discrepancies, incomplete or omitted information,
and the general lag in data accumulation pose a real problem in
assembling an accurate and timely depiction of gasoline trade.
While accounting discrepancies between statistical databases are
non-reconcilable, determining trade quantities in spite of unit
differences is possible. Adjusting for various units of measure
is accomplished using specific gravities (density). Upon converting
and compiling all data from various sources for years 2003 - 2005,
approximately 50% - 75% of gasoline purchased by Iran can be characterized.
Although these results will be useful in evaluating sanctions,
they may be insufficient to create the desired economic impact.
Further research is warranted to build upon these findings.
Optimization of the CLAIRE Ion Beam Extraction and Transport System Using Computer
Simulations. NAN XU (University of California, Berkeley, Berkeley, CA, 94720) DAMON S. TODD (Lawrence Berkeley
National Laboratory, Berkley, CA, 94720)
Center for Low
Energy Astrophysics and Interdisciplinary Research (CLAIRE) is
a proposed nuclear astrophysics facility under design at the Lawrence
Berkeley National Laboratory. The facility will measure cross sections
relevant to stellar burning, namely 3He(4He,)7Be,
a reaction which is one of the leading sources of uncertainty when
correlating solar neutrino data with theoretical solar models.
A beam line concept has been developed to extract and transport
a tightly focused (sub-centermeter), high current (100 mA), low
energy (50 keV~300 keV) 3He+ ion beam to a high density gas jet target. The beam is first
extracted from a plasma ion source, and is then focused by two
solenoid lenses. An acceleration column is placed to accelerate
the beam to a higher energy. The envelope of the accelerated beam
is kept as small as possible by another lens before going through
a 60° analyzing magnet for filtering. The last focusing solenoid
lens produces the desired beam size on the target. An extensive
simulation program was employed to optimize the extraction and
the transport of a 100 mA, 3He+ beam at 50 keV. The source extraction electrodes will have to
undergo further shaping including rounding of corners, but provide
the preliminary source configuration that can be used to design
the remainder to the beam transport system. Initial work was done
on the acceleration column to insure that accelerated beams can
arrive at the source with similar qualities, but further modifications
of the simulation are needed and further fine tuning must take
place for the final design. The detailed analysis of this simulation
will be shown and discussed.
Previous, Current, and Predicted Trends for Applications Using Source Material
as Covered by the U.S. Nuclear Regulatory Commission General License. CASSANDRA BEATTY (Cornell University, Ithaca, NY, 14850) EVA HICKEY (Pacific Northwest National Laboratory, Richland, WA, 99352)
With sensitivity
to terrorism having heightened since 9/11 and the nuclear energy
industry planning to expand in the near future, monitoring the
use of fissile and fissionable materials is becoming ever more
important. The products and processes that use naturally occurring
radioactive materials must be reviewed not only to protect worldwide
radioactive resources but the general public as well. The U.S.
Nuclear Regulatory Commission (NRC) provides a general license
for agencies to use and transfer not more than 15 pounds of materials
that contain 0.05% by weight uranium, thorium, or any combination
thereof. Regardless, current industrial trends indicate a general
decline in the use of thorium and uranium. Thorium was traditionally
used in ceramics for refractory purposes but now is primarily used
in scientific research and a few electrical applications. Uranium,
once popular in pigments and glazes, is now almost entirely limited
to military applications that require special licensure and scientific
research. Industry substitutes and alternate processes that do
not involve uranium and thorium are becoming increasingly popular.
If regulatory pressure and public sentiment continue to impede
the ease of use of naturally occurring radioactive materials, the
NRC general license may become obsolete with respect to uranium
and thorium.
Proton Recoil Detectors and Fission Ionization Chambers for Neutron Dosimetry. BRENT WILSON (Merced College, Mered, CA, 95340) PEGGY MCMAHAN
(Lawrence Berkeley National
Laboratory, Berkley, CA, 94720)
Neutrons are ionizing
particles, which cause damage to human cells, including astronauts,
and electronics. They are difficult to directly detect due to a neutral
charge; however, there are several different ways to develop a neutron
detector to measure neutron flux indirectly. This research involved
the creation and development of two neutron detectors: the prototypes
of a proton recoil detector and a fission ionization chamber. The
intention was to measure neutrons of 5 to 30 MeV, but since the neutron
beam was not available, a proton beam was used instead. A proton
recoil detector is composed of a solid-state detector, which electronically
counts how many protons are being recoiled out of a plastic medium
to determine the incident number of neutrons. In this particular
prototype, a 50.0 MeV proton beam was used to show that this prototype
worked for the first phase of testing. The next phase of testing
will include neutron beams with energies between 5 and 30 MeV for
actual proton recoil and a plastic medium containing an ample amount
of hydrogen, like polyethylene terephthalate (Mylar). A fission ionization
chamber indirectly counts the number of neutrons by means of a gas-filled
chamber and fissile foil (e.g., thorium), in which fission fragments
produce ion charges, so that measuring the total charge count leads
to a calculation of neutron flux. In this particular prototype, an
americium-beryllium source was used as a neutron emitter for testing
the ion charge collection. The chamber was filled with nitrogen gas
at one atmosphere pressure and contained two electrodes, biased to
-325 V, and the other used for ion collection to electronics. The
prototype fission ionization chamber has just been completed, and
tests for functionality are currently being conducted. The next prototype
of the fission ionization chamber will include evaporation of the 232Th
onto a window and neutron tests from 5 to 30 MeV in beam.
Reliability of Large Power Supplies for a DIII-D Tokamak. CHRISTOPHER
O'CONNOR (Idaho State University, Pocatello, ID, 83209) LEE CADWALLADER (Idaho National Laboratory, Idaho
Falls, ID, 83415)
This summer I performed
data analysis and wrote the first draft of report INL/EXT-06-11555
which contains a reliability analysis of magnet and plasma heating
power supplies in use at the DIII-D magnetic fusion experiment operated
by General Atomics in San Diego, California. Many types of power
supplies are required to operate the experiment. The magnets require
ac to dc power conversion, the neutral beam injectors require several
types of power supplies, and the plasma heating requires high amperage
power supplies. The power supplies for the now DIII-D tokamak were
installed and commissioned during the late 1970’s and the beginning
of the 1980’s. DIII-D operation began in 1987 and the Trouble Report
data collection began in May 1987. For this analysis I reviewed and
categorized over 1700 trouble reports on thirty large power supplies
for the toroidal field coil, ohmic heating coil, field shaping coils,
and neutral beams. After completing that analysis I compared the
results to similar data work on the Joint European Torus in the United
Kingdom. The data comparisons ranged between good and fair, helping
to validate the data values obtained from these two independent fusion
experiments. These data results will be added to a component failure
rate data base that is used to support fusion experiment reliability,
availability, and safety assessment.
Study of Beam Spin Asymmetry in Exclusive πo
Production. IAN HOWLEY (The College of William
and Mary, Williamsburg, VA, 23186) HARUT AVAKIAN (Thomas Jefferson National Accelerator Facility, Newport News, VA, 23606)
Describing and
understanding atomic nuclei is a puzzle that has intrigued scientists
for decades. Approximately ten years ago, a way to describe nucleon
structure, referred to as Generalized Parton Distribution (GPD),
was introduced. GPDs are a way of describing scattering and production
processes in a single framework. Deeply Virtual Compton Scattering
(DVCS) is a process that scatters a photon from a proton and detects
a scattered electron, a proton, and one photon in the final state.
From DVCS, GPDs can be extracted in order to lead us to a more complete
picture of nucleon structure. The focus of this study is to understand
the beam spin asymmetry (BSA) of the neutral πo meson,
a main source of background during the DVCS process. To calculate
the BSA, the number of πo events
with positive helicity (spin) and negative helicity were counted
by integrating histograms with Gaussians fits. It is shown that there
is a significant non-zero BSA in production of exclusive πo,
namely 0.0655 ± 0.0022. In the analysis of previous experiments,
the BSA of πo was
assumed to be zero and therefore ignored. Now, since it is proven
to exist, it can be taken into account in future DVCS studies. A
deeper understanding of background processes (πo) in the DVCS will allow precision measurements of GPDs, providing
new insight concerning the structure of nucleons.
System Dynamics: JAIMEE WILLIAMS
(Brigham Young University, Provo, UT, 84602) JACOB JACOBSON (Idaho National Laboratory, Idaho
Falls, ID, 83415)
VISION (Verifiable
Fuel Cycle Simulation Model) is a dynamic model of the nuclear fuel
cycle developed at the Idaho National Laboratory (INL). The model
tracks the mass of useable fuel, dangerous isotopes, and weapons
useable material for adding different types of fuel cycle scenarios
to the U.S. reactor fleet. Speed and ease of use differentiate VISION
from other more complex models. VISION was developed in a modeling
program called POWERSIM, which has uncertainty analysis built in
which is necessary to gain a valuable estimation of the cost associated
with nuclear fuel cycle. Unfortunately POWERSIM’s sampling method
fails to distinguish the economic sub-model from the main VISION
model. A consequence is that POWERSIM reruns the entire model each
time the economic sub-model is run; although no new information is
gained. A good sampling size of 10,000 runs at thirty seconds per
run would take three and a half days. The objective of this project
was to develop a simple sampling method implementing a Latin hypercube
algorithm. Latin Hypercube Sampling (LHS) is a stratified sampling
technique where the random variable distributions are divided into
equal probability intervals. A probability is randomly selected from
within each interval for each basic event. Generally, LHS will require
fewer samples than simple Monte Carlo Sampling. However, due to the
stratification method used, it may take longer to generate a value
than for a Monte Carlo Sampling however, the LHS technique will give
us a more accurate cost analysis. The Latin hypercube algorithm we
implemented works by dividing up the cost distributions into two
hundred equally probable events and randomly sampling from them.
The key to our approach was decoupling the economic sub-model from
the main model, meaning we only ran the VISION model once for numerous
iterations on the economics sub-model. Our new approach allowed us
to sample 10,000 runs in two minutes, which is a vast improvement
over the old sampling methods. The approach implemented allows VISION
users to easily access cost analysis data without waiting for extended
periods of time. This is in keeping with the objectives sought by
VISION; speed and ease of use.
The Optimization of Environmental Sample Data Analysis and Visualization. MATTHEW ANDERSEN (Southern Adventist University, Collegedale, TN, 37315)
DIANE FISCHER (Oak Ridge National Laboratory, Oak
Ridge, TN, 37831)
For the last 10
years, the International Atomic Energy Agency (IAEA) has been collecting,
organizing, and storing vast amounts of environmental sampling (ES)
data. ES data are used by the IAEA to detect undeclared nuclear activities
all across the world. Currently, the analysis of this data is time-consuming
and inefficient due to a lack of integrated data evaluation tools.
The first objective in providing a solution to this problem was to
evaluate multiple software suites used in data modeling. The second
objective was to develop an easy-to-use, multifunctional graphical
user interface (GUI) that allows quick customization and visualization
of ES data analysis information using one, or a combination of several,
of the options explored in the first objective. The evaluation process
included examining the software’s documentation; downloading and
testing freeware, trialware, or full versions of the software; and
attending software tutorials. Initial models for the interface were
based upon current IAEA methodologies and inquiries concerning desired
features for the data analysis and visualization output. Several
books on nuclear forensics and programming were used in the maturing
of the GUI’s design and functionality. The finalized GUI was developed
for the Microsoft Excel 2003 software package using Excel’s integrated
Visual Basic for Applications programming language. This new interface
allows users to more efficiently add to or modify the visualization
of the data. Fast access to functionality not previously available
was also incorporated. New features include the ability to plot multiple
data sets on the same graph, based on country, facility name, facility
code, material balance area, location, or any combination of these,
as well as the ability to remove specific data sets from a given
graph. This new GUI gives the IAEA a graphical tool that will aid
in understanding and analyzing ES data. The improvements offered
by the software will allow personnel to make more efficient use of
their time while having the tools needed to help them make more-informed
decisions. The customization and functionality of this new model
permits adaptation to many other data analysis and visualization
scenarios, not just those involved with nuclear safeguards data.
As with any software, future work will include adjustment to new
technology and the implementation of additional features as output
requirements change.
The Re-creation of the Flow Nuclear and Chemical Simulation Program as a Cross-Platform,
Fully-Customizable Application. BRYAN
BURKE (University of Tennesse, Knoxville, TN, 37916) JUAN FERRADA (Oak Ridge National Laboratory, Oak
Ridge, TN, 37831)
FLOW® is a nuclear
and chemical software simulation tool originally written in 1991
for the Disk Operating System (DOS). Recently there arose a need
to update the application to take advantage of new technologies and
programming languages for the purposes of cross-platform availability
and eventually Internet-based access and execution. In preparation
for this project, several days were dedicated to using the original,
full-featured DOS version of the application and the more recent
Windows®-based Visual Basic® beta version. Once a basic familiarity
with the program had been established, the Java® and Python® programming
languages were selected as the first options for coding the program’s
new graphical user-interface and simulation back-end, respectively.
Research was done using the official Sun Microsystems® Java Application
Programming Interface (API) reference and the official Python library
reference. As robust, cross-platform, and widely available languages,
these were determined to be suitable for the new version of FLOW.
As of this writing, the new FLOW is completely customizable and allows
for simulations of arbitrary size and complexity to be created and
executed on at least three platforms: Windows, Apple Macintosh®,
and Linux. Sensitivity and uncertainty analysis are not currently
implemented; however at least one, if not both, are expected to be
included by the end of the summer, 2006. Finally, preliminary work
is being done to determine the viability of implementing an algorithm
which, given constraints, inputs and tools, would determine the most
efficient simulation for accomplishing a given task. This application
has numerous possibilities, and its utility is not limited to nuclear
and chemical research. It could also easily be adapted to run on
a centrally located server, accessible via the Internet and, if the
need should arise, to take advantage of a multi-processor computer
for optimal performance.
The Standardization and Upgrade of Isotopic Enrichment Measurement Software
through the Analysis of Enriched Uranium Standards. LINDSAY
OWENS (Brigham Young University
- Idaho, Rexburg, ID, 83460)
MARY D. EIPELDAUER (Oak Ridge National Laboratory, Oak
Ridge, TN, 37831)
There are many
accepted isotopic enrichment measurement software packages used to
identify and measure levels of enriched uranium and plutonium. The
basis for the following project has come about in response to inconsistencies
in the types and versions of software being used. In addition to
comparing the accepted software, the goal is to decide on a single
international standard. The United States Department of Energy/National
Nuclear Security Administration through Oak Ridge National Laboratory
(ORNL), Lawrence Livermore National Laboratory, Los Alamos National
Laboratory, in conjunction with the Brazilian-Argentine Agency for
Accounting and Control of Nuclear Materials, are testing and evaluating
isotopic enrichment measurement software packages to identify the
most effective software. The software packages undergoing testing
at ORNL are: WinU235, NaIGEM, MGAU (v3.21 and v4.0), and ISOTOPIC.
In order to test these software programs, the Safeguards Laboratory
at ORNL is conducting eight experiments. The setups for the experiments
consist of germanium and sodium iodide detectors in combination with
a variety of multi-channel analyzers. The experiments have been prearranged
to include a variety of different measurement distances, attenuator
materials, and thicknesses of attenuators. The eight uranium standards
used range from depleted uranium (0.31% enriched) up to highly enriched
uranium (93.17% enriched). For each standard, spectra are collected
for 1000 seconds and repeated for six trials. In Experiment 1, which
used a Canberra Planar germanium detector with a MCA-166 multi-channel
analyzer, the spectra were analyzed using MGAU v3.21, and the six
trials for each spectrum were condensed by calculating the averages
for the following categories: Measured Percentage of U-235 - Declared
Percentage of U-235, Standard Deviation [Measured -Declared/Declared
Weight Percentage], Measured Percentage of U-235, Absolute Error,
and Percent Error. The work completed thus far is a small part of
a much larger project, and thousands of spectra remain to be analyzed.
In order to better understand how the software programs compare to
each other and eventually decide upon a single international standard,
the data gleaned from analyzing the spectra must be compressed and
organized in such a way that a comparison can be made. A significant
amount of work remains in the present efforts to standardize and
upgrade existing isotopic enrichment measurement software.
Thermo-hydraulic Design and Analysis of Lead Coolant Test Facility (LCTF). RYAN DALLING (Brigham Young University - Idaho, Rexburg, ID, 83440) SOLI KHERICHA (Idaho National Laboratory, Idaho
Falls, ID, 83415)
The Lead Fast Reactor
(LFR) is one of the six concepts selected on the Generation IV Road
Map by the Generation IV International Forum. If certain technical
innovations can be proven in the LFR reactor concept, it will provide
a unique and attractive nuclear energy system. Thus, advancement
of the LRF beyond the conceptual phase will require lab demonstrations
and tests involving many research and development issues. The Idaho
National Laboratory (INL) is working on such test loops by further
developing the LCTF. The laboratory demonstration of key attributes
of the LFR design can be provided by the LCTF which would conduct
such tests on certain issues. The thermo-hydraulic tests will allow
the LCTF to prove the functionality of the many attractive attributes
provided by the LFR. In order to build the LCTF, a thermo-hydraulic
analysis of the LCTF was conducted to produce a proposed preliminary
design and concept. This analysis was first conducted using a Microsoft
Excel spreadsheet with lead as the primary coolant, and then conducted
in RELAP5-3d with lead-bismuth as the primary coolant. An envelope
of variation of various LCTF parameters providing different design
options was created using the results of these analyses, which will
facilitate any further R&D needs in the future when the LCTF
is to be further developed. The two models (Excel, RELAP5-3d) provide
sufficient, valuable information to make preliminary design decisions
of the LCTF.
Tritium diffusivity in metals; response of a tritium monitor to Cs-137 gammas;
dose-response relationship function of species mass, DNA content
and chromosomes. CHRISTOPHER COPELAND (Morehouse College, Atlanta, GA, 30314) MICHAEL SINGH (Lawrence Livermore
National Laboratory, Livermore, CA, 94550)
Tritium will be
used as a fuel for the NIF ignition experiments. Understanding its
behavior in various materials is important to evaluate inventory
and to develop safety plans for handling tritiated hardware. Since
tritium monitors will be used for evaluating airborne tritium concentration,
the response of tritium monitor, an ion chamber, was calculated as
a function of distance from the center of the chamber to the source
location. A Cs-137 gamma check source was used to determine the experimental
response of the meter as a function of distance from the center of
the chamber. Cs-137 emits beta radiation (95% - 0.514 MeV, and 5%
- 1.18 MeV; with 0.661 MeV gammas). Its half-life is about 30.07
years. By correlating a simple relationship between the tritium energy
deposition and gamma energy deposit in the chamber volume, an external
gamma source can be used to both check the response and calibrate
the meter precisely. Also had a brief opportunity to study the radiation
dose-response relationship, primarily for acute doses, for various
species as function of DNA content, number of chromosomes, body mass,
etc. Some discussions were held in the areas of radiobiology and
nuclear medicine.
