A cohesive database for predicting long-term corrosion/erosion of steel exposed
to flowing liquid lead/lead bismuth eutectic. JANA JENSEN
(Brigham Young University
- Idaho, Rexburg, ID, 83440)
SOLI KHERICHA (Idaho National Laboratory, Idaho
Falls, ID, 83415)
In connection
with: NING LI and HUIDAN YU(Los Alamos National Laboratory, Los
Alamos, NM 87545). Liquid lead or lead-bismuth eutectic (Pb/LBE)
is a good candidate for the coolant in accelerator-driven systems
or advanced nuclear reactors of the future. However, corrosion
of the container and structural materials that house the Pb/LBE
presents a critical challenge. Experimentally an active oxygen
control technique has been developed to mitigate corrosion and
contamination in the liquid. This technique was developed and researched
in many laboratories and under numerous conditions. In this work,
the wide-ranging experimental test results reported by groups from
around the world were collected and a cohesive database was created.
The database categorizes and compares the type of structural material,
oxygen concentration, velocity of Pb/LBE, characterizations of
the different loops, and oxide layer thickness/weight loss, etc.
Through this database, an analysis based on kinetic modeling of
the oxidation and corrosion of steels in Pb/LBE was preformed.
Tedmon’s model of oxidation was used as an oxide growth model.
In connection with the completed database, this model was used
to find the parabolic growth constant(Kp) and the scale removal
rate(Kr) for many of the collected experiments. For instance, the
Kp for Idaho National Laboratory’s loop at 700oC
with Fe-3.82%Si sample was calculated to be 8.97E-17 m2/s. Under the same conditions Kr was 7.47E-12 m/s. Using these
constants it was calculated that the oxide thickness of Fe-3.82%
under the same conditions would stabilize to be 6.0E-6 m. Utilizing
the data sets with different loop conditions, oxidation and corrosion
rates will be extracted and further research will be done to predict
long-term corrosion rates which are very difficult to measure in
the short to medium duration tests. Having this complete and defined
database will assist the finding and development of the optimal
steel and operating conditions based on the short to mid-term tests;
long-term tests and verification will still be needed.
Characterization of Immobilized Urease and the Potential for 90Sr Sequestration. DESIREE SWEET (University of Texas at Austin, Austin,
TX, 78712) YOSHIKO FUJITA (Idaho National Laboratory, Idaho Falls,
ID, 83415)
A new technique
for 90Sr sequestration in the subsurface is being investigated
by the Idaho National Laboratory in collaboration with University
of Idaho at Idaho Falls. The technique is based on the idea that
urea hydrolysis, catalyzed by immobilized urease, will accelerate
the rate of calcite precipitation in the subsurface. To prove the
validity of this technique, the kinetics of the immobilized urease
and calcite precipitation must be modeled. The effect of the precipitation
on porosity and permeability must be seen, and it must be proven
that the technique can capture 90Sr. Urea Hydrolysis refers to
the reaction of urea and water catalyzed by the urease enzyme.
The products of urea hydrolysis are ammonia and carbon dioxide.
Urease is an enzyme produced by environmental microorganisms that
currently exist in the subsurface. Consequently, many problems
associated with injection of a reactant can be avoided. A result
of urea hydrolysis is that it increases the carbonate alkalinity,
thus it is a particularly attractive remediation technique in subsurface
environments which are saturated with respect to calcite, as the
likelihood of calcite precipitation becomes even greater. The urea
hydrolysis accelerates the rate at which calcite can be precipitated,
which accelerates the rate at which 90Sr may be coprecipitated,
and removed from the subsurface.
Detecting and Quantifying Heavy Metal Contamination in Water. MATTHEW
LARSEN (Brigham Young University
- Idaho, Rexburg, ID, 83460)
ANGELICA STORMBERG (Idaho National Laboratory, Idaho
Falls, ID, 83415)
The DOE has a
goal of remediating environmental contaminants. We must first know
where the contaminants are, and in what concentration. For detection
of heavy metals in aqueous media a transgenic nematode has been
developed. C. elegens releases a Green Flourescent Protein (GFP)
upon contact with heavy metals. Our work was to calibrate the amount
of flouresence with the concentration of heavy metal contamination.
Water samples can be analyzed in 24 hours, and cost less than 10
cents per sample. We were able to analyze five metals: Zinc, Lead,
Mercury, Cadmium, and Nickel. Each was analyzed at 4 different
concentrations. The calibration curves developed may be used to
test a water sample and determine the concentration of the heavy
metal contaminants.
Eddy Current Non-destructive Inspection Using Giant Magnetoresistive Technology. STEVEN GARDNER (Brigham Young University - Idaho, Rexburg, ID, 83460) DENNIS C. KUNERTH, PH.D. (Idaho National Laboratory, Idaho Falls, ID, 83415)
A prototype eddy
current probe utilizing giant Magnetoresistive technology was found
to have the following benefits: 1. It functions at very low frequencies
(DC to 30 kHz) and deep sample depths. 2. The probe can be characterized
to reveal thickness of an aluminum sample up to 10 mm thick, and
much thicker in stainless steel and other less conductive metals.
3. The probe design uses a noise reduction coil and shield system
which increases signal to noise ratio by nulling drive coil noise.
This probe would be ideal for testing thickness of metals with
low magnetic permeability. It is also effective at locating defects
greater than 0.25 mm on the surface or within the depth of penetration
as determined by the relationship depth (m)
= v(1/ (p*f*µ0*µr*s)) where µ0 is
the permeability of free space, µr is the relative magnetic permeability and s is
the electrical conductivity. Its limitations include: 1. It was
unable to function at frequencies greater than 30 kHz. 2. It was
not able to detect defects smaller than .25 mm or surface defects
which did not extend this same distance or more into the metal.
Attempts were also made to operate the probe using pulse and linear
sweep drives. These attempts did not create satisfactory results.
Much of the lack of success could be due to the fact that it was
not possible to null the drive signal using the noise reduction
coil for either the pulse or the sweep drive methods. The inability
to resolve small defects, and the limitations on the frequency
range appear to be caused by the large coil geometry and the inductance
change introduced by the iron shield.
Extraction of Actinide Elements. SARA MONTGOMERY
(Rochester Institute of Technology, Rochester, NY, 14623) JEFF
GIGLIO (Idaho National Laboratory, Idaho Falls, ID, 83415)
Advanced fuel
specimens of the Materials and Fuel Complex (MFC) containing Plutonium,
Americium, Neptunium, and Zirconium are prepared and sent to the
Advance Test Reactor (ATR) and exposed to neutron bombardment.
Characterization is performed on fuel stock material products before
fabrication of metallic rods, before irradiation, and post irradiation
(PIE). Characterization of the fuel samples is complicated because
of isobaric interferences using inductively coupled plasma mass
spectrometry (ICP-MS). In addition, background complications and
wavelength overlaps complicate analyses by inductively coupled
plasma atomic emission spectroscopy (ICP-AES). To minimize interferences,
and reduce the overall actinide content of the samples (ALARA considerations)
a means of separating the actinides from each other and removal
of the actinides from a sample (i.e. "Clean-up) is needed.
The objective to the research was to simplify separation schemes
using TRU™ resin and manual Gas Pressurized Extraction Chromatography.
The removal of the actinides will allow for more accurate and safer
analysis of fuel samples for trace element impurities (before irradiation)
and fission products after irradiation. The TRU resin worked well
for the retention of Pu and U. However, Np proved to be problematic.
More work is needed to fix the oxidation state of the Np for better
retention. The removal of Pu from the TRU resin was accomplished.
However, the U was not removed from the resin material with the
acid used. The TRU resin worked well in the “Clean-up” of the actinides.
Internal IT Communication through Use of Web Applications. CHRISTOPHER
DUNCAN (Brigham Young University, Provo, UT, 84606) CARL FENNON (Idaho National Laboratory, Idaho
Falls, ID, 83415)
In large organizations,
IT issues that affect many users need effective communication to
ensure the quickest, most efficient, and reasonable response from
both end users and IT staff. The IT infrastructure at the Idaho
National Laboratory, or INL, comprises both an Operations Center
to handle calls and a Field Services arm to make service calls
to its thousands of clients. Currently, INL IT communicates information
regarding issues that affect many users via email or phone. To
unify response from IT and other staff (and to eliminate emails),
it became important to explore how the IT organization could more
efficiently communicate about these issues by using web or other
applications, the Operations Center’s several plasma screens, and
Field Services’ Blackberry devices. Using free PHP scripts to connect
XHTML pages to the laboratory’s SQL Server 2000 databases, a web
application (of approximately 7000 lines of code) was created to
store and retrieve information on current IT issues. To take advantage
of the Operation Center’s Plasma screens, a similar web application
was used to fill an entire plasma screen in addition to two smaller
java based applications that display less of the same information
as the original web application. Pending approval from the INL
Cyber Security Department, a setup for blackberries was created
with access to a SSL secure page using RSS technology to transport
the same information as on the main web application in a simplified,
secure, and "real-time" format. If all prove to be fairly
error-free and stable, then the system would provide an efficient
way of communicating issues for INL IT. If a server, network, or
other system goes down, the technician that works the problem can
efficiently and conveniently let everyone at the laboratory know
about the problem and take appropriate action. IT and other staff
at the laboratory can all do their jobs with greater confidence
and less stress because of access to this forum for technology
issues that affect multiple individuals at the laboratory.
Lead Coolant Test Facility. JAMES
WAGONER (University of Idaho, Moscow, ID, 83843) SOLI KHERICHA (Idaho National Laboratory, Idaho
Falls, ID, 83415)
The Lead Fast
Generation IV Reactor holds a lot of promise for the future of
Nuclear Power. Before a Lead Fast Reactor (LFR) can be built, a
lot of research has to be conducted. The best way to conduct this
research would be to construct a Lead Coolant Test Facility (pictured
center). The Lead Coolant Test Facility (LCTF) would be a small
scale, prototypical Facility. Electric power rods would replace
the nuclear core and the thermal energy generated would be dissipated
through CO2 and cooling water. In order to build this facility,
drawings must be made and managers must be convinced that it must
be built. These drawings and visual aids are what I completed this
summer.
Modeling X-ray Imaging with Monte Carlo N-Particle Software. JEREMIAH
RUESCH (California State University Chico, Chico, CA, 95929) DR. TIMOTHY RONEY (Idaho National Laboratory, Idaho
Falls, ID, 83415)
Monte Carlo simulation
uses stochastic (random sampling) processes to solve equations
that are difficult to solve by other means. For radiation transport
the Boltzmann equation may be solved by Monte Carlo methods. Monte
Carlo N-Particle (MCNP), a stochastic approach to solving the Boltzmann
equation is utilized for our study. To ensure accuracy between
the output of MCNP and known analytic results, a simple geometry
is created with a monoenergetic pencil beam source shooting through
a homogeneous material to a single detector element. The simulation
was performed for three material thicknesses. The simulated detector
response is used to derive the x-ray linear attenuation coefficient
(LAC) of the material from Beer’s Law and compared to the known
LAC of the material for the energy of the source. The processed
MCNP results were less than one percent different from the known
LAC. To begin modeling the radiographic imaging process the material
was changed to be spatially varying, the single detector element
was replaced by a linear detector array of six elements, and the
source changed from a pencil beam to a cone-beam configuration.
The source was centered vertically on the linear detector array
with the face of the array perpendicular to the source. The distance
between source and detector is held fixed. The object is defined
as a rectangular block of iron with a rectangular aluminum insert.
The object is located so that its face is perpendicular to the
source, a distance of two centimeters from the detector array,
and is then held fixed in this location. Moving the source and
detector array to one end of the object, a run of MCNP is taken,
creating a single vertical line of image data. The source and detector
array are then moved a distance of one detector width and the simulation
is repeated yielding an adjoining detector line. This process is
repeated until the entire object is scanned and a two-dimensional
image is produced. The images produced in this manner appear to
have qualitative spatial and contrast features in agreement with
our intuition. We have demonstrated the potential for using a stochastic
particle transport modeling code (MCNP) to simulate x-ray imaging
and have developed confidence in the numerical results by comparing
derived quantities with known quantities (linear attenuation coefficients).
Comparisons with experimental data are needed to validate the methods
employed. This will be our next step.
Production of Syngas for Fischer-Tropsch Synthesis. LANE KNIGHTON
(Brigham Young University, Provo, UT, 84606) LANCE LAUERHASS (Idaho National Laboratory, Idaho
Falls, ID, 83415)
Objective: Analyze
various operations involved in production of syngas and Fischer-Tropsh
(FT) liquids to optimize generation of desirable products and predict
the amount and type of products generated per feedstock type and
amount. Fischer-Tropsch synthesis is used to make synthetic fuels
such as diesel fuel and gasoline. Interested companies have asked
INL to perform such process simulations in order to have an idea
of the products they can generate as well as the waste that must
be cleaned and disposed of. Background: Syngas is mainly a mixture
of H2 and CO along with some impurities. Syngas is generated by
gasifying or pyrolyzing organic material at high temperature. Typical
feedstock can include: 1) Used tires (tire-derived fuel or TDF)
2) Biomass 3) Coal (CTL-Coal to liquids) 4) Natural gas (GTL-Gas
to Liquids) 5) Municipal Solid Waste (MSW) 6) Plastics Waste 7)
Carpet fluff 8) Any other carbon containing material or waste The
feedstock used in these simulations were TDF, herbaceous, and carpet
fluff. Willow, corn stover, wood chips, and straw compositions
were averaged and used as the herbaceous feedstock. Some uses for
syn gas are shown in Figure 1. Some uses that are receiving attention
now are Fischer-Tropsch synthesis and power generation. Some companies
desire to have hybrid plants that divert a portion of the syngas
to produce electrical power by means of a gas turbine & generator
setup, while diverting the rest of the syngas to produce FT liquids.
The optimum combination between power generation and FT liquids
production from an economical standpoint is being investigated.
Some industries such as steel, paper making, etc… want to have
small scale gasifiers on site to provide process heat and power
generation for the plant.
Qualitative Analysis. CARMELITA ROSALES (Idaho State University, Pocatello, ID, 83209) ROBERT RICHARDS (Idaho National Laboratory, Idaho
Falls, ID, 83415)
Qualitative analysis
is research that focuses on how individuals and groups view and
understand the world. Qualitative research is one of the two major
approaches to research methodology in social science and involves
investigating opinions, behaviors and experiences from the informants'
points of view and constructing meaning out of their experiences.
Three methods of gathering qualitative data include: participant
observation, interview, and document analysis. The Center for Human
Performance Improvement (HPI) administered a baseline survey to
three separate organizations within the INL. The purpose of the
baseline was to measure the strengths or weaknesses of specific
organizational attributes. After researching and studying the qualitative
analysis processes, we developed our own methodology for analyzing
the survey comments. We conducted a qualitative analysis of the
comments that were gathered by these surveys; we received over
5,500 comments from the three organizations. We read through each
section, came up with themes that appeared in each area, and then
found themes that represented the entire survey, we then wrote
a report of our findings. Each organization was given its report
and improvement actions are being pursued. As the report for one
of the organizations was a strong indication of a problem, we decided
to study the safety culture for that organization in an attempt
to discover what factors contributed to this organization’s view
on current safety programs.
Radiochemical and Elemental Analysis of Zorita Pressure Vessel Materials. MICHAEL KING (Baker University, Baldwin
City, KS, 66006) JACQUELINE FONNESBECK (Idaho National Laboratory, Idaho
Falls, ID, 83415)
Despite the fact
that nuclear energy has the technological capability to take the
place of fossil fuel as the world’s primary energy source, there
is still overwhelming opposition toward nuclear energy in many
countries. One particular example of recent opposition to nuclear
power occurred in Spain where President Jose Luis Zapatero shut
down the Jose Cabrera (Zorita) Nuclear Power Plant in April of
2006 after thirty-eight years of operation. Closure of the plant
not only reduces the energy production capabilities of Spain, but
it also presents a convoluted and expensive clean up effort. Before
demolition of the 160 MW pressurized water reactor used at Zorita
can commence, various analyses must be preformed to determine the
level of radioactivity present in the reactor materials. The scope
of work consists of the radiochemical and elemental analysis of
the reactor pressure vessel plate materials that were abstracted
from the Zorita reactor. The primary focus will be determining
and classifying "Greater than Class C Waste" isotopes
including: H-3, C-14, Ni-59, Ni-63, Co-60, Sr-90, Nb-94, Tc-99,
I-129 and Cs-137. Class C Waste materials constitute the highest
level of radioactivity which can be considered low level waste
and is usually stored in a landfill. Storage protocol for greater
than class C waste is more stringent and is typically stored in
permanent repositories. In order to determine the composition and
radiological hazards associated with the pressure vessel materials,
various analyses and instrumentation is required. Neutron activation
experiments will be performed at Washington State University to
determine the majority of the elements present in the steel samples.
Additional steel samples will be dissolved at the Materials and
Fuels Complex and the dissolver solution will be analyzed using
various spectrometers and counting instruments including: Inductively
Coupled Plasma Mass Spectrometer, Inductively Coupled Plasma Atomic
Emission Spectrometer, Gamma Spectrometer, Liquid Scintillation
Counter, and X-Ray LEPS. Concurrently, solid pressure vessel samples
will be combusted in a LECO Carbon Analyzer. The C-14 and H-3 will
be collected from the combustion process and liquid scintillation
counting used to determine the quantity of each. The results from
all the analyses will be compiled and the quantity of each isotope
will be reported to Westinghouse Electric in parts per million.
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.
Selection of a Model Extremophilic Bacterium for Biohydrogen Production Studies. CHUCK PEPE-RANNEY (Colorado School
of Mines, Golden, CO, 80401) DEBORAH NEWBY (Idaho
National Laboratory, Idaho
Falls, ID, 83415)
Carboxydotrophic
hydrogen producing microorganisms show the ability to couple carbon
monoxide oxidation with hydrogen production according to the following
equation: CO + H2O
CO2 +
H2.
These carboxydotrophs have been found in several different environments
including deep sea thermal vents, swamps and hot springs. They
have been found as far away as Kunashir Island off the Kamchatka
Peninsula and as nearby as Norris Geyser Basin in Yellowstone National
Park. As interest in the production of clean fuels grows, researchers
are investigating using carboxydotrophs to produce hydrogen from
feedstock gases rich in carbon monoxide. One such feedstock is
coal derived synthesis gas. Microbiologists at Idaho National Laboratory
are investigating the use of carboxydotrophic hydrogen producing
microorganisms to improve hydrogen production from residual carbon
monoxide following catalytic reforming processes for coal derived
synthesis gas. Synthesis gas is kept at high temperatures during
reforming, and as such, thermophilic hydrogenogens have been chosen
for this study. This summer’s research focused on isolating novel
carboxydotrophic hydrogen producing organisms from hot spring environments.
Future research will compare the hydrogen production potential
of novel thermophilic carboxydotrophs to those previously cultured
and a model organism for bench-scale biohydrogen production studies
will be chosen.
Sulfuric Acid Materials Test Loop. DANIEL
LAMONE (The Ohio State University, Columbus, OH, 43210)
STEVEN SHERMAN (Idaho National Laboratory, Idaho
Falls, ID, 83415)
Several hydrogen
production processes are currently under investigation by the US
Department of Energy (DOE) and several foreign governments, most
notably France and Japan, for use in a co-located nuclear plant/hydrogen
production facility. One of these processes is the Sulfur-Iodine
Thermochemical Process. This process utilizes a series of chemical
reactions that are driven by the thermal energy from a Very High
Temperature Gas-Cooled Reactor (VHTR) to thermochemically split
water into hydrogen and oxygen. The high-temperature chemical step
in this process thermally decomposes sulfuric acid (H2SO4) at 850° C,
imposing extreme demands on the process materials. To date, little
research has been conducted in the US to study the long-term effects
of these conditions on structural materials and components, and
there are no existing facilities beyond the bench-top for performing
such tests. Therefore, there is a need for a closed experimental
loop containing sulfuric acid that is capable of exposing samples
and integrated components (e.g. heat exchangers, valve designs,
etc.) to sulfuric acid decomposition products at high temperatures
(750-850 °C) for long periods of time. The loop must be capable
of long-term, continuous operation (hundreds to thousands of hours)
under simulated operational conditions that are to be found in
the actual production facility, accommodate different component
prototype designs and their respective testing requirements, and
operate safely during all periods of operation. This loop will
be built and operated at a US Department of Energy (DOE) facility
or partner facility under the direction of the DOE Nuclear Hydrogen
Initiative (NHI). This project provides a conceptual design for
such a materials and component test loop and will serve as a starting
point for more the more detailed design and safety analysis work
that will be needed once the loop is scheduled for construction
and operation.
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 Theoretical Calculation of Phase Diagrams and Thermophysical Properties
of Potential Nuclear Fuel Alloys. COREY
WESTFALL (Albertson College of Idaho, Caldwell, ID, 83605) IRINA
GLAGOLENKO (Idaho National Laboratory, Idaho Falls, ID, 83415)
With the increase
of nuclear power plants, nuclear waste is becoming an increasing
environmental concern. By transmuting the Actinides in a burner
reactor, the amount of nuclear waste can be decreased significantly.
Zirconium based alloys have been considered for use in burner reactors,
but due to the rarity and dangers of the Actinides, little, if
any, Actinide-Zirconium alloy data exists. To supplement this data,
Thermo-Calc®, a thermodynamic modeling software, was used in conjunction
with TCNF2®, a nuclear fuel database, to create phase diagrams
and property plots for the Actinide-Zirconium binaries, a pseudo-binary
for Am-Pu-Zr, and multiple ternaries for U-Pu-Zr. The graphs were
then compared to experimental plots to identify errors in TCNF2® and
to determine the alloy data needed to correct the database. The
melting temperatures were calculated for multiple alloys of interest
in burner reactors. Thermo-Calc® was shown to perform very well
calculating the melting temperatures and most of the binaries,
but TCNF2® was shown to be lacking data for Np-Zr, most Americium
alloy data, and ternary data. Future work includes the characterization
of the recommended alloys and that incorporation of this data into
TCNF2®.
The Tricks of Trigonometry. JENNIFER OBRAY (Brigham Young
University- Idaho, Rexburg, ID, 83440) DON DUDENHOEFFER (Idaho National Laboratory, Idaho
Falls, ID, 83415)
The Critical
Infrastructure Protection project is tasked with the protection
of physical and cyber security assets which are important to our
nation. They are so important that the destruction or impairment
of these assets would weaken our national security, the security
of our national economic policies, and/or national public health
and safety. For this portion of the project an information portal
was created on the Intranet at the Idaho National Laboratory which
contains subjects on Critical Infrastructure Protection. The portal
is a means to access and add content that pertains to this important
and growing field. Since recent disasters such as the attack of
September 11, 2001 and Hurricane Katrina, along with other threats,
we have realized the weight of this protection program and we have
been working to make the Critical Infrastructure Protection project
stronger. The information portal that I have created gives people
an opportunity to find the information they need pertaining to
different subjects involving the protection programs. The information
provided in the portal was given to me by my mentor, Don Dudenhoeffer,
who had previously decided what to include in the Intranet portal.
I then took that information, organized it, and added it to the
portal in the proper format. For example, there are models of Hurricane
Katrina evacuation plans to provide information for people who
may be working to improve the evacuation time or process. This
useful portal is not only a place to find information but it is
also a place to add other information. There is an upload form
under each of the different subjects that allows anyone with useful
information relating to the subjects to be able to upload it onto
the page so that other people may use it in their research. This
project will increase people’s ability to quickly find the information
they need in order to make decisions about national security and
protection programs, thusly protecting us and the physical and
cyber assets of this nation.
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.
Uncertainty of Available Energy and Available Power. SHAWN
ALLRED (University of Wyoming, Laramie, WY, 82070) JON CHRISTOPHERSEN (Idaho National Laboratory, Idaho
Falls, ID, 83415)
Documenting the
uncertainty analysis of the derived parameters grouped as Available
Energy (AE) and Available Power (AP) for battery cells is a very
complex problem. The error is an unknown combination of both linearity
and offset; the analysis computes the uncertainty both ways and
then the most conservative method is used (which is the worst case
scenario). Each method requires the use of over 134 equations,
some of which are derived and some are measured values. This includes
the measurement device error (calibration error) and bit resolution
and analog noise error (standard deviation error). The implementation
of these equations to acquire a closed form answer was done using
Matlab (an array based programming language). The uncertainty is
automatically computed and will become part of the reported results
for future battery testing.
We Control the Phonons: Coherent Control of Surface Phonons with a Picosecond
Pulse Laser. RYAN LEWIS (Whitman College, Walla
Walla, WA, 99362) DAVID HURLEY (Idaho National Laboratory, Idaho
Falls, ID, 83415)
All over the
world, scientists use lasers to produce very high frequency sound
waves, often using a pump and probe beam to produce and detect
the phonons. In this experiment, we shine our pump beam onto a
semiconductor sample (either Si or GaAs) beneath an Al grating-thusly
generating a coherent surface acoustic wave. Furthermore, we employ
a Michelson interferometer to produce a second, time-delayed pump
pulse, which produces a second surface acoustic wave. With fine
tuning of the micrometer, we achieve both constructive and destructive
interference of the waves. Such coherent control will be useful
in piezoelectric eddy current imaging, as well as managing the
induced strain on quantum structures.
Wind Energy: Changing the Future One Gust at a Time. SHARLA
BOARDMAN (Brigham Young University, Provo, UT, 84606) GARY SEIFERT (Idaho National Laboratory, Idaho
Falls, ID, 83415)
This project
was focused on improving the possibilities of wind power in southeast
Idaho. The main objectives were to set up anemometers, calculate
wind data, create a kiosk proposal for a local wind farm, and accumulate
lesson plans and activities for the Idaho National Lab (INL) wind
outreach program. In order to accomplish the objectives the team
went into the field to set up an anemometer tower. An anemometer
is an electronic device that measures the constant wind speed for
one month’s time. Over a years time the team would return to the
site each month to replace the chip and collect the previous month
data from the chip. The data was then recorded into a program called
Symphonie Data Retriever which uploaded the information to the
INL website. The next step in the project was to take this knowledge
about anemometers and correlate it with lessons and activities
for elementary and secondary education students. These lessons
provided students the basic concepts about wind power and renewable
energy. These concepts are found in most state education standards.
The Outreach website now houses lesson plans for grades k-12. A
college lesson plan curriculum is currently under development.
Another focus for this summer included the proposal for the Wolverine
Creek Wind Farm. This kiosk includes design plans for a visitors’ information
center, as well as the information that would be most beneficial
to the viewers. The idea for the kiosk was presented without any
design or cost constraints. Initially, a brainstorming session
was held to determine possible structure layouts for the informational
area. Once several plans were formulated, cost analysis as well
as feasibility was required to compile and create a professional
proposal. The Outreach website provides critical wind energy information
to students at all educational levels. Once the students obtain
this wind energy education, they are better prepared to make future
decisions that affect the environment.
