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2 x 2 Polyethylene Reflected and Moderated Highly Enriched Uranium System with Rhenium
The 2 × 2 array HEU-Re experiment was performed on the Planet universal critical assembly machine on November 4th, 2003 at the Los Alamos Critical Experiments Facility (LACEF) at Los Alamos National Laboratory (LANL). For this experiment, there were 10 ½ units, each full unit containing four HEU foils and two rhenium foils. The top unit contained only two HEU foils and two rhenium foils. A total of 42 HEU foils were used for this experiment. Rhenium is a desirable cladding material for space nuclear power applications. This experiment consisted of HEU foils interleaved with rhenium foils and is moderated and reflected by polyethylene plates. A unit consisted of a polyethylene plate, which has a recess for rhenium foils, and four HEU foils in a single layer in the top recess of each polyethylene plate. The Planet universal criticality assembly machine has been previously used in experiments containing HEU foils interspersed with SiO2 (HEU-MET-THERM-001), Al (HEU-MET-THERM-008), MgO (HEU-MET-THERM-009), Gd foils (HEU-MET-THERM-010), 2 × 2 × 26 Al (HEU-MET-THERM-012), Fe (HEU-MET-THERM-013 and HEU-MET-THERM-015), 2 × 2 × 23 SiO2 (HEU-MET-THERM-014), 2 × 2 × 11 hastalloy plates (HEU-MET-THERM-016), and concrete (HEU-MET-THERM-018). The 2 × 2 array of HEU-Re is considered acceptable …
Date:
September 1, 2010
Creator:
Ellis, A. Nichole; Hutchinson, Jesson; Bess, John D.; Polyakov, Dmitry N.; Glushkov, Evgeny S. & Glushkov, Alexey E.
Object Type:
Report
System:
The UNT Digital Library
100-NR-2 Apatite Treatability Test: High-Concentration Calcium-Citrate-Phosphate Solution Injection for In Situ Strontium-90 Immobilization
Following an evaluation of potential strontium-90 (90Sr) treatment technologies and their applicability under 100-NR-2 hydrogeologic conditions, the U.S. Department of Energy (DOE), Fluor Hanford, Inc. (now CH2M Hill Plateau Remediation Company [CHPRC]), Pacific Northwest National Laboratory, and the Washington State Department of Ecology agreed that the long-term strategy for groundwater remediation at the 100-N Area should include apatite as the primary treatment technology. This agreement was based on results from an evaluation of remedial alternatives that identified the apatite permeable reactive barrier (PRB) technology as the approach showing the greatest promise for reducing 90Sr flux to the Columbia River at a reasonable cost. This letter report documents work completed to date on development of a high-concentration amendment formulation and initial field-scale testing of this amendment solution.
Date:
September 1, 2010
Creator:
Vermeul, Vincent R.; Fritz, Brad G.; Fruchter, Jonathan S.; Szecsody, James E. & Williams, Mark D.
Object Type:
Report
System:
The UNT Digital Library
2009 Groundwater Monitoring Report Central Nevada Test Area, Corrective Action Unit 443
This report presents the 2009 groundwater monitoring results collected by the U.S. Department of Energy (DOE) Office of Legacy Management (LM) for the Central Nevada Test Area (CNTA) Subsurface Corrective Action Unit (CAU) 443. Responsibility for the environmental site restoration of CNTA was transferred from the DOE Office of Environmental Management to LM on October 1, 2006. The environmental restoration process and corrective action strategy for CAU 443 are conducted in accordance with the Federal Facility Agreement and Consent Order entered into by DOE, the U.S. Department of Defense, and the State of Nevada. The corrective action strategy for the site includes proof-of-concept monitoring in support of site closure. This report summarizes investigation activities associated with CAU 443 that were conducted at the site from October 2008 through December 2009. It also represents the first year of the enhanced monitoring network and begins the new 5-year proof-of-concept monitoring period that is intended to validate the compliance boundary
Date:
September 1, 2010
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
2010 Remediation Effectiveness Report for the U.S. Department of Energy Oak Ridge Reservation, Oak Ridge, Tennessee - Data and Evaluations
Under the requirements of the Oak Ridge Reservation (ORR) Federal Facility Agreement (FFA) established between the U.S. Department of Energy (DOE), the U.S. Environmental Protection Agency, (EPA) and the Tennessee Department of Environment and Conservation (TDEC) in 1992, all environmental restoration activities on the ORR are performed in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Since the 1990s, the environmental restoration activities have experienced a gradual shift from characterization to remediation. As this has occurred, it has been determined that the assessment of the individual and cumulative performance of all ORR CERCLA remedial actions (RAs) is most effectively tracked in a single document. The Remediation Effectiveness Report (RER) is an FFA document intended to collate all ORR CERCLA decision requirements, compare pre- and post-remediation conditions at CERCLA sites, and present the results of any required post-decision remediation effectiveness monitoring. First issued in 1997, the RER has been reissued annually to update the performance histories of completed actions and to add descriptions of new CERCLA actions. Monitoring information used in the 2010 RER to assess remedy performance was collected and/or compiled by DOE's Water Resources Restoration Program (WRRP). Only data used to assess performance of …
Date:
September 1, 2010
Creator:
Bechtel Jacobs
Object Type:
Report
System:
The UNT Digital Library
2D Thermal Hydraulic Analysis and Benchmark in Support of HFIR LEU Conversion using COMSOL
The research documented herein was funded by a research contract between the Research Reactors Division (RRD) of Oak Ridge National Laboratory (ORNL) and the University of Tennessee, Knoxville (UTK) Mechanical, Aerospace and Biomedical Engineering Department (MABE). The research was governed by a statement of work (SOW) which clearly defines nine specific tasks. This report is outlined to follow and document the results of each of these nine specific tasks. The primary goal of this phase of the research is to demonstrate, through verification and validation methods, that COMSOL is a viable simulation tool for thermal-hydraulic modeling of the High Flux Isotope Reactor (HFIR) core. A secondary goal of this two-dimensional phase of the research is to establish methodology and data base libraries that are also needed in the full three-dimensional COMSOL simulation to follow. COMSOL version 3.5a was used for all of the models presented throughout this report.
Date:
September 1, 2010
Creator:
Freels, James D; Bodey, Isaac T; Lowe, Kirk T & Arimilli, Rao V
Object Type:
Report
System:
The UNT Digital Library
3D Technology for intelligent trackers
At Super-LHC luminosity it is expected that the standard suite of level 1 triggers for CMS will saturate. Information from the tracker will be needed to reduce trigger rates to satisfy the level 1 bandwidth. Tracking trigger modules which correlate information from closely-spaced sensor layers to form an on-detector momentum filter are being developed by several groups. We report on a trigger module design which utilizes three dimensional integrated circuit technology incorporating chips which are connected both to the top and bottom sensor, providing the ability to filter information locally. A demonstration chip, the VICTR, has been submitted to the Chartered/Tezzaron two-tier 3D run coordinated by Fermilab. We report on the 3D design concept, the status of the VICTR chip and associated sensor integration utilizing oxide bonding.
Date:
September 1, 2010
Creator:
Lipton, Ronald
Object Type:
Article
System:
The UNT Digital Library
Accelerating Commercialization of Algal Biofuels Through Partnerships (Brochure)
This brochure describes NREL's algal biofuels research capabilities and partnership opportunities.
Date:
September 1, 2010
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Acceptance sampling using judgmental and randomly selected samples
We present a Bayesian model for acceptance sampling where the population consists of two groups, each with different levels of risk of containing unacceptable items. Expert opinion, or judgment, may be required to distinguish between the high and low-risk groups. Hence, high-risk items are likely to be identifed (and sampled) using expert judgment, while the remaining low-risk items are sampled randomly. We focus on the situation where all observed samples must be acceptable. Consequently, the objective of the statistical inference is to quantify the probability that a large percentage of the unsampled items in the population are also acceptable. We demonstrate that traditional (frequentist) acceptance sampling and simpler Bayesian formulations of the problem are essentially special cases of the proposed model. We explore the properties of the model in detail, and discuss the conditions necessary to ensure that required samples sizes are non-decreasing function of the population size. The method is applicable to a variety of acceptance sampling problems, and, in particular, to environmental sampling where the objective is to demonstrate the safety of reoccupying a remediated facility that has been contaminated with a lethal agent.
Date:
September 1, 2010
Creator:
Sego, Landon H.; Shulman, Stanley A.; Anderson, Kevin K.; Wilson, John E.; Pulsipher, Brent A. & Sieber, W. Karl
Object Type:
Report
System:
The UNT Digital Library
Accuracy Based Generation of Thermodynamic Properties for Light Water in RELAP5-3D
RELAP5-3D interpolates to obtain thermodynamic properties for use in its internal calculations. The accuracy of the interpolation was determined for the original steam tables currently used by the code. This accuracy evaluation showed that the original steam tables are generally detailed enough to allow reasonably accurate interpolations in most areas needed for typical analyses of nuclear reactors cooled by light water. However, there were some regions in which the original steam tables were judged to not provide acceptable accurate results. Revised steam tables were created that used a finer thermodynamic mesh between 4 and 21 MPa and 530 and 640 K. The revised steam tables solved most of the problems observed with the original steam tables. The accuracies of the original and revised steam tables were compared throughout the thermodynamic grid.
Date:
September 1, 2010
Creator:
Davis, Cliff B.
Object Type:
Article
System:
The UNT Digital Library
Adagio 4.18 user's guide.
Adagio is a Lagrangian, three-dimensional, implicit code for the analysis of solids and structures. It uses a multi-level iterative solver, which enables it to solve problems with large deformations, nonlinear material behavior, and contact. It also has a versatile library of continuum and structural elements, and an extensive library of material models. Adagio is written for parallel computing environments, and its solvers allow for scalable solutions of very large problems. Adagio uses the SIERRA Framework, which allows for coupling with other SIERRA mechanics codes. This document describes the functionality and input structure for Adagio.
Date:
September 1, 2010
Creator:
Spencer, Benjamin Whiting
Object Type:
Report
System:
The UNT Digital Library
Advanced Cell Development and Degradation Studies
The Idaho National Laboratory (INL) has been researching the application of solid-oxide electrolysis cells for large-scale hydrogen production from steam over a temperature range of 800 to 900ºC. From 2003 – 2009, this work was sponsored by the DOE Nuclear Hydrogen Initiative (NHI). Starting in 2010, the HTE research program has been sponsored by the Next Generation Nuclear Plant (NGNP) program. HTSE research priorities in FY10 are centered on understanding and reducing cell and stack performance degradation to an acceptable level to advance the technology readiness level of HTSE and to justify further large-scale demonstration activities. This report provides a summary of our FY10 experimental program, which has been focused on advanced cell and stack development and degradation studies. Advanced cell and stack development activities are under way at five technology partners: MSRI, Versa Power, Ceramatec, NASA Glenn, and St. Gobain. Performance evaluation of the advanced technology cells and stacks has been performed by the technology partners, by MIT and the University of Connecticut and at the INL HTE Laboratory. Summaries of these development activities and test results are presented.
Date:
September 1, 2010
Creator:
O'Brien, J. E.; Stoots, C. M.; Herring, J. S.; O'Brien, R. C.; Condie, K. G.; Sohal, M. et al.
Object Type:
Report
System:
The UNT Digital Library
ADVANCED RADIOISOTOPE HEAT SOURCE AND PROPULSION SYSTEMS FOR PLANETARY EXPLORATION
The exploration of planetary surfaces and atmospheres may be enhanced by increasing the range and mobility of a science platform. Fundamentally, power production and availability of resources are limiting factors that must be considered for all science and exploration missions. A novel power and propulsion system is considered and discussed with reference to a long-range Mars surface exploration mission with in-situ resource utilization. Significance to applications such as sample return missions is also considered. Key material selections for radioisotope encapsulation techniques are presented.
Date:
September 1, 2010
Creator:
O'Brien, R. C.; Howe, S. D. & Werner, J. E.
Object Type:
Article
System:
The UNT Digital Library
Advanced Simulation and Optimization Tools for Dynamic Aperture of Non-scaling FFAGs and Accelerators including Modern User Interfaces
With the U.S. experimental effort in HEP largely located at laboratories supporting the operations of large, highly specialized accelerators, colliding beam facilities, and detector facilities, the understanding and prediction of high energy particle accelerators becomes critical to the success, overall, of the DOE HEP program. One area in which small businesses can contribute to the ongoing success of the U.S. program in HEP is through innovations in computer techniques and sophistication in the modeling of high-energy accelerators. Accelerator modeling at these facilities is performed by experts with the product generally highly specific and representative only of in-house accelerators or special-interest accelerator problems. Development of new types of accelerators like FFAGs with their wide choices of parameter modifications, complicated fields, and the simultaneous need to efficiently handle very large emittance beams requires the availability of new simulation environments to assure predictability in operation. In this, ease of use and interfaces are critical to realizing a successful model, or optimization of a new design or working parameters of machines. In Phase I, various core modules for the design and analysis of FFAGs were developed and Graphical User Interfaces (GUI) have been investigated instead of the more general yet less easily manageable console-type …
Date:
September 1, 2010
Creator:
Mills, F.; Makino, K.; Berz, M. & Johnstone, C.
Object Type:
Report
System:
The UNT Digital Library
Advanced Sodium Fast Reactor Accident Source Terms : Research Needs
An expert opinion elicitation has been used to evaluate phenomena that could affect releases of radionuclides during accidents at sodium-cooled fast reactors. The intent was to identify research needed to develop a mechanistic model of radionuclide release for licensing and risk assessment purposes. Experts from the USA, France, the European Union, and Japan identified phenomena that could affect the release of radionuclides under hypothesized accident conditions. They qualitatively evaluated the importance of these phenomena and the need for additional experimental research. The experts identified seven phenomena that are of high importance and have a high need for additional experimental research: High temperature release of radionuclides from fuel during an energetic event<U+F0B7>Energetic interactions between molten reactor fuel and sodium coolant and associated transfer of radionuclides from the fuel to the coolant<U+F0B7>Entrainment of fuel and sodium bond material during the depressurization of a fuel rod with breached cladding<U+F0B7>Rates of radionuclide leaching from fuel by liquid sodium<U+F0B7>Surface enrichment of sodium pools by dissolved and suspended radionuclides<U+F0B7>Thermal decomposition of sodium iodide in the containment atmosphere<U+F0B7>Reactions of iodine species in the containment to form volatile organic iodides. Other issues of high importance were identified that might merit further research as development of the mechanistic model …
Date:
September 1, 2010
Creator:
Powers, Dana Auburn; Clement, Bernard; Denning, Richard; Ohno, Shuji & Zeyen, Roland
Object Type:
Report
System:
The UNT Digital Library
Advanced Soldier Thermoelectric Power System for Power Generation from Battlefield Heat Sources
The U.S. military uses large amounts of fuel during deployments and battlefield operations. This project sought to develop a lightweight, small form-factor, soldier-portable advanced thermoelectric (TE) system prototype to recover and convert waste heat from various deployed military equipment (i.e., diesel generators/engines, incinerators, vehicles, and potentially mobile kitchens), with the ultimate purpose of producing power for soldier battery charging, advanced capacitor charging, and other battlefield power applications. The technical approach employed microchannel technology, a unique “power panel” approach to heat exchange/TE system integration, and newly-characterized LAST (lead-antimony-silver-telluride) and LASTT (lead-antimony-silver-tin-telluride) TE materials segmented with bismuth telluride TE materials in designing a segmented-element TE power module and system. This project researched never-before-addressed system integration challenges (thermal expansion, thermal diffusion, electrical interconnection, thermal and electrical interfaces) of designing thin “power panels” consisting of alternating layers of thin, microchannel heat exchangers (hot and cold) sandwiching thin, segmented-element TE power generators. The TE properties, structurally properties, and thermal fatigue behavior of LAST and LASTT materials were developed and characterized such that the first segmented-element TE modules using LAST / LASTT materials were fabricated and tested at hot-side temperatures = 400 °C and cold-side temperatures = 40 °C. LAST / LASTT materials were successfully segmented …
Date:
September 1, 2010
Creator:
Hendricks, Terry J.; Hogan, Tim; Case, Eldon D. & Cauchy, Charles J.
Object Type:
Report
System:
The UNT Digital Library
Advanced Test Reactor Core Modeling Update Project Annual Report for Fiscal Year 2010
Legacy computational reactor physics software tools and protocols currently used for support of Advanced Test Reactor (ATR) core fuel management and safety assurance and, to some extent, experiment management are obsolete, inconsistent with the state of modern nuclear engineering practice, and are becoming increasingly difficult to properly verify and validate (V&V). Furthermore, the legacy staff knowledge required for application of these tools and protocols from the 1960s and 1970s is rapidly being lost due to staff turnover and retirements. In 2009 the Idaho National Laboratory (INL) initiated a focused effort to address this situation through the introduction of modern high-fidelity computational software and protocols, with appropriate V&V, within the next 3-4 years via the ATR Core Modeling and Simulation and V&V Update (or “Core Modeling Update”) Project. This aggressive computational and experimental campaign will have a broad strategic impact on the operation of the ATR, both in terms of improved computational efficiency and accuracy for support of ongoing DOE programs as well as in terms of national and international recognition of the ATR National Scientific User Facility (NSUF).
Date:
September 1, 2010
Creator:
Aryaeinejad, Rahmat; Crawford, Douglas S.; DeHart, Mark D.; Griffith, George W.; Lucas, D. Scott; Nielsen, Joseph W. et al.
Object Type:
Report
System:
The UNT Digital Library
Aerosol cluster impact and break-up : II. Atomic and Cluster Scale Models.
Understanding the interaction of aerosol particle clusters/flocs with surfaces is an area of interest for a number of processes in chemical, pharmaceutical, and powder manufacturing as well as in steam-tube rupture in nuclear power plants. Developing predictive capabilities for these applications involves coupled phenomena on multiple length and timescales from the process macroscopic scale ({approx}1m) to the multi-cluster interaction scale (1mm-0.1m) to the single cluster scale ({approx}1000 - 10000 particles) to the particle scale (10nm-10{micro}m) interactions, and on down to the sub-particle, atomic scale interactions. The focus of this report is on the single cluster scale; although work directed toward developing better models of particle-particle interactions by considering sub-particle scale interactions and phenomena is also described. In particular, results of mesoscale (i.e., particle to single cluster scale) discrete element method (DEM) simulations for aerosol cluster impact with rigid walls are presented. The particle-particle interaction model is based on JKR adhesion theory and is implemented as an enhancement to the granular package in the LAMMPS code. The theory behind the model is outlined and preliminary results are shown. Additionally, as mentioned, results from atomistic classical molecular dynamics simulations are also described as a means of developing higher fidelity models of particle-particle …
Date:
September 1, 2010
Creator:
Lechman, Jeremy B. & Takato, Yoichi (State University of New York at Buffalo, Buffalo, NY)
Object Type:
Report
System:
The UNT Digital Library
Age-aware solder performance models : level 2 milestone completion.
Legislated requirements and industry standards are replacing eutectic lead-tin (Pb-Sn) solders with lead-free (Pb-free) solders in future component designs and in replacements and retrofits. Since Pb-free solders have not yet seen service for long periods, their long-term behavior is poorly characterized. Because understanding the reliability of Pb-free solders is critical to supporting the next generation of circuit board designs, it is imperative that we develop, validate and exercise a solder lifetime model that can capture the thermomechanical response of Pb-free solder joints in stockpile components. To this end, an ASC Level 2 milestone was identified for fiscal year 2010: Milestone 3605: Utilize experimentally validated constitutive model for lead-free solder to simulate aging and reliability of solder joints in stockpile components. This report documents the completion of this milestone, including evidence that the milestone completion criteria were met and a summary of the milestone Program Review.
Date:
September 1, 2010
Creator:
Neilsen, Michael K.; Vianco, Paul Thomas; Neidigk, Matthew Aaron & Holm, Elizabeth Ann
Object Type:
Report
System:
The UNT Digital Library
AGR-2 Data Qualification Interim Report
Projects for the very high temperature reactor (VHTR) Technology Development Office program provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR program established the NGNP Data Management and Analysis System (NDMAS) to manage and document VHTR data qualification, for storage of the data in a readily accessible electronic form, and to assist in the analysis and presentation of the data. This document gives the status of NDMAS processing and qualification of data associated with the initial reactor cycle (147A) of the second Advanced Gas Reactor (AGR-2) experiment which began on June 21, 2010. Because it is early in the AGR-2 experiment, data from only two AGR-2 data streams are reported on: Fuel Fabrication and Fuel Irradiation data. As of August 1, 2010, approximately 311,000 irradiation data records have been stored in NDMAS, and qualification tests are in progress. Preliminary information indicates that TC 2 in Capsule 2 failed prior to start of the experiment, and NDMAS testing has thus far identified only two invalid data values from the METSO data collection system …
Date:
September 1, 2010
Creator:
Abbott, Michael L.
Object Type:
Report
System:
The UNT Digital Library
Algal Biofuels; Algal Biofuels R&D at NREL (Brochure)
An overview of NREL's algal biofuels projects, including U.S. Department of Energy-funded work, projects with U.S. and international partners, and Laboratory Directed Research and Development projects.
Date:
September 1, 2010
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Algorithm and exploratory study of the Hall MHD Rayleigh-Taylor instability.
This report is concerned with the influence of the Hall term on the nonlinear evolution of the Rayleigh-Taylor (RT) instability. This begins with a review of the magnetohydrodynamic (MHD) equations including the Hall term and the wave modes which are present in the system on time scales short enough that the plasma can be approximated as being stationary. In this limit one obtains what are known as the electron MHD (EMHD) equations which support two characteristic wave modes known as the whistler and Hall drift modes. Each of these modes is considered in some detail in order to draw attention to their key features. This analysis also serves to provide a background for testing the numerical algorithms used in this work. The numerical methods are briefly described and the EMHD solver is then tested for the evolution of whistler and Hall drift modes. These methods are then applied to study the nonlinear evolution of the MHD RT instability with and without the Hall term for two different configurations. The influence of the Hall term on the mixing and bubble growth rate are analyzed.
Date:
September 1, 2010
Creator:
Gardiner, Thomas Anthony
Object Type:
Report
System:
The UNT Digital Library
American Recovery and Reinvestment Act (ARRA) FEMP Technical Assistance for Geothermal Resource Evaluation Projects
The purpose of this document is to report on the evaluation of geothermal resource potential on and around three different United States (U. S.) Air Force Bases (AFBs): Nellis AFB and Air Force Range (AFR) in the State of Nevada (see maps 1 and 5), Holloman AFB in the State of New Mexico (see map 2), and Mountain Home AFB in the State of Idaho (see map 3). All three sites are located in semi-arid parts of the western U. S. The U. S. Air Force, through its Air Combat Command (ACC) located at Langley AFB in the State of Virginia, asked the Federal Energy Management Program (FEMP) for technical assistance to conduct technical and feasibility evaluations for the potential to identify viable geothermal resources on or around three different AFBs. Idaho National Laboratory (INL) is supporting FEMP in providing technical assistance to a number of different Federal Agencies. For this report, the three different AFBs are considered one project because they all deal with potential geothermal resource evaluations. The three AFBs will be evaluated primarily for their opportunity to develop a geothermal resource of high enough quality grade (i.e., temperature, productivity, depth, etc.) to consider the possibility for generation …
Date:
September 1, 2010
Creator:
Breckenridge, Robert P.; Wood, Thomas R. & Renner, Joel
Object Type:
Report
System:
The UNT Digital Library
American Recovery and Reinvestment Act (ARRA) FEMP Technical Assistance Installation Management Command Southeast (IMCOM-SE) Fast Pyrolysis Technology Demonstration Fort Bragg, North Carolina
FEMP technical assistance for the ESTCP Fast Pyrolysis project.
Date:
September 1, 2010
Creator:
Valkenburt, Corinne & Fowler, Kimberly M.
Object Type:
Report
System:
The UNT Digital Library
Analysis of advanced biofuels.
Long chain alcohols possess major advantages over ethanol as bio-components for gasoline, including higher energy content, better engine compatibility, and less water solubility. Rapid developments in biofuel technology have made it possible to produce C{sub 4}-C{sub 5} alcohols efficiently. These higher alcohols could significantly expand the biofuel content and potentially replace ethanol in future gasoline mixtures. This study characterizes some fundamental properties of a C{sub 5} alcohol, isopentanol, as a fuel for homogeneous-charge compression-ignition (HCCI) engines. Wide ranges of engine speed, intake temperature, intake pressure, and equivalence ratio are investigated. The elementary autoignition reactions of isopentanol is investigated by analyzing product formation from laser-photolytic Cl-initiated isopentanol oxidation. Carbon-carbon bond-scission reactions in the low-temperature oxidation chemistry may provide an explanation for the intermediate-temperature heat release observed in the engine experiments. Overall, the results indicate that isopentanol has a good potential as a HCCI fuel, either in neat form or in blend with gasoline.
Date:
September 1, 2010
Creator:
Dec, John E.; Taatjes, Craig A.; Welz, Oliver & Yang, Yi
Object Type:
Report
System:
The UNT Digital Library