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1

Fuel Grading Study on a Low-Enriched Uranium Fuel Design for the High Flux Isotope Reactor  

Science Conference Proceedings (OSTI)

An engineering design study that would enable the conversion of the High Flux Isotope Reactor (HFIR) from high-enriched uranium to low-enriched uranium fuel is ongoing at Oak Ridge National Laboratory. The computational models used to search for a low-enriched uranium (LEU) fuel design that would meet the requirements for the conversion study, and the recent results obtained with these models during FY 2009, are documented and discussed in this report. Estimates of relevant reactor performance parameters for the LEU fuel core are presented and compared with the corresponding data for the currently operating high-enriched uranium fuel core. These studies indicate that the LEU fuel design would maintain the current performance of the HFIR with respect to the neutron flux to the central target region, reflector, and beam tube locations.

Ilas, Germina [ORNL; Primm, Trent [ORNL

2009-11-01T23:59:59.000Z

2

Reference (Axially Graded) Low Enriched Uranium Fuel Design for the High Flux Isotope Reactor (HFIR)  

Science Conference Proceedings (OSTI)

During the past five years, staff at the Oak Ridge National Laboratory (ORNL) have studied the issue of whether the HFIR could be converted to low enriched uranium (LEU) fuel without degrading the performance of the reactor. Using state-of-the-art reactor physics methods and behind-the-state-of-the-art thermal hydraulics methods, the staff have developed fuel plate designs (HFIR uses two types of fuel plates) that are believed to meet physics and thermal hydraulic criteria provided the reactor power is increased from 85 to 100 MW. The paper will present a defense of the results by explaining the design and validation process. A discussion of the requirements for showing applicability of analyses to approval for loading the fuel to HFIR lead test core irradiation currently scheduled for 2016 will be provided. Finally, the potential benefits of upgrading thermal hydraulics methods will be discussed.

Ilas, Germina [ORNL; Primm, Trent [ORNL

2010-01-01T23:59:59.000Z

3

Axial grading of inert matrix fuels  

Science Conference Proceedings (OSTI)

Burning actinides in an inert matrix fuel to 750 MWd/kg IHM results in a significant reduction in transuranic isotopes. However, achieving this level of burnup in a standard light water reactor would require residence times that are twice that of uranium dioxide fuels. The reactivity of an inert matrix assembly at the end of life is less than 1/3 of its beginning of life reactivity leading to undesirable radial and axial power peaking in the reactor core. Here we show that axial grading of the inert matrix fuel rods can reduce peaking significantly. Monte Carlo simulations are used to model the assembly level power distributions in both ungraded and graded fuel rods. The results show that an axial grading of uranium dioxide and inert matrix fuels with erbium can reduces power peaking by more than 50% in the axial direction. The reduction in power peaking enables the core to operate at significantly higher power. (authors)

Recktenwald, G. D.; Deinert, M. R. [Dept. of Mechanical Engineering, Univ. of Texas, Austin, TX (United States)

2012-07-01T23:59:59.000Z

4

Low-Enriched Uranium Fuel Design with Two-Dimensional Grading for the High Flux Isotope Reactor  

Science Conference Proceedings (OSTI)

An engineering design study of the conversion of the High Flux Isotope Reactor (HFIR) from high-enriched uranium (HEU) to low-enriched uranium (LEU) fuel is ongoing at Oak Ridge National Laboratory. The computational models developed during fiscal year 2010 to search for an LEU fuel design that would meet the requirements for the conversion and the results obtained with these models are documented and discussed in this report. Estimates of relevant reactor performance parameters for the LEU fuel core are presented and compared with the corresponding data for the currently operating HEU fuel core. The results obtained indicate that the LEU fuel design would maintain the current performance of the HFIR with respect to the neutron flux to the central target region, reflector, and beam tube locations under the assumption that the operating power for the reactor fueled with LEU can be increased from the current value of 85 MW to 100 MW.

Ilas, Germina [ORNL; Primm, Trent [ORNL

2011-05-01T23:59:59.000Z

5

Hot Cell Examination of Weapons-Grade MOX Fuel  

SciTech Connect

The U.S. Department of Energy has decided to dispose of a portion of the nation s surplus weapons-grade plutonium by reconstituting it into mixed oxide (MOX) fuel and irradiating it in commercial power reactors. Four lead assemblies were manufactured with weapons-grade MOX and irradiated to a maximum fuel rod burnup of 47.3 MWd/kg. As part of the fuel qualification process, five fuel rods with varying burnups and plutonium contents were selected from one of the assemblies and shipped to Oak Ridge National Laboratory for hot cell examination. This is the first hot cell examination of weapons-grade MOX fuel. The rods have been examined nondestructively with the ADEPT apparatus and are currently being destructively examined. Examinations completed to date include length measurements, visual examination, gamma scanning, profilometry, eddy-current testing, gas measurement and analysis, and optical metallography. Representative results of these examinations are reviewed and found to be consistent with predictions and with prior experience with reactor-grade MOX fuel. The results will be used to support licensing of weapons-grade MOX for batch use in commercial power reactors.

Morris, Robert Noel [ORNL; Bevard, Bruce Balkcom [ORNL; McCoy, Kevin [Areva NP

2010-01-01T23:59:59.000Z

6

FRACTIONATION OF LIGNOCELLULOSIC BIOMASS FOR FUEL-GRADE ETHANOL PRODUCTION  

SciTech Connect

PureVision Technology, Inc. (PureVision) of Fort Lupton, Colorado is developing a process for the conversion of lignocellulosic biomass into fuel-grade ethanol and specialty chemicals in order to enhance national energy security, rural economies, and environmental quality. Lignocellulosic-containing plants are those types of biomass that include wood, agricultural residues, and paper wastes. Lignocellulose is composed of the biopolymers cellulose, hemicellulose, and lignin. Cellulose, a polymer of glucose, is the component in lignocellulose that has potential for the production of fuel-grade ethanol by direct fermentation of the glucose. However, enzymatic hydrolysis of lignocellulose and raw cellulose into glucose is hindered by the presence of lignin. The cellulase enzyme, which hydrolyzes cellulose to glucose, becomes irreversibly bound to lignin. This requires using the enzyme in reagent quantities rather than in catalytic concentration. The extensive use of this enzyme is expensive and adversely affects the economics of ethanol production. PureVision has approached this problem by developing a biomass fractionator to pretreat the lignocellulose to yield a highly pure cellulose fraction. The biomass fractionator is based on sequentially treating the biomass with hot water, hot alkaline solutions, and polishing the cellulose fraction with a wet alkaline oxidation step. In September 2001 PureVision and Western Research Institute (WRI) initiated a jointly sponsored research project with the U.S. Department of Energy (DOE) to evaluate their pretreatment technology, develop an understanding of the chemistry, and provide the data required to design and fabricate a one- to two-ton/day pilot-scale unit. The efforts during the first year of this program completed the design, fabrication, and shakedown of a bench-scale reactor system and evaluated the fractionation of corn stover. The results from the evaluation of corn stover have shown that water hydrolysis prior to alkaline hydrolysis may be beneficial in removing hemicellulose and lignin from the feedstock. In addition, alkaline hydrolysis has been shown to remove a significant portion of the hemicellulose and lignin. The resulting cellulose can be exposed to a finishing step with wet alkaline oxidation to remove the remaining lignin. The final product is a highly pure cellulose fraction containing less than 1% of the native lignin with an overall yield in excess of 85% of the native cellulose. This report summarizes the results from the first year's effort to move the technology to commercialization.

F.D. Guffey; R.C. Wingerson

2002-10-01T23:59:59.000Z

7

Functionally Graded Cathodes for Solid Oxide Fuel Cells  

DOE Green Energy (OSTI)

This DOE SECA project focused on both experimental and theoretical understanding of oxygen reduction processes in a porous mixed-conducting cathode in a solid oxide fuel cell (SOFC). Elucidation of the detailed oxygen reduction mechanism, especially the rate-limiting step(s), is critical to the development of low-temperature SOFCs (400 C to 700 C) and to cost reduction since much less expensive materials may be used for cell components. However, cell performance at low temperatures is limited primarily by the interfacial polarization resistances, specifically by those associated with oxygen reduction at the cathode, including transport of oxygen gas through the porous cathode, the adsorption of oxygen onto the cathode surface, the reduction and dissociation of the oxygen molecule (O{sub 2}) into the oxygen ion (O{sup 2-}), and the incorporation of the oxygen ion into the electrolyte. In order to most effectively enhance the performance of the cathode at low temperatures, we must understand the mechanism and kinetics of the elementary processes at the interfaces. Under the support of this DOE SECA project, our accomplishments included: (1) Experimental determination of the rate-limiting step in the oxygen reduction mechanism at the cathode using in situ FTIR and Raman spectroscopy, including surface- and tip-enhanced Raman spectroscopy (SERS and TERS). (2) Fabrication and testing of micro-patterned cathodes to compare the relative activity of the TPB to the rest of the cathode surface. (3) Construction of a mathematical model to predict cathode performance based on different geometries and microstructures and analyze the kinetics of oxygen-reduction reactions occurring at charged mixed ionic-electronic conductors (MIECs) using two-dimensional finite volume models with ab initio calculations. (4) Fabrication of cathodes that are graded in composition and microstructure to generate large amounts of active surface area near the cathode/electrolyte interface using a novel combustion chemical vapor deposition (CCVD) technique. (5) Application of advanced quantum chemical calculations to interpret measured spectroscopic information, as well as to guide design of high efficient cathode materials.

YongMan Choi; Meilin Liu

2006-09-30T23:59:59.000Z

8

SNG or syn-gas from wet solid waste and low grade fuels  

SciTech Connect

The substitute natural gas (SNG) or a synthesis gas (syngas) is prepared by partly oxidizing wastes and low-grade fuels (peat, lignite, many forms of biomass) containing 0.5-30 times as much water as the dry solids with O or air at 240-300/sup 0/C and 70-100 atmospheres. Sulfur in high S coal is oxidized selectively to SO/sub 4//sup -2/, and the heat to bring the combustible to the necessary temperature is supplied by burning part of the combustible itself. The residual solids (now 70-95% of the original fuel) are mechanically separated from all but 0.5-2 lb water. These solids come from the dewatering unit at a high pressure and may be passed, without loss of pressure or temperature to be gasified in conventional processes and gasifiers by partial oxidation.

Othmer, D.F.

1981-02-17T23:59:59.000Z

9

High-grade paper recycling: A program management perspective  

Science Conference Proceedings (OSTI)

Recycling of high-grade paper is one method of reducing the use of natural resources and the amount of waste being emitted into the environment, both in the process of manufacturing and in the disposal of unneeded documents. The Air Force Materiel Command (AFMC) is a significant user of high-grade paper, thus recycling represents a potential saving to society in the form of lessened negative impact on the environment as the result of AFMC operations. The possibility also exists for AFMC to reduce operating costs. The purpose of this study is to explore means of reducing high-grade paper disposal by AFMC, examine program management of high-grade paper recycling by AFMC, and apply effective program management processes to the AFMC high-grade paper recycling program.

Carter, R.L.

1999-03-01T23:59:59.000Z

10

Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) High  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

High Occupancy Vehicle (HOV) Lane Exemption to someone by High Occupancy Vehicle (HOV) Lane Exemption to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) High Occupancy Vehicle (HOV) Lane Exemption on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) High Occupancy Vehicle (HOV) Lane Exemption on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) High Occupancy Vehicle (HOV) Lane Exemption on Google Bookmark Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) High Occupancy Vehicle (HOV) Lane Exemption on Delicious Rank Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) High Occupancy Vehicle (HOV) Lane Exemption on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) High Occupancy Vehicle (HOV) Lane Exemption on

11

Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) High  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

High Occupancy Vehicle (HOV) Lane Exemption to someone by High Occupancy Vehicle (HOV) Lane Exemption to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) High Occupancy Vehicle (HOV) Lane Exemption on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) High Occupancy Vehicle (HOV) Lane Exemption on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) High Occupancy Vehicle (HOV) Lane Exemption on Google Bookmark Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) High Occupancy Vehicle (HOV) Lane Exemption on Delicious Rank Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) High Occupancy Vehicle (HOV) Lane Exemption on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) High Occupancy Vehicle (HOV) Lane Exemption on

12

High performance internal reforming unit for high temperature fuel cells  

DOE Patents (OSTI)

A fuel reformer having an enclosure with first and second opposing surfaces, a sidewall connecting the first and second opposing surfaces and an inlet port and an outlet port in the sidewall. A plate assembly supporting a catalyst and baffles are also disposed in the enclosure. A main baffle extends into the enclosure from a point of the sidewall between the inlet and outlet ports. The main baffle cooperates with the enclosure and the plate assembly to establish a path for the flow of fuel gas through the reformer from the inlet port to the outlet port. At least a first directing baffle extends in the enclosure from one of the sidewall and the main baffle and cooperates with the plate assembly and the enclosure to alter the gas flow path. Desired graded catalyst loading pattern has been defined for optimized thermal management for the internal reforming high temperature fuel cells so as to achieve high cell performance.

Ma, Zhiwen (Sandy Hook, CT); Venkataraman, Ramakrishnan (New Milford, CT); Novacco, Lawrence J. (Brookfield, CT)

2008-10-07T23:59:59.000Z

13

Alternative Fuels Data Center: Alternative Fuel Vehicle Decal and High  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Decal and High Occupancy Vehicle (HOV) Lane Exemption to someone by Decal and High Occupancy Vehicle (HOV) Lane Exemption to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel Vehicle Decal and High Occupancy Vehicle (HOV) Lane Exemption on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel Vehicle Decal and High Occupancy Vehicle (HOV) Lane Exemption on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel Vehicle Decal and High Occupancy Vehicle (HOV) Lane Exemption on Google Bookmark Alternative Fuels Data Center: Alternative Fuel Vehicle Decal and High Occupancy Vehicle (HOV) Lane Exemption on Delicious Rank Alternative Fuels Data Center: Alternative Fuel Vehicle Decal and High Occupancy Vehicle (HOV) Lane Exemption on Digg Find More places to share Alternative Fuels Data Center: Alternative

14

High loading uranium fuel plate  

DOE Patents (OSTI)

Two embodiments of a high uranium fuel plate are disclosed which contain a meat comprising structured uranium compound confined between a pair of diffusion bonded ductile metal cladding plates uniformly covering the meat, the meat having a uniform high fuel loading comprising a content of uranium compound greater than about 45 Vol. % at a porosity not greater than about 10 Vol. %. In a first embodiment, the meat is a plurality of parallel wires of uranium compound. In a second embodiment, the meat is a dispersion compact containing uranium compound. The fuel plates are fabricated by a hot isostatic pressing process.

Wiencek, Thomas C. (Bolingbrook, IL); Domagala, Robert F. (Indian Head Park, IL); Thresh, Henry R. (Palos Heights, IL)

1990-01-01T23:59:59.000Z

15

Corrosion and Cracking of Carbon Steel in Fuel Grade Ethanol  

Science Conference Proceedings (OSTI)

Environmentally Assisted Cracking of Carbon Steel in High Temperature Geothermal Well · Evaluation of the Susceptibility to Hydrogen Assisted Cracking in ...

16

Neutronics and safety characteristics of a 100% MOX fueled PWR using weapons grade plutonium  

Science Conference Proceedings (OSTI)

Preliminary neutronics and safety studies, pertaining to the feasibility of using 100% weapons grade mixed-oxide (MOX) fuel in an advanced PWR Westinghouse design are presented in this paper. The preliminary results include information on boron concentration, power distribution, reactivity coefficients and xenon and control rode worth for the initial and the equilibrium cycle. Important safety issues related to rod ejection and steam line break accidents and shutdown margin requirements are also discussed. No significant change from the commercial design is needed to denature weapons-grade plutonium under the current safety and licensing criteria.

Biswas, D.; Rathbun, R.; Lee, Si Young [Westinghouse Savannah River Co., Aiken, SC (United States); Rosenthal, P. [Westinghouse Electric Corp., Pittsburgh, PA (United States)

1993-12-31T23:59:59.000Z

17

Fuel grade ethanol by solvent extraction: Final subcontract report  

DOE Green Energy (OSTI)

This report summarizes final results for ethanol recovery by solvent extraction and extractive distillation. At conclusion this work can be summarized as ethanol dehydration and recovery dilute fermentates is feasible using liquid/liquid extraction and extractive distillation. Compared to distillation, the economics are more attractive for less than 5 wt % ethanol. However, an economic bias in favor of SEED appears to exist even for 10 wt % feeds. It is of particular interest to consider the group extraction of ethanol and acetic acid followed by conversion to a mixture of ethanol and ethyl acetate. The latter species is a more valuable commodity and group extraction of inhibitory species is one feature of liquid/liquid extraction that is not easily accomodated using distillation. Upflow immobilized reactors offer the possibility of achieving high substrate conversion while also maintaining low metabolite concentrations. However, many questions remain to be answered with such a concept. 135 refs., 42 figs., 61 tabs.

Tedder, D.W.

1987-04-01T23:59:59.000Z

18

Functionally Graded Cathodes for Solid Oxide Fuel Cells  

DOE Green Energy (OSTI)

The main objective of this DOE project is to demonstrate that the performance and long-term stability of the state-of-the-art LSCF cathode can be enhanced by a catalytically active coating (e.g., LSM or SSC). We have successfully developed a methodology for reliably evaluating the intrinsic surface catalytic properties of cathode materials. One of the key components of the test cell is a dense LSCF film, which will function as the current collector for the electrode material under evaluation to eliminate the effect of ionic and electronic transport. Since it is dense, the effect of geometry would be eliminated as well. From the dependence of the electrode polarization resistance on the thickness of a dense LSCF electrode and on partial pressure of oxygen, we have confirmed that the surface catalytic activity of LSCF limits the performances of LSCF-based cathodes. Further, we have demonstrated, using test cells of different configurations, that the performance of LSCF-based electrodes can be significantly enhanced by infiltration of a thin film of LSM or SSC. In addition, the stability of LSCF-based cathodes was also improved by infiltration of LSM or SSC. While the concept feasibility of the electrode architecture is demonstrated, many details are yet to be determined. For example, it is not clear how the surface morphology, composition, and thickness of the coatings change under operating conditions over time, how these changes influence the electrochemical behavior of the cathodes, and how to control the microscopic details of the coatings in order to optimize the performance. The selection of the catalytic materials as well as the detailed microstructures of the porous LSCF and the catalyst layer may critically impact the performance of the proposed cathodes. Further, other fundamental questions still remain; it is not clear why the degradation rates of LSCF cathodes are relatively high, why a LSM coating improves the stability of LSCF cathodes, which catalysts would be most effective for LSCF, and how to achieve further enhancement of the performance and stability of SOFC cathodes.

Lei Yang; Ze Liu; Shizhone Wang; Jaewung Lee; Meilin Liu

2008-04-30T23:59:59.000Z

19

High-burnup fuel and the impact on fuel management  

SciTech Connect

Competition in the electric utility industry has forced utilities to reduce cost. For a nuclear utility, this means a reduction of both the nuclear fuel cost and the operating and maintenance cost. To this extent, utilities are pursuing longer cycles. To reduce the nuclear fuel cost, utilities are trying to reduce batch size while increasing cycle length. Yankee Atomic Electric Company has performed a number of fuel cycle studies to optimize both batch size and cycle length; however, certain burnup-related constraints are encountered. As a result of these circumstances, longer fuel cycles make it increasingly difficult to simultaneously meet the burnup-related fuel design constraints and the technical specification limits. Longer cycles require fuel assemblies to operate for longer times at relatively high power. If utilities continue to pursue longer cycles to help reduce nuclear fuel cost, changes may need to be made to existing fuel burnup limits.

Cacciapouti, R.J.; Weader, R.J. [Yankee Atomic Electric Co., Bolton, MA (United States)

1996-12-31T23:59:59.000Z

20

Fuel Cells - The Reality of a High Technology  

E-Print Network (OSTI)

A fuel cell power plant is an energy conversion device which can continuously transform the chemical energy of natural gas into utility grade electricity and usable heat. The characteristics of high electrical conversion efficiencies (40 to 55%), potentially high fuel utilization efficiencies (>80%), excellent AC power quality, environmental compatibility, modular design, and good reliability are some of the reasons why fuel cells have the potential to be one of the best cogeneration devices available. This paper will emphasize the status of phosphoric acid fuel cell technology focusing in on the field test results to date with small 40 Kilowatt (kW) onsite fuel cell power plants being designed, developed, and field tested principally under the support of the Gas Utility Industry. Over 40 units are being installed by 30 gas and combination utility companies throughout the United States to evaluate the operating experience of onsite fuel cell technology. In addition, the paper will briefly provide the status of a similar project, funded by the electric utility industry, to demonstrate multimegawatt-sized fuel cell power plants. Lastly, the paper will try to bring into focus the status of the more advanced carbonate and solid oxide fuel cell technologies.

Cuttica, J. J.

1984-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "high grade fuel" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

Fossil Fuels Study Guide - High School | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Fuels Study Guide - High School Fossil Fuels Study Guide - High School Fossil Fuels Study Guide - High School More Documents & Publications Coal Study Guide for Elementary School...

22

Evaluation of weapons-grade mixed oxide fuel performance in U.S. Light Water Reactors using COMETHE 4D release 23 computer code  

E-Print Network (OSTI)

The COMETHE 4D Release 23 computer code was used to evaluate the thermal, chemical and mechanical performance of weapons-grade MOX fuel irradiated under U.S. light water reactor typical conditions. Comparisons were made to and UO? fuels exhibited similar conventional UO? fuel. Weapons-grade MOX behavior. However, MOX fuel rods feature higher fuel centerline temperatures due to a lower thermal conductivity. Moreover, higher diffusion in MOX fuel results in a slightly higher fission gas release. Finally, MOX fuel shows better mechanical behavior than UO? fuel due to lower pellet-cladding mechanical interaction and rod deformation. These results indicate that the MOX fuel meets all potential licensing requirements.

Bellanger, Philippe

1999-01-01T23:59:59.000Z

23

CONVERSION OF RUSSIAN WEAPON-GRADE PLUTONIUM INTO OXIDE FOR MIXED OXIDE (MOX) FUEL FABRICATION.  

SciTech Connect

Progress has been made in the Russian Federation towards the conversion of weapons-grade plutonium (w-Pu) into plutonium oxide (PuO{sub 2}) suitable for further manufacture into mixed oxide (MOX) fuels. This program is funded both by French Commissariat x 1'Energie Atomique (CEA) and the US National Nuclear Security Administration (NNSA). The French program was started as a way to make available their expertise gained from manufacturing MOX fuel. The US program was started in 1998 in response to US proliferation concerns and the acknowledged international need to decrease available w-Pu. Russia has selected both the conversion process and the manufacturing site. This paper discusses the present state of development towards fulfilling this mission: the demonstration plant designed to process small amounts of Pu and validate all process stages and the industrial plant that will process up to 5 metric tons of Pu per year.

Glagovski, E.; Kolotilov, Y.; Glagolenko, Y.; Zygmunt, Stanley J.; Mason, C. F. V. (Caroline F. V.); Hahn, W. K. (Wendy K.); Durrer, R. E. (Russell E.); Thomas, S.; Sicard, B.; Herlet, N.; Fraize, G.; Villa, A.

2001-01-01T23:59:59.000Z

24

Effect of Weight and Roadway Grade on the Fuel Economy of Class-8 Frieght Trucks  

DOE Green Energy (OSTI)

In 2006-08, the Oak Ridge National Laboratory, in collaboration with several industry partners, collected real-world performance and situational data for long-haul operations of Class-8 trucks from a fleet engaged in normal freight operations. Such data and information are useful to support Class-8 modeling of combination truck performance, technology evaluation efforts for energy efficiency, and to provide a means of accounting for real-world driving performance within combination truck research and analyses. The present study used the real-world information collected in that project to analyze the effects that vehicle speed and vehicle weight have on the fuel efficiency of Class-8 trucks. The analysis focused on two type of terrains, flat (roadway grades ranging from -1% to 1%) and mild uphill terrains (roadway grades ranging from 1% to 3%), which together covered more than 70% of the miles logged in the 2006-08 project (note: almost 2/3 of the distance traveled on mild uphill terrains was on terrains with 1% to 2% grades). In the flat-terrain case, the results of the study showed that for light and medium loads, fuel efficiency decreases considerably as speed increases. For medium-heavy and heavy loads (total vehicle weight larger than 65,000 lb), fuel efficiency tends to increase as the vehicle speed increases from 55 mph up to about 58-60 mph. For speeds higher than 60 mph, fuel efficiency decreases at an almost constant rate with increasing speed. At any given speed, fuel efficiency decreases and vehicle weight increases, although the relationship between fuel efficiency and vehicle weight is not linear, especially for vehicle weights above 65,000 lb. The analysis of the information collected while the vehicles were traveling on mild upslope terrains showed that the fuel efficiency of Class-8 trucks decreases abruptly with vehicle weight ranging from light loads up to medium-heavy loads. After that, increases in the vehicle weight only decrease fuel efficiency slightly. Fuel efficiency also decreases significantly with speed, but only for light and medium loads. For medium-heavy and heavy, FE is almost constant for speeds ranging from 57 to about 66 mph. For speeds higher than 66 mph, the FE decreases with speed, but at a lower rate than for light and medium loads. Statistical analyses that compared the fuel efficiencies obtained when the vehicles were traveling at 59 mph vs. those achieved when they were traveling at 65 mph or 70 mph indicated that the former were, on average, higher than the latter. This result was statistically significant at the 99.9% confidence level (note: the Type II error i.e., the probability of failing to reject the null hypothesis when the alternative hypothesis is true was 18% and 6%, respectively).

Franzese, Oscar [ORNL; Davidson, Diane [ORNL

2011-11-01T23:59:59.000Z

25

Fabrication of Highly Luminescent Graded Core/Shell ...  

Paul Alivisatos, Erik Scher, and Liberato Manna have grown graded shells on CdSe core nanorods. Traditional techniques have ...

26

Alternative Fuels Data Center: High Occupancy Vehicle (HOV) and High  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

High Occupancy Vehicle High Occupancy Vehicle (HOV) and High Occupancy Toll (HOT) Lane Exemption to someone by E-mail Share Alternative Fuels Data Center: High Occupancy Vehicle (HOV) and High Occupancy Toll (HOT) Lane Exemption on Facebook Tweet about Alternative Fuels Data Center: High Occupancy Vehicle (HOV) and High Occupancy Toll (HOT) Lane Exemption on Twitter Bookmark Alternative Fuels Data Center: High Occupancy Vehicle (HOV) and High Occupancy Toll (HOT) Lane Exemption on Google Bookmark Alternative Fuels Data Center: High Occupancy Vehicle (HOV) and High Occupancy Toll (HOT) Lane Exemption on Delicious Rank Alternative Fuels Data Center: High Occupancy Vehicle (HOV) and High Occupancy Toll (HOT) Lane Exemption on Digg Find More places to share Alternative Fuels Data Center: High

27

Economics of producing fuel-grade alcohol from corn in western Ohio  

Science Conference Proceedings (OSTI)

The production of significant quantities of alcohol fuel will have important effects on the use of agricultural resources, including increased food prices. The two major objectives of this research were to determine (1) the potential effects of alcohol-fuel production on agriculture, and (2) the increase in energy prices needed for alcohol-fuel production to become economic. Western Ohio (the Corn Belt part of the state) was chosen for study. A quadratic-programming model with crop, livestock, and alcohol-fuel-production activities was used for analysis. Four alcohol-fuel-production levels were analyzed: 100, 200, 300 and 400 million gallons. The 400-million-gallon level represents western Ohio's share of alcohol-fuel production for a national gasohol program. The production of alcohol results in a high protein by-product feed that can substitute for soybean meal. Efficient use of this by-product is a crucial factor affecting resource use and food prices. At low alcohol-fuel production levels, 80% of the additional cropland required for increased corn production comes from the cropland released through by-product feeding. However, as alcohol-fuel production increases, livestock's ability to use efficiently this by-product feed decreases. This in turn, reduces greatly the cropland that can be released for increased corn production. Consequently, food prices increase substantially. The quantity of land released through by-product feeding, at high alcohol-fuel-production levels, can be increased if the corn is first wet milled. Wet milling produces high-protein feeds that can be used more efficiently by livestock. For alcohol-fuel production to become economic, crude oil prices must increase by ten cents per gallon for the wet-milling process and 22 cents per gallon for the conventional distillery process (1981 $).

Ott, S.L.

1981-01-01T23:59:59.000Z

28

Neutronic evaluation of a non-fertile fuel for the disposition of weapons-grade plutonium in a boiling water reactor  

Science Conference Proceedings (OSTI)

A new non-fertile, weapons-grade plutonium oxide fuel concept is developed and evaluated for deep burn applications in a boiling water reactor environment using the General Electric 8x8 Advanced Boiling Water Reactor (ABWR) fuel assembly dimensions and pitch. Detailed infinite lattice fuel burnup results and neutronic performance characteristics are given and although preliminary in nature, clearly demonstrate the fuel`s potential as an effective means to expedite the disposition of plutonium in existing light water reactors. The new non-fertile fuel concept is an all oxide composition containing plutonia, zirconia, calcia, and erbia having the following design weight percentages: 8.3; 80.4; 9.7; and 1.6. This fuel composition in an infinite fuel lattice operating at linear heat generation rates of 6.0 or 12.0 kW/ft per rod can remain critical for up to 1,200 and 600 Effective Full Power Days (EFPD), respectively, and achieve a burnup of 7.45 {times} 10{sup 20} f/cc. These burnups correspond to a 71--73% total plutonium isotope destruction and a 91--94% destruction of the {sup 239}Pu isotope for the 0--40% moderator steam void condition. Total plutonium destruction greater than 73% is possible with a fuel management scheme that allows subcritical fuel assemblies to be driven by adjacent high reactivity assemblies. The fuel exhibits very favorable neutron characteristics from beginning-of-life (BOL) to end-of-life (EOL). Prompt fuel Doppler coefficient of reactivity are negative, with values ranging between {minus}0.4 to {minus}2.0 pcm/K over the temperature range of 900 to 2,200 K. The ABWR fuel lattice remains in an undermoderated condition for both hot operational and cold startup conditions over the entire fuel burnup lifetime.

Sterbentz, J.W.

1994-10-01T23:59:59.000Z

29

High Density Fuel Development for Research Reactors  

SciTech Connect

An international effort to develop, qualify, and license high and very high density fuels has been underway for several years within the framework of multi-national RERTR programs. The current development status is the result of significant contributions from many laboratories, specifically CNEA in Argentina, AECL in Canada, CEA in France, TUM in Germany, KAERI in Korea, VNIIM, RDIPE, IPPE, NCCP and RIARR in Russia, INL, ANL and Y-12 in USA. These programs are mainly engaged with UMo dispersion fuels with densities from 6 to 8 gU/cm3 (high density fuel) and UMo monolithic fuel with density as high as 16 gU/cm3 (very high density fuel). This paper, mainly focused on the French & US programs, gives the status of high density UMo fuel development and perspectives on their qualification.

Daniel Wachs; Dennis Keiser; Mitchell Meyer; Douglas Burkes; Curtis Clark; Glenn Moore; Jan-Fong Jue; Totju Totev; Gerard Hofman; Tom Wiencek; Yeon So Kim; Jim Snelgrove

2007-09-01T23:59:59.000Z

30

Multicomponent fuel vaporization at high pressures.  

DOE Green Energy (OSTI)

We extend our multicomponent fuel model to high pressures using a Peng-Robinson equation of state, and implement the model into KIVA-3V. Phase equilibrium is achieved by equating liquid and vapor fugacities. The latent heat of vaporization and fuel enthalpies are also corrected for at high pressures. Numerical simulations of multicomponent evaporation are performed for single droplets for a diesel fuel surrogate at different pressures.

Torres, D. J. (David J.); O'Rourke, P. J. (Peter J.)

2002-01-01T23:59:59.000Z

31

An Innovative High Thermal Conductivity Fuel Design  

SciTech Connect

Thermal conductivity of the fuel in today's Light Water Reactors, Uranium dioxide, can be improved by incorporating a uniformly distributed heat conducting network of a higher conductivity material, Silicon Carbide. The higher thermal conductivity of SiC along with its other prominent reactor-grade properties makes it a potential material to address some of the related issues when used in UO2 [97% TD]. This ongoing research, in collaboration with the University of Florida, aims to investigate the feasibility and develop a formal methodology of producing the resultant composite oxide fuel. Calculations of effective thermal conductivity of the new fuel as a function of %SiC for certain percentages and as a function of temperature are presented as a preliminary approach. The effective thermal conductivities are obtained at different temperatures from 600K to 1600K. The corresponding polynomial equations for the temperature-dependent thermal conductivities are given based on the simulation results. Heat transfer mechanism in this fuel is explained using a finite volume approach and validated against existing empirical models. FLUENT 6.1.22 was used for thermal conductivity calculations and to estimate reduction in centerline temperatures achievable within such a fuel rod. Later, computer codes COMBINE-PC and VENTURE-PC were deployed to estimate the fuel enrichment required, to maintain the same burnup levels, corresponding to a volume percent addition of SiC.

Jamil A. Khan

2009-11-21T23:59:59.000Z

32

Effect of Highly Enriched/Highly Burnt UO2 Fuels on Fuel Cycle Costs, Radiotoxicity, and Nuclear Design Parameters  

Science Conference Proceedings (OSTI)

Technical Paper / Advances in Nuclear Fuel Management - Increased Enrichment/High Burnup and Light Water Reactor Fuel Cycle Optimization

Robert Gregg; Andrew Worrall

33

HIGH DENSITY NUCLEAR FUEL COMPOSITION  

DOE Patents (OSTI)

ABS>A nuclear fuel consisting essentially of uranium monocarbide and containing 2.2 to 4.6 wt% carbon, 0.1 to 2.3 wt% oxygen, 0.05 to 2.5 wt% nitrogen, and the balance uranium was developed. The maximum oxygen content was less than one-half the carbon content by weight and the carbon, oxygen, and nitrogen are present as a single phase substituted solid solution of UC, C, O, and N. A method of preparing the fuel composition is described. (AEC)

Litton, F.B.

1962-07-17T23:59:59.000Z

34

High-density Fuel Development for High Performance Research ...  

Science Conference Proceedings (OSTI)

Abstract Scope, High density UMo (7-12wt% Mo) fuel for high performance research ... High Energy X-ray Diffraction Study of Deformation Behavior of Alloy HT9.

35

High resolution fossil fuel combustion CO2 emission fluxes for...  

NLE Websites -- All DOE Office Websites (Extended Search)

High resolution fossil fuel combustion CO2 emission fluxes for the United States Title High resolution fossil fuel combustion CO2 emission fluxes for the United States Publication...

36

High-pressure coal fuel processor development  

DOE Green Energy (OSTI)

Caterpillar shares DOE/METC interest in demonstrating the technology required to displace petroleum-based engine fuels with various forms of low cost coal. Current DOE/METC programs on mild gasification and coal-water-slurries are addressing two approaches to this end. Engine and fuel processor system concept studies by Caterpillar have identified a third, potentially promising, option. This option includes high-pressure fuel processing of run-of-the-mine coal and direct injection of the resulting low-Btu gas stream into an ignition assisted, high compression ratio diesel engine. The compactness and predicted efficiency of the system make it suitable for application to line-haul railroad locomotives. A successful conclusion of the program will enable further component development work and full-scale system demonstrations of this potentially important technology. This paper covers the work on fuel processor rig testing completed in FY92.

Greenhalgh, M.L.; Wen, C.S.; Smith, L.

1992-12-31T23:59:59.000Z

37

High-pressure coal fuel processor development  

DOE Green Energy (OSTI)

Caterpillar shares DOE/METC interest in demonstrating the technology required to displace petroleum-based engine fuels with various forms of low cost coal. Current DOE/METC programs on mild gasification and coal-water-slurries are addressing two approaches to this end. Engine and fuel processor system concept studies by Caterpillar have identified a third, potentially promising, option. This option includes high-pressure fuel processing of run-of-the-mine coal and direct injection of the resulting low-Btu gas stream into an ignition assisted, high compression ratio diesel engine. The compactness and predicted efficiency of the system make it suitable for application to line-haul railroad locomotives. A successful conclusion of the program will enable further component development work and full-scale system demonstrations of this potentially important technology. This paper covers the work on fuel processor rig testing completed in FY92.

Greenhalgh, M.L.; Wen, C.S.; Smith, L.

1992-01-01T23:59:59.000Z

38

Prospects for increased low-grade bio-fuels use in home and commercial heating applications  

E-Print Network (OSTI)

Though we must eventually find viable alternatives for fossil fuels in large segments of the energy market, there are economically attractive fossil fuel alternatives today for niche markets. The easiest fossil fuels to ...

Pendray, John Robert

2007-01-01T23:59:59.000Z

39

High Specific Power, Direct Methanol Fuel Cell Stack  

NLE Websites -- All DOE Office Websites (Extended Search)

High Specific Power, Direct Methanol Fuel Cell Stack High Specific Power, Direct Methanol Fuel Cell Stack High Specific Power, Direct Methanol Fuel Cell Stack The present invention is a fuel cell stack including at least one direct methanol fuel cell. Available for thumbnail of Feynman Center (505) 665-9090 Email High Specific Power, Direct Methanol Fuel Cell Stack The present invention is a fuel cell stack including at least one direct methanol fuel cell. A cathode manifold is used to convey ambient air to each fuel cell, and an anode manifold is used to convey liquid methanol fuel to each fuel cell. Tie-bolt penetrations and tie-bolts are spaced evenly around the perimeter to hold the fuel cell stack together. Each fuel cell uses two graphite-based plates. One plate includes a cathode active area that is defined by serpentine channels connecting the inlet manifold

40

Fuel  

E-Print Network (OSTI)

heavy-water-moderated, light-water-moderated and liquid-metal cooled fast breeder reactors fueled with natural or low-enriched uranium and containing thorium mixed with the uranium or in separate target channels. U-232 decays with a 69-year half-life through 1.9-year half-life Th-228 to Tl-208, which emits a 2.6 MeV gamma ray upon decay. We find that pressurized light-water-reactors fueled with LEU-thorium fuel at high burnup (70 MWd/kg) produce U-233 with U-232 contamination levels of about 0.4 percent. At this contamination level, a 5 kg sphere of U-233 would produce a gammaray dose rate of 13 and 38 rem/hr at 1 meter one and ten years after chemical purification respectively. The associated plutonium contains 7.5 percent of the undesirable heat-generating 88-year half-life isotope Pu-238. However, just as it is possible to produce weapon-grade plutonium in low-burnup fuel, it is also practical to use heavy-water reactors to produce U-233 containing only a few ppm of U-232 if the thorium is segregated in “target ” channels and discharged a few times more frequently than the natural-uranium “driver ” fuel. The dose rate from a 5-kg solid sphere of U-233 containing 5 ppm U-232 could be reduced by a further factor of 30, to about 2 mrem/hr, with a close-fitting lead sphere weighing about 100 kg. Thus the proliferation resistance of thorium fuel cycles depends very much upon how they are implemented. The original version of this manuscript was received by Science & Global Security on

Jungmin Kang A

2001-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "high grade fuel" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

High-pressure coal fuel processor development  

DOE Green Energy (OSTI)

Caterpillar shares DOE/METC interest in demonstrating the technology required to displace petroleum-based engine fuels with various forms of low cost coal. Current DOE/METC programs on mild gasification and coal-water-slurries are addressing two approaches to this end. Engine and fuel processor system concept studies by Caterpillar have identified a third, potentially promising, option. This option includes high-pressure fuel processing of run-of-the-mine coal and direct injection of the resulting low-Btu gas stream into an ignition assisted, high compression ratio diesel engine. The compactness and predicted efficiency of the system make it suitable for application to line-haul railroad locomotives. Two overall conclusions resulted from Task 1. First direct injected, ignition assisted Diesel cycle engine combustion systems can be suitably modified to efficiently utilize low-Btu gas fuels. Second, high pressure gasification of selected run-of-the-mine coals in batch-loaded fuel processors is feasible. These two findings, taken together, significantly reduce the perceived technical risk associated with the further development of the proposed coal gas fueled Diesel cycle power plant concept. The significant conclusions from Task 2 were: An engine concept, derived from a Caterpillar 3600 series engine, and a fuel processor concept, based on scaling up a removable-canister configuration from the test rig, appear feasible; and although the results of this concept study are encouraging, further, full-scale component research and development are required before attempting a full-scale integrated system demonstration effort.

Greenhalgh, M.L. (Caterpillar, Inc., Peoria, IL (United States))

1992-12-01T23:59:59.000Z

42

Establishing a Cost Basis for Converting the High Flux Isotope Reactor from High Enriched to Low Enriched Uranium Fuel  

Science Conference Proceedings (OSTI)

Under the auspices of the Global Threat Reduction Initiative Reduced Enrichment for Research and Test Reactors Program, the National Nuclear Security Administration /Department of Energy (NNSA/DOE) has, as a goal, to convert research reactors worldwide from weapons grade to non-weapons grade uranium. The High Flux Isotope Reactor (HFIR) at Oak Ridge National Lab (ORNL) is one of the candidates for conversion of fuel from high enriched uranium (HEU) to low enriched uranium (LEU). A well documented business model, including tasks, costs, and schedules was developed to plan the conversion of HFIR. Using Microsoft Project, a detailed outline of the conversion program was established and consists of LEU fuel design activities, a fresh fuel shipping cask, improvements to the HFIR reactor building, and spent fuel operations. Current-value costs total $76 million dollars, include over 100 subtasks, and will take over 10 years to complete. The model and schedule follows the path of the fuel from receipt from fuel fabricator to delivery to spent fuel storage and illustrates the duration, start, and completion dates of each subtask to be completed. Assumptions that form the basis of the cost estimate have significant impact on cost and schedule.

Primm, Trent [ORNL; Guida, Tracey [University of Pittsburgh

2010-02-01T23:59:59.000Z

43

High-pressure coal fuel processor development  

DOE Green Energy (OSTI)

The objective of Subtask 1.1 Engine Feasibility was to conduct research needed to establish the technical feasibility of ignition and stable combustion of directly injected, 3,000 psi, low-Btu gas with glow plug ignition assist at diesel engine compression ratios. This objective was accomplished by designing, fabricating, testing and analyzing the combustion performance of synthesized low-Btu coal gas in a single-cylinder test engine combustion rig located at the Caterpillar Technical Center engine lab in Mossville, Illinois. The objective of Subtask 1.2 Fuel Processor Feasibility was to conduct research needed to establish the technical feasibility of air-blown, fixed-bed, high-pressure coal fuel processing at up to 3,000 psi operating pressure, incorporating in-bed sulfur and particulate capture. This objective was accomplished by designing, fabricating, testing and analyzing the performance of bench-scale processors located at Coal Technology Corporation (subcontractor) facilities in Bristol, Virginia. These two subtasks were carried out at widely separated locations and will be discussed in separate sections of this report. They were, however, independent in that the composition of the synthetic coal gas used to fuel the combustion rig was adjusted to reflect the range of exit gas compositions being produced on the fuel processor rig. Two major conclusions resulted from this task. First, direct injected, ignition assisted Diesel cycle engine combustion systems can be suitably modified to efficiently utilize these low-Btu gas fuels. Second, high pressure gasification of selected run-of-the-mine coals in batch-loaded fuel processors is feasible. These two findings, taken together, significantly reduce the perceived technical risks associated with the further development of the proposed coal gas fueled Diesel cycle power plant concept.

Greenhalgh, M.L.

1992-11-01T23:59:59.000Z

44

Alternative Fuels Data Center: Authorization for High Occupancy Vehicle  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Authorization for High Authorization for High Occupancy Vehicle (HOV) Lane Exemption to someone by E-mail Share Alternative Fuels Data Center: Authorization for High Occupancy Vehicle (HOV) Lane Exemption on Facebook Tweet about Alternative Fuels Data Center: Authorization for High Occupancy Vehicle (HOV) Lane Exemption on Twitter Bookmark Alternative Fuels Data Center: Authorization for High Occupancy Vehicle (HOV) Lane Exemption on Google Bookmark Alternative Fuels Data Center: Authorization for High Occupancy Vehicle (HOV) Lane Exemption on Delicious Rank Alternative Fuels Data Center: Authorization for High Occupancy Vehicle (HOV) Lane Exemption on Digg Find More places to share Alternative Fuels Data Center: Authorization for High Occupancy Vehicle (HOV) Lane Exemption on

45

,- A Model for Syringe Grading Based on Extracted Features From High Dimensional Friction Data  

E-Print Network (OSTI)

In the biomedical products industry, measures of the quality of individual clinical specimens or manufacturing production units are often available in the form of high dimensional data such as continuous recordings obtained from an analytical instrument. These recordings are then examined by experts in the field who extract certain features and use these to classify individuals. To formalize and quantify this procedure an approach for extracting features from recordings based on nonparametric regression is described. These features are then used to build a classification model which incorporates the knowledge of the expert automatically. The procedure is presented via an example involving the grading of syringes from associated friction profile data. Features of the syringe friction profiles used in the classification are extracted via smoothing splines and grades of the syringes are assigned by an expert tribologist. A nonlinear classification model is constructed to predict syringe grades based on the extracted features. The classification model makes it possible to grade syringes automatically without

Gerry Gray; David Martin; Perry Haal; Series M. Oconnel; G. Gray; P. Haal; Michael O' connell; Doug Nychka; Gerry Gray; David Martin; Perry Haal

1993-01-01T23:59:59.000Z

46

Analysis of High-Collapse Grade P110 Coupling Failures  

Science Conference Proceedings (OSTI)

These failures have typically occurred during fracturing operations, when the couplings are subjected to particularly high hoop stresses, and have cumulatively  ...

47

Polyelectrolyte Materials for High Temperature Fuel Cells  

NLE Websites -- All DOE Office Websites (Extended Search)

Polyelectrolyte Materials for High Polyelectrolyte Materials for High 3M (3M) Temperature Fuel Cells John B. Kerr Lawrence Berkeley National Laboratory (LBNL) Collaborators: Los Alamos National Laboratory (LANL). February 13, 2007 This presentation does not contain any proprietary or confidential information Team Members: Nitash Blasara, Rachel Segalman, Adam Weber (LBNL). Bryan Pivovar, James Boncella (LANL) Steve Hamrock Objectives * Investigate the use of solid polyelectrolyte proton conductors that do not require the presence of water. * Prepare solid electrolytes where only the proton moves. - Measure conductivity, mechanical/thermal properties of Nafion® and other polyelectrolytes doped with imidazoles. Compare with water doped materials. - Covalently attach imidazoles to side chains of ionomers with

48

Preparation of high temperature gas-cooled reactor fuel element  

DOE Patents (OSTI)

This invention relates to a method for the preparation of high temperature gas-cooled reactor (HTGR) fuel elements wherein uncarbonized fuel rods are inserted in appropriate channels of an HTGR fuel element block and the entire block is inserted in an autoclave for in situ carbonization under high pressure. The method is particularly applicable to remote handling techniques.

Bradley, Ronnie A. (Oak Ridge, TN); Sease, John D. (Knoxville, TN)

1976-01-01T23:59:59.000Z

49

Fuel Cell Technologies Office: 2005 High Temperature Membrane Working Group  

NLE Websites -- All DOE Office Websites (Extended Search)

About About Printable Version Share this resource Send a link to Fuel Cell Technologies Office: 2005 High Temperature Membrane Working Group Meeting Archives to someone by E-mail Share Fuel Cell Technologies Office: 2005 High Temperature Membrane Working Group Meeting Archives on Facebook Tweet about Fuel Cell Technologies Office: 2005 High Temperature Membrane Working Group Meeting Archives on Twitter Bookmark Fuel Cell Technologies Office: 2005 High Temperature Membrane Working Group Meeting Archives on Google Bookmark Fuel Cell Technologies Office: 2005 High Temperature Membrane Working Group Meeting Archives on Delicious Rank Fuel Cell Technologies Office: 2005 High Temperature Membrane Working Group Meeting Archives on Digg Find More places to share Fuel Cell Technologies Office: 2005 High

50

Fuel Cell Technologies Office: 2004 High Temperature Membrane Working Group  

NLE Websites -- All DOE Office Websites (Extended Search)

About About Printable Version Share this resource Send a link to Fuel Cell Technologies Office: 2004 High Temperature Membrane Working Group Meeting Archives to someone by E-mail Share Fuel Cell Technologies Office: 2004 High Temperature Membrane Working Group Meeting Archives on Facebook Tweet about Fuel Cell Technologies Office: 2004 High Temperature Membrane Working Group Meeting Archives on Twitter Bookmark Fuel Cell Technologies Office: 2004 High Temperature Membrane Working Group Meeting Archives on Google Bookmark Fuel Cell Technologies Office: 2004 High Temperature Membrane Working Group Meeting Archives on Delicious Rank Fuel Cell Technologies Office: 2004 High Temperature Membrane Working Group Meeting Archives on Digg Find More places to share Fuel Cell Technologies Office: 2004 High

51

Fuel Cell Technologies Office: 2010 High Temperature Membrane Working Group  

NLE Websites -- All DOE Office Websites (Extended Search)

About About Printable Version Share this resource Send a link to Fuel Cell Technologies Office: 2010 High Temperature Membrane Working Group Meeting Archives to someone by E-mail Share Fuel Cell Technologies Office: 2010 High Temperature Membrane Working Group Meeting Archives on Facebook Tweet about Fuel Cell Technologies Office: 2010 High Temperature Membrane Working Group Meeting Archives on Twitter Bookmark Fuel Cell Technologies Office: 2010 High Temperature Membrane Working Group Meeting Archives on Google Bookmark Fuel Cell Technologies Office: 2010 High Temperature Membrane Working Group Meeting Archives on Delicious Rank Fuel Cell Technologies Office: 2010 High Temperature Membrane Working Group Meeting Archives on Digg Find More places to share Fuel Cell Technologies Office: 2010 High

52

Fuel Cell Technologies Office: 2007 High Temperature Membrane Working Group  

NLE Websites -- All DOE Office Websites (Extended Search)

About About Printable Version Share this resource Send a link to Fuel Cell Technologies Office: 2007 High Temperature Membrane Working Group Meeting Archives to someone by E-mail Share Fuel Cell Technologies Office: 2007 High Temperature Membrane Working Group Meeting Archives on Facebook Tweet about Fuel Cell Technologies Office: 2007 High Temperature Membrane Working Group Meeting Archives on Twitter Bookmark Fuel Cell Technologies Office: 2007 High Temperature Membrane Working Group Meeting Archives on Google Bookmark Fuel Cell Technologies Office: 2007 High Temperature Membrane Working Group Meeting Archives on Delicious Rank Fuel Cell Technologies Office: 2007 High Temperature Membrane Working Group Meeting Archives on Digg Find More places to share Fuel Cell Technologies Office: 2007 High

53

On the use of high performance annular fuel in PWRs  

E-Print Network (OSTI)

Recently, MIT's Center for Advanced Nuclear Energy Systems developed a new high burnup annular fuel that features both internal and external cooling. Implementation of this fuel design in current pressurized water reactors ...

Feng, Bo, Ph. D. Massachusetts Institute of Technology

2008-01-01T23:59:59.000Z

54

New Type Bainitic Steel for Grade R5 High Performance Offshore ...  

Science Conference Proceedings (OSTI)

Abstract Scope, A new type bainitic steel for grade R5 (typical composition: 0.21C -0.90Mn-0.25Si-1.90Cr-0.9Ni-0.45Mo-microalloy) high performance offshore ...

55

Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

High Occupancy Vehicle High Occupancy Vehicle (HOV) Lane Exemption to someone by E-mail Share Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on Facebook Tweet about Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on Twitter Bookmark Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on Google Bookmark Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on Delicious Rank Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on Digg Find More places to share Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type High Occupancy Vehicle (HOV) Lane Exemption

56

Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

High Occupancy Vehicle High Occupancy Vehicle (HOV) Lane Exemption to someone by E-mail Share Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on Facebook Tweet about Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on Twitter Bookmark Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on Google Bookmark Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on Delicious Rank Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on Digg Find More places to share Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type High Occupancy Vehicle (HOV) Lane Exemption

57

Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

High Occupancy Vehicle High Occupancy Vehicle (HOV) Lane Exemption to someone by E-mail Share Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on Facebook Tweet about Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on Twitter Bookmark Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on Google Bookmark Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on Delicious Rank Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on Digg Find More places to share Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type High Occupancy Vehicle (HOV) Lane Exemption

58

Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

High Occupancy Vehicle High Occupancy Vehicle (HOV) Lane Exemption to someone by E-mail Share Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on Facebook Tweet about Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on Twitter Bookmark Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on Google Bookmark Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on Delicious Rank Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on Digg Find More places to share Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type High Occupancy Vehicle (HOV) Lane Exemption

59

Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

High Occupancy Vehicle High Occupancy Vehicle (HOV) Lane Exemption to someone by E-mail Share Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on Facebook Tweet about Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on Twitter Bookmark Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on Google Bookmark Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on Delicious Rank Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on Digg Find More places to share Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type High Occupancy Vehicle (HOV) Lane Exemption

60

Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

High Occupancy Vehicle High Occupancy Vehicle (HOV) Lane Exemption to someone by E-mail Share Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on Facebook Tweet about Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on Twitter Bookmark Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on Google Bookmark Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on Delicious Rank Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on Digg Find More places to share Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type High Occupancy Vehicle (HOV) Lane Exemption

Note: This page contains sample records for the topic "high grade fuel" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

High Occupancy Vehicle High Occupancy Vehicle (HOV) Lane Exemption to someone by E-mail Share Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on Facebook Tweet about Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on Twitter Bookmark Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on Google Bookmark Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on Delicious Rank Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on Digg Find More places to share Alternative Fuels Data Center: High Occupancy Vehicle (HOV) Lane Exemption on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type High Occupancy Vehicle (HOV) Lane Exemption

62

Fuel Cell Technologies Office: 2009 High Temperature Membrane Working Group  

NLE Websites -- All DOE Office Websites (Extended Search)

9 High Temperature 9 High Temperature Membrane Working Group Meeting Archives to someone by E-mail Share Fuel Cell Technologies Office: 2009 High Temperature Membrane Working Group Meeting Archives on Facebook Tweet about Fuel Cell Technologies Office: 2009 High Temperature Membrane Working Group Meeting Archives on Twitter Bookmark Fuel Cell Technologies Office: 2009 High Temperature Membrane Working Group Meeting Archives on Google Bookmark Fuel Cell Technologies Office: 2009 High Temperature Membrane Working Group Meeting Archives on Delicious Rank Fuel Cell Technologies Office: 2009 High Temperature Membrane Working Group Meeting Archives on Digg Find More places to share Fuel Cell Technologies Office: 2009 High Temperature Membrane Working Group Meeting Archives on AddThis.com...

63

High Performance Fuel Desing for Next Generation Pressurized Water Reactors  

SciTech Connect

The use of internally and externally cooled annular fule rods for high power density Pressurized Water Reactors is assessed. The assessment included steady state and transient thermal conditions, neutronic and fuel management requirements, mechanical vibration issues, fuel performance issues, fuel fabrication methods and econmic assessment. The investigation was donducted by a team from MIT, Westinghouse, Gamma Engineering, Framatome ANP, and AECL. The analyses led to the conclusion that raising the power density by 50% may be possible with this advanced fuel. Even at the 150% power level, the fuel temperature would be a few hundred degrees lower than the current fuel temperatre. Significant economic and safety advantages can be obtained by using this fuel in new reactors. Switching to this type of fuel for existing reactors would yield safety advantages, but the economic return is dependent on the duration of plant shutdown to accommodate higher power production. The main feasiblity issue for the high power performance appears to be the potential for uneven splitting of heat flux between the inner and outer fuel surfaces due to premature closure of the outer fuel-cladding gap. This could be overcome by using a very narrow gap for the inner fuel surface and/or the spraying of a crushable zirconium oxide film at the fuel pellet outer surface. An alternative fuel manufacturing approach using vobropacking was also investigated but appears to yield lower than desirable fuel density.

Mujid S. Kazimi; Pavel Hejzlar

2006-01-31T23:59:59.000Z

64

Feasibility study for fuel grade ethanol complex, Kennewick, Washington. Volume II of V. Market evaluation  

SciTech Connect

Midwestern corn prices are projected to increase continuously over the next five years, while Distillers Dried Grains (DDGS) prices are projected to decline and not recover until 1985. If midwestern shippers are successful in negotiating favorable freight rates for DDGS, local prices could also decline during the period from 1981 to 1985. If they are not successful and freight rates continue to increase over the period, adequate regional and export markets will be available for all the DDGS produced by Omega Fuels, at prices competitive with other regional feed supplements. Large volumes of midwestern corn are currently exported from Seattle-Tacoma. Rail lines serving this port pass near the Omega Fuels' plant site in Kennewick, Washington. Therefore, start-up of the plant using midwestern corn should not be difficult. The corn oil by-product can be easily marketed in the region at prices competitive with soy oil. As production becomes established, the corn oil may be able to command its traditional premium price. Coal ash, mineral sludge, and CO/sub 2/ by-products may find local markets - if they are actively marketed by Omega Fuels. These by-products are not expected to produce significant revenues. However, if markets are not sought, conventional disposal methods will be a net cost to the operation of the plant. The market for ethanol in the region will have to be expanded significantly to absorb Omega Fuels' production. Unleaded regular is gasohol's major competitor. As such, the wholesale price of unleaded regular gasoline will control the selling price of ethanol.

1981-07-01T23:59:59.000Z

65

Alternative Fuels Data Center: Hybrid Electric Vehicle (HEV) High Occupancy  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Hybrid Electric Hybrid Electric Vehicle (HEV) High Occupancy Vehicle (HOV) Lane Exemption to someone by E-mail Share Alternative Fuels Data Center: Hybrid Electric Vehicle (HEV) High Occupancy Vehicle (HOV) Lane Exemption on Facebook Tweet about Alternative Fuels Data Center: Hybrid Electric Vehicle (HEV) High Occupancy Vehicle (HOV) Lane Exemption on Twitter Bookmark Alternative Fuels Data Center: Hybrid Electric Vehicle (HEV) High Occupancy Vehicle (HOV) Lane Exemption on Google Bookmark Alternative Fuels Data Center: Hybrid Electric Vehicle (HEV) High Occupancy Vehicle (HOV) Lane Exemption on Delicious Rank Alternative Fuels Data Center: Hybrid Electric Vehicle (HEV) High Occupancy Vehicle (HOV) Lane Exemption on Digg Find More places to share Alternative Fuels Data Center: Hybrid

66

Thermal regimes of high burn-up nuclear fuel rod  

E-Print Network (OSTI)

The temperature distribution in the nuclear fuel rods for high burn-up is studied. We use the numerical and analytical approaches. It is shown that the time taken to have the stationary thermal regime of nuclear fuel rod is less than one minute. We can make the inference that the behavior of the nuclear fuel rod can be considered as a stationary task. Exact solutions of the temperature distribution in the fuel rods in the stationary case are found. Thermal regimes of high burn-up the nuclear fuel rods are analyzed.

Kudryashov, Nikolai A; Chmykhov, Mikhail A; 10.1016/j.cnsns.2009.05.063

2012-01-01T23:59:59.000Z

67

High Performance Diesel Fueled Cabin Heater  

DOE Green Energy (OSTI)

Recent DOE-OHVT studies show that diesel emissions and fuel consumption can be greatly reduced at truck stops by switching from engine idle to auxiliary-fired heaters. Brookhaven National Laboratory (BNL) has studied high performance diesel burner designs that address the shortcomings of current low fire-rate burners. Initial test results suggest a real opportunity for the development of a truly advanced truck heating system. The BNL approach is to use a low pressure, air-atomized burner derived form burner designs used commonly in gas turbine combustors. This paper reviews the design and test results of the BNL diesel fueled cabin heater. The burner design is covered by U.S. Patent 6,102,687 and was issued to U.S. DOE on August 15, 2000.The development of several novel oil burner applications based on low-pressure air atomization is described. The atomizer used is a pre-filming, air blast nozzle of the type commonly used in gas turbine combustion. The air pressure used can b e as low as 1300 Pa and such pressure can be easily achieved with a fan. Advantages over conventional, pressure-atomized nozzles include ability to operate at low input rates without very small passages and much lower fuel pressure requirements. At very low firing rates the small passage sizes in pressure swirl nozzles lead to poor reliability and this factor has practically constrained these burners to firing rates over 14 kW. Air atomization can be used very effectively at low firing rates to overcome this concern. However, many air atomizer designs require pressures that can be achieved only with a compressor, greatly complicating the burner package and increasing cost. The work described in this paper has been aimed at the practical adaptation of low-pressure air atomization to low input oil burners. The objective of this work is the development of burners that can achieve the benefits of air atomization with air pressures practically achievable with a simple burner fan.

Butcher, Tom

2001-08-05T23:59:59.000Z

68

Fabrication of high exposure nuclear fuel pellets  

DOE Patents (OSTI)

A method is disclosed for making a fuel pellet for a nuclear reactor. A mixture is prepared of PuO.sub.2 and UO.sub.2 powders, where the mixture contains at least about 30% PuO.sub.2, and where at least about 12% of the Pu is the Pu.sup.240 isotope. To this mixture is added about 0.3 to about 5% of a binder having a melting point of at least about 250.degree. F. The mixture is pressed to form a slug and the slug is granulated. Up to about 4.7% of a lubricant having a melting point of at least about 330.degree. F. is added to the granulated slug. Both the binder and the lubricant are selected from a group consisting of polyvinyl carboxylate, polyvinyl alcohol, naturally occurring high molecular weight cellulosic polymers, chemically modified high molecular weight cellulosic polymers, and mixtures thereof. The mixture is pressed to form a pellet and the pellet is sintered.

Frederickson, James R. (Richland, WA)

1987-01-01T23:59:59.000Z

69

Premixer Design for High Hydrogen Fuels  

DOE Green Energy (OSTI)

This 21-month project translated DLN technology to the unique properties of high hydrogen content IGCC fuels, and yielded designs in preparation for a future testing and validation phase. Fundamental flame characterization, mixing, and flame property measurement experiments were conducted to tailor computational design tools and criteria to create a framework for predicting nozzle operability (e.g., flame stabilization, emissions, resistance to flashback/flame-holding and auto-ignition). This framework was then used to establish, rank, and evaluate potential solutions to the operability challenges of IGCC combustion. The leading contenders were studied and developed with the most promising concepts evaluated via computational fluid dynamics (CFD) modeling and using the design rules generated by the fundamental experiments, as well as using GE's combustion design tools and practices. Finally, the project scoped the necessary steps required to carry the design through mechanical and durability review, testing, and validation, towards full demonstration of this revolutionary technology. This project was carried out in three linked tasks with the following results. (1) Develop conceptual designs of premixer and down-select the promising options. This task defined the ''gap'' between existing design capabilities and the targeted range of IGCC fuel compositions and evaluated the current capability of DLN pre-mixer designs when operated at similar conditions. Two concepts (1) swirl based and (2) multiple point lean direct injection based premixers were selected via a QFD from 13 potential design concepts. (2) Carry out CFD on chosen options (1 or 2) to evaluate operability risks. This task developed the leading options down-selected in Task 1. Both a GE15 swozzle based premixer and a lean direct injection concept were examined by performing a detailed CFD study wherein the aerodynamics of the design, together with the chemical kinetics of the combustion process, were analyzed to evaluate the performance of the different concepts. Detailed 1-D analysis was performed to provide 1-step NOx and 1-step combustion models that could be utilized in CFD to provide more accurate estimates of NOx for more complicated combustion designs. The swozzle results identified potential problems with flame holding, flashback and with adequate mixing. Flame holding issues were further evaluated with laboratory testing to determine under what conditions a jet in cross flow would flame hold. Additional CFD analysis was also performed on fuel injection from a peg to simulate fuel injection off a vane's trailing edge. This task was concluded with a Conceptual Design Review of the two selected design concepts. (3) Optimize design and re-evaluate operability risks. This task extended the analysis of LDI concepts and increased understanding of the optimal design configuration. Designs were selected for subscale combustion laboratory testing and then modeled using CFD to validate CFD methodology. CFD provided a good qualitative match and reasonable quantitative match with the test results. Tests and CFD modeling indicated a path to low NOx combustion with no diluent addition. Different swirler designs were also evaluated and the most promising, a counter rotating swirler, was selected for further evaluation. CFD modeling was performed and the design was optimized to improve mixing. CFD modeling indicated the potential for low NOx combustion without diluent addition. CFD was validated against cold flow testing on a swirler using helium injection in place of hydrogen. Further validation work is still needed to ensure the ability to accurately model the mixing of swirling flows. Entitlement testing was performed on a perfectly premixed H2/N2/air mixture. Results showed that low NOx could be obtained at the temperatures of interest (7FB conditions) with no diluent addition. Results also showed that further NOx reductions might be possible by taking advantage of the very rapid H2 reaction to reduce combustor length and hence residence time. These results also in

Benjamin P. Lacy; Keith R. McManus; Balachandar Varatharajan; Biswadip Shome

2005-12-16T23:59:59.000Z

70

Fuel Cell Technologies Office: High Temperature Membrane Working Group  

NLE Websites -- All DOE Office Websites (Extended Search)

High Temperature Membrane Working Group High Temperature Membrane Working Group The High Temperature Membrane Working Group consists of government, industry, and university researchers interested in developing high temperature membranes for fuel cells. Description Technical Targets Meetings Contacts Description Polymer electrolyte membrane (PEM) fuel cells typically operate at temperatures no higher than 60°C-80°C due to structural limitations of the membrane. Operating PEM fuel cell stacks at higher temperatures (120°C for transportation and 150°C for stationary applications), however, would yield significant energy benefits. For example, heat rejection is easier at higher temperatures, which would allow use of smaller heat exchangers in fuel cell power systems. In addition, for reformate fuel cell systems, carbon monoxide (CO) tolerance of the stack is less problematic at higher temperatures, which would reduce the size requirements or possibly eliminate the need for some CO clean-up beds in the fuel processor.

71

Premixed direct injection nozzle for highly reactive fuels  

Science Conference Proceedings (OSTI)

A fuel/air mixing tube for use in a fuel/air mixing tube bundle is provided. The fuel/air mixing tube includes an outer tube wall extending axially along a tube axis between an inlet end and an exit end, the outer tube wall having a thickness extending between an inner tube surface having a inner diameter and an outer tube surface having an outer tube diameter. The tube further includes at least one fuel injection hole having a fuel injection hole diameter extending through the outer tube wall, the fuel injection hole having an injection angle relative to the tube axis. The invention provides good fuel air mixing with low combustion generated NOx and low flow pressure loss translating to a high gas turbine efficiency, that is durable, and resistant to flame holding and flash back.

Ziminsky, Willy Steve; Johnson, Thomas Edward; Lacy, Benjamin Paul; York, William David; Uhm, Jong Ho; Zuo, Baifang

2013-09-24T23:59:59.000Z

72

Molten salt fuels with high plutonium solubility  

DOE Patents (OSTI)

The present invention includes a composition of LiF--ThF.sub.4--UF.sub.4--PuF.sub.3 for use as a fuel in a nuclear engine.

Moir, Ralph W; Turchi, Patrice E.A.; Shaw, Henry F; Kaufman, Larry

2013-08-13T23:59:59.000Z

73

Hydrothermal processing of high-lipid biomass to fuels  

E-Print Network (OSTI)

High-lipid algae are potential sources of biofuels. Lipids in this biomass provide a straightforward chemical route to hydrocarbon-based high energy-density fuels needed for diesel and jet engines. However, current schemes ...

Johnson, Michael C., Ph. D. Massachusetts Institute of Technology

2012-01-01T23:59:59.000Z

74

Fuel Flexible Combustion Systems for High-Efficiency Utilization of Opportunity Fuels in Gas Turbines  

SciTech Connect

The purpose of this program was to develop low-emissions, efficient fuel-flexible combustion technology which enables operation of a given gas turbine on a wider range of opportunity fuels that lie outside of current natural gas-centered fuel specifications. The program encompasses a selection of important, representative fuels of opportunity for gas turbines with widely varying fundamental properties of combustion. The research program covers conceptual and detailed combustor design, fabrication, and testing of retrofitable and/or novel fuel-flexible gas turbine combustor hardware, specifically advanced fuel nozzle technology, at full-scale gas turbine combustor conditions. This project was performed over the period of October 2008 through September 2011 under Cooperative Agreement DE-FC26-08NT05868 for the U.S. Department of Energy/National Energy Technology Laboratory (USDOE/NETL) entitled "Fuel Flexible Combustion Systems for High-Efficiency Utilization of Opportunity Fuels in Gas Turbines". The overall objective of this program was met with great success. GE was able to successfully demonstrate the operability of two fuel-flexible combustion nozzles over a wide range of opportunity fuels at heavy-duty gas turbine conditions while meeting emissions goals. The GE MS6000B ("6B") gas turbine engine was chosen as the target platform for new fuel-flexible premixer development. Comprehensive conceptual design and analysis of new fuel-flexible premixing nozzles were undertaken. Gas turbine cycle models and detailed flow network models of the combustor provide the premixer conditions (temperature, pressure, pressure drops, velocities, and air flow splits) and illustrate the impact of widely varying fuel flow rates on the combustor. Detailed chemical kinetic mechanisms were employed to compare some fundamental combustion characteristics of the target fuels, including flame speeds and lean blow-out behavior. Perfectly premixed combustion experiments were conducted to provide experimental combustion data of our target fuels at gas turbine conditions. Based on an initial assessment of premixer design requirements and challenges, the most promising sub-scale premixer concepts were evaluated both experimentally and computationally. After comprehensive screening tests, two best performing concepts were scaled up for further development. High pressure single nozzle tests were performed with the scaled premixer concepts at target gas turbine conditions with opportunity fuels. Single-digit NOx emissions were demonstrated for syngas fuels. Plasma-assisted pilot technology was demonstrated to enhance ignition capability and provide additional flame stability margin to a standard premixing fuel nozzle. However, the impact of plasma on NOx emissions was observed to be unacceptable given the goals of this program and difficult to avoid.

Venkatesan, Krishna

2011-11-30T23:59:59.000Z

75

Low contaminant formic acid fuel for direct liquid fuel cell  

Science Conference Proceedings (OSTI)

A low contaminant formic acid fuel is especially suited toward use in a direct organic liquid fuel cell. A fuel of the invention provides high power output that is maintained for a substantial time and the fuel is substantially non-flammable. Specific contaminants and contaminant levels have been identified as being deleterious to the performance of a formic acid fuel in a fuel cell, and embodiments of the invention provide low contaminant fuels that have improved performance compared to known commercial bulk grade and commercial purified grade formic acid fuels. Preferred embodiment fuels (and fuel cells containing such fuels) including low levels of a combination of key contaminants, including acetic acid, methyl formate, and methanol.

Masel, Richard I. (Champaign, IL); Zhu, Yimin (Urbana, IL); Kahn, Zakia (Palatine, IL); Man, Malcolm (Vancouver, CA)

2009-11-17T23:59:59.000Z

76

Fuels  

NLE Websites -- All DOE Office Websites (Extended Search)

Goals > Fuels Goals > Fuels XMAT for nuclear fuels XMAT is ideally suited to explore all of the radiation processes experienced by nuclear fuels.The high energy, heavy ion accleration capability (e.g., 250 MeV U) can produce bulk damage deep in the sample, achieving neutron type depths (~10 microns), beyond the range of surface sputtering effects. The APS X-rays are well matched to the ion beams, and are able to probe individual grains at similar penetrations depths. Damage rates to 25 displacements per atom per hour (DPA/hr), and doses >2500 DPA can be achieved. MORE» Fuels in LWRs are subjected to ~1 DPA per day High burn-up fuel can experience >2000 DPA. Traditional reactor tests by neutron irradiation require 3 years in a reactor and 1 year cool down. Conventional accelerators (>1 MeV/ion) are limited to <200-400 DPAs, and

77

The Fuel Accident Condition Simulator (FACS) furnace system for high temperature performance testing of VHTR fuel  

SciTech Connect

The AGR-1 irradiation of TRISO-coated particle fuel specimens was recently completed and represents the most successful such irradiation in US history, reaching peak burnups of greater than 19% FIMA with zero failures out of 300,000 particles. An extensive post-irradiation examination (PIE) campaign will be conducted on the AGR-1 fuel in order to characterize the irradiated fuel properties, assess the in-pile fuel performance in terms of coating integrity and fission metals release, and determine the fission product retention behavior during high temperature safety testing. A new furnace system has been designed, built, and tested to perform high temperature accident tests. The Fuel Accident Condition Simulator furnace system is designed to heat fuel specimens at temperatures up to 2000 degrees C in helium while monitoring the release of volatile fission metals (e.g. Cs, Ag, Sr, and Eu), iodine, and fission gases (Kr, Xe). Fission gases released from the fuel to the sweep gas are monitored in real time using dual cryogenic traps fitted with high purity germanium detectors. Condensable fission products are collected on a plate attached to a water-cooled cold finger that can be exchanged periodically without interrupting the test. Analysis of fission products on the condensation plates involves dry gamma counting followed by chemical analysis of selected isotopes. This paper will describe design and operational details of the Fuel Accident Condition Simulator furnace system and the associated fission gas monitoring system, as well as preliminary system calibration results.

Paul A. Demkowicz; David V. Laug; Dawn M. Scates; Edward L. Reber; Lyle G. Roybal; John B. Walter; Jason M. Harp; Robert N. Morris

2012-10-01T23:59:59.000Z

78

High temperature solid electrolyte fuel cell configurations and interconnections  

DOE Patents (OSTI)

High temperature fuel cell configurations and interconnections are made including annular cells having a solid electrolyte sandwiched between thin film electrodes. The cells are electrically interconnected along an elongated axial outer surface.

Isenberg, Arnold O. (Forest Hills, PA)

1984-01-01T23:59:59.000Z

79

Innovative fuel designs for high power density pressurized water reactor  

E-Print Network (OSTI)

One of the ways to lower the cost of nuclear energy is to increase the power density of the reactor core. Features of fuel design that enhance the potential for high power density are derived based on characteristics of ...

Feng, Dandong, Ph. D. Massachusetts Institute of Technology

2006-01-01T23:59:59.000Z

80

X-ray Imaging of Shock Waves Generated by High-Pressure Fuel...  

NLE Websites -- All DOE Office Websites (Extended Search)

X-ray Imaging of Shock Waves Generated by High-Pressure Fuel Sprays High-pressure, high-speed fuel sprays are a critical technology for many applications including fuel injection...

Note: This page contains sample records for the topic "high grade fuel" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


81

HIGH ENERGY LIQUID FUELS FROM PLANTS  

DOE Green Energy (OSTI)

The heptane extract of Euphorbia lathyris has a low oxygen content and a heat valve of 42 MJ/kg which is comparable to that of crude oil (44 MJ/kg). These qualities indicate a potential for use as fuel or chemical feedstock material. Therefore we have investigated the chemical composition of this fraction in some detail. Since the amoun of the methanol fraction is quite substantial we have also identified the major components of this fraction.

Nemethy, E. K.; Otvos, J. W.; Calvin, M.

1980-10-01T23:59:59.000Z

82

TRIGA high wt -% LEU fuel development program. Final report  

SciTech Connect

The principal purpose of this work was to investigate the characteristics of TRIGA fuel where the contained U-235 was in a relatively high weight percent (wt %) of LEU (low enriched uranium - enrichment of less than 20%) rather than a relatively low weight percent of HEU (high enriched uranium). Fuel with up to 45 wt % U was fabricated and found to be acceptable after metallurgical examinations, fission product retention tests and physical property examinations. Design and safety analysis studies also indicated acceptable prompt negative temperature coefficient and core lifetime characteristics for these fuels.

West, G.B.

1980-07-01T23:59:59.000Z

83

High velocity continuous-flow reactor for the production of solar grade silicon. Second quarterly report  

DOE Green Energy (OSTI)

The objective is to determine the feasibility of a high volume-high velocity continuous reduction reactor as an economical means for producing solar grade polycrystalline silicon. Preheated streams of hydrogen and bromosilanes are used as feed to the reduction reactor. Nucleation and deposition sites are provided by the additional feed of preheated silicon particles to the reactor. The effort has been directed at studying the chemistry taking place in the reactor, determining the factors which influence its course, and making necessary reactor modifications as dictated by observed results. The initial reactor design has been extensively changed. Energy losses due to gas expansion in the nozzle/mixer section of the reactor dictated these design changes. A ''Tee'' configuration, in which the two preheated gas streams are merged at right angles without any expansion, has replaced the nozzle/mixer. Results of the hydrogen reduction of tetrabromosilane with and without the use of silicon deposition substrate particles are analyzed.

Woerner, L.

1978-03-01T23:59:59.000Z

84

High Efficiency Direct Carbon and Hydrogen Fuel Cells for Fossil Fuel Power Generation  

SciTech Connect

Hydrogen he1 cells have been under development for a number of years and are now nearing commercial applications. Direct carbon fuel cells, heretofore, have not reached practical stages of development because of problems in fuel reactivity and cell configuration. The carbon/air fuel cell reaction (C + O{sub 2} = CO{sub 2}) has the advantage of having a nearly zero entropy change. This allows a theoretical efficiency of 100 % at 700-800 C. The activities of the C fuel and CO{sub 2} product do not change during consumption of the fuel. Consequently, the EMF is invariant; this raises the possibility of 100% fuel utilization in a single pass. (In contrast, the high-temperature hydrogen fuel cell has a theoretical efficiency of and changes in fuel activity limit practical utilizations to 75-85%.) A direct carbon fuel cell is currently being developed that utilizes reactive carbon particulates wetted by a molten carbonate electrolyte. Pure COZ is evolved at the anode and oxygen from air is consumed at the cathode. Electrochemical data is reported here for the carbon/air cell utilizing carbons derived from he1 oil pyrolysis, purified coal, purified bio-char and petroleum coke. At 800 O C, a voltage efficiency of 80% was measured at power densities of 0.5-1 kW/m2. Carbon and hydrogen fuels may be produced simultaneously at lugh efficiency from: (1) natural gas, by thermal decomposition, (2) petroleum, by coking or pyrolysis of distillates, (3) coal, by sequential hydrogasification to methane and thermal pyrolysis of the methane, with recycle of the hydrogen, and (4) biomass, similarly by sequential hydrogenation and thermal pyrolysis. Fuel production data may be combined with direct C and H2 fuel cell operating data for power cycle estimates. Thermal to electric efficiencies indicate 80% HHV [85% LHV] for petroleum, 75.5% HHV [83.4% LHV] for natural gas and 68.3% HHV [70.8% LHV] for lignite coal. Possible benefits of integrated carbon and hydrogen fuel cell power generation cycles are: (1) increased efficiency by a factor of up to 2 over many conventional fossil fuel steam plants, (2) reduced power generation cost, especially for increasing fossil fuel cost, (3) reduced CO2 emission per kWh, and (4) direct sequestration or reuse (e.g., in enhanced oil or NG recovery) of the CO{sub 2} product.

Steinberg, M; Cooper, J F; Cherepy, N

2002-01-02T23:59:59.000Z

85

EA-0510: High-Temperature Solid Oxide Fuel Cell (Sofc) Generator...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

510: High-Temperature Solid Oxide Fuel Cell (Sofc) Generator Development Project (METC), Churchill, Pennsylvania EA-0510: High-Temperature Solid Oxide Fuel Cell (Sofc) Generator...

86

Tritium production using highly enriched fuel  

SciTech Connect

Preliminary studies utilizing the MOFDA code have been made for tritium production at the K reactors using 33 and 35 grams per foot oralloy (93.5% U-235) in aluminum in conjunction with standard K5N and K5E fuel elements, respectively. For this report, it was assumed that all tritium would be produced in discrete charges of LiAl target elements. It is intended that the study will be extended at some later time to include LiAl splines. The analysis includes the effect of coolant loss on reactivity for hot-or-cold and green-or-exposed conditions for several oralloy loading fractions.

Miller, R.L.

1967-12-18T23:59:59.000Z

87

Coal-fueled high-speed diesel engine development  

DOE Green Energy (OSTI)

The objectives of this program are to study combustion feasibility by running Series 149 engine tests at high speeds with a fuel injection and combustion system designed for coal-water-slurry (CWS). The following criteria will be used to judge feasibility: (1) engine operation for sustained periods over the load range at speeds from 600 to 1900 rpm. The 149 engine for mine-haul trucks has a rated speed of 1900 rpm; (2) reasonable fuel economy and coal burnout rate; (3) reasonable cost of the engine design concept and CWS fuel compared to future oil prices.

Not Available

1991-11-01T23:59:59.000Z

88

Materials testing and development of functionally graded composite fuel cladding and piping for the Lead-Bismuth cooled nuclear reactor  

E-Print Network (OSTI)

This study has extended the development of an exciting technology which promises to enable the Pb-Bi eutectic cooled reactors to operate at temperatures up to 650-700°C. This new technology is a functionally graded composite ...

Fray, Elliott Shepard

2013-01-01T23:59:59.000Z

89

High efficiency carbonate fuel cell/turbine hybrid power cycle  

Science Conference Proceedings (OSTI)

The hybrid power cycle studies were conducted to identify a high efficiency, economically competitive system. A hybrid power cycle which generates power at an LHV efficiency > 70% was identified that includes an atmospheric pressure direct carbonate fuel cell, a gas turbine, and a steam cycle. In this cycle, natural gas fuel is mixed with recycled fuel cell anode exhaust, providing water for reforming fuel. The mixed gas then flows to a direct carbonate fuel cell which generates about 70% of the power. The portion of the anode exhaust which is not recycled is burned and heat transferred through a heat exchanger (HX) to the compressed air from a gas turbine. The heated compressed air is then heated further in the gas turbine burner and expands through the turbine generating 15% of the power. Half the exhaust from the turbine provides air for the anode exhaust burner. All of the turbine exhaust eventually flows through the fuel cell cathodes providing the O2 and CO2 needed in the electrochemical reaction. Exhaust from the cathodes flows to a steam system (heat recovery steam generator, staged steam turbine generating 15% of the cycle power). Simulation of a 200 MW plant with a hybrid power cycle had an LHV efficiency of 72.6%. Power output and efficiency are insensitive to ambient temperature, compared to a gas turbine combined cycle; NOx emissions are 75% lower. Estimated cost of electricity for 200 MW is 46 mills/kWh, which is competitive with combined cycle where fuel cost is > $5.8/MMBTU. Key requirement is HX; in the 200 MW plant studies, a HX operating at 1094 C using high temperature HX technology currently under development by METC for coal gassifiers was assumed. A study of a near term (20 MW) high efficiency direct carbonate fuel cell/turbine hybrid power cycle has also been completed.

Steinfeld, G.; Maru, H.C. [Energy Research Corp., Danbury, CT (United States); Sanderson, R.A. [Sanderson (Robert) and Associates, Wethersfield, CT (United States)

1996-07-01T23:59:59.000Z

90

HIGH EFFICIENCY GENERATION OF HYDROGEN FUELS USING NUCLEAR POWER  

SciTech Connect

OAK B202 HIGH EFFICIENCY GENERATION OF HYDROGEN FUELS USING NUCLEAR POWER. Combustion of fossil fuels, used to power transportation, generate electricity, heat homes and fuel industry provides 86% of the world's energy. Drawbacks to fossil fuel utilization include limited supply, pollution, and carbon dioxide emissions. Carbon dioxide emissions, thought to be responsible for global warming, are now the subject of international treaties. Together, these drawbacks argue for the replacement of fossil fuels with a less-polluting potentially renewable primary energy such as nuclear energy. Conventional nuclear plants readily generate electric power but fossil fuels are firmly entrenched in the transportation sector. Hydrogen is an environmentally attractive transportation fuel that has the potential to displace fossil fuels. Hydrogen will be particularly advantageous when coupled with fuel cells. Fuel cells have higher efficiency than conventional battery/internal combustion engine combinations and do not produce nitrogen oxides during low-temperature operation. Contemporary hydrogen production is primarily based on fossil fuels and most specifically on natural gas. When hydrogen is produced using energy derived from fossil fuels, there is little or no environmental advantage. There is currently no large scale, cost-effective, environmentally attractive hydrogen production process available for commercialization, nor has such a process been identified. The objective of this work is to find an economically feasible process for the production of hydrogen, by nuclear means, using an advanced high-temperature nuclear reactor as the primary energy source. Hydrogen production by thermochemical water-splitting (Appendix A), a chemical process that accomplishes the decomposition of water into hydrogen and oxygen using only heat or, in the case of a hybrid thermochemical process, by a combination of heat and electrolysis, could meet these goals. Hydrogen produced from fossil fuels has trace contaminants (primarily carbon monoxide) that are detrimental to precious metal catalyzed fuel cells, as is now recognized by many of the world's largest automobile companies. Thermochemical hydrogen will not contain carbon monoxide as an impurity at any level. Electrolysis, the alternative process for producing hydrogen using nuclear energy, suffers from thermodynamic inefficiencies in both the production of electricity and in electrolytic parts of the process. The efficiency of electrolysis (electricity to hydrogen) is currently about 80%. Electric power generation efficiency would have to exceed 65% (thermal to electrical) for the combined efficiency to exceed the 52% (thermal to hydrogen) calculated for one thermochemical cycle. Thermochemical water-splitting cycles have been studied, at various levels of effort, for the past 35 years. They were extensively studied in the late 70s and early 80s but have received little attention in the past 10 years, particularly in the U.S. While there is no question about the technical feasibility and the potential for high efficiency, cycles with proven low cost and high efficiency have yet to be developed commercially. Over 100 cycles have been proposed, but substantial research has been executed on only a few. This report describes work accomplished during a three-year project whose objective is to ''define an economically feasible concept for production of hydrogen, by nuclear means, using an advanced high temperature nuclear reactor as the energy source.'' The emphasis of the first phase was to evaluate thermochemical processes which offer the potential for efficient, cost-effective, large-scale production of hydrogen from water in which the primary energy input is high temperature heat from an advanced nuclear reactor and to select one (or, at most three) for further detailed consideration. During Phase 1, an exhaustive literature search was performed to locate all cycles previously proposed. The cycles located were screened using objective criteria to determine which could

BROWN,LC; BESENBRUCH,GE; LENTSCH,RD; SCHULTZ,KR; FUNK,JF; PICKARD,PS; MARSHALL,AC; SHOWALTER,SK

2003-06-01T23:59:59.000Z

91

HIGH EFFICIENCY GENERATION OF HYDROGEN FUELS USING NUCLEAR POWER  

DOE Green Energy (OSTI)

OAK B202 HIGH EFFICIENCY GENERATION OF HYDROGEN FUELS USING NUCLEAR POWER. Combustion of fossil fuels, used to power transportation, generate electricity, heat homes and fuel industry provides 86% of the world's energy. Drawbacks to fossil fuel utilization include limited supply, pollution, and carbon dioxide emissions. Carbon dioxide emissions, thought to be responsible for global warming, are now the subject of international treaties. Together, these drawbacks argue for the replacement of fossil fuels with a less-polluting potentially renewable primary energy such as nuclear energy. Conventional nuclear plants readily generate electric power but fossil fuels are firmly entrenched in the transportation sector. Hydrogen is an environmentally attractive transportation fuel that has the potential to displace fossil fuels. Hydrogen will be particularly advantageous when coupled with fuel cells. Fuel cells have higher efficiency than conventional battery/internal combustion engine combinations and do not produce nitrogen oxides during low-temperature operation. Contemporary hydrogen production is primarily based on fossil fuels and most specifically on natural gas. When hydrogen is produced using energy derived from fossil fuels, there is little or no environmental advantage. There is currently no large scale, cost-effective, environmentally attractive hydrogen production process available for commercialization, nor has such a process been identified. The objective of this work is to find an economically feasible process for the production of hydrogen, by nuclear means, using an advanced high-temperature nuclear reactor as the primary energy source. Hydrogen production by thermochemical water-splitting (Appendix A), a chemical process that accomplishes the decomposition of water into hydrogen and oxygen using only heat or, in the case of a hybrid thermochemical process, by a combination of heat and electrolysis, could meet these goals. Hydrogen produced from fossil fuels has trace contaminants (primarily carbon monoxide) that are detrimental to precious metal catalyzed fuel cells, as is now recognized by many of the world's largest automobile companies. Thermochemical hydrogen will not contain carbon monoxide as an impurity at any level. Electrolysis, the alternative process for producing hydrogen using nuclear energy, suffers from thermodynamic inefficiencies in both the production of electricity and in electrolytic parts of the process. The efficiency of electrolysis (electricity to hydrogen) is currently about 80%. Electric power generation efficiency would have to exceed 65% (thermal to electrical) for the combined efficiency to exceed the 52% (thermal to hydrogen) calculated for one thermochemical cycle. Thermochemical water-splitting cycles have been studied, at various levels of effort, for the past 35 years. They were extensively studied in the late 70s and early 80s but have received little attention in the past 10 years, particularly in the U.S. While there is no question about the technical feasibility and the potential for high efficiency, cycles with proven low cost and high efficiency have yet to be developed commercially. Over 100 cycles have been proposed, but substantial research has been executed on only a few. This report describes work accomplished during a three-year project whose objective is to ''define an economically feasible concept for production of hydrogen, by nuclear means, using an advanced high temperature nuclear reactor as the energy source.'' The emphasis of the first phase was to evaluate thermochemical processes which offer the potential for efficient, cost-effective, large-scale production of hydrogen from water in which the primary energy input is high temperature heat from an advanced nuclear reactor and to select one (or, at most three) for further detailed consideration. During Phase 1, an exhaustive literature search was performed to locate all cycles previously proposed. The cycles located were screened using objective criteria to determine which could benefit, in terms of efficien

BROWN,LC; BESENBRUCH,GE; LENTSCH,RD; SCHULTZ,KR; FUNK,JF; PICKARD,PS; MARSHALL,AC; SHOWALTER,SK

2003-06-01T23:59:59.000Z

92

High-pressure coal fuel processor development. Final report  

DOE Green Energy (OSTI)

Caterpillar shares DOE/METC interest in demonstrating the technology required to displace petroleum-based engine fuels with various forms of low cost coal. Current DOE/METC programs on mild gasification and coal-water-slurries are addressing two approaches to this end. Engine and fuel processor system concept studies by Caterpillar have identified a third, potentially promising, option. This option includes high-pressure fuel processing of run-of-the-mine coal and direct injection of the resulting low-Btu gas stream into an ignition assisted, high compression ratio diesel engine. The compactness and predicted efficiency of the system make it suitable for application to line-haul railroad locomotives. Two overall conclusions resulted from Task 1. First direct injected, ignition assisted Diesel cycle engine combustion systems can be suitably modified to efficiently utilize low-Btu gas fuels. Second, high pressure gasification of selected run-of-the-mine coals in batch-loaded fuel processors is feasible. These two findings, taken together, significantly reduce the perceived technical risk associated with the further development of the proposed coal gas fueled Diesel cycle power plant concept. The significant conclusions from Task 2 were: An engine concept, derived from a Caterpillar 3600 series engine, and a fuel processor concept, based on scaling up a removable-canister configuration from the test rig, appear feasible; and although the results of this concept study are encouraging, further, full-scale component research and development are required before attempting a full-scale integrated system demonstration effort.

Greenhalgh, M.L. [Caterpillar, Inc., Peoria, IL (United States)

1992-12-01T23:59:59.000Z

93

High Temperature BOP and Fuel Processing  

NLE Websites -- All DOE Office Websites (Extended Search)

D D e e p p a a r r t t m m e e n n t t o o f f E E n n e e r r g g y y F F u u e e l l l l l l n n g g C C e e M M a a n n u u f f a a c c t t u u r r i i R R & & D D W W o o r r k k s s h h o o p p H H i i g g h h T T e e m m p p e e r r a a t t u u r r e e B B O O P P a a n n d d F F u u e e l l i i n n g g P P r r o o c c e e s s s s A A u u g g u u s s t t 1 1 1 1 - - 1 1 2 2 , , 2 2 0 0 1 1 1 1 A A g g e e n n d d a a Acumentrics Overview & Approach Fuel Preparation Reforming Heat Recovery Gas Utilities Power Conversion & Controls Conclusion A A c c u u m m e e n n t t r r i i c c s s C C o o r r p p o o r r a a t t i i o o n n Strategic Partners * ~ 95 Employees * Manufacturing since 1994 *Based in Westwood, Mass. *~40,000 sq. ft facility * Critical disciplines in-house Electrical Engineering Mechanical Engineering Chemical Engineering Thermal Modeling Ceramics Processing Manufacturing Sales & Marketing Automation Finance A A c c u u m m e e n n t t r r i i c c s s B B a a t t t t e e r r y y - - b b a a s s e e d d U U P P S S Uninterruptible

94

Long-term management of high-level radioactive waste (HLW) and spent nuclear fuel (SNF)  

Energy.gov (U.S. Department of Energy (DOE))

GC-52 provides legal advice to DOE regarding the long-term management of high-level radioactive waste (HLW) and spent nuclear fuel (SNF). SNF is nuclear fuel that has been used as fuel in a reactor...

95

High-efficiency cell structures and processes applied to photovoltaic-grade Czochralski silicon  

DOE Green Energy (OSTI)

The authors performed a detailed study to examine the limiting performance available using photovoltaic-grade Cz silicon. Photovoltaic-grade silicon refers to silicon produced by the photovoltaic industry, which may differ from the silicon used in the semiconductor device industry in impurity and defect concentrations.The study included optimization of fabrication processes, development of advanced device structures, and detailed model calculations to project future performance improvements. Process and device optimization resulted in demonstration of 75-{micro}s bulk lifetimes and 17.6%-efficient large-area cells using photovoltaic-grade Cz silicon. Detailed calculations based on the material and device evaluation of the present work project efficiencies of 20% for photovoltaic-grade Cz silicon with properly optimized processing and device structures.

Gee, J.M. [Sandia National Labs., Albuquerque, NM (United States). Photovoltaic System Components Dept.; King, R.R.; Mitchell, K.W. [Siemens Solar Industries, Camarillo, CA (United States)

1996-12-01T23:59:59.000Z

96

Strategies for denaturing the weapons-grade plutonium stockpile  

SciTech Connect

In the next few years, approximately 50 metric tons of weapons-grade plutonium and 150 metric tons of highly-enriched uranium (HEU) may be removed from nuclear weapons in the US and declared excess. These materials represent a significant energy resource that could substantially contribute to our national energy requirements. HEU can be used as fuel in naval reactors, or diluted with depleted uranium for use as fuel in commercial reactors. This paper proposes to use the weapons-grade plutonium as fuel in light water reactors. The first such reactor would demonstrate the dual objectives of producing electrical power and denaturing the plutonium to prevent use in nuclear weapons.

Buckner, M.R.; Parks, P.B.

1992-10-01T23:59:59.000Z

97

A high converter concept for fuel management with blanket fuel assemblies in boiling water reactors  

SciTech Connect

Studies on the natural Uranium saving and waste reduction potential of a multiple-plant BWR system were performed. The BWR High Converter system should enable a multiple recycling of MOX fuel in current BWR plants by introducing blanket fuel assemblies and burning Uranium and MOX fuel separately. The feasibility of Uranium cores with blankets and full-MOX cores with Plutonium qualities as low as 40% were studied. The power concentration due to blanket insertion is manageable with modern fuel and acceptable values for the thermal limits and reactivity coefficients were obtained. While challenges remain, full-MOX cores also complied with the main design criteria. The combination of Uranium and Plutonium burners in appropriate proportions could enable obtaining as much as 40% more energy out of Uranium ore. Moreover, a proper adjustment of blanket average stay and Plutonium qualities could lead to a system with nearly no Plutonium left for final disposal. The achievement of such goals with current light water technology makes the BWR HC concept an attractive option to improve the fuel cycle until Gen-IV designs are mature. (authors)

Martinez-Frances, N.; Timm, W.; Rossbach, D. [AREVA, AREVA NP, Erlangen (Germany)

2012-07-01T23:59:59.000Z

98

Adaptable Sensor Packaging for High Temperature Fossil Fuel Energy System  

NLE Websites -- All DOE Office Websites (Extended Search)

Adaptable Sensor Packaging for High Adaptable Sensor Packaging for High Temperature Fossil Fuel Energy Systems Background The Advanced Research Sensors and Controls Program is leading the effort to develop sensing and control technologies and methods to achieve automated and optimized intelligent power systems. The program is led by the U.S. Department of Energy (DOE) Office of Fossil Energy National Energy Technology Laboratory (NETL) and is implemented through research and development agreements with other

99

Economic incentives and recommended development for commercial use of high burnup fuels in the once-through LWR fuel cycle  

Science Conference Proceedings (OSTI)

This study calculates the reduced uranium requirements and the economic incentives for increasing the burnup of current design LWR fuels from the current range of 25 to 35 MWD/Kg to a range of 45 to 55 MWD/Kg. The changes in fuel management strategies which may be required to accommodate these high burnup fuels and longer fuel cycles are discussed. The material behavior problems which may present obstacles to achieving high burnup or to license fuel are identified and discussed. These problems are presented in terms of integral fuel response and the informational needs for commercial and licensing acceptance. Research and development programs are outlined which are aimed at achieving a licensing position and commercial acceptance of high burnup fuels.

Stout, R.B.; Merckx, K.R.; Holm, J.S.

1981-01-01T23:59:59.000Z

100

Improved Survival With Radiation Therapy in High-Grade Soft Tissue Sarcomas of the Extremities: A SEER Analysis  

Science Conference Proceedings (OSTI)

Purpose: The benefit of radiation therapy in extremity soft tissue sarcomas remains controversial. The purpose of this study was to determine the effect of radiation therapy on overall survival among patients with primary soft tissue sarcomas of the extremity who underwent limb-sparing surgery. Methods and Materials: A retrospective study from the Surveillance, Epidemiology, and End Results (SEER) database that included data from January 1, 1988, to December 31, 2005. A total of 6,960 patients constituted the study population. Overall survival curves were constructed using the Kaplan-Meir method and for patients with low- and high-grade tumors. Hazard ratios were calculated based on multivariable Cox proportional hazards models. Results: Of the cohort, 47% received radiation therapy. There was no significant difference in overall survival among patients with low-grade tumors by radiation therapy. In high-grade tumors, the 3-year overall survival was 73% in patients who received radiation therapy vs. 63% for those who did not receive radiation therapy (p < 0.001). On multivariate analysis, patients with high-grade tumors who received radiation therapy had an improved overall survival (hazard ratio 0.67, 95% confidence interval 0.57-0.79). In patients receiving radiation therapy, 13.5% received it in a neoadjuvant setting. The incidence of patients receiving neoadjuvant radiation did not change significantly between 1988 and 2005. Conclusions: To our knowledge, this is the largest population-based study reported in patients undergoing limb-sparing surgery for soft tissue sarcomas of the extremities. It reports that radiation was associated with improved survival in patients with high-grade tumors.

Koshy, Matthew, E-mail: mkoshy@umm.ed [Department of Radiation Oncology, University of Maryland School of Medicine, Baltimore, MD (United States); Rich, Shayna E. [Department of Epidemiology and Preventive Medicine, University of Maryland School of Medicine, Baltimore, MD (United States); Mohiuddin, Majid M. [Department of Radiation Oncology, University of Maryland School of Medicine, Baltimore, MD (United States)

2010-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "high grade fuel" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


101

Issues in the use of Weapons-Grade MOX Fuel in VVER-1000 Nuclear Reactors: Comparison of UO2 and MOX Fuels  

Science Conference Proceedings (OSTI)

The purpose of this report is to quantify the differences between mixed oxide (MOX) and low-enriched uranium (LEU) fuels and to assess in reasonable detail the potential impacts of MOX fuel use in VVER-1000 nuclear power plants in Russia. This report is a generic tool to assist in the identification of plant modifications that may be required to accommodate receiving, storing, handling, irradiating, and disposing of MOX fuel in VVER-1000 reactors. The report is based on information from work performed by Russian and U.S. institutions. The report quantifies each issue, and the differences between LEU and MOX fuels are described as accurately as possible, given the current sources of data.

Carbajo, J.J.

2005-05-27T23:59:59.000Z

102

Fuel Cell/Turbine Ultra High Efficiency Power System  

DOE Green Energy (OSTI)

FuelCell Energy, INC. (FCE) is currently involved in the design of ultra high efficiency power plants under a cooperative agreement (DE-FC26-00NT40) managed by the National Energy Technology Laboratory (NETL) as part of the DOE's Vision 21 program. Under this project, FCE is developing a fuel cell/turbine hybrid system that integrates the atmospheric pressure Direct FuelCell{reg_sign} (DFC{reg_sign}) with an unfired Brayton cycle utilizing indirect heat recovery from the power plant. Features of the DFC/T{trademark} system include: high efficiency, minimal emissions, simplicity in design, direct reforming internal to the fuel cell, no pressurization of the fuel cell, independent operating pressure of the fuel cell and turbine, and potential cost competitiveness with existing combined cycle power plants at much smaller sizes. Objectives of the Vision 21 Program include developing power plants that will generate electricity with net efficiencies approaching 75 percent (with natural gas), while producing sulfur and nitrogen oxide emissions of less than 0.01 lb/million BTU. These goals are significant improvements over conventional power plants, which are 35-60 percent efficient and produce emissions of 0.07 to 0.3 lb/million BTU of sulfur and nitrogen oxides. The nitrogen oxide and sulfur emissions from the DFC/T system are anticipated to be better than the Vision 21 goals due to the non-combustion features of the DFC/T power plant. The expected high efficiency of the DFC/T will also result in a 40-50 percent reduction in carbon dioxide emissions compared to conventional power plants. To date, the R&D efforts have resulted in significant progress including proof-of-concept tests of a sub-scale power plant built around a state-of-the-art DFC stack integrated with a modified Capstone Model 330 Microturbine. The objectives of this effort are to investigate the integration aspects of the fuel cell and turbine and to obtain design information and operational data that will be utilized in the design of a 40-MW high efficiency Vision 21 power plant. Additionally, these tests are providing the valuable insight for DFC/Turbine power plant potential for load following, increased reliability, and enhanced operability.

Hossein, Ghezel-Ayagh

2001-11-06T23:59:59.000Z

103

Materials for High-Pressure Fuel Injection Systems  

DOE Green Energy (OSTI)

The high-level goal of this multi-year effort was to facilitate the Advanced Combustion Engine goal of 20% improvement (compared to 2009 baseline) of commercial engine efficiency by 2015. A sub-goal is to increase the reliability of diesel fuel injectors by investigating modelbased scenarios that cannot be achieved by empirical, trial and error methodologies alone. During this three-year project, ORNL developed the methodology to evaluate origins and to record the initiation and propagation of fatigue cracks emanating from holes that were electrodischarge machined (EDM), the method used to form spray holes in fuel injector tips. Both x-ray and neutron-based methods for measuring residual stress at four different research facilities were evaluated to determine which, if any, was most applicable to the fuel injector tip geometry. Owing to the shape and small volumes of material involved in the sack area, residual stress data could only be obtained in the walls of the nozzle a few millimeters back from the tip, and there was a hint of only a small compressive stress. This result was consistent with prior studies by Caterpillar. Residual stress studies were suspended after the second year, reserving the possibility of pursuing this in the future, if and when methodology suitable for injector sacks becomes available. The smooth specimen fatigue behavior of current fuel injector steel materials was evaluated and displayed a dual mode initiation behavior. At high stresses, cracks started at machining flaws in the surface; however, below a critical threshold stress of approximately 800 MPa, cracks initiated in the bulk microstructure, below the surface. This suggests that for the next generation for high-pressure fuel injector nozzles, it becomes increasingly important to control the machining and finishing processes, especially if the stress in the tip approaches or exceeds that threshold level. Fatigue tests were also conducted using EDM notches in the gage sections. Compared to the smooth specimens, EDM notching led to a severe reduction in total fatigue life. A reduction in fatigue life of nearly four orders of magnitude can occur at an EDM notch the approximate size of fuel injector spray holes. Consequently, the initiation and propagation behavior of cracks from small spray holes is relevant for generation of design quality data for the next generation diesel fuel injection devices. This is especially true since the current design methodologies usually rely on the less conservative smooth specimen fatigue testing results, and since different materials can have varying levels of notch fatigue resistance.

Blau, P.; Shyam, A.; Hubbard, C.; Howe, J.; Trejo, R.; Yang, N. (Caterpillar, Inc. Technical Center); Pollard, M. (Caterpillar, Inc. Technical Center)

2011-09-30T23:59:59.000Z

104

Breakout Group 5: Solid Oxide Fuel Cells  

NLE Websites -- All DOE Office Websites (Extended Search)

than 50 kW; do not restrict fuel choice o Combined heat and power applications maximize SOFC benefit of high grade waste heat o Critical and remote power are good early market...

105

Safeguards Guidance for Prismatic Fueled High Temperature Gas Reactors (HTGR)  

National Nuclear Security Administration (NNSA)

5) 5) August 2012 Guidance for High Temperature Gas Reactors (HTGRs) with Prismatic Fuel INL/CON-12-26130 Revision 0 Safeguards-by-Design: Guidance for High Temperature Gas Reactors (HTGRs) With Prismatic Fuel Philip Casey Durst (INL Consultant) August 2012 DISCLAIMER This information was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness, of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. References herein to any specific commercial product,

106

Isotope correlation studies relative to high enrichment test reactor fuels  

SciTech Connect

Several correlations of fission product isotopic ratios with atom percent fission and neutron flux, for highly enriched /sup 235/U fuel irradiated in two different water moderated thermal reactors, have been evaluated. In general, excellent correlations were indicated for samples irradiated in the same neutron spectrum; however, significant differences in the correlations were noted with the change in neutron spectrum. For highly enriched /sup 235/U fuel, the correlation of the isotopic ratio /sup 143/Nd//sup 145 +146/Nd with atom percent fission has wider applicability than the other fission product isotopic ratio evaluated. The /sup 137/Cs//sup 135/Cs atom ratio shows promise for correlation with neutron flux. Correlations involving heavy element ratios are very sensitive to the neutron spectrum.

Maeck, W.J.; Tromp, R.L.; Duce, F.A.; Emel, W.A.

1978-06-01T23:59:59.000Z

107

Modular, High-Volume Fuel Cell Leak-Test Suite and Process  

DOE Green Energy (OSTI)

Fuel cell stacks are typically hand-assembled and tested. As a result the manufacturing process is labor-intensive and time-consuming. The fluid leakage in fuel cell stacks may reduce fuel cell performance, damage fuel cell stack, or even cause fire and become a safety hazard. Leak check is a critical step in the fuel cell stack manufacturing. The fuel cell industry is in need of fuel cell leak-test processes and equipment that is automatic, robust, and high throughput. The equipment should reduce fuel cell manufacturing cost.

Ru Chen; Ian Kaye

2012-03-12T23:59:59.000Z

108

Locations of Spent Nuclear Fuel and High-Level Radioactive Waste  

Energy.gov (U.S. Department of Energy (DOE))

Map of the United States of America showing the locations of spent nuclear fuel and high-level radioactive waste.

109

The design of high power density annular fuel for LWRs  

E-Print Network (OSTI)

Fuel performance models have been developed to assess the performance of internally and externally cooled LWR annular fuel. Such fuel may be operated at 30-50% higher core power density than the current operating LWRs, and ...

Yuan, Yi, 1975-

2004-01-01T23:59:59.000Z

110

Production of high density fuel through low temperature devolatilization of fossil fuels with hydrogen and iron oxides  

DOE Patents (OSTI)

A method is provided for producing high-energy high-density fuels and valuable co-products from fossil fuel sources which comprises the low temperature devolatilization of a fossil fuel such as coal in a moving fluid-bed reactor at a temperature of about 450-650C in the presence of hydrogen and iron oxides. The method is advantageous in that high quality liquid fuels are obtained in addition to valuable co-products such as elemental iron, elemental sulfur and carbon black, and the process is carried out efficiently with a large number of recyclable steps. In addition, the hydropyrolysis of the present invention can produce a highly reactive low-sulfur char which is convertible into a slurry fuel. 1 fig.

Khan, M.R.

1990-01-29T23:59:59.000Z

111

Fuel Cell Technologies Office: DOE Hydrogen Delivery High-Pressure...  

NLE Websites -- All DOE Office Websites (Extended Search)

Energy Efficiency and Renewable Energy EERE Home | Programs & Offices | Consumer Information Fuel Cell Technologies Office Search Search Help Fuel Cell Technologies Office HOME...

112

MEMS Fuel Cells – Low Temp – High Power Density  

The miniature fuel-cell technology uses thin-film fuel ... Reduced life cycle cost in comparison to ... for the Department of Energy's National Nuclear Security ...

113

Fuel Cell Technologies Office: High Temperature Membrane Working...  

NLE Websites -- All DOE Office Websites (Extended Search)

Polymer electrolyte membrane (PEM) fuel cells typically operate at temperatures no higher than 60C-80C due to structural limitations of the membrane. Operating PEM fuel...

114

Upgrading of biorenewables to high energy density fuels  

DOE Green Energy (OSTI)

According to a recent report, lignocellulose is the most abundant renewable biological resource on earth, with an annual production of {approx} 200 x 10{sup 9} tons. Conversion of lignocellulosics derived from wood, agricultural wastes, and woody grasses into liquid fuels and value-added chemical feedstocks is an active area of research that has seen an explosion of effort due to the need to replace petroleum based sources. The carbohydrates D-glucose (C{sub 6}), L-arabinose (C{sub 5}), and D-xylose (C{sub 5}) are readily obtained from the hydrolysis of lignocellulose and constitute the most abundant renewable organic carbon source on the planet. Because they are naturally produced on such a large scale, these sugars have the greatest potential to displace petrochemical derived transportation fuel. Recent efforts in our laboratories aimed towards the production of high energy density transportation fuels from carbohydrates have been structured around the parameters of selective carbohydrate carbon chain extension chemistries, low reaction temperatures, and the desired use of water or neat substrate as the solvent. Some of our efforts in this regard will be presented.

Gordon, John C [Los Alamos National Laboratory; Batista, Enrique R [Los Alamos National Laboratory; Chen, Weizhong [Los Alamos National Laboratory; Currier, Robert P [Los Alamos National Laboratory; Dirmyer, Matthew R [Los Alamos National Laboratory; John, Kevin D [Los Alamos National Laboratory; Kim, Jin K [Los Alamos National Laboratory; Keith, Jason [Los Alamos National Laboratory; Martin, Richard L [Los Alamos National Laboratory; Pierpont, Aaron W [Los Alamos National Laboratory; Silks Ill, L. A. "" Pete [Los Alamos National Laboratory; Smythe, Mathan C [Los Alamos National Laboratory; Sutton, Andrew D [Los Alamos National Laboratory; Taw, Felicia L [Los Alamos National Laboratory; Trovitch, Ryan J [Los Alamos National Laboratory; Vasudevan, Kalyan V [Los Alamos National Laboratory; Waidmann, Christopher R [Los Alamos National Laboratory; Wu, Ruilian [Los Alamos National Laboratory; Baker, R. Thomas [UNIV OF OTTAWWA; Schlaf, Marcel [UNIV OF GUELPH

2010-12-07T23:59:59.000Z

115

High Energy Absorption Top Nozzle For A Nuclaer Fuel Assembly  

DOE Patents (OSTI)

A high energy absorption top nozzle for a nuclear fuel assembly that employs an elongated upper tubular housing and an elongated lower tubular housing slidable within the upper tubular housing. The upper and lower housings are biased away from each other by a plurality of longitudinally extending springs that are restrained by a longitudinally moveable piston whose upward travel is limited within the upper housing. The energy imparted to the nozzle by a control rod scram is mostly absorbed by the springs and the hydraulic affect of the piston within the nozzle.

Sparrow, James A. (Irmo, SC); Aleshin, Yuriy (Columbia, SC); Slyeptsov, Aleksey (Columbia, SC)

2004-05-18T23:59:59.000Z

116

Update on US High Density Fuel Fabrication Development  

SciTech Connect

Second generation uranium molybdenum fuel has shown excellent in-reactor irradiation performance. This metallic fuel type is capable of being fabricated at much higher loadings than any presently used research reactor fuel. Due to the broad range of fuel types this alloy system encompasses—fuel powder to monolithic foil and binary fuel systems to multiple element additions—significant amounts of research and development have been conducted on the fabrication of these fuels. This paper presents an update of the US RERTR effort to develop fabrication techniques and the fabrication methods used for the RERTR-9A miniplate test.

C.R. Clark; G.A. Moore; J.F. Jue; B.H. Park; N.P. Hallinan; D.M. Wachs; D.E. Burkes

2007-03-01T23:59:59.000Z

117

Bio-Fuel Production Assisted with High Temperature Steam Electrolysis  

SciTech Connect

Two hybrid energy processes that enable production of synthetic liquid fuels that are compatible with the existing conventional liquid transportation fuels infrastructure are presented. Using biomass as a renewable carbon source, and supplemental hydrogen from high-temperature steam electrolysis (HTSE), these two hybrid energy processes have the potential to provide a significant alternative petroleum source that could reduce dependence on imported oil. The first process discusses a hydropyrolysis unit with hydrogen addition from HTSE. Non-food biomass is pyrolyzed and converted to pyrolysis oil. The pyrolysis oil is upgraded with hydrogen addition from HTSE. This addition of hydrogen deoxygenates the pyrolysis oil and increases the pH to a tolerable level for transportation. The final product is synthetic crude that could then be transported to a refinery and input into the already used transportation fuel infrastructure. The second process discusses a process named Bio-Syntrolysis. The Bio-Syntrolysis process combines hydrogen from HTSE with CO from an oxygen-blown biomass gasifier that yields syngas to be used as a feedstock for synthesis of liquid synthetic crude. Conversion of syngas to liquid synthetic crude, using a biomass-based carbon source, expands the application of renewable energy beyond the grid to include transportation fuels. It can also contribute to grid stability associated with non-dispatchable power generation. The use of supplemental hydrogen from HTSE enables greater than 90% utilization of the biomass carbon content which is about 2.5 times higher than carbon utilization associated with traditional cellulosic ethanol production. If the electrical power source needed for HTSE is based on nuclear or renewable energy, the process is carbon neutral. INL has demonstrated improved biomass processing prior to gasification. Recyclable biomass in the form of crop residue or energy crops would serve as the feedstock for this process. A process model of syngas production using high temperature electrolysis and biomass gasification is presented. Process heat from the biomass gasifier is used to heat steam for the hydrogen production via the high temperature steam electrolysis process. Oxygen produced form the electrolysis process is used to control the oxidation rate in the oxygen-blown biomass gasifier.

Grant Hawkes; James O'Brien; Michael McKellar

2012-06-01T23:59:59.000Z

118

An integrated performance model for high temperature gas cooled reactor coated particle fuel  

E-Print Network (OSTI)

The performance of coated fuel particles is essential for the development and deployment of High Temperature Gas Reactor (HTGR) systems for future power generation. Fuel performance modeling is indispensable for understanding ...

Wang, Jing, 1976-

2004-01-01T23:59:59.000Z

119

NEUTRONIC AND THERMAL HYDRAULIC DESIGNS OF ANNULAR FUEL FOR HIGH POWER DENSITY BWRS  

E-Print Network (OSTI)

As a promising new fuel for high power density light water reactors, the feasibility of using annular fuel for BWR services is explored from both thermal hydraulic and neutronic points of view. Keeping the bundle size ...

Morra, P.

120

Mechanism of oxygen reduction reaction on transition metal oxide catalysts for high temperature fuel cells  

E-Print Network (OSTI)

The solid oxide fuel cell (SOFC) with its high energy conversion efficiency, low emissions, silent operation and its ability to utilize commercial fuels has the potential to create a large impact on the energy landscape. ...

La O', Gerardo Jose Cordova

2008-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "high grade fuel" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


121

Spent fuel and high-level radioactive waste transportation report  

SciTech Connect

This publication is intended to provide its readers with an introduction to the issues surrounding the subject of transportation of spent nuclear fuel and high-level radioactive waste, especially as those issues impact the southern region of the United States. It was originally issued by the Southern States Energy Board (SSEB) in July 1987 as the Spent Nuclear Fuel and High-Level Radioactive Waste Transportation Primer, a document patterned on work performed by the Western Interstate Energy Board and designed as a ``comprehensive overview of the issues.`` This work differs from that earlier effort in that it is designed for the educated layman with little or no background in nuclear waste issues. In addition, this document is not a comprehensive examination of nuclear waste issues but should instead serve as a general introduction to the subject. Owing to changes in the nuclear waste management system, program activities by the US Department of Energy and other federal agencies and developing technologies, much of this information is dated quickly. While this report uses the most recent data available, readers should keep in mind that some of the material is subject to rapid change. SSEB plans periodic updates in the future to account for changes in the program. Replacement pages sew be supplied to all parties in receipt of this publication provided they remain on the SSEB mailing list.

1989-11-01T23:59:59.000Z

122

Spent fuel and high-level radioactive waste transportation report  

SciTech Connect

This publication is intended to provide its readers with an introduction to the issues surrounding the subject of transportation of spent nuclear fuel and high-level radioactive waste, especially as those issues impact the southern region of the United States. It was originally issued by the Southern States Energy Board (SSEB) in July 1987 as the Spent Nuclear Fuel and High-Level Radioactive Waste Transportation Primer, a document patterned on work performed by the Western Interstate Energy Board and designed as a ``comprehensive overview of the issues.`` This work differs from that earlier effort in that it is designed for the educated layman with little or no background in nuclear waste issues. In addition, this document is not a comprehensive examination of nuclear waste issues but should instead serve as a general introduction to the subject. Owing to changes in the nuclear waste management system, program activities by the US Department of Energy and other federal agencies and developing technologies, much of this information is dated quickly. While this report uses the most recent data available, readers should keep in mind that some of the material is subject to rapid change. SSEB plans periodic updates in the future to account for changes in the program. Replacement pages will be supplied to all parties in receipt of this publication provided they remain on the SSEB mailing list.

1990-11-01T23:59:59.000Z

123

Spent Fuel and High-Level Radioactive Waste Transportation Report  

SciTech Connect

This publication is intended to provide its readers with an introduction to the issues surrounding the subject of transportation of spent nuclear fuel and high-level radioactive waste, especially as those issues impact the southern region of the United States. It was originally issued by SSEB in July 1987 as the Spent Nuclear Fuel and High-Level Radioactive Waste Transportation Primer, a document patterned on work performed by the Western Interstate Energy Board and designed as a ``comprehensive overview of the issues.`` This work differs from that earlier effort in that it is designed for the educated layman with little or no background in nuclear waste Issues. In addition. this document is not a comprehensive examination of nuclear waste issues but should instead serve as a general introduction to the subject. Owing to changes in the nuclear waste management system, program activities by the US Department of Energy and other federal agencies and developing technologies, much of this information is dated quickly. While this report uses the most recent data available, readers should keep in mind that some of the material is subject to rapid change. SSEB plans periodic updates in the future to account for changes in the program. Replacement pages will be supplied to all parties in receipt of this publication provided they remain on the SSEB mailing list.

1992-03-01T23:59:59.000Z

124

High Surface Area Molybdenum Nitride Support for Fuel Cell Electrodes  

SciTech Connect

Alternative supports for polymer electrolyte membrane fuel cells were synthesized and catalytic activity was explored using electrochemical analysis. High surface area, molybdenum nitride supports were synthesized by rapidly heating a gel of polyethyleneimine bound molybdenum in a tube furnace under a forming gas atmosphere. Subsequent disposition of platinum through an incipient wetness approach lead to dispersed crystallites of platinum on the conductive support. All the ceramic materials were characterized with XRD, SEM, TEM and electrochemical analysis. The supports without platinum are highly stable to acidic aqueous conditions and show no signs of oxygen reduction reactivity (ORR). However, once the 20 wt % platinum is added to the material, ORR activity comparable to XC72 based materials is observed.

Blackmore, Karen [Los Alamos National Laboratory (LANL); Elbaz, L [Los Alamos National Laboratory (LANL); Bauer, E D [Los Alamos National Laboratory (LANL); Brosha, Eric [Los Alamos National Laboratory (LANL); More, Karren Leslie [ORNL; Mccleskey, T [Los Alamos National Laboratory (LANL); Burrell, A [Los Alamos National Laboratory (LANL)

2011-01-01T23:59:59.000Z

125

Alternative Fuel School Buses Earn High Marks: Reprint from Alternative Fuel News, Vol. 5, No. 3  

DOE Green Energy (OSTI)

A two-page article on school buses that run on alternative fuels including biodiesel and compressed natural gas. Reprinted from Alternative Fuel News, published by the Clean Cities Program of DOE.

Not Available

2002-11-01T23:59:59.000Z

126

The Complete Burning of Weapons Grade Plutonium and Highly Enriched Uranium with (Laser Inertial Fusion-Fission Energy) LIFE Engine  

Science Conference Proceedings (OSTI)

The National Ignition Facility (NIF) project, a laser-based Inertial Confinement Fusion (ICF) experiment designed to achieve thermonuclear fusion ignition and burn in the laboratory, is under construction at the Lawrence Livermore National Laboratory (LLNL) and will be completed in April of 2009. Experiments designed to accomplish the NIF's goal will commence in late FY2010 utilizing laser energies of 1 to 1.3 MJ. Fusion yields of the order of 10 to 20 MJ are expected soon thereafter. Laser initiated fusion-fission (LIFE) engines have now been designed to produce nuclear power from natural or depleted uranium without isotopic enrichment, and from spent nuclear fuel from light water reactors without chemical separation into weapons-attractive actinide streams. A point-source of high-energy neutrons produced by laser-generated, thermonuclear fusion within a target is used to achieve ultra-deep burn-up of the fertile or fissile fuel in a sub-critical fission blanket. Fertile fuels including depleted uranium (DU), natural uranium (NatU), spent nuclear fuel (SNF), and thorium (Th) can be used. Fissile fuels such as low-enrichment uranium (LEU), excess weapons plutonium (WG-Pu), and excess highly-enriched uranium (HEU) may be used as well. Based upon preliminary analyses, it is believed that LIFE could help meet worldwide electricity needs in a safe and sustainable manner, while drastically shrinking the nation's and world's stockpile of spent nuclear fuel and excess weapons materials. LIFE takes advantage of the significant advances in laser-based inertial confinement fusion that are taking place at the NIF at LLNL where it is expected that thermonuclear ignition will be achieved in the 2010-2011 timeframe. Starting from as little as 300 to 500 MW of fusion power, a single LIFE engine will be able to generate 2000 to 3000 MWt in steady state for periods of years to decades, depending on the nuclear fuel and engine configuration. Because the fission blanket in a fusion-fission hybrid system is subcritical, a LIFE engine can burn any fertile or fissile nuclear material, including unenriched natural or depleted U and SNF, and can extract a very high percentage of the energy content of its fuel resulting in greatly enhanced energy generation per metric ton of nuclear fuel, as well as nuclear waste forms with vastly reduced concentrations of long-lived actinides. LIFE engines could thus provide the ability to generate vast amounts of electricity while greatly reducing the actinide content of any existing or future nuclear waste and extending the availability of low cost nuclear fuels for several thousand years. LIFE also provides an attractive pathway for burning excess weapons Pu to over 99% FIMA (fission of initial metal atoms) without the need for fabricating or reprocessing mixed oxide fuels (MOX). Because of all of these advantages, LIFE engines offer a pathway toward sustainable and safe nuclear power that significantly mitigates nuclear proliferation concerns and minimizes nuclear waste. An important aspect of a LIFE engine is the fact that there is no need to extract the fission fuel from the fission blanket before it is burned to the desired final level. Except for fuel inspection and maintenance process times, the nuclear fuel is always within the core of the reactor and no weapons-attractive materials are available outside at any point in time. However, an important consideration when discussing proliferation concerns associated with any nuclear fuel cycle is the ease with which reactor fuel can be converted to weapons usable materials, not just when it is extracted as waste, but at any point in the fuel cycle. Although the nuclear fuel remains in the core of the engine until ultra deep actinide burn up is achieved, soon after start up of the engine, once the system breeds up to full power, several tons of fissile material is present in the fission blanket. However, this fissile material is widely dispersed in millions of fuel pebbles, which can be tagged as individual accountable items, and thus made difficult to diver

Farmer, J C; Diaz de la Rubia, T; Moses, E

2008-12-23T23:59:59.000Z

127

High-Level Functional and Operational Requirements for the Advanced Fuel Cycle Facilty  

SciTech Connect

High-Level Functional & Operational Requirements for the AFCF -This document describes the principal functional and operational requirements for the proposed Advanced Fuel Cycle Facility (AFCF). The AFCF is intended to be the world's foremost facility for nuclear fuel cycle research, technology development, and demonstration. The facility will also support the near-term mission to develop and demonstrate technology in support of fuel cycle needs identified by industry, and the long-term mission to retain and retain U.S. leadership in fuel cycle operations. The AFCF is essential to demonstrate a more proliferation-resistant fuel cycle and make long-term improvements in fuel cycle effectiveness, performance and economy.

Charles Park

2006-12-01T23:59:59.000Z

128

High Temperature Fuel Cell Tri-Generation of Power, Heat & H2 from Biogas  

NLE Websites -- All DOE Office Websites (Extended Search)

National Fuel Cell Research Center, 2012 1/22 National Fuel Cell Research Center, 2012 1/22 High Temperature Fuel Cell Tri-Generation of Power, Heat & H 2 from Biogas Jack Brouwer, Ph.D. June 19, 2012 DOE/ NREL Biogas Workshop - Golden, CO © National Fuel Cell Research Center, 2012 2/22 Outline * Introduction and Background * Tri-Generation/Poly-Generation Analyses * OCSD Project Introduction © National Fuel Cell Research Center, 2012 3/22 Introduction and Background * Hydrogen fuel cell vehicle performance is outstanding * Energy density of H 2 is much greater than batteries * Rapid fueling, long range ZEV * H 2 must be produced * energy intensive, may have emissions, fossil fuels, economies of scale * Low volumetric energy density of H 2 compared to current infrastructure fuels (@ STP)

129

Performance Assessment of High Burnup Fuel From Limerick  

Science Conference Proceedings (OSTI)

GE11 design (9x9 lattice) fuel was irradiated to ~52 and ~65 GWd/MTU average bundle exposures at Exelon's Limerick Unit 1 and Limerick Unit 2 reactors. The project goal was to characterize the behavior of modern boiling water reactor (BWR) fuel at exposures beyond current fuel licensing limits. Additionally, the program examined both GE11 and GE13 fuel rods (irradiated to ~51-55 GWd/MTU) to assess the effects of noble metal chemical addition (NMCA) and variations in fuel cladding fabrication processes on...

2008-01-31T23:59:59.000Z

130

High-efficiency one-sun photovoltaic module demonstration using solar-grade CZ silicon. Final report  

DOE Green Energy (OSTI)

This work was performed jointly by Sandia National Laboratories (Albuquerque, NM) and Siemens Solar Industries (Camarillo, CA) under a Cooperative Research and Development Agreement (CRADA 1248). The work covers the period May 1994 to March 1996. The purpose of the work was to explore the performance potential of commercial, photovoltaic-grade Czochralski (Cz) silicon, and to demonstrate this potential through fabrication of high-efficiency cells and a module. Fabrication of the module was omitted in order to pursue further development of advanced device structures. The work included investigation of response of the material to various fabrication processes, development of advanced cell structures using the commercial material, and investigation of the stability of Cz silicon solar cells. Some important achievements of this work include the following: post-diffusion oxidations were found to be a possible source of material contamination; bulk lifetimes around 75 pts were achieved; efficiencies of 17.6% and 15.7% were achieved for large-area cells using advanced cell structures (back-surface fields and emitter wrap-through); and preliminary investigations into photodegradation in Cz silicon solar cells found that oxygen thermal donors might be involved. Efficiencies around 20% should be possible with commercial, photovoltaic-grade silicon using properly optimized processes and device structures.

Gee, J.M.

1996-10-01T23:59:59.000Z

131

Application of Critical Strain Energy Density to Predicting High-Burnup Fuel Rod Failure  

Science Conference Proceedings (OSTI)

This report documents responses to Nuclear Regulatory Commission (NRC) staff concerning application of critical strain energy density (CSED) to predicting high-burnup fuel rod failure.

2005-09-26T23:59:59.000Z

132

High uranium density dispersion fuel for the reduced enrichment of research and test reactors program.  

E-Print Network (OSTI)

??This work describes the fabrication of a high uranium density fuel for the Reduced Enrichment of Research and Test Reactors Program. In an effort to… (more)

[No author

2006-01-01T23:59:59.000Z

133

APPLICATION OF CERAMICS TO HIGH PRESSURE FUEL SYSTEMS  

DOE Green Energy (OSTI)

Diesel fuel systems are facing increased demands as engines with reduced emissions are developed. Injection pressures have increased to provide finer atomization of fuel for more efficient combustion, Figure 1. This increases the mechanical loads on the system and requires tighter clearances between plungers and bores to prevent leakage. At the same time, fuel lubricity has decreased as a byproduct of reducing the sulfur levels in fuel. Contamination of fuel by water and debris is an ever-present problem. For oil-lubricated fuel system components, increased soot loading in the oil results in increased wear rates. Additionally, engine manufacturers are lengthening warranty periods for engines and systems. This combination of factors requires the development of new materials to counteract the harsher tribological environment.

Mandler, Jr., William F.

2000-08-20T23:59:59.000Z

134

New Developments in High Velocity Air-fuel Spraying  

Science Conference Proceedings (OSTI)

This is possible because of the low temperature of air-fuel combustion. The heating of the spray ... Conditioning of Composite Lubricant Powder for Cold Spray.

135

Next-generation nuclear fuel withstands high-temperature accident...  

NLE Websites -- All DOE Office Websites (Extended Search)

(more than 200 degrees Celsius greater than postulated accident conditions) most fission products remained inside the fuel particles, which each boast their own primary...

136

High-Activity Dealloyed Catalysts - DOE Hydrogen and Fuel Cells...  

NLE Websites -- All DOE Office Websites (Extended Search)

9 FY 2012 Annual Progress Report DOE Hydrogen and Fuel Cells Program Frederick T. Wagner (Primary Contact), Anusorn Kongkanand General Motors, LLC (GM) 10 Carriage St. Honeoye...

137

Durability of Low Platinum Fuel Cells Operating at High Power...  

NLE Websites -- All DOE Office Websites (Extended Search)

cells, 2nd International Workshop on Degradation Issues in Fuel Cells, Thessaloniki, Greece, September 21-23, 2011. 9. R. Subbaraman, Ex-situ Potentiostatic and Potentiodynamic...

138

Tribological behavior of near-frictionless carbon coatings in high- and low-sulfur diesel fuels.  

DOE Green Energy (OSTI)

The sulfur content in diesel fuel has a significant effect on diesel engine emissions, which are currently subject to environmental regulations. It has been observed that engine particulate and gaseous emissions are directly proportional to fuel sulfur content. With the introduction of low-sulfur fuels, significant reductions in emissions are expected. The process of sulfur reduction in petroleum-based diesel fuels also reduces the lubricity of the fuel, resulting in premature failure of fuel injectors. Thus, another means of preventing injector failures is needed for engines operating with low-sulfur diesel fuels. In this study, the authors evaluated a near-frictionless carbon (NFC) coating (developed at Argonne National Laboratory) as a possible solution to the problems associated with fuel injector failures in low-lubricity fuels. Tribological tests were conducted with NFC-coated and uncoated H13 and 52100 steels lubricated with high- and low- sulfur diesel fuels in a high-frequency reciprocating test machine. The test results showed that the NFC coatings reduced wear rates by a factor of 10 over those of uncoated steel surfaces. In low-sulfur diesel fuel, the reduction in wear rate was even greater (i.e., by a factor of 12 compared to that of uncoated test pairs), indicating that the NFC coating holds promise as a potential solution to wear problems associated with the use of low-lubricity diesel fuels.

Alzoubi, M. F.; Ajayi, O. O.; Eryilmaz, O. L.; Ozturk, O.; Erdemir, A.; Fenske, G.

2000-01-19T23:59:59.000Z

139

MICROSTRUCTURE AND MECHANICAL PROPERTY PERFORMANCE OF COMMERCIAL GRADE API PIPELINE STEELS IN HIGH PRESSURE GASEOUS HYDROGEN  

Science Conference Proceedings (OSTI)

The continued growth of the world s developing countries has placed an ever increasing demand on traditional fossil fuel energy sources. This development has lead to increasing research and development of alternative energy sources. Hydrogen gas is one of the potential alternative energy sources under development. Currently the most economical method of transporting large quantities of hydrogen gas is through steel pipelines. It is well known that hydrogen embrittlement has the potential to degrade steel s mechanical properties when hydrogen migrates into the steel matrix. Consequently, the current pipeline infrastructure used in hydrogen transport is typically operated in a conservative fashion. This operational practice is not conducive to economical movement of significant volumes of hydrogen gas as an alternative to fossil fuels. The degradation of the mechanical properties of steels in hydrogen service is known to depend on the microstructure of the steel. Understanding the levels of mechanical property degradation of a given microstructure when exposed to hydrogen gas under pressure can be used to evaluate the suitability of the existing pipeline infrastructure for hydrogen service and guide alloy and microstructure design for new hydrogen pipeline infrastructure. To this end, the 2 Copyright 2010 by ASME microstructures of relevant steels and their mechanical properties in relevant gaseous hydrogen environments must be fully characterized to establish suitability for transporting hydrogen. A project to evaluate four commercially available pipeline steels alloy/microstructure performance in the presences of gaseous hydrogen has been funded by the US Department of Energy along with the private sector. The microstructures of four pipeline steels were characterized and then tensile testing was conducted in gaseous hydrogen and helium at pressures of 800, 1600 and 3000 psi. Based on measurements of reduction of area, two of the four steels that performed the best across the pressure range were selected for evaluation of fracture and fatigue performance in gaseous hydrogen at 800 and 3000 psi. This paper will describe the work performed on four commercially available pipeline steels in the presence of gaseous hydrogen at pressures relevant for transport in pipelines. Microstructures and mechanical property performances will be compared. In addition, recommendations for future work related to gaining a better understanding of steel pipeline performance in hydrogen service will be discussed.

Stalheim, Mr. Douglas [DGS Metallurgical Solutions Inc; Boggess, Todd [Secat; San Marchi, Chris [Sandia National Laboratories (SNL); Jansto, Steven [Reference Metals Company; Somerday, Dr. B [Sandia National Laboratories (SNL); Muralidharan, Govindarajan [ORNL; Sofronis, Prof. Petros [University of Illinois

2010-01-01T23:59:59.000Z

140

On0Line Fuel Failure Monitor for Fuel Testing and Monitoring of Gas Cooled Very High Temperature Reactor  

Science Conference Proceedings (OSTI)

IVery High Temperature Reactors (VHTR) utilize the TRISO microsphere as the fundamental fuel unit in the core. The TRISO microsphere (~ 1- mm diameter) is composed of a UO2 kernel surrounded by a porous pyrolytic graphite buffer, an inner pyrolytic graphite layer, a silicon carbide (SiC) coating, and an outer pyrolytic graphite layer. The U-235 enrichment of the fuel is expected to range from 4% – 10% (higher enrichments are also being considered). The layer/coating system that surrounds the UO2 kernel acts as the containment and main barrier against the environmental release of radioactivity. To understand better the behavior of this fuel under in-core conditions (e.g., high temperature, intense fast neutron flux, etc.), the US Department of Energy (DOE) is launching a fuel testing program that will take place at the Advanced Test Reactor (ATR) located at Idaho National Laboratory (INL). During this project North Carolina State University (NCSU) researchers will collaborate with INL staff for establishing an optimized system for fuel monitoring for the ATR tests. In addition, it is expected that the developed system and methods will be of general use for fuel failure monitoring in gas cooled VHTRs.

Ayman I. Hawari; Mohamed A. Bourham

2010-04-22T23:59:59.000Z

Note: This page contains sample records for the topic "high grade fuel" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

Effect of High Reactor Water Zinc on Fuel Performance in Quad Cities 2  

Science Conference Proceedings (OSTI)

Due to reduction in feedwater Fe, reactor water Zn concentrations have been increasing in U.S. boiling water reactors (BWRs). The fuel performance experience base is limited to 8 to 10 ppb, and no fuel surveillance was performed in a plant operated with greater than 12 ppb reactor water Zn. The impact of high reactor water Zn on fuel performance is unknown. However, the change in the trends is large enough to raise a concern, and it requires a confirmation of the fuel performance with fuel ...

2013-07-02T23:59:59.000Z

142

A Study on Beneficiation of Low Grade High-Phosphorus Iron Ore  

Science Conference Proceedings (OSTI)

Arc Plasma Smelting of Niobium Pentoxide towards Production of Nb Metal ... Passes Laser Phase Transformation Hardening by Using High-Power Direct Diode Laser ... Preparation of Metallized Pellets and Recovery of Tin and Zinc from Tin, ...

143

Low-Enriched Fuel Design Concept for the Prismatic Very High Temperature Reactor Core  

SciTech Connect

A new non-TRISO fuel and clad design concept is proposed for the prismatic, heliumcooled Very High Temperature Reactor core. The new concept could substantially reduce the current 10-20 wt% TRISO uranium enrichments down to 4-6 wt% for both initial and reload cores. The proposed fuel form would be a high-temperature, high-density uranium ceramic, for example UO2, configured into very small diameter cylindrical rods. The small diameter fuel rods significantly increase core reactivity through improved neutron moderation and fuel lumping. Although a high-temperature clad system for the concept remains to be developed, recent success in tube fabrication and preliminary irradiation testing of silicon carbide (SiC) cladding for light water reactor applications offers good potential for this application, and for future development of other carbide clad designs. A high-temperature ceramic fuel, together with a high-temperature clad material, could also lead to higher thermal safety margins during both normal and transient reactor conditions relative to TRISO fuel. The calculated neutronic results show that the lowenrichment, small diameter fuel rods and low thermal neutron absorbing clad retain the strong negative Doppler fuel temperature coefficient of reactivity that ensures inherent safe operation of the VHTR, and depletion studies demonstrate that an 18-month power cycle can be achieved with the lower enrichment fuel.

Sterbentz, James W

2007-05-01T23:59:59.000Z

144

Alternative Fuels Data Center: Plug-In Electric Vehicle (PEV) High  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Plug-In Electric Plug-In Electric Vehicle (PEV) High Occupancy Vehicle (HOV) Lane and Parking Fee Exemptions to someone by E-mail Share Alternative Fuels Data Center: Plug-In Electric Vehicle (PEV) High Occupancy Vehicle (HOV) Lane and Parking Fee Exemptions on Facebook Tweet about Alternative Fuels Data Center: Plug-In Electric Vehicle (PEV) High Occupancy Vehicle (HOV) Lane and Parking Fee Exemptions on Twitter Bookmark Alternative Fuels Data Center: Plug-In Electric Vehicle (PEV) High Occupancy Vehicle (HOV) Lane and Parking Fee Exemptions on Google Bookmark Alternative Fuels Data Center: Plug-In Electric Vehicle (PEV) High Occupancy Vehicle (HOV) Lane and Parking Fee Exemptions on Delicious Rank Alternative Fuels Data Center: Plug-In Electric Vehicle (PEV) High Occupancy Vehicle (HOV) Lane and Parking Fee Exemptions on Digg

145

Power-grade butanol recovery and utilization  

DOE Green Energy (OSTI)

As an alternative to the traditional recovery systems, it was proposed in a previous publication that the n-butanol/acetone/ethanol fermentation products could be recovered as a power grade fuel blend and used directly as a fuel. This would affect a savings in process energy requirements because each chemical component would not have to be processed individually to technical grade purity. Further, some residual water could be tolerated in the fuel blend. To develop such a power grade fuel recovery scheme beyond the conceptual stage, the Energy Research and Resource Division of the Kansas Energy Office undertook a two-fold program to demonstrate and test a power grade butanol/acetone/ethanol fuel recovery system, and further to demonstrate the feasibility of using the fuel blend in a standard type engine. A development program was initiated to accomplish the following objectives: design and test an operational power grade butanol recovery plant that would operate at one liter per hour output; and test and assess the performance of power grade butanol in a spark ignition automotive engine. This project has demonstrated that recovery of a power grade butanol fuel blend is simple and can be accomplished at a considered energy advantage over ethanol. It was further demonstrated that such a power grade blend works well in a typical spark ignition engine.

Noon, R.

1982-02-12T23:59:59.000Z

146

High-alcohol microemulsion fuel performance in a diesel engine  

DOE Green Energy (OSTI)

Incidence of methanol use in diesel engines is increasing rapidly due to the potential to reduce both diesel particulate emissions and petroleum consumption. Because simple alcohols and conventional diesel fuel are normally immiscible, most tests to date have used neat to near-neat alcohol, or blends incorporating surfactants or other alcohols. Alcohol's poor ignition quality usually necssitates the use of often expensive cetane enhancers, full-time glow plugs, or spark assist. Reported herein are results of screening tests of clear microemulsion and micellar fuels which contain 10 to 65% C{sub 1}--C{sub 4} alcohol. Ignition performance and NO emissions were measured for clear, stable fuel blends containing alcohols, diesel fuel and additives such as alkyl nitrates, acrylic acids, and several vegetable oil derivatives. Using a diesel engine calibrated with reference fuels, cetane numbers for fifty four blends were estimated. The apparent cetane numbers ranged from around 20 to above 50 with the majority between 30 and 45. Emissions of nitric oxide were measured for a few select fuels and were found to be 10 to 20% lower than No. 2 diesel fuel. 36 refs., 87 figs., 8 tabs.

West, B.H.; Compere, A.L.; Griffith, W.L.

1990-01-01T23:59:59.000Z

147

Engine with hydraulic fuel injection and ABS circuit using a single high pressure pump  

DOE Patents (OSTI)

An engine system comprises a hydraulically actuated fuel injection system and an ABS circuit connected via a fluid flow passage that provides hydraulic fluid to both the fuel injection system and to the ABS circuit. The hydraulically actuated system includes a high pressure pump. The fluid control passage is in fluid communication with an outlet from the high pressure pump.

Bartley, Bradley E. (Manito, IL); Blass, James R. (Bloomington, IL); Gibson, Dennis H. (Chillicothe, IL)

2001-01-01T23:59:59.000Z

148

High efficiency carbonate fuel cell/turbine hybrid power cycles  

SciTech Connect

Carbonate fuel cells developed in commercial 2.85 MW size, have an efficiency of 57.9%. Studies of higher efficiency hybrid power cycles were conducted to identify an economically competitive system and an efficiency over 65%. A hybrid power cycle was identified that includes a direct carbonate fuel cell, a gas turbine, and a steam cycle, which generates power at a LHV efficiency over 70%; it is called a Tandem Technology Cycle (TTC). In a TTC operating on natural gas fuel, 95% of the fuel is mixed with recycled fuel cell anode exhaust, providing water for reforming the fuel, and flows to a direct carbonate fuel cell system which generates 72% of the power. The portion of fuel cell anode exhaust not recycled, is burned and heat is transferred to compressed air from a gas turbine, heating it to 1800 F. The stream is then heated to 2000 F in gas turbine burner and expands through the turbine generating 13% of the power. Half the gas turbine exhaust flows to anode exhaust burner and the rest flows to the fuel cell cathodes providing the O2 and CO2 needed in the electrochemical reaction. Studies of the TTC for 200 and 20 MW size plants quantified performance, emissions and cost-of-electricity, and compared the TTC to gas turbine combined cycles. A 200-MW TTC plant has an efficiency of 72.6%; estimated cost of electricity is 45.8 mills/kWhr. A 20-MW TTC plant has an efficiency of 65.2% and a cost of electricity of 50 mills/kWhr.

Steinfeld, G.

1996-12-31T23:59:59.000Z

149

EA-0510: High-Temperature Solid Oxide Fuel Cell (Sofc) Generator  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

510: High-Temperature Solid Oxide Fuel Cell (Sofc) Generator 510: High-Temperature Solid Oxide Fuel Cell (Sofc) Generator Development Project (METC), Churchill, Pennsylvania EA-0510: High-Temperature Solid Oxide Fuel Cell (Sofc) Generator Development Project (METC), Churchill, Pennsylvania SUMMARY This EA evaluates the environmental impacts of a proposal to enter into a 5-year cooperative agreement with the Westinghouse Electric Corporation for the development of high-temperature solid oxide fuel cell generators near Pittsburgh, Pennsylvania. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD August 1, 1991 EA-0510: Final Environmental Assessment High-Temperature Solid Oxide Fuel Cell (Sofc) Generator Development Project (METC) August 1, 1991 EA-0510: Finding of No Significant Impact

150

Methods for manufacturing porous nuclear fuel elements for high-temperature gas-cooled nuclear reactors  

SciTech Connect

Methods for manufacturing porous nuclear fuel elements for use in advanced high temperature gas-cooled nuclear reactors (HTGR's). Advanced uranium bi-carbide, uranium tri-carbide and uranium carbonitride nuclear fuels can be used. These fuels have high melting temperatures, high thermal conductivity, and high resistance to erosion by hot hydrogen gas. Tri-carbide fuels, such as (U,Zr,Nb)C, can be fabricated using chemical vapor infiltration (CVI) to simultaneously deposit each of the three separate carbides, e.g., UC, ZrC, and NbC in a single CVI step. By using CVI, a thin coating of nuclear fuel may be deposited inside of a highly porous skeletal structure made, for example, of reticulated vitreous carbon foam.

Youchison, Dennis L. (Albuquerque, NM); Williams, Brian E. (Pocoima, CA); Benander, Robert E. (Pacoima, CA)

2010-02-23T23:59:59.000Z

151

Porous nuclear fuel element for high-temperature gas-cooled nuclear reactors  

SciTech Connect

Porous nuclear fuel elements for use in advanced high temperature gas-cooled nuclear reactors (HTGR's), and to processes for fabricating them. Advanced uranium bi-carbide, uranium tri-carbide and uranium carbonitride nuclear fuels can be used. These fuels have high melting temperatures, high thermal conductivity, and high resistance to erosion by hot hydrogen gas. Tri-carbide fuels, such as (U,Zr,Nb)C, can be fabricated using chemical vapor infiltration (CVI) to simultaneously deposit each of the three separate carbides, e.g., UC, ZrC, and NbC in a single CVI step. By using CVI, the nuclear fuel may be deposited inside of a highly porous skeletal structure made of, for example, reticulated vitreous carbon foam.

Youchison, Dennis L. (Albuquerque, NM); Williams, Brian E. (Pacoima, CA); Benander, Robert E. (Pacoima, CA)

2011-03-01T23:59:59.000Z

152

Safeguards Guidance for Prismatic Fueled High Temperature Gas...  

National Nuclear Security Administration (NNSA)

as opposed to a water cooled (LWR) core that can be opened, the IAEA is in the process of developing methods to verify the fuel in the HTGR core. These are discussed in more detail...

153

An evolutionary fuel assembly design for high power density BWRs  

E-Print Network (OSTI)

An evolutionary BWR fuel assembly design was studied as a means to increase the power density of current and future BWR cores. The new assembly concept is based on replacing four traditional assemblies and large water gap ...

Karahan, Aydin

2007-01-01T23:59:59.000Z

154

NREL Team Creates High-Activity, Durable Platinum Extended Surface Catalyst for Fuel Cells (Fact Sheet)  

DOE Green Energy (OSTI)

Researchers with NREL's Fuel Cell team showed that platinum can replace copper nanowires in such a way that high-surface-area and high-specific-activity catalysts are produced, potentially allowing for lower-cost catalysts.

Not Available

2011-02-01T23:59:59.000Z

155

Establishing Specifications for Low Enriched Uranium Fuel Operations Conducted Outside the High Flux Isotope Reactor Site  

SciTech Connect

The National Nuclear Security Administration (NNSA) has funded staff at Oak Ridge National Laboratory (ORNL) to study the conversion of the High Flux Isotope Reactor (HFIR) from the current, high enriched uranium fuel to low enriched uranium fuel. The LEU fuel form is a metal alloy that has never been used in HFIR or any HFIR-like reactor. This report provides documentation of a process for the creation of a fuel specification that will meet all applicable regulations and guidelines to which UT-Battelle, LLC (UTB) the operating contractor for ORNL - must adhere. This process will allow UTB to purchase LEU fuel for HFIR and be assured of the quality of the fuel being procured.

Pinkston, Daniel [ORNL; Primm, Trent [ORNL; Renfro, David G [ORNL; Sease, John D [ORNL

2010-10-01T23:59:59.000Z

156

Embrittlement and DBTT of High-Burnup PWR Fuel Cladding Alloys | Department  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Embrittlement and DBTT of High-Burnup PWR Fuel Cladding Alloys Embrittlement and DBTT of High-Burnup PWR Fuel Cladding Alloys Embrittlement and DBTT of High-Burnup PWR Fuel Cladding Alloys Structural analyses of high-burnup (HBU) fuel require cladding mechanical properties and failure limits to assess fuel behavior during long-term dry-cask storage and transportation. Pre-storage drying-transfer operations and early stage storage subject cladding to higher temperatures and pressure-induced tensile hoop stresses relative to in-reactor operation and pool storage. Under these conditions, radial hydrides may precipitate during slow cooling and provide an additional embrittlement mechanism as the cladding temperature decreases below the ductile-to-brittle transition temperature (DBTT). Graphic and photographic details of the testing are

157

High Burn-Up Properties of the Fuel Variants Irradiated in IFA-649  

Science Conference Proceedings (OSTI)

The "standard product" uranium dioxide (UO2) fuel pellet has remained unchanged for many years and provides excellent performance in all but the most extreme reactor operation. The requirement to prolong fuel residence in commercial reactors, thus increasing discharge levels of burn-up, has led to a need for detailed measurements of high burn-up properties under a variety of normal and off-normal conditions. The changes in fuel material properties, such as density and swelling, ...

2013-01-31T23:59:59.000Z

158

High Voltage CMOS Control Interface for Astronomy - Grade Charged Coupled Devices  

E-Print Network (OSTI)

The Pan-STARRS telescope consists of an array of smaller mirrors viewed by a Gigapixel arrays of CCDs. These focal planes employ Orthogonal Transfer CCDs (OTCCDs) to allow on-chip image stabilization. Each OTCCD has advanced logic features that are controlled externally. A CMOS Interface Device for High Voltage has been developed to provide the appropiate voltage signal levels from a readout and control system designated STARGRASP. OTCCD chip output levels range from -3.3V to 16.7V, with two different output drive strenghts required depending on load capacitance (50pF and 1000pF), with 24mA of drive and a rise time on the order of 100ns. Additional testing ADC structures have been included in this chip to evaluate future functional additions for a next version of the chip.

Martin, Elena; Koga, Aaron; Ruckman, Larry; Onaka, Peter; Tonry, John; Lee, Aaron

2008-01-01T23:59:59.000Z

159

Used Fuel Disposition Campaign Phase I Ring Compression Testing of High  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Phase I Ring Compression Testing of Phase I Ring Compression Testing of High Burnup Cladding Used Fuel Disposition Campaign Phase I Ring Compression Testing of High Burnup Cladding The purpose of ring compression testing is to generate data to support the development of the technical basis for extended storage and transportation of high-burnup fuel. This report highlights the results of completed Phase I testing of high-burnup M5® cladding and the revised three-year test plan. The goal of the ring compression testing is to identify process conditions that would minimize radial-hydride formation and the corresponding DBTT of high-burnup fuel cladding and to generate data and models to support the development of the technical basis for extended storage and transportation of high-burnup fuel.

160

Phase II Trial of Radiotherapy After Hyperbaric Oxygenation With Multiagent Chemotherapy (Procarbazine, Nimustine, and Vincristine) for High-Grade Gliomas: Long-Term Results  

Science Conference Proceedings (OSTI)

Purpose: To analyze the long-term results of a Phase II trial of radiotherapy given immediately after hyperbaric oxygenation (HBO) with multiagent chemotherapy in adults with high-grade gliomas. Methods and Materials: Patients with histologically confirmed high-grade gliomas were administered radiotherapy in daily 2 Gy fractions for 5 consecutive days per week up to a total dose of 60 Gy. Each fraction was administered immediately after HBO, with the time interval from completion of decompression to start of irradiation being less than 15 minutes. Chemotherapy consisting of procarbazine, nimustine, and vincristine and was administered during and after radiotherapy. Results: A total of 57 patients (39 patients with glioblastoma and 18 patients with Grade 3 gliomas) were enrolled from 2000 to 2006, and the median follow-up of 12 surviving patients was 62.0 months (range, 43.2-119.1 months). All 57 patients were able to complete a total radiotherapy dose of 60 Gy immediately after HBO with one course of concurrent chemotherapy. The median overall survival times in all 57 patients, 39 patients with glioblastoma and 18 patients with Grade 3 gliomas, were 20.2 months, 17.2 months, and 113.4 months, respectively. On multivariate analysis, histologic grade alone was a significant prognostic factor for overall survival (p < 0.001). During treatments, no patients had neutropenic fever or intracranial hemorrhage, and no serious nonhematologic or late toxicities were seen in any of the 57 patients. Conclusions: Radiotherapy delivered immediately after HBO with multiagent chemotherapy was safe, with virtually no late toxicities, and seemed to be effective in patients with high-grade gliomas.

Ogawa, Kazuhiko, E-mail: kogawa@med.u-ryukyu.ac.jp [Department of Radiology, University of the Ryukyus, Okinawa (Japan); Ishiuchi, Shogo [Department of Neurosurgery, University of the Ryukyus, Okinawa (Japan); Inoue, Osamu [Department of Hyperbaric Medicine, University of the Ryukyus, Okinawa (Japan); Yoshii, Yoshihiko [Department of Neurosurgery, University of the Ryukyus, Okinawa (Japan); Department of Neurosurgery, Tsukuba Memorial Hospital, Tsukuba (Japan); Saito, Atsushi [Department of Neurosurgery, University of the Ryukyus, Okinawa (Japan); Department of Neurosurgery, Tsukuba Medical Center Hospital, Tsukuba (Japan); Watanabe, Takashi [Department of Neurosurgery, University of the Ryukyus, Okinawa (Japan); Iraha, Shiro [Department of Radiology, Okinawa South Medical Center, Okinawa (Japan); Department of Radiology, University of the Ryukyus, Okinawa (Japan); Toita, Takafumi; Kakinohana, Yasumasa; Ariga, Takuro; Kasuya, Goro; Murayama, Sadayuki [Department of Radiology, University of the Ryukyus, Okinawa (Japan)

2012-02-01T23:59:59.000Z

Note: This page contains sample records for the topic "high grade fuel" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


161

Deep Burn Develpment of Transuranic Fuel for High-Temperature Helium-Cooled Reactors - July 2010  

SciTech Connect

The DB Program Quarterly Progress Report for April - June 2010, ORNL/TM/2010/140, was distributed to program participants on August 4. This report discusses the following: (1) TRU (transuranic elements) HTR (high temperature helium-cooled reactor) Fuel Modeling - (a) Thermochemical Modeling, (b) 5.3 Radiation Damage and Properties; (2) TRU HTR Fuel Qualification - (a) TRU Kernel Development, (b) Coating Development, (c) ZrC Properties and Handbook; and (3) HTR Fuel Recycle - (a) Recycle Processes, (b) Graphite Recycle, (c) Pyrochemical Reprocessing - METROX (metal recovery from oxide fuel) Process Development.

Snead, Lance Lewis [ORNL; Besmann, Theodore M [ORNL; Collins, Emory D [ORNL; Bell, Gary L [ORNL

2010-08-01T23:59:59.000Z

162

PREPARING THE HIGH FLUX ISOTOPE REACTOR FOR CONVERSION TO LOW ENRICHED URANIUM FUEL ? EXTENDING CYCLE BURNUP  

Science Conference Proceedings (OSTI)

Reactor performance studies have been completed for conceptual plate designs and show that maintaining reactor performance while converting HFIR from high enriched to low enriched uranium (20 wt % 235U) fuel requires extending the end-of-life burnup value for HFIR fuel from the current nominal value of 2200 MWD to 2600 MWD. The current fuel fabrication procedure is discussed and changes that would be required to this procedure are identified. Design and safety related analyses that are required for the certification of a new fuel are identified. Qualification tests and comments regarding the regulatory approval process are provided along with a conceptual schedule.

Primm, Trent [ORNL; Chandler, David [ORNL

2009-01-01T23:59:59.000Z

163

Nano Sensor Networks for Tailored Operation of Highly Efficient Gas-To-Liquid Fuels Catalysts  

E-Print Network (OSTI)

Nano Sensor Networks for Tailored Operation of Highly Efficient Gas-To-Liquid Fuels Catalysts Eisa Engineering at University of New South Wales. #12;1 Introduction Gas-to-liquid (GTL) compounds are clean fuels for converting natural gas to the liquid hydrocarbons [1]. However, the reaction is a complex network of many

New South Wales, University of

164

Poolside Examination Data on High-Duty BWR Fuel Exposed to 52 GWd/MTU:  

Science Conference Proceedings (OSTI)

Poolside examinations conducted on boiling water reactor (BWR) fuel exposed to 52 GWd/MTU under high-duty operating conditions are providing data needed to justify extending allowable burnup limits. The good condition of the examined fuel assemblies allowed four of them to be reinserted for an additional 2-year duty cycle to provide data at even higher burnup levels.

1999-09-07T23:59:59.000Z

165

Graphical and tabular summaries of decay characteristics for once-through PWR, LMFBR, and FFTF fuel cycle materials. [Spent fuel, high-level waste fuel can scrap  

SciTech Connect

Based on the results of ORIGEN2 and a newly developed code called ORMANG, graphical and summary tabular characteristics of spent fuel, high-level waste, and fuel assembly structural material (cladding) waste are presented for a generic pressurized-water reactor (PWR), a liquid-metal fast breeder reactor (LMFBR), and the Fast Flux Test Facility (FFTF). The characteristics include radioactivity, thermal power, and toxicity (water dilution volume). Given are graphs and summary tables containing characteristic totals and the principal nuclide contributors as well as graphs comparing the three reactors for a single material and the three materials for a single reactor.

Croff, A.G.; Liberman, M.S.; Morrison, G.W.

1982-01-01T23:59:59.000Z

166

PHASE ANALYSES OF URANIUM-BEARING MINERALS FROM THE HIGH GRADE ORE, NOPAL I, PENA BLANCA, MEXICO  

SciTech Connect

The Nopal I uranium deposit is located in the Pena Blanca district, approximately 40 miles north of Chihuahua City, Mexico. The deposit was formed by hydrothermal processes within the fracture zone of welded silicic volcanic tuff. The ages of volcanic formations are between 35 to 44 m.y. and there was secondary silicification of most of the formations. After the formation of at least part of the uranium deposit, the ore body was uplifted above the water table and is presently exposed at the surface. Detailed petrographic characterization, electron microprobe backscatter electron (BSE) imagery, and selected x-ray maps for the samples from Nopal I high-grade ore document different uranium phases in the ore. There are at least two stages of uranium precipitation. A small amount of uraninite is encapsulated in silica. Hexavalent uranium may also have been a primary precipitant. The uranium phases were precipitated along cleavages of feldspars, and along fractures in the tuff. Energy dispersive spectrometer data and x-ray maps suggest that the major uranium phases are uranophane and weeksite. Substitutions of Ca and K occur in both phases, implying that conditions were variable during the mineralization/alteration process, and that compositions of the original minerals have a major influence on later stage alteration. Continued study is needed to fully characterize uranium behavior in these semi-arid to arid conditions.

M. Ren; P. Goodell; A. Kelts; E.Y. Anthony; M. Fayek; C. Fan; C. Beshears

2005-07-11T23:59:59.000Z

167

Processing of FRG high-temperature gas-cooled reactor fuel elements at General Atomic under the US/FRG cooperative agreement for spent fuel elements  

Science Conference Proceedings (OSTI)

The Federal Republic of Germany (FRG) and the United States (US) are cooperating on certain aspects of gas-cooled reactor technology under an umbrella agreement. Under the spent fuel treatment development section of the agreement, both FRG mixed uranium/ thorium and low-enriched uranium fuel spheres have been processed in the Department of Energy-sponsored cold pilot plant for high-temperature gas-cooled reactor (HTGR) fuel processing at General Atomic Company in San Diego, California. The FRG fuel spheres were crushed and burned to recover coated fuel particles suitable for further treatment for uranium recovery. Successful completion of the tests described in this paper demonstrated certain modifications to the US HTGR fuel burining process necessary for FRG fuel treatment. Results of the tests will be used in the design of a US/FRG joint prototype headend facility for HTGR fuel.

Holder, N.D.; Strand, J.B.; Schwarz, F.A.; Drake, R.N.

1981-11-01T23:59:59.000Z

168

High Pressure Fuel Storage Cylinders Periodic Inspection and End of Life Issues  

NLE Websites -- All DOE Office Websites (Extended Search)

6/2010 6/2010 www.cleanvehicle.org 1 High Pressure Fuel Storage Cylinders Periodic Inspection and End of Life Issues DOE Vehicular Tank Workshop April 29, 2010 Douglas Horne, PE The Facts  High pressure Type 4 gaseous fuel tanks are now designed under standards that specify finite lifetimes of 15, 20 and 25 years based on specific design and testing (the HGV2 standard under development had a life as short as 10 years as an option)  It is unique within the transportation industry to have a critical device (the fuel tank) with a designated life that may be shorter than the vehicle itself  Although vehicle owners are told up front of the limited life fuel storage cylinders some tend to forget after 15 years  A parallel concern is the requirement for these fuel tanks

169

Fueling Requirements for Steady State high butane current fraction discharges  

SciTech Connect

The CT injector originally used for injecting CTs into 1T toroidal field discharges in the TdeV tokamak was shipped PPPL from the Affiliated Customs Brokers storage facility in Montreal during November 2002. All components were transported safely, without damage, and are currently in storage at PPPL, waiting for further funding in order to begin advanced fueling experiments on NSTX. The components are currently insured through the University of Washington. Several technical presentations were made to investigate the feasibility of the CT injector installation on NSTX. These technical presentations, attached to this document, were: (1) Motivation for Compact Toroida Injection in NSTX; (2) Assessment of the Engineering Feasibility of Installing CTF-II on NSTX; (3) Assessment of the Cost for CT Installation on NSTX--A Peer Review; and (4) CT Fueling for NSTX FY 04-08 steady-state operation needs.

R.Raman

2003-10-08T23:59:59.000Z

170

Quadrilateral Cooperation on High-density Low-enriched Uranium Fuel  

NLE Websites -- All DOE Office Websites (Extended Search)

Quadrilateral Cooperation on High-density Low-enriched Uranium Fuel Quadrilateral Cooperation on High-density Low-enriched Uranium Fuel Production: Fact Sheet | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Fact Sheets > Quadrilateral Cooperation on High-density Low-enriched Uranium Fuel ... Fact Sheet Quadrilateral Cooperation on High-density Low-enriched Uranium Fuel

171

Development of Alternative and Durable High Performance Cathode Supports for PEM Fuel Cells  

NLE Websites -- All DOE Office Websites (Extended Search)

Alternative and Durable High Alternative and Durable High Performance Cathode Supports for PEM Fuel Cells Development of Alternative and Durable High Development of Alternative and Durable High Performance Cathode Supports for PEM Fuel Cells Performance Cathode Supports for PEM Fuel Cells PNNL: Yong Wang Conrad Zhang Vilayanur Viswanath Yuehe Lin Jun Liu Project kick Project kick - - off meeting off meeting Feb 13 Feb 13 - - 14, 2007 14, 2007 Ballard Power Systems: Stephen Campbell University of Delaware: Jingguang Chen ORNL: Sheng Dai 2 Technical Issues and Objective Technical Issues and Objective Current technical issues z Carbon support „ Susceptible to oxidation under fuel cell operating conditions. „ Oxidation further catalyzed by Pt „ Corrosion leads to Pt migration and agglomeration

172

High Aspect Ratio Nano-Structured Pt-based PEM Fuel Cell Catalysts...  

NLE Websites -- All DOE Office Websites (Extended Search)

or * nanoplates - Ni, Co, and Fe have been selected as V.D.14 High Aspect Ratio Nano-Structured Pt-Based PEM Fuel Cell Catalysts Table 1. Technical Targets for...

173

Development of a High Temperature Gas-Cooled Reactor TRISO-coated particle fuel chemistry model  

E-Print Network (OSTI)

The first portion of this work is a comprehensive analysis of the chemical environment in a High Temperature Gas-Cooled Reactor TRISO fuel particle. Fission product inventory versus burnup is calculated. Based on those ...

Diecker, Jane T

2005-01-01T23:59:59.000Z

174

High Performance Fuel Design for Next Generation PWRs: 11th Quarterly Report  

E-Print Network (OSTI)

I. Technical Narrative: The overall objective of this NERI project is to examine the potential for a high performance advanced fuel for Pressurized Water Reactors (PWRs), which would accommodate a substantial increase of ...

Kazimi, Mujid S.

175

High Performance Fuel Design for Next Generation PWRs 2nd Annual Report  

E-Print Network (OSTI)

The overall objective of this NERI project is to examine the potential for a high performance advanced fuel design for Pressurized Water Reactors (PWRs), which would accommodate a substantial increase of core power density ...

Ballinger, Ronald G.

176

Design strategies for optimizing high burnup fuel in pressurized water reactors  

E-Print Network (OSTI)

This work is focused on the strategy for utilizing high-burnup fuel in pressurized water reactors (PWR) with special emphasis on the full array of neutronic considerations. The historical increase in batch-averaged discharge ...

Xu, Zhiwen, 1975-

2003-01-01T23:59:59.000Z

177

Low Cost High-H2 Syngas Production for Power and Liquid Fuels  

NLE Websites -- All DOE Office Websites (Extended Search)

Low Cost High-H2 Syngas Production for Power and Liquid Fuels Gas Technology Institute (GTI) Project Number: FE0011958 Project Description Proof-of-concept of a metal-polymeric...

178

Quadrilateral Cooperation on High-density Low-enriched Uranium Fuel  

National Nuclear Security Administration (NNSA)

Quadrilateral Cooperation on High-density Low-enriched Uranium Fuel Quadrilateral Cooperation on High-density Low-enriched Uranium Fuel Production: Fact Sheet | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Fact Sheets > Quadrilateral Cooperation on High-density Low-enriched Uranium Fuel ... Fact Sheet Quadrilateral Cooperation on High-density Low-enriched Uranium Fuel

179

Method to fabricate high performance tubular solid oxide fuel cells  

DOE Patents (OSTI)

In accordance with the present disclosure, a method for fabricating a solid oxide fuel cell is described. The method includes forming an asymmetric porous ceramic tube by using a phase inversion process. The method further includes forming an asymmetric porous ceramic layer on a surface of the asymmetric porous ceramic tube by using a phase inversion process. The tube is co-sintered to form a structure having a first porous layer, a second porous layer, and a dense layer positioned therebetween.

Chen, Fanglin; Yang, Chenghao; Jin, Chao

2013-06-18T23:59:59.000Z

180

The evaluation of a coal-derived liquid as a feedstock for the production of high-density aviation turbine fuel  

DOE Green Energy (OSTI)

The conversion of coal-derived liquids to transportation fuels has been the subject of many studies sponsored by the US Department of Energy and the US Department of Defense. For the most part, these studies evaluated conventional petroleum processes for the production of specification-grade fuels. Recently, however, the interest of these two departments expanded to include the evaluation of alternate fossil fuels as a feedstock for the production of high-density aviation turbine fuel. In this study, we evaluated five processes for their ability to produce intermediates from a coal-derived liquid for the production of high-density turbine fuel. These processes include acid-base extraction to reduce the heteroatom content of the middle distillate and the atmospheric and vacuum gas oils, solvent dewaxing to reduce the paraffin (alkane) content of the atmospheric and vacuum gas oils, Attapulgus clay treatment to reduce the heteroatom content of the middle distillate, coking to reduce the distillate range of the vacuum gas oil, and hydrogenation to remove heteroatoms and to saturate aromatic rings in the middle distillate and atmospheric gas oil. The chemical and physical properties that the US Air Force considers critical for the development of high-denisty aviation turbine fuel are specific gravity and net heat of combustion. The target minimum values for these properties are a specific gravity of at least 0.85 and a net heat of combustion of at least 130,000 Btu/gal. In addition, the minimum hydrogen content is 13.0 wt %, the maximum freeze point is {minus}53{degrees}F ({minus}47{degrees}C), the maximum amount of aromatics is about 25 to 30 vol %, and the maximum amount of paraffins is 10 vol %. 13 refs., 20 tabs.

Thomas, K.P.; Hunter, D.E.

1989-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "high grade fuel" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

HIGH EFFICIENCY, LOW EMISSIONS, SOLID OXIDE FUEL CELL SYSTEMS FOR MULTIPLE APPLICATIONS  

DOE Green Energy (OSTI)

Technology Management Inc. (TMI), teamed with the Ohio Office of Energy Efficiency and Renewable Energy, has engineered, constructed, and demonstrated a stationary, low power, multi-module solid oxide fuel cell (SOFC) prototype system operating on propane and natural gas. Under Phase I, TMI successfully operated two systems in parallel, in conjunction with a single DC-AC inverter and battery bus, and produced net AC electricity. Phase II testing expanded to include alternative and renewable fuels typically available in rural regions of Ohio. The commercial system is expected to have ultra-low pollution, high efficiency, and low noise. The TMI SOFC uses a solid ceramic electrolyte operating at high temperature (800-1000 C) which electrochemically converts gaseous fuels (hydrogen or mixed gases) and oxygen into electricity. The TMI system design oxidizes fuel primarily via electrochemical reactions and uses no burners (which pollute and consume fuel)--resulting in extremely clean exhaust. The use of proprietary sulfur tolerant materials developed by TMI allows system operation without additional fuel pre-processing or sulfur removal. Further, the combination of high operating temperatures and solid state operation increases the potential for higher reliability and efficiencies compared to other types of fuel cells. Applications for the TMI SOFC system cover a wide range of transportation, building, industrial, and military market sectors. A generic technology, fuel cells have the potential to be embodied into multiple products specific to Department of Energy (DOE) Office of Energy Efficiency and Renewable Energy (EERE) program areas including: Fuel Cells and Microturbines, School Buildings, Transportation, and Bioenergy. This program focused on low power stationary applications using a multi-module system operating on a range of common fuels. By producing clean electricity more efficiently (thus using less fuel), fuel cells have the triple effect of cleaning up the environment, reducing the amount of fuel consumed and, for energy intensive manufacturers, boosting their profits (by reducing energy expenses). Compared to conventional power generation technologies such as internal combustion engines, gas turbines, and coal plants, fuel cells are extremely clean and more efficient, particularly at smaller scales.

Sara Ward; Michael A. Petrik

2004-07-28T23:59:59.000Z

182

High-Grade Glioma Relationship to the Neural Stem Cell Compartment: A Retrospective Review of 104 Cases  

Science Conference Proceedings (OSTI)

Purpose: To assess the incidence of involvement of the neural stem cell (NSC) compartment by high-grade astrocytomas in a series of adult patients. Methods and Materials: One hundred four initial diagnostic cranial magnetic resonance imaging series were reviewed. For each series, the gross tumor volume (GTV; enhancing tumor on T{sub 1}), edema (hyperintensity on T{sub 2} FLAIR), and the NSC compartment (hippocampal formation and lateral ventricle plus a 5-mm expansion) were identified. Involvement of NSC by GTV and edema was assessed. For tumors not involving NSC, we measured distances from NSC to GTV and edema. Maximum diameters of GTV were measured for each case. Subset analysis was performed for GTV of {<=}2 cm and {<=}3 cm in maximum diameter to assess the incidence of involvement of NSC by this group of smaller tumors. For 10 representative tumors, minimum distances from GTV center to NSC were calculated. Results: A total of 103/104 (99.0%) tumors, regardless of GTV maximum diameter, demonstrated involvement of NSC. A total of 101/104 (97.1%) tumors had NSC involvement by GTV, and 2/104 (1.9%) patients showed edema only. For GTV not involving NSC, the mean distance from NSC to GTV was 0.8 cm (range, 0.5--1.4 cm). The mean shortest distance from the center of GTV to NSC was 1.5 cm (range, 0.9--2.6 cm). Involvement of NSC by GTV was 90.9% (10/11 tumors) for GTV of {<=}2 cm and 95.7% (22/23 tumors) for GTV of {<=}3 cm. Conclusions: Our results support the hypothesis that the NSC compartment represents the putative site of origin for these tumors. NSC involvement does not appear to represent a volumetric phenomenon.

Marsh, James C., E-mail: james_c_marsh@rush.edu [Department of Radiation Oncology, Rush University Medical Center, Chicago, Illinois (United States); Wendt, Julie A. [Silver Cross Hospital, Joliet, Illinois (United States); Herskovic, Arnold M.; Diaz, Aidnag; Gielda, Benjamin T. [Department of Radiation Oncology, Rush University Medical Center, Chicago, Illinois (United States); Byrne, Richard W. [Department of Neurosurgery, Rush University Medical Center, Chicago, Illinois (United States)

2012-02-01T23:59:59.000Z

183

Spent Fuel and High-Level Waste Requirements (Maine) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Spent Fuel and High-Level Waste Requirements (Maine) Spent Fuel and High-Level Waste Requirements (Maine) Spent Fuel and High-Level Waste Requirements (Maine) < Back Eligibility Agricultural Commercial Construction Fed. Government Fuel Distributor General Public/Consumer Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Low-Income Residential Multi-Family Residential Municipal/Public Utility Nonprofit Residential Retail Supplier Rural Electric Cooperative Schools State/Provincial Govt Systems Integrator Transportation Tribal Government Utility Program Info State Maine Program Type Safety and Operational Guidelines Provider Public Utilities Commission All proposed nuclear power generation facilities must be certified by the Public Utilities Commission under this statute prior to construction and

184

Advanced Fuel/Cladding Testing Capabilities in the ORNL High Flux Isotope Reactor  

Science Conference Proceedings (OSTI)

The ability to test advanced fuels and cladding materials under reactor operating conditions in the United States is limited. The Oak Ridge National Laboratory (ORNL) High Flux Isotope Reactor (HFIR) and the newly expanded post-irradiation examination (PIE) capability at the ORNL Irradiated Fuels Examination Laboratory provide unique support for this type of advanced fuel/cladding development effort. The wide breadth of ORNL's fuels and materials research divisions provides all the necessary fuel development capabilities in one location. At ORNL, facilities are available from test fuel fabrication, to irradiation in HFIR under either thermal or fast reactor conditions, to a complete suite of PIEs, and to final product disposal. There are very few locations in the world where this full range of capabilities exists. New testing capabilities at HFIR have been developed that allow testing of advanced nuclear fuels and cladding materials under prototypic operating conditions (i.e., for both fast-spectrum conditions and light-water-reactor conditions). This paper will describe the HFIR testing capabilities, the new advanced fuel/cladding testing facilities, and the initial cooperative irradiation experiment that begins this year.

Ott, Larry J [ORNL; Ellis, Ronald James [ORNL; McDuffee, Joel Lee [ORNL; Spellman, Donald J [ORNL; Bevard, Bruce Balkcom [ORNL

2009-01-01T23:59:59.000Z

185

The Advanced High-Temperature Reactor (AHTR) for Producing Hydrogen to Manufacture Liquid Fuels  

DOE Green Energy (OSTI)

Conventional world oil production is expected to peak within a decade. Shortfalls in production of liquid fuels (gasoline, diesel, and jet fuel) from conventional oil sources are expected to be offset by increased production of fuels from heavy oils and tar sands that are primarily located in the Western Hemisphere (Canada, Venezuela, the United States, and Mexico). Simultaneously, there is a renewed interest in liquid fuels from biomass, such as alcohol; but, biomass production requires fertilizer. Massive quantities of hydrogen (H2) are required (1) to convert heavy oils and tar sands to liquid fuels and (2) to produce fertilizer for production of biomass that can be converted to liquid fuels. If these liquid fuels are to be used while simultaneously minimizing greenhouse emissions, nonfossil methods for the production of H2 are required. Nuclear energy can be used to produce H2. The most efficient methods to produce H2 from nuclear energy involve thermochemical cycles in which high-temperature heat (700 to 850 C) and water are converted to H2 and oxygen. The peak nuclear reactor fuel and coolant temperatures must be significantly higher than the chemical process temperatures to transport heat from the reactor core to an intermediate heat transfer loop and from the intermediate heat transfer loop to the chemical plant. The reactor temperatures required for H2 production are at the limits of practical engineering materials. A new high-temperature reactor concept is being developed for H2 and electricity production: the Advanced High-Temperature Reactor (AHTR). The fuel is a graphite-matrix, coated-particle fuel, the same type that is used in modular high-temperature gas-cooled reactors (MHTGRs). The coolant is a clean molten fluoride salt with a boiling point near 1400 C. The use of a liquid coolant, rather than helium, reduces peak reactor fuel and coolant temperatures 100 to 200 C relative to those of a MHTGR. Liquids are better heat transfer fluids than gases and thus reduce three temperature losses in the system associated with (1) heat transfer from the fuel to the reactor coolant, (2) temperature rise across the reactor core, and (3) heat transfer across the heat exchangers between the reactor and H2 production plant. Lowering the peak reactor temperatures and thus reducing the high-temperature materials requirements may make the AHTR the enabling technology for low-cost nuclear hydrogen production.

Forsberg, C.W.; Peterson, P.F.; Ott, L.

2004-10-06T23:59:59.000Z

186

Fuel Cell Technologies Office: 2006 High Temperature Membrane...  

NLE Websites -- All DOE Office Websites (Extended Search)

Systems for High Temperature, Low Relative Humidity Polymer-Type Membranes, Andrew Herring, Colorado School of Mines (PDF 213 KB) Design and Development of High-Performance...

187

Final Technical Report, Oct 2004 - Nov. 2006, High Performance Flexible Reversible Solid Oxide Fuel Cell  

SciTech Connect

This report summarizes the work performed for the program entitled “High Performance Flexible Reversible Solid Oxide Fuel Cell” under Cooperative Agreement DE-FC36-04GO14351 for the U. S. Department of Energy. The overall objective of this project is to demonstrate a single modular stack that generates electricity from a variety of fuels (hydrogen and other fuels such as biomass, distributed natural gas, etc.) and when operated in the reverse mode, produces hydrogen from steam. This project has evaluated and selected baseline cell materials, developed a set of materials for oxygen and hydrogen electrodes, and optimized electrode microstructures for reversible solid oxide fuel cells (RSOFCs); and demonstrated the feasibility and operation of a RSOFC multi-cell stack. A 10-cell reversible SOFC stack was operated over 1000 hours alternating between fuel cell (with hydrogen and methane as fuel) and steam electrolysis modes. The stack ran very successfully with high power density of 480 mW/cm2 at 0.7V and 80% fuel utilization in fuel cell mode and >6 SLPM hydrogen production in steam electrolysis mode using about 1.1 kW electrical power. The hydrogen generation is equivalent to a specific capability of 2.59 Nm3/m2 with electrical energy demand of 3 kWh/Nm3. The performance stability in electrolysis mode was improved vastly during the program with a degradation rate reduction from 8000 to 200 mohm-cm2/1000 hrs. This was accomplished by increasing the activity and improving microstructure of the oxygen electrode. Both cost estimate and technology assessment were conducted. Besides the flexibility running under both fuel cell mode and electrolysis mode, the reversible SOFC system has the potentials for low cost and high efficient hydrogen production through steam electrolysis. The cost for hydrogen production at large scale was estimated at ~$2.7/kg H2, comparing favorably with other electrolysis techology.

Guan, Jie; Minh, Nguyen

2007-02-21T23:59:59.000Z

188

A disposition strategy for highly enriched, aluminum-based fuel from research and test reactors  

SciTech Connect

The strategy proposed in this paper offers the Department of Energy an approach for disposing of aluminum-based, highly enriched uranium (HEU) spent fuels from foreign and domestic research reactors. The proposal is technically, socially, and economically sound. If implemented, it would advance US non-proliferation goals while also disposing of the spent fuel`s waste by timely and proven methods using existing technologies and facilities at SRS without prolonged and controversial storage of the spent fuel. The fuel would be processed through 221-H. The radioactive fission products (waste) would be treated along with existing SRS high level waste by vitrifying it as borosilicate glass in the Defense Waste Processing Facility (DWPF) for disposal in the national geological repository. The HEU would be isotopically diluted, during processing, to low-enriched uranium (LEU) which can not be used to make weapons, thus eliminating proliferation concerns. The LEU can be sold to fabricators of either research reactor fuel or commercial power fuel. This proposed processing-LEU recycle approach has several important advantages over other alternatives, including: Lowest capital investment; lowest net total cost; quickest route to acceptable waste form and final geologic disposal; and likely lowest safety, health, and environmental impacts.

McKibben, J.M.; Gould, T.H.; McDonell, W.R.; Bickford, W.E.

1994-11-01T23:59:59.000Z

189

Materials and Modules for Low Cost, High Performance Fuel Cell Humidifiers  

NLE Websites -- All DOE Office Websites (Extended Search)

Kick-off Meeting, Kick-off Meeting, Wash. D.C - 10/01/2009 Materials and Modules for Low Cost, High Performance Fuel Cell Humidifiers Prime Contractor: W. L. Gore & Associates Elkton, MD Principal Investigator: William B. Johnson Sub-Contractor: dPoint Technologies Vancouver, BC W. L. Gore & Associates, Inc. DOE Kick-off Meeting, Wash. D.C - 10/01/2009 Ahluwalia, et. al, ibid. Mirza, Z. DOE Hydrogen Program Review, June 9-13, 2008; Washington, DC Background W. L. Gore & Associates, Inc. DOE Kick-off Meeting, Wash. D.C - 10/01/2009 Objective and Technical Barriers Addressed More efficient, low-cost humidifiers can increase fuel cell inlet humidity: Reduce system cost and size of balance of plant; Improve fuel cell performance; Improve fuel cell durability. OBJECTIVE: Demonstrate a durable, high performance water

190

G. Uniform Engine Fuels and Automotive Lubricants ...  

Science Conference Proceedings (OSTI)

... 3.6. Fuel Oils. 3.6.1. Labeling of Grade Required. – Fuel Oil shall be identified by the grades of No. ... 3.10. Liquefied Petroleum Gas (LPG). ...

2013-10-25T23:59:59.000Z

191

High Performance Catalytic Heat Exchanger for SOFC Systems - FuelCell Energy  

NLE Websites -- All DOE Office Websites (Extended Search)

Catalytic Heat Catalytic Heat Exchanger for SOFC Systems-FuelCell Energy Background In a typical solid oxide fuel cell (SOFC) power generation system, hot (~900 °C) effluent gas from a catalytic combustor serves as the heat source within a high-temperature heat exchanger, preheating incoming fresh air for the SOFC's cathode. The catalytic combustor and the cathode air heat exchanger together represent the largest opportunity for cost

192

Coal-fueled high-speed diesel engine development: Task 2, Market assessment and economic analysis  

DOE Green Energy (OSTI)

Based on the preliminary coal engine design developed, this task was conducted to identify the best opportunity(s) to enter the market with the future coal-fueled, high-speed diesel engine. The results of this market and economic feasibility assessment will be used to determine what specific heavy duty engine application(s) are most attractive for coal fuel, and also define basic economic targets for the engine to be competitive.

Not Available

1991-12-01T23:59:59.000Z

193

Advanced LWR Fuel Testing Capabilities in the ORNL High Flux Isotope Reactor  

Science Conference Proceedings (OSTI)

A new test capability for the High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory (ORNL) is being developed that will allow testing of advanced nuclear fuels and cladding materials under prototypic light-water reactor (LWR) operating conditions in less time than it takes in other research reactors. This paper will describe the HFIR testing capabilities, the new advanced fuel/cladding testing facilities, and the initial cooperative irradiation experiments currently planned to start in late 2008.

Ott, Larry J [ORNL; McDuffee, Joel Lee [ORNL; Spellman, Donald J [ORNL

2008-01-01T23:59:59.000Z

194

Test and Evaluation of a High Efficiency Residential Fuel Cell System  

Science Conference Proceedings (OSTI)

A confluence of industry drivers, including the availability of low-cost natural gas, is creating new market opportunities for natural gas-based distributed generation. Solid oxide fuel cell systems (SOFC) are a potentially attractive option because of their high electrical efficiency (50–60% lower heating value (LHV)). This report documents two years of testing and evaluation of a 1.5 kW SOFC residential system provided by Ceramics Fuel Cell Limited. Tests were conducted in collaboration with ...

2013-12-20T23:59:59.000Z

195

High Strength Carbon Fibers - DOE Hydrogen and Fuel Cells Program...  

NLE Websites -- All DOE Office Websites (Extended Search)

System and yielding 15 Msi modulus and 150 ksi. Technical Barriers High-strength carbon fibers account for approximately 65% of the cost of the high-pressure storage tanks....

196

Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation - Vandellos II Reactor  

Science Conference Proceedings (OSTI)

This report is one of the several recent NUREG/CR reports documenting benchmark-quality radiochemical assay data and the use of the data to validate computer code predictions of isotopic composition for spent nuclear fuel, to establish the uncertainty and bias associated with code predictions. The experimental data analyzed in the current report were acquired from a high-burnup fuel program coordinated by Spanish organizations. The measurements included extensive actinide and fission product data of importance to spent fuel safety applications, including burnup credit, decay heat, and radiation source terms. Six unique spent fuel samples from three uranium oxide fuel rods were analyzed. The fuel rods had a 4.5 wt % {sup 235}U initial enrichment and were irradiated in the Vandellos II pressurized water reactor operated in Spain. The burnups of the fuel samples range from 42 to 78 GWd/MTU. The measurements were used to validate the two-dimensional depletion sequence TRITON in the SCALE computer code system.

Ilas, Germina [ORNL; Gauld, Ian C [ORNL

2011-01-01T23:59:59.000Z

197

A Phase I Study of the Combination of Sorafenib With Temozolomide and Radiation Therapy for the Treatment of Primary and Recurrent High-Grade Gliomas  

SciTech Connect

Purpose: Despite recent advances in the management of high-grade and recurrent gliomas, survival remains poor. Antiangiogenic therapy has been shown to be efficacious in the treatment of high-grade gliomas both in preclinical models and in clinical trials. We sought to determine the safety and maximum tolerated dose of sorafenib when combined with both radiation and temozolomide in the primary setting or radiation alone in the recurrent setting. Methods and Materials: This was a preclinical study and an open-label phase I dose escalation trial. Multiple glioma cell lines were analyzed for viability after treatment with radiation, temozolomide, or sorafenib or combinations of them. For patients with primary disease, sorafenib was given concurrently with temozolomide (75 mg/m{sup 2}) and 60 Gy radiation, for 30 days after completion of radiation. For patients with recurrent disease, sorafenib was combined with a hypofractionated course of radiation (35 Gy in 10 fractions). Results: Cell viability was significantly reduced with the combination of radiation, temozolomide, and sorafenib or radiation and sorafenib. Eighteen patients (11 in the primary cohort, 7 in the recurrent cohort) were enrolled onto this trial approved by the institutional review board. All patients completed the planned course of radiation therapy. The most common toxicities were hematologic, fatigue, and rash. There were 18 grade 3 or higher toxicities. The median overall survival was 18 months for the entire population. Conclusions: Sorafenib can be safely combined with radiation and temozolomide in patients with high-grade glioma and with radiation alone in patients with recurrent glioma. The recommended phase II dose of sorafenib is 200 mg twice daily when combined with temozolomide and radiation and 400 mg with radiation alone. To our knowledge, this is the first publication of concurrent sorafenib with radiation monotherapy or combined with radiation and temozolomide.

Den, Robert B., E-mail: robert.den@jeffersonhospital.org [Department of Radiation Oncology, Jefferson Medical College of Thomas Jefferson University, Philadelphia, Pennsylvania (United States); Kamrava, Mitchell [Radiation Oncology Branch, National Cancer Institute, Bethesda, Maryland (United States)] [Radiation Oncology Branch, National Cancer Institute, Bethesda, Maryland (United States); Sheng, Zhi [Howard Hughes Medical Institute, Programs in Gene Function and Expression and Molecular Medicine, University of Massachusetts Medical School, Worcester, Massachusetts (United States)] [Howard Hughes Medical Institute, Programs in Gene Function and Expression and Molecular Medicine, University of Massachusetts Medical School, Worcester, Massachusetts (United States); Werner-Wasik, Maria; Dougherty, Erin; Marinucchi, Michelle [Department of Radiation Oncology, Jefferson Medical College of Thomas Jefferson University, Philadelphia, Pennsylvania (United States)] [Department of Radiation Oncology, Jefferson Medical College of Thomas Jefferson University, Philadelphia, Pennsylvania (United States); Lawrence, Yaacov R. [Department of Radiation Oncology, Jefferson Medical College of Thomas Jefferson University, Philadelphia, Pennsylvania (United States) [Department of Radiation Oncology, Jefferson Medical College of Thomas Jefferson University, Philadelphia, Pennsylvania (United States); Center for Translational Research in Radiation Oncology, Sheba Medical Center (Israel); Hegarty, Sarah; Hyslop, Terry [Department of Biostatistics, Jefferson Medical College of Thomas Jefferson University, Philadelphia, Pennsylvania (United States)] [Department of Biostatistics, Jefferson Medical College of Thomas Jefferson University, Philadelphia, Pennsylvania (United States); Andrews, David W.; Glass, Jon [Department of Neurosurgery, Jefferson Medical College of Thomas Jefferson University, Philadelphia, Pennsylvania (United States)] [Department of Neurosurgery, Jefferson Medical College of Thomas Jefferson University, Philadelphia, Pennsylvania (United States); Friedman, David P. [Department of Radiology, Jefferson Medical College of Thomas Jefferson University, Philadelphia, Pennsylvania (United States)] [Department of Radiology, Jefferson Medical College of Thomas Jefferson University, Philadelphia, Pennsylvania (United States); Green, Michael R. [Howard Hughes Medical Institute, Programs in Gene Function and Expression and Molecular Medicine, University of Massachusetts Medical School, Worcester, Massachusetts (United States)] [Howard Hughes Medical Institute, Programs in Gene Function and Expression and Molecular Medicine, University of Massachusetts Medical School, Worcester, Massachusetts (United States); Camphausen, Kevin [Radiation Oncology Branch, National Cancer Institute, Bethesda, Maryland (United States)] [Radiation Oncology Branch, National Cancer Institute, Bethesda, Maryland (United States); Dicker, Adam P. [Department of Radiation Oncology, Jefferson Medical College of Thomas Jefferson University, Philadelphia, Pennsylvania (United States)] [Department of Radiation Oncology, Jefferson Medical College of Thomas Jefferson University, Philadelphia, Pennsylvania (United States)

2013-02-01T23:59:59.000Z

198

Deep Burn: Development of Transuranic Fuel for High-Temperature Helium-Cooled Reactors- Monthly Highlights October 2010  

Science Conference Proceedings (OSTI)

The DB Program monthly highlights report for September 2010, ORNL/TM-2010/252, was distributed to program participants by email on October 26. This report discusses: (1) Core and Fuel Analysis; (2) Spent Fuel Management; (3) Fuel Cycle Integration of the HTR (high temperature helium-cooled reactor); (4) TRU (transuranic elements) HTR Fuel Qualification; (5) HTR Spent Fuel Recycle - (a) TRU Kernel Development (ORNL), (b) Coating Development (ORNL), (c) Characterization Development and Support, (d) ZrC Properties and Handbook; and (6) HTR Fuel Recycle.

Snead, Lance Lewis [ORNL; Besmann, Theodore M [ORNL; Collins, Emory D [ORNL; Bell, Gary L [ORNL

2010-11-01T23:59:59.000Z

199

HIGH-TEMPERATURE TUBULAR SOLID OXIDE FUEL CELL GENERATOR DEVELOPMENT  

DOE Green Energy (OSTI)

During the Westinghouse/USDOE Cooperative Agreement period of November 1, 1990 through November 30, 1997, the Westinghouse solid oxide fuel cell has evolved from a 16 mm diameter, 50 cm length cell with a peak power of 1.27 watts/cm to the 22 mm diameter, 150 cm length dimensions of today's commercial prototype cell with a peak power of 1.40 watts/cm. Accompanying the increase in size and power density was the elimination of an expensive EVD step in the manufacturing process. Demonstrated performance of Westinghouse's tubular SOFC includes a lifetime cell test which ran for a period in excess of 69,000 hours, and a fully integrated 25 kWe-class system field test which operated for over 13,000 hours at 90% availability with less than 2% performance degradation over the entire period. Concluding the agreement period, a 100 kW SOFC system successfully passed its factory acceptance test in October 1997 and was delivered in November to its demonstration site in Westervoort, The Netherlands.

S.E. Veyo

1998-09-01T23:59:59.000Z

200

Criticality issues with highly enriched fuels in a repository environment  

SciTech Connect

This paper presents preliminary analysis of a volcanic tuff repository containing a combination of low enrichment commercial spent nuclear fuels (SNF) and DOE-owned SNF packages. These SNFs were analyzed with respect to their criticality risks. Disposal of SNF packages containing significant fissile mass within a geologic repository must comply with current regulations relative to criticality safety during transportation and handling within operational facilities. However, once the repository is closed, the double contingency credits for criticality safety are subject to unremediable degradation, (e.g., water intrusion, continued presence of neutron absorbers in proximity to fissile material, and fissile material reconfiguration). The work presented in this paper focused on two attributes of criticality in a volcanic tuff repository for near-field and far-field scenarios: (1) scenario conditions necessary to have a criticality, and (2) consequences of a nuclear excursion that are components of risk. All criticality consequences are dependent upon eventual water intrusion into the repository and subsequent breach of the disposal package. Key criticality parameters necessary for a critical assembly are: (1) adequate thermal fissile mass, (2) adequate concentration of fissile material, (3) separation of neutron poison from fissile materials, and (4) sufficient neutron moderation (expressed in units of moderator to fissile atom ratios). Key results from this study indicated that the total energies released during a single excursion are minimal (comparable to those released in previous solution accidents), and the maximum frequency of occurrence is bounded by the saturation and temperature recycle times, thus resulting in small criticality risks.

Taylor, L.L. [Lockheed Martin Idaho Technologies Co., Idaho Falls, ID (United States); Sanchez, L.C.; Rath, J.S. [Sandia National Labs., Albuquerque, NM (United States)

1998-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "high grade fuel" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

Fuel Cell Technologies Office: 2003 High Temperature Membrane...  

NLE Websites -- All DOE Office Websites (Extended Search)

in New Electrolytes, Bryan Pivovar, LANL (PDF 731 KB) Hetero-Polyacids, Andrew Herring, Colorado School of Mines (PDF 5 MB) New Polymeric Proton Conductors for High...

202

Core-Protected Platinum Monolayer Shell High-Stability Electrocatalysts for Fuel-Cell Cathodes  

Science Conference Proceedings (OSTI)

Platinum monolayers can act as shells for palladium nanoparticles to lead to electrocatalysts with high activities and an ultralow platinum content, but high platinum utilization. The stability derives from the core protecting the shell from dissolution. In fuel-cell tests, no loss of platinum was observed in 200,000 potential cycles, whereas loss of palladium was significant.

K Sasaki; H Naohara; Y Cai; Y Choi; P Liu; M Vukmirovic; J Wang; R Adzic

2011-12-31T23:59:59.000Z

203

Shutdown Margin for High Conversion BWRs Operating in Th-233U Fuel Cycle  

E-Print Network (OSTI)

Several reactivity control system design options are explored in order to satisfy shutdown margin (SDM) requirements in a high conversion BWRs operating in Th-233U fuel cycle (Th-RBWR). The studied has an axially heterogeneous fuel assembly structure with a single fissile zone sandwiched between two fertile blanket zones. The utilization of an originally suggested RBWR Y-shape control rod in Th-RBWR is shown to be insufficient for maintaining adequate SDM to balance the high negative reactivity feedbacks, while maintaining fuel breeding potential, core power rating, and minimum Critical Power Ratio (CPR). Instead, an alternative assembly design, also relying on heterogeneous fuel zoning, is proposed for achieving fissile inventory ratio (FIR) above unity, adequate SDM and meeting minimum CPR limit at thermal core output matching the ABWR power. The new concept was modeled as a single 3-dimensional fuel assembly having reflective radial boundaries, using the BGCore system, which consists of the MCNP code coupled with fuel depletion and thermo-hydraulic feedback modules.

Yaniv Shaposhnik; Eugene Shwageraus; Ezra Elias

2013-09-27T23:59:59.000Z

204

AIR SHIPMENT OF HIGHLY ENRICHED URANIUM SPENT NUCLEAR FUEL FROM ROMANIA AND LIBYA  

SciTech Connect

In June 2009 Romania successfully completed the world’s first air shipment of highly enriched uranium (HEU) spent nuclear fuel transported in Type B(U) casks under existing international laws and without special exceptions for the air transport licenses. Special 20-foot ISO shipping containers and cask tiedown supports were designed to transport Russian TUK 19 shipping casks for the Romanian air shipment and the equipment was certified for all modes of transport, including road, rail, water, and air. In December 2009 Libya successfully used this same equipment for a second air shipment of HEU spent nuclear fuel. Both spent fuel shipments were transported by truck from the originating nuclear facilities to nearby commercial airports, were flown by commercial cargo aircraft to a commercial airport in Yekaterinburg, Russia, and then transported by truck to their final destinations at the Production Association Mayak facility in Chelyabinsk, Russia. Both air shipments were performed under the Russian Research Reactor Fuel Return Program (RRRFR) as part of the U.S. National Nuclear Security Administration (NNSA) Global Threat Reduction Initiative (GTRI). The Romania air shipment of 23.7 kg of HEU spent fuel from the VVR S research reactor was the last of three HEU fresh and spent fuel shipments under RRRFR that resulted in Romania becoming the 3rd RRRFR participating country to remove all HEU. Libya had previously completed two RRRFR shipments of HEU fresh fuel so the 5.2 kg of HEU spent fuel air shipped from the IRT 1 research reactor in December made Libya the 4th RRRFR participating country to remove all HEU. This paper describes the equipment, preparations, and license approvals required to safely and securely complete these two air shipments of spent nuclear fuel.

Christopher Landers; Igor Bolshinsky; Ken Allen; Stanley Moses

2010-07-01T23:59:59.000Z

205

Vortex combustor for low NOX emissions when burning lean premixed high hydrogen content fuel  

Science Conference Proceedings (OSTI)

A trapped vortex combustor. The trapped vortex combustor is configured for receiving a lean premixed gaseous fuel and oxidant stream, where the fuel includes hydrogen gas. The trapped vortex combustor is configured to receive the lean premixed fuel and oxidant stream at a velocity which significantly exceeds combustion flame speed in a selected lean premixed fuel and oxidant mixture. The combustor is configured to operate at relatively high bulk fluid velocities while maintaining stable combustion, and low NOx emissions. The combustor is useful in gas turbines in a process of burning synfuels, as it offers the opportunity to avoid use of diluent gas to reduce combustion temperatures. The combustor also offers the possibility of avoiding the use of selected catalytic reaction units for removal of oxides of nitrogen from combustion gases exiting a gas turbine.

Steele, Robert C; Edmonds, Ryan G; Williams, Joseph T; Baldwin, Stephen P

2012-11-20T23:59:59.000Z

206

Vortex combustor for low NOx emissions when burning lean premixed high hydrogen content fuel  

DOE Patents (OSTI)

A trapped vortex combustor. The trapped vortex combustor is configured for receiving a lean premixed gaseous fuel and oxidant stream, where the fuel includes hydrogen gas. The trapped vortex combustor is configured to receive the lean premixed fuel and oxidant stream at a velocity which significantly exceeds combustion flame speed in a selected lean premixed fuel and oxidant mixture. The combustor is configured to operate at relatively high bulk fluid velocities while maintaining stable combustion, and low NOx emissions. The combustor is useful in gas turbines in a process of burning synfuels, as it offers the opportunity to avoid use of diluent gas to reduce combustion temperatures. The combustor also offers the possibility of avoiding the use of selected catalytic reaction units for removal of oxides of nitrogen from combustion gases exiting a gas turbine.

Steele, Robert C. (Woodinville, WA); Edmonds, Ryan G. (Renton, WA); Williams, Joseph T. (Kirkland, WA); Baldwin, Stephen P. (Winchester, MA)

2009-10-20T23:59:59.000Z

207

High conversion Th-U{sup 233} fuel assembly for current generation of PWRs  

SciTech Connect

This paper presents a preliminary design of a high conversion Th-U{sup 233} fuel assembly applicable for current generation of Pressurized Water Reactor (PWRs). The considered fuel assembly has a typical 17 x 17 PWR lattice. However in order to increase the conversion of Th{sup 232} to U{sup 233}, the assembly was subdivided into the two regions called seed and blanket. The central seed region has a higher than blanket U{sup 233} content and acts as a neutron source for the peripheral blanket region. The latest acts as a U{sup 233} breeder. While the seed fuel pins have a standard dimensions the blanket fuel radius was increased in order to reduce the moderation and to facilitate the resonance neutron absorption in blanket Th{sup 232}. The U{sup 233} content in the seed and blanket regions was optimized to achieve maximal initial to discharged fissile inventory ratio (FIR) taking into account the target fuel cycle length of 12 months with 3-batch reloading scheme. In this study the neutronic calculations were performed on the fuel assembly level using Helios deterministic lattice transport code. The fuel cycle length and the core k{sub eff} were estimated by applying the Non Linear Reactivity Model. The applicability of the HELIOS code for the analysis of the Th-based high conversion designs was confirmed with the help of continuous-energy Monte-Carlo code SERPENT. The results of optimization studies show that for the heterogeneous seed and blanket (SB) fuel assembly the FIR of about 0.95 can be achieved. (authors)

Baldova, D.; Fridman, E. [Reactor Safety Div., Helmholtz-Zentrum Dresden-Rossendorf, POB 510119, Dresden, 01314 (Germany)

2012-07-01T23:59:59.000Z

208

High-energy-density solid and liquid hydrocarbon fuels. Final report, July 1987-December 1988  

Science Conference Proceedings (OSTI)

The development of new high-energy hydrocarbon fuels for use in air-breathing missiles has been the objective of a number of investigations which have received support during the past decade through programs sponsored by the Air Force Systems Command and/or the Naval Air Systems Command. The key characteristics which must be met by potential cruise missile fuels have been described by Burdette and coworkers. A primary requirement in this regard is that candidate fuels must possess high net volumetric heat of combustion (preferably greater than 160,000 BTU/gallon). In order to meet the primary requirement of high net volumetric heat of combustion, hydrocarbon systems have been sought which maximize the ratio of carbon-atom to hydrogen-atom content have been sought that maximize the ratio n/m.(JES)

Marchand, A.P.

1989-02-01T23:59:59.000Z

209

Fuel Cell Technologies Office: High-Throughput/Combinatorial...  

NLE Websites -- All DOE Office Websites (Extended Search)

High-ThroughputCombinatorial Techniques in Hydrogen Storage Materials R&D On June 26, 2007 the Hydrogen Storage Program of the U.S. Department of Energy (DOE) held a one-day...

210

Design of annular fuel for high power density BWRs  

E-Print Network (OSTI)

Enabling high power density in the core of Boiling Water Reactors (BWRs) is economically profitable for existing or new reactors. In this work, we examine the potential for increasing the power density in BWR plants by ...

Morra, Paolo

2005-01-01T23:59:59.000Z

211

High-uranium-loaded U/sub 3/O/sub 8/--Al fuel element development program  

SciTech Connect

The High-Uranium-Loaded U/sub 3/O/sub 8/--Al Fuel Development Program supports Argonne National Laboratory efforts to develop high-uranium-density research and test reactor fuel to accommodate use of low-uranium enrichment. The goal is to fuel most research and test reactors with uranium of less than 20% enrichment for the purpose of lowering the potential for diversion of highly-enriched material for nonpeaceful usages.

Martin, M.M.

1978-01-01T23:59:59.000Z

212

Comparison of selected foreign plans and practices for spent fuel and high-level waste management  

Science Conference Proceedings (OSTI)

This report describes the major parameters for management of spent nuclear fuel and high-level radioactive wastes in selected foreign countries as of December 1989 and compares them with those in the United States. The foreign countries included in this study are Belgium, Canada, France, the Federal Republic of Germany, Japan, Sweden, Switzerland, and the United Kingdom. All the countries are planning for disposal of spent fuel and/or high-level wastes in deep geologic repositories. Most countries (except Canada and Sweden) plan to reprocess their spent fuel and vitrify the resultant high-level liquid wastes; in comparison, the US plans direct disposal of spent fuel. The US is planning to use a container for spent fuel as the primary engineered barrier. The US has the most developed repository concept and has one of the earliest scheduled repository startup dates. The repository environment presently being considered in the US is unique, being located in tuff above the water table. The US also has the most prescriptive regulations and performance requirements for the repository system and its components. 135 refs., 8 tabs.

Schneider, K.J.; Mitchell, S.J.; Lakey, L.T.; Johnson, A.B. Jr.; Hazelton, R.F.; Bradley, D.J.

1990-04-01T23:59:59.000Z

213

Liquid Fuel Production from Biomass via High Temperature Steam Electrolysis  

DOE Green Energy (OSTI)

A process model of syngas production using high temperature electrolysis and biomass gasification is presented. Process heat from the biomass gasifier is used to heat steam for the hydrogen production via the high temperature steam electrolysis process. Hydrogen from electrolysis allows a high utilization of the biomass carbon for syngas production. Oxygen produced form the electrolysis process is used to control the oxidation rate in the oxygen-fed biomass gasifier. Based on the gasifier temperature, 94% to 95% of the carbon in the biomass becomes carbon monoxide in the syngas (carbon monoxide and hydrogen). Assuming the thermal efficiency of the power cycle for electricity generation is 50%, (as expected from GEN IV nuclear reactors), the syngas production efficiency ranges from 70% to 73% as the gasifier temperature decreases from 1900 K to 1500 K. Parametric studies of system pressure, biomass moisture content and low temperature alkaline electrolysis are also presented.

Grant L. Hawkes; Michael G. McKellar

2009-11-01T23:59:59.000Z

214

Durability of Low Pt Fuel Cells Operating at High Power Density  

NLE Websites -- All DOE Office Websites (Extended Search)

SPIRE Program Kickoff SPIRE Program Kickoff Topic 3A. Cell Degradation Studies / Degradation Studies Durability of Low Pt Fuel Cells Operating at High Power Density US DOE Fuel Cell Projects Kickoff Meeting DOE Award: DE-EE0000469 October 1 st , 2009 Program Objectives The objective of this program is to study and identify strategies to assure durability of fuel cells designed to meet DOE cost targets. Technical Barriers Barrier Approach Strategy A. Durability Reinforced, Stabilized Membrane MEA Partner Durability-Enhanced Electrodes Electrocatalyst/MEA Partner Optimized Operating Conditions Parametric model & experimental studies B. Cost Low Pt Loadings (0.2 mg/cm 2 ) Electrocatalyst/MEA Partner High Power Density (>1.0W/cm 2 ) Open Flowfield Stack Metallic Stack Architecture Incumbent Derivative

215

LNG Vehicle High-Pressure Fuel System and ''Cold Energy'' Utilization  

Science Conference Proceedings (OSTI)

A high-pressure fuel system for LNG vehicles with direct-injection natural gas engines has been developed and demonstrated on a heavy-duty truck. A new concept for utilizing the ''cold energy'' associated with LNG vehicles to generate mechanical power to drive auxiliary equipment (such as high-pressure fuel pumps) has also been developed and demonstrated in the laboratory. The high-pressure LNG fuel system development included the design and testing of a new type of cryogenic pump utilizes multiple chambers and other features to condense moderate quantities of sucked vapor and discharge supercritical LNG at 3,000 to 4,000 psi. The pump was demonstrated on a Class 8 truck with a Westport high-pressure direct-injection Cummins ISX engine. A concept that utilizes LNG's ''cold energy'' to drive a high-pressure fuel pump without engine attachments or power consumption was developed. Ethylene is boiled and superheated by the engine coolant, and it is cooled and condensed by rejecting h eat to the LNG. Power is extracted in a full-admission blowdown process, and part of this power is applied to pump the ethylene liquid to the boiler pressure. Tests demonstrated a net power output of 1.1. hp at 1.9 Lbm/min of LNG flow, which is adequate to isentropically pump the LNG to approximately 3,400 psi..

powers,Charles A.; Derbidge, T. Craig

2001-03-27T23:59:59.000Z

216

Experimental and Modeling Study of the Flammability of Fuel Tank Headspace Vapors from High Ethanol Content Fuels  

DOE Green Energy (OSTI)

Study determined the flammability of fuel tank headspace vapors as a function of ambient temperature for seven E85 fuel blends, two types of gasoline, and denatured ethanol at a low tank fill level.

Gardiner, D.; Bardon, M.; Pucher, G.

2008-10-01T23:59:59.000Z

217

High-pressure coal fuel processor development. Task 1, Proof of principle testing  

DOE Green Energy (OSTI)

The objective of Subtask 1.1 Engine Feasibility was to conduct research needed to establish the technical feasibility of ignition and stable combustion of directly injected, 3,000 psi, low-Btu gas with glow plug ignition assist at diesel engine compression ratios. This objective was accomplished by designing, fabricating, testing and analyzing the combustion performance of synthesized low-Btu coal gas in a single-cylinder test engine combustion rig located at the Caterpillar Technical Center engine lab in Mossville, Illinois. The objective of Subtask 1.2 Fuel Processor Feasibility was to conduct research needed to establish the technical feasibility of air-blown, fixed-bed, high-pressure coal fuel processing at up to 3,000 psi operating pressure, incorporating in-bed sulfur and particulate capture. This objective was accomplished by designing, fabricating, testing and analyzing the performance of bench-scale processors located at Coal Technology Corporation (subcontractor) facilities in Bristol, Virginia. These two subtasks were carried out at widely separated locations and will be discussed in separate sections of this report. They were, however, independent in that the composition of the synthetic coal gas used to fuel the combustion rig was adjusted to reflect the range of exit gas compositions being produced on the fuel processor rig. Two major conclusions resulted from this task. First, direct injected, ignition assisted Diesel cycle engine combustion systems can be suitably modified to efficiently utilize these low-Btu gas fuels. Second, high pressure gasification of selected run-of-the-mine coals in batch-loaded fuel processors is feasible. These two findings, taken together, significantly reduce the perceived technical risks associated with the further development of the proposed coal gas fueled Diesel cycle power plant concept.

Greenhalgh, M.L.

1992-11-01T23:59:59.000Z

218

High-temperature fuel cell research and development. Final technical status report, June 1977-September 1978  

DOE Green Energy (OSTI)

An initial survey of the literature produced a list of ceramic materials with properties which made them potential candidates for use in molten-carbonate fuel cell tiles or electrodes. Seven of the materials in the original list were dropped from consideration because of unfavorable thermodynamic properties; four materials were set aside because of high cost, lack of availability, or fabrication difficulties. Thirteen compositions were tested statically at 1000 K in a Li/sub 2/CO/sub 3/-K/sub 2/CO/sub 3/ bath under a dry CO/sub 2/ atmosphere. Only four of the materials tested showed severe degradation reactions in the molten carbonate. A low-temperature process for forming small diameter, high-aspect ratio ceramic fibers for fuel cell use has been developed. A short-term program to initiate a computer study on the thermodynamic analysis of fuel cell materials was initiated at Montana State University. The report on this program is included as Appendix B. The MHD and high-temperature fuel cell literature was surveyed, and material properties were evaluated to identify MHD materials with potential use for fuel cell applications. A technology transfer report of these findings was prepared. This report is included as Appendix A. Laboratory facilities were established to conduct research on interfacial diffusion processes which could be detrimental to successful long-term operation of the solid-electrolyte fuel cell. A variety of physical and chemical techniques were examined for the preparation of high-density substituted LaCrO/sub 3/ which was to be one component of a diffusion couple with Y/sub 2/O/sub 3/-stabilized ZrO/sub 2/. Hydrolysis of a mixed metal-nitrate solution with urea produced the most reactive powder. A final theoretical density of almost 98% was attained in cold-pressed sintered discs of this material. (Extensive list of references)

Not Available

1978-10-15T23:59:59.000Z

219

Configuration adjustment potential of the Very High Temperature Reactor prismatic cores with advanced actinide fuels  

E-Print Network (OSTI)

Minor actinides represent the long-term radiotoxicity of nuclear wastes. As one of their potential incineration options, partitioning and transmutation in fission reactors are seriously considered worldwide. If implemented, these technologies could also be a source of nuclear fuel materials required for sustainability of nuclear energy. The objective of this research was to evaluate performance characteristics of Very High Temperature Reactors (VHTRs) and their variations due to configuration adjustments targeting achievability of spectral variations. The development of realistic whole-core 3D VHTR models and their benchmarking against experimental data was an inherent part of the research effort. Although the performance analysis was primarily focused on prismatic core configurations, 3D pebble-bed core models were also created and analyzed. The whole-core 3D models representing the prismatic block and pebble-bed cores were created for use with the SCALE 5.0 code system. Each of the models required the Dancoff correction factor to be externally calculated. The code system DANCOFF-MCThe whole-core/system 3D models with multi-heterogeneity treatments were validated by the benchmark problems. Obtained results are in agreement with the available High Temperature Test Reactor data. Preliminary analyses of actinide-fueled VHTR configurations have indicated promising performance characteristics. Utilization of minor actinides as a fuel component would facilitate development of new fuel cycles and support sustainability of a fuel source for nuclear energy assuring future operation of Generation IV nuclear energy systems. was utilized to perform the Dancoff factor calculations.

Ames, David E, II

2006-08-01T23:59:59.000Z

220

Evaluation of MHD materials for use in high-temperature fuel cells  

DOE Green Energy (OSTI)

The MHD and high-temperature fuel cell literature was surveyed for data pertaining to materials properties in order to identify materials used in MHD power generation which also might be suitable for component use in high-temperature fuel cells. Classes of MHD-electrode materials evaluated include carbides, nitrides, silicides, borides, composites, and oxides. Y/sub 2/O/sub 3/-stabilized ZrO/sub 2/ used as a reference point to evaluate materials for use in the solid-oxide fuel cell. Physical and chemical properties such as electrical resistivity, coefficient of thermal expansion, and thermodynamic stability toward oxidation were used to screen candidate materials. A number of the non-oxide ceramic MHD-electrode materials appear promising for use in the solid-electrolyte and molten-carbonate fuel cell as anodes or anode constituents. The MHD-insulator materials appear suitable candidates for electrolyte-support tiles in the molten-carbonate fuel cells. The merits and possible problem areas for these applications are discussed and additional needed areas of research are delineated.

Guidotti, R.

1978-06-15T23:59:59.000Z

Note: This page contains sample records for the topic "high grade fuel" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

Evaluation of High Off-Gas Failures in Barrier and Non-Barrier BWR Fuel  

Science Conference Proceedings (OSTI)

Recent failures in BWR fuel have resulted in the formation of long axial cracks and very high activity releases originating from just one or two failed and degraded rods. This report evaluates case histories of a selected set of BWR failure events to help understand the phenomena that cause certain rods to degrade after the formation of an initially minor cladding defect.

1994-04-26T23:59:59.000Z

222

ENVIRONMENTAL BIOTECHNOLOGY Electricity generation at high ionic strength in microbial fuel  

E-Print Network (OSTI)

ENVIRONMENTAL BIOTECHNOLOGY Electricity generation at high ionic strength in microbial fuel cell organic matter using elec- trochemically active bacteria as catalysts to generate electrical energy of the most exciting applications of MFCs is their use as benthic unattended generators to power electrical

Sun, Baolin

223

CATALYSTS FOR HIGH CETANE ETHERS AS DIESEL FUELS  

DOE Green Energy (OSTI)

A tungstena-zirconia (WZ) catalyst has been investigated for coupling methanol and isobutanol to unsymmetrical ethers, i.e. methyl isobutyl ether (MIBE) and compared with earlier studied sulfated-zirconia (SZ) and Nafion-H catalysts. In all cases, the ether synthesis mechanism is a dual site S{sub N}2 process involving competitive adsorption of reactants on proximal acid sites. At low reaction temperatures, methylisobutylether (MIBE) is the predominant product. However, at temperatures >135 C the WZ catalyst is very good for dehydration of isobutanol to isobutene. The surface acid sites of the WZ catalyst and a Nafion-H catalyst were diagnosed by high resolution X-ray photoelectron spectroscopy (XPS) of N 1s shifts after adsorption of amines. Using pyridine, ethylenediamine, and triethylamine, it is shown that WZ has heterogeneous strong Broensted acid sites. Theoretical study located the transition state of the alcohol coupling reaction on proximal Broensted acid sites and accounted well for XPS core-level shifts upon surface acid-base interactions. While computations have not been carried out with WZ, it is shown that the SZ catalyst is a slightly stronger acid than CF{sub 3}SO{sub 3}H (a model for Nafion-H) by 1.3-1.4 kcal/mol. A novel sulfated zirconia catalyst having proximal strong Broensted acid sites was synthesized and shown to have significantly enhanced activity and high selectivity in producing MIBE or isobutene from methanol/isobutanol mixtures. The catalyst was prepared by anchoring 1,2-ethanediol bis(hydrogen sulfate) salt precursor onto zirconium hydroxide, followed by calcination to remove the -(CH{sub 2}CH{sub 2})- bridging residues.

Kamil Klier; Richard G. Herman; Heock-Hoi Kwon; James G. C. Shen; Qisheng Ma; Robert A. Hunsicker; Andrew P. Butler; Scott J. Bollinger

2003-03-01T23:59:59.000Z

224

A rational minor actinide (MA) recycling concept based on innovative oxide fuel with high AM content  

Science Conference Proceedings (OSTI)

A rational MA recycle concept based on high Am content fuel has been proposed. A design study of an Am- MOX fabrication plant, which is a key facility for the MA recycle concept, has been done and the facility concept was clarified from the viewpoint of basic process viability. Preliminary cost estimation suggested that the total construction cost of the MA recycle facilities including Am-MOX, Np-MOX and MA recovery could be comparable with that of the large scale LWR-MOX fabrication plant required for plutonium in LWR fuel cycle. (authors)

Tanaka, Kenya; Sato, Isamu; Ishii, Tetsuya; Yoshimochi, Hiroshi; Asaga, Takeo [Japan Atomic Energy Agency, 4002 Narita-cho, O-arai-machi, Higasiibaraki-gun, Ibaraki-ken, 311-1393 (Japan); Kurosaki, Ken [Osaka University, 2-1 Yamadaoka, Suita-shi, Osaka 565-0871 (Japan)

2007-07-01T23:59:59.000Z

225

Fuel cells as a backup energy source for high availability network servers  

E-Print Network (OSTI)

This thesis proposes an uninterruptible power supply, UPS for high availability servers with fuel cells as its back up energy source. The system comprises a DC to DC converter designed to accommodate the fuel cellâ s wide output voltage range. A server power supply is specified, designed and simulated for use with this UPS. The UPS interfaces internal to the server power supply, instead of providing standard AC power. This topology affords enhanced protection from faults and increases overall efficiency of the system by removing power conversions. The UPS is simulated with the designed power supply to demonstrate its effectiveness.

Humphrey, Daniel Alan

2008-08-01T23:59:59.000Z

226

Oxidation of automotive primary reference fuels in a high pressure flow reactor  

DOE Green Energy (OSTI)

Automotive engine knock limits the maximum operating compression ratio and ultimate thermodynamic efficiency of spark-ignition (SI) engines. In compression-ignition (CI) or diesel cycle engines the premixed urn phase, which occurs shortly after injection, determines the time it takes for autoignition to occur. In order to improve engine efficiency and to recommend more efficient, cleaner-burning alternative fuels, we must understand the chemical kinetic processes which lead to autoignition in both SI and CI engines. These engines burn large molecular-weight blended fuels, a class to which the primary reference fuels (PRF), n-heptane and isooctane belong. In this study, experiments were performed under engine-like conditions in a high pressure flow reactor using both the pure PRF fuels and their mixtures in the temperature range 550-880 K and at 12.5 atm pressure. These experiments not only provide information on the reactivity of each fuel but also identify the major intermediate products formed during the oxidation process. A detailed chemical kinetic mechanism is used to simulate these experiments and comparisons of experimentally measures and model predicted profiles for O{sub 2}, CO, CO{sub 2}, H{sub 2}O and temperature rise are presented. Intermediates identified in the flow reactor are compared with those present in the computations, and the kinetic pathways leading to their formation are discussed. In addition, autoignition delay times measured in a shock tube over the temperature range 690- 1220 K and at 40 atm pressure were simulated. Good agreement between experiment and simulation was obtained for both the pure fuels and their mixtures. Finally, quantitative values of major intermediates measured in the exhaust gas of a cooperative fuels research engine operating under motored engine conditions are presented together with those predicted by the detailed method.

Curran, H.J.; Pitz, W.J.; Westbrook, C.K. [Lawrence Livermore National Lab., CA (United States); Callahan, C.V.; Dryer, F.L. [Princeton Univ., Areospace Engineering. NJ (United States)

1998-01-01T23:59:59.000Z

227

Novel Gas Sensors for High-Temperature Fossil Fuel Applications  

SciTech Connect

SRI International (SRI) is developing ceramic-based microsensors to detect exhaust gases such as NO, NO{sub 2}, and CO in advanced combustion and gasification systems under this DOE NETL-sponsored research project. The sensors detect the electrochemical activity of the exhaust gas species on catalytic electrodes attached to a solid state electrolyte and are designed to operate at the high temperatures, elevated pressures, and corrosive environments typical of large power generation exhausts. The sensors can be easily integrated into online monitoring systems for active emission control. The ultimate objective is to develop sensors for multiple gas detection in a single package, along with data acquisition and control software and hardware, so that the information can be used for closed-loop control in novel advanced power generation systems. This report details the Phase I Proof-of-Concept, research activities performed from October 2003 to March 2005. SRI's research work includes synthesis of catalytic materials, sensor design and fabrication, software development, and demonstration of pulse voltammetric analysis of NO, NO{sub 2}, and CO gases on catalytic electrodes.

Palitha Jayaweera; Francis Tanzella

2005-03-01T23:59:59.000Z

228

High resolution fossil fuel combustion CO2 emission fluxes for the United States  

E-Print Network (OSTI)

interannual variations in fossil fuel emissions. J. Geophys.Treat CO 2 from fossil fuel burning: global distribution ofdioxide emissions from fossil fuel consumption and cement

Gurney, Kevin R.

2010-01-01T23:59:59.000Z

229

Analysis and design of high frequency link power conversion systems for fuel cell power conditioning  

E-Print Network (OSTI)

In this dissertation, new high frequency link power conversion systems for the fuel cell power conditioning are proposed to improve the performance and optimize the cost, size, and weight of the power conversion systems. The first study proposes a new soft switching technique for the phase-shift controlled bi-directional dc-dc converter. The described dc-dc converter employs a low profile high frequency transformer and two active full-bridge converters for bidirectional power flow capability. The proposed new soft switching technique guarantees soft switching over wide range from no load to full load without any additional circuit components. The load range for proposed soft switching technique is analyzed by mathematical approach with equivalent circuits and verified by experiments. The second study describes a boost converter cascaded high frequency link direct dc-ac converter suitable for fuel cell power sources. A new multi-loop control for a boost converter to reduce the low frequency input current harmonics drawn from the fuel cell is proposed, and a new PWM technique for the cycloconverter at the secondary to reject the low order harmonics in the output voltages is presented. The performance of the proposed scheme is verified by the various simulations and experiments, and their trade-offs are described in detail using mathematical evaluation approach. The third study proposes a current-fed high frequency link direct dc-ac converter suitable for residential fuel cell power systems. The high frequency full-bridge inverter at the primary generates sinusoidally PWM modulated current pulses with zero current switching (ZCS), and the cycloconverter at the secondary which consists of only two bidirectional switches and output filter capacitors produces sinusoidally modulated 60Hz split single phase output voltage waveforms with near zero current switching. The active harmonic filter connected to the input terminal compensates the low order input current harmonics drawn from the fuel cell without long-term energy storage devices such as batteries and super capacitors.

Song, Yu Jin

2004-08-01T23:59:59.000Z

230

High Conversion of Coal to Transportation Fuels for the Future With Low HC Gas Production  

DOE Green Energy (OSTI)

An announced objective of the Department of Energy in funding this work, and other current research in coal liquefaction, is to produce a synthetic crude from coal at a cost lower than $30.00 per barrel (Task A). A second objective, reflecting a recent change in direction in the synthetic fuels effort of DOE, is to produce a fuel which is low in aromatics, yet of sufficiently high octane number for use in the gasoline- burning transportation vehicles of today. To meet this second objective, research was proposed, and funding awarded, for conversion of the highly-aromatic liquid product from coal conversion to a product high in isoparaffins, which compounds in the gasoline range exhibit a high octane number (Task B).

Alex G. Oblad; Wendell H. Wiser

1996-07-01T23:59:59.000Z

231

RUSSIAN-ORIGIN HIGHLY ENRICHED URANIUM SPENT NUCLEAR FUEL SHIPMENT FROM BULGARIA  

SciTech Connect

In July 2008, the Global Threat Reduction Initiative and the IRT 2000 research reactor in Sofia, Bulgaria, operated by the Institute for Nuclear Research and Nuclear Energy (INRNE), safely shipped 6.4 kilograms of Russian origin highly enriched uranium (HEU) spent nuclear fuel (SNF) to the Russian Federation. The shipment, which resulted in the removal of all HEU from Bulgaria, was conducted by truck, barge, and rail modes of transport across two transit countries before reaching the final destination at the Production Association Mayak facility in Chelyabinsk, Russia. This paper describes the work, equipment, organizations, and approvals that were required to complete the spent fuel shipment and provides lessons learned that might assist other research reactor operators with their own spent nuclear fuel shipments.

Kelly Cummins; Igor Bolshinsky; Ken Allen; Tihomir Apostolov; Ivaylo Dimitrov

2009-07-01T23:59:59.000Z

232

Pu-Zr alloy for high-temperature foil-type fuel  

DOE Patents (OSTI)

A nuclear reactor fuel alloy consists essentially of from slightly greater than 7 to about 4 w/o zirconium, balance plutonium, and is characterized in that the alloy is castable and is rollable to thin foils. A preferred embodiment of about 7 w/o zirconium, balance plutonium, has a melting point substantially above the melting point of plutonium, is rollable to foils as thin as 0.0005 inch thick, and is compatible with cladding material when repeatedly cycled to temperatures above 650.degree. C. Neutron reflux densities across a reactor core can be determined with a high-temperature activation-measurement foil which consists of a fuel alloy foil core sandwiched and sealed between two cladding material jackets, the fuel alloy foil core being a 7 w/o zirconium, plutonium foil which is from 0.005 to 0.0005 inch thick.

McCuaig, Franklin D. (LaGrange, IL)

1977-01-01T23:59:59.000Z

233

Full-length high-temperature severe fuel damage test No. 1  

SciTech Connect

This report describes the first full-length high-temperature test (FLHT-1) performed by Pacific Northwest Laboratory (PNL) in the National Research Universal (NRU) reactor at Chalk River, Ontario, Canada. The test is part of a series of experiments being performed for the NRC as a part of their Severe Fuel Damage Program and is one of several planned for PNL`s Coolant Boilaway and Damage Progression Program. The report summarizes the test design and test plan. it also provides a summary and discussion of the data collected during the test and of the photos taken during the post-test examination. All objectives for the test were met. The key objective was to demonstrate that severe fuel damage tests on full-length fuel bundles can be safely conducted in the NRU reactor.

Rausch, W.N.; Hesson, G.M.; Pilger, J.P.; King, L.L.; Goodman, R.L.; Panisko, F.E.

1993-08-01T23:59:59.000Z

234

Solution High-Energy Burst Assembly (SHEBA) results from subprompt critical experiments with uranyl fluoride fuel  

SciTech Connect

The Solution High-Energy Burst Assembly (SHEBA) was originally constructed during 1980 and was designed to be a clean free-field geometry, right-circular, cylindrically symmetric critical assembly employing U(5%)O{sub 2}F{sub 2} solution as fuel. A second version of SHEBA, employing the same fuel but equipped with a fuel pump and shielding pit, was commissioned in 1993. This report includes data and operating experience for the 1993 SHEBA only. Solution-fueled benchmark work focused on the development of experimental measurements of the characterization of SHEBA; a summary of the results are given. A description of the system and the experimental results are given in some detail in the report. Experiments were designed to: (1) study the behavior of nuclear excursions in a low-enrichment solution, (2) evaluate accidental criticality alarm detectors for fuel-processing facilities, (3) provide radiation spectra and dose measurements to benchmark radiation transport calculations on a low-enrichment solution system similar to centrifuge enrichment plants, and (4) provide radiation fields to calibrate personnel dosimetry. 15 refs., 37 figs., 10 tabs.

Cappiello, C.C.; Butterfield, K.B.; Sanchez, R.G. [and others

1997-10-01T23:59:59.000Z

235

Development of high energy density fuels from mild gasification of coal  

SciTech Connect

The overall objective of the program is the determination of the minimal processing requirements to produce High Energy Density Fuels (HEDF), meeting a minimal energy density of 130,000 Btu/gal (conventional jet fuels have energy densities in the vicinity of 115,000--120,000 Btu/gal) and having acceptable advanced fuel specifications in accordance with the three defined categories of HEDF. The program encompasses assessing current technology capability; selecting acceptable processing and refining schemes; and generating samples of advanced test fuels. A task breakdown structure was developed containing eight key tasks. This report summarizes the work that Amoco Oil Company (AOC), as key subcontractor, performed in the execution of Task 4, Proposed Upgrading Schemes for Advanced Fuel. The intent of the Task 4 study was to represent all the candidate processing options, that were either studied in the experimental efforts of Task 3 or were available from the prior art in the open literature, in a linear program (LP) model. The LP model would allow scaling of the bench-scale Task 3 results to commercial scale and would perform economic evaluations on any combination of the processes which might be used to make HEDF. Section 2.0 of this report summarizes the process and economic bases used. Sections 3.0 and 4.0 details the economics and processing sensitivities for HEDF production. 1 ref., 15 figs., 9 tabs.

Not Available

1990-10-01T23:59:59.000Z

236

Assessment of Non-Fuel, Advanced Compressed Air Energy Storage Systems to Support High Wind Penetration  

Science Conference Proceedings (OSTI)

This report summarizes the status and progress of the RD&D work at EPRI on adiabatic no-fuel Compressed Air Energy Storage (CAES) for wind integration. Bulk energy storage (BES) has latent value in the electric grid, enhances grid reliability, and is well suited to address wind integration related challenges. Without storage, extensive ramping and spinning reserve backup of thermal generators is required, at associated high costs, poor thermal performance, poor down ramp capability and high emissions. Fu...

2009-11-16T23:59:59.000Z

237

High-temperature Chemical Compatibility of As-fabricated TRIGA Fuel and Type 304 Stainless Steel Cladding  

SciTech Connect

Chemical interaction between TRIGA fuel and Type-304 stainless steel cladding at relatively high temperatures is of interest from the point of view of understanding fuel behavior during different TRIGA reactor transient scenarios. Since TRIGA fuel comes into close contact with the cladding during irradiation, there is an opportunity for interdiffusion between the U in the fuel and the Fe in the cladding to form an interaction zone that contains U-Fe phases. Based on the equilibrium U-Fe phase diagram, a eutectic can develop at a composition between the U6Fe and UFe2 phases. This eutectic composition can become a liquid at around 725°C. From the standpoint of safe operation of TRIGA fuel, it is of interest to develop better understanding of how a phase with this composition may develop in irradiated TRIGA fuel at relatively high temperatures. One technique for investigating the development of a eutectic phase at the fuel/cladding interface is to perform out-of-pile diffusion-couple experiments at relatively high temperatures. This information is most relevant for lightly irradiated fuel that just starts to touch the cladding due to fuel swelling. Similar testing using fuel irradiated to different fission densities should be tested in a similar fashion to generate data more relevant to more heavily irradiated fuel. This report describes the results for TRIGA fuel/Type-304 stainless steel diffusion couples that were annealed for one hour at 730 and 800°C. Scanning electron microscopy with energy- and wavelength-dispersive spectroscopy was employed to characterize the fuel/cladding interface for each diffusion couple to look for evidence of any chemical interaction. Overall, negligible fuel/cladding interaction was observed for each diffusion couple.

Dennis D. Keiser, Jr.; Jan-Fong Jue; Eric Woolstenhulme; Kurt Terrani; Glenn A. Moore

2012-09-01T23:59:59.000Z

238

Assessment of high-burnup LWR fuel response to reactivity-initiated accidents  

E-Print Network (OSTI)

The economic advantages of longer fuel cycle, improved fuel utilization and reduced spent fuel storage have been driving the nuclear industry to pursue higher discharge burnup of Light Water Reactor (LWR) fuel. A design ...

Liu, Wenfeng, Ph.D. Massachusetts Institute of Technology

2007-01-01T23:59:59.000Z

239

High quality metamorphic graded buffers with lattice-constants intermediate to GaAs an InP for device applications  

E-Print Network (OSTI)

We have investigated the use of a continuous, linear grading scheme for compositionally-graded metamorphic InxGal-As buffers on GaAs, which can be used as virtual substrates for optical emitters operating at wavelengths > ...

Lee, Kenneth Eng Kian

2009-01-01T23:59:59.000Z

240

STABLE HIGH CONDUCTIVITY BILAYERED ELECTROLYTES FOR LOW TEMPERATURE SOLID OXIDE FUEL CELLS  

DOE Green Energy (OSTI)

Solid oxide fuel cells (SOFCs) are the future of energy production in America. They offer great promise as a clean and efficient process for directly converting chemical energy to electricity while providing significant environmental benefits (they produce negligible hydrocarbons, CO, or NO{sub x} and, as a result of their high efficiency, produce about one-third less CO{sub 2} per kilowatt hour than internal combustion engines). Unfortunately, the current SOFC technology, based on a stabilized zirconia electrolyte, must operate in the region of 1000 C to avoid unacceptably high ohmic losses. These high temperatures demand (a) specialized (expensive) materials for the fuel cell interconnects and insulation, (b) time to heat up to the operating temperature and (c) energy input to arrive at the operating temperature. Therefore, if fuel cells could be designed to give a reasonable power output at low to intermediate1 temperatures tremendous benefits may be accrued. At low temperatures, in particular, it becomes feasible to use ferritic steel for interconnects instead of expensive and brittle ceramic materials such as those based on LaCrO{sub 3}. In addition, sealing the fuel cell becomes easier and more reliable; rapid start-up is facilitated; thermal stresses (e.g., those caused by thermal expansion mismatches) are reduced; radiative losses ({approx}T{sup 4}) become minimal; electrode sintering becomes negligible and (due to a smaller thermodynamic penalty) the SOFC operating cycle (heating from ambient) would be more efficient. Combined, all these improvements further result in reduced initial and operating costs. The problem is, at lower temperatures the conductivity of the conventional stabilized zirconia electrolyte decreases to the point where it cannot supply electrical current efficiently to an external load. The primary objectives of the proposed research are to develop a stable high conductivity (> 0.05 S cm{sup -1} at {le} 550 C) electrolyte for lower temperature SOFCs. This objective is specifically directed toward meeting the lowest (and most difficult) temperature criteria for the 21st Century Fuel Cell Program. Meeting this objective provides a potential for future transportation applications of SOFCs, where their ability to directly use hydrocarbon fuels could permit refueling within the existing transportation infrastructure. In order to meet this objective we are developing a functionally gradient bilayer electrolyte comprised of bismuth oxide on the air side and ceria on the fuel side. Bismuth oxide and doped ceria are among the highest ionic conducting electrolytes and in fact bismuth oxide based electrolytes are the only known solid oxide electrolytes to have an ionic conductivity that meets the program conductivity goal.

Eric D. Wachsman; Keith L. Duncan

2001-09-30T23:59:59.000Z

Note: This page contains sample records for the topic "high grade fuel" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


241

High sensitivity assay of cement encapsulated spent nuclear fuel sludge using the Imaging Passive Active Neutron (IPAN) system  

SciTech Connect

A new technique has been developed for high sensitivity assay of grouted spent nuclear fuel (SNF) sludge waste in 208 liter drums. The method uses the Imaging Passive Active Neutron (IPAN{sup TM}) system to provide regulatory acceptable measurements. At the Waste Receiving and Processing (WRAP) Facility in Hanford, two IPAN{sup TM} systems have been successfully calibrated and validated for assay of SNF grouted sludge drums (encapsulated with a cement mixture). The systems have been demonstrated to be capable of performing low level waste (LLW) / transuranic (TRU) waste sorting even in the presence of high gamma radiation fields emitted by the fission and activation products associated with SNF. The active and passive modes of the IPAN{sup TM} provide a wide dynamic range of assay: from below the TRU/LLW sorting threshold (100 nCi/g or 3700 Bq/g) up to several hundred grams of Weapons Grade Pu Equivalent. A new calibration technique was developed that uses a radial weighted average method to define the imaging response matrix. This method provides the required sensitivity to the height distribution of special nuclear material within the 208 liter drum, and makes use of the uniform radial distribution that will occur for a distribution of a large population of small particles in a homogeneous matrix. Extensive validation and testing with specially designed surrogate grouted sludge drums and radioactive standards have resulted in regulatory acceptance of this technique, permitting ultimate disposal of the SNF sludge drums at the Waste Isolation Pilot Plant. (authors)

Simpson, A.P. [BIL Solutions Inc, Santa Fe, NM (United States); Abdurrahman, N.M. [Fluor Hanford, Richland, WA (United States)

2007-07-01T23:59:59.000Z

242

RELAP5 model of the high flux isotope reactor with low enriched fuel thermal flux profiles  

Science Conference Proceedings (OSTI)

The High Flux Isotope Reactor (HFIR) currently uses highly enriched uranium (HEU) fabricated into involute-shaped fuel plates. It is desired that HFIR be able to use low enriched uranium (LEU) fuel while preserving the current performance capability for its diverse missions in material irradiation studies, isotope production, and the use of neutron beam lines for basic research. Preliminary neutronics and depletion simulations of HFIR with LEU fuel have arrived to feasible fuel loadings that maintain the neutronics performance of the reactor. This article illustrates preliminary models developed for the analysis of the thermal-hydraulic characteristics of the LEU core to ensure safe operation of the reactor. The beginning of life (BOL) LEU thermal flux profile has been modeled in RELAP5 to facilitate steady state simulation of the core cooling, and of anticipated and unanticipated transients. Steady state results are presented to validate the new thermal power profile inputs. A power ramp, slow depressurization at the outlet, and flow coast down transients are also evaluated. (authors)

Banfield, J.; Mervin, B.; Hart, S.; Ritchie, J.; Walker, S.; Ruggles, A.; Maldonado, G. I. [Dept. of Nuclear Engineering, Univ. of Tennessee Knoxville, Knoxville, TN 37996-2300 (United States)

2012-07-01T23:59:59.000Z

243

Fluid-Structure Interaction Modeling of High-Aspect Ratio Nuclear Fuel Plates Using COMSOL  

SciTech Connect

The High Flux Isotope Reactor at the Oak Ridge National Lab is in the research stage of converting its fuel from high-enriched uranium to low-enriched uranium. Due to different physical properties of the new fuel and changes to the internal fuel plate design, the current safety basis must be re-evaluated through rigorous computational analyses. One of the areas being explored is the fluid-structure interaction phenomenon due to the interaction of thin fuel plates (50 mils thickness) and the cooling fluid (water). Detailed computational fluid dynamics and fluid-structure interaction simulations have only recently become feasible due to improved numerical algorithms and advancements in computing technology. For many reasons including the already built-in fluid-structure interaction module, COMSOL has been chosen for this complex problem. COMSOL's ability to solve multiphysics problems using a fully-coupled and implicit solution algorithm is crucial in obtaining a stable and accurate solution. Our initial findings show that COMSOL can accurately model such problems due to its ability to closely couple the fluid dynamics and the structural dynamics problems.

Curtis, Franklin G [ORNL] ORNL; Ekici, Kivanc [ORNL] ORNL; Freels, James D [ORNL] ORNL

2013-01-01T23:59:59.000Z

244

Neutronic Analysis of an Advanced Fuel Design Concept for the High Flux Isotope Reactor  

Science Conference Proceedings (OSTI)

This study presents the neutronic analysis of an advanced fuel design concept for the Oak Ridge National Laboratory (ORNL) High Flux Isotope Reactor (HFIR) that could significantly extend the current fuel cycle length under the existing design and safety criteria. A key advantage of the fuel design herein proposed is that it would not require structural changes to the present HFIR core, in other words, maintaining the same rated power and fuel geometry (i.e., fuel plate thickness and coolant channel dimensions). Of particular practical importance, as well, is the fact that the proposed change could be justified within the bounds of the existing nuclear safety basis. The simulations herein reported employed transport theory-based and exposure-dependent eigenvalue characterization to help improve the prediction of key fuel cycle parameters. These parameters were estimated by coupling a benchmarked three-dimensional MCNP5 model of the HFIR core to the depletion code ORIGEN via the MONTEBURNS interface. The design of an advanced HFIR core with an improved fuel loading is an idea that evolved from early studies by R. D. Cheverton, formerly of ORNL. This study contrasts a modified and increased core loading of 12 kg of 235U against the current core loading of 9.4 kg. The simulations performed predict a cycle length of 39 days for the proposed fuel design, which represents a 50% increase in the cycle length in response to a 25% increase in fissile loading, with an average fuel burnup increase of {approx}23%. The results suggest that the excess reactivity can be controlled with the present design and arrangement of control elements throughout the core's life. Also, the new power distribution is comparable or even improved relative to the current power distribution, displaying lower peak to average fission rate densities across the inner fuel element's centerline and bottom cells. In fact, the fission rate density in the outer fuel element also decreased at these key locations for the proposed design. Overall, it is estimated that the advanced core design could increase the availability of the HFIR facility by {approx}50% and generate {approx}33% more neutrons annually, which is expected to yield sizeable savings during the remaining life of HFIR, currently expected to operate through 2014. This study emphasizes the neutronics evaluation of a new fuel design. Although a number of other performance parameters of the proposed design check favorably against the current design, and most of the core design features remain identical to the reference, it is acknowledged that additional evaluations would be required to fully justify the thermal-hydraulic and thermal-mechanical performance of a new fuel design, including checks for cladding corrosion performance as well as for industrial and economic feasibility.

Xoubi, Ned [ORNL; Primm, Trent [ORNL; Maldonado, G. Ivan [University of Tennessee, Knoxville (UTK)

2009-01-01T23:59:59.000Z

245

High-Energy Delayed Gamma Spectroscopy for Spent Nuclear Fuel Assay  

SciTech Connect

High-accuracy, direct, nondestructive measurement of fissile and fissionable isotopes in spent fuel, particularly the Pu isotopes, is a well-documented, but still unmet challenge in international safeguards. As nuclear fuel cycles propagate around the globe, the need for improved materials accountancy techniques for irradiated light-water reactor fuel will increase. This modeling study investigates the use of delayed gamma rays from fission-product nuclei to directly measure the relative concentrations of U-235, Pu-239, and Pu-241 in spent fuel assemblies. The method is based on the unique distribution of fission-product nuclei produced from fission in each of these fissile isotopes. Fission is stimulated in the assembly with a pulse-capable source of interrogating neutrons. The measured distributions of the short-lived fission products from the unknown sample are then fit with a linear combination of the known fission-product yield curves from pure U-235, Pu-239, and Pu-241 to determine the original proportions of these fissile isotopes. Modeling approaches for the intense gamma-ray background promulgated by the long-lived fission-product inventory and for the high-energy gamma-ray signatures emitted by short-lived fission products from induced fission are described. Benchmarking measurements are presented and compare favorably with the results of these models. Results for the simulated assay of simplified individual fuel elements ranging from fresh to 60 GWd/MTU burnup demonstrate the utility of the modeling methods for viability studies, although additional work is needed to more realistically assess the potential of High-Energy Delayed Gamma Spectroscopy (HEDGS).

Campbell, Luke W.; Smith, Leon E.; Misner, Alex C.

2011-02-01T23:59:59.000Z

246

High resolution fossil fuel combustion CO2 emission fluxes for the United States  

SciTech Connect

Quantification of fossil fuel CO{sub 2} emissions at fine space and time resolution is emerging as a critical need in carbon cycle and climate change research. As atmospheric CO{sub 2} measurements expand with the advent of a dedicated remote sensing platform and denser in situ measurements, the ability to close the carbon budget at spatial scales of {approx}100 km{sup 2} and daily time scales requires fossil fuel CO{sub 2} inventories at commensurate resolution. Additionally, the growing interest in U.S. climate change policy measures are best served by emissions that are tied to the driving processes in space and time. Here we introduce a high resolution data product (the 'Vulcan' inventory: www.purdue.edu/eas/carbon/vulcan/) that has quantified fossil fuel CO{sub 2} emissions for the contiguous U.S. at spatial scales less than 100 km{sup 2} and temporal scales as small as hours. This data product, completed for the year 2002, includes detail on combustion technology and 48 fuel types through all sectors of the U.S. economy. The Vulcan inventory is built from the decades of local/regional air pollution monitoring and complements these data with census, traffic, and digital road data sets. The Vulcan inventory shows excellent agreement with national-level Department of Energy inventories, despite the different approach taken by the DOE to quantify U.S. fossil fuel CO{sub 2} emissions. Comparison to the global 1{sup o} x 1{sup o} fossil fuel CO{sub 2} inventory, used widely by the carbon cycle and climate change community prior to the construction of the Vulcan inventory, highlights the space/time biases inherent in the population-based approach.

Gurney, Kevin R.; Mendoza, Daniel L.; Zhou, Yuyu; Fischer, Marc L.; Miller, Chris C.; Geethakumar, Sarath; de la Rue du Can, Stephane

2009-03-19T23:59:59.000Z

247

High resolution fossil fuel combustion CO{sub 2} emission fluxes for the United States  

SciTech Connect

Quantification of fossil fuel CO{sub 2} emissions at fine space and time resolution is emerging as a critical need in carbon cycle and climate change research. As atmospheric CO{sub 2} measurements expand with the advent of a dedicated remote sensing platform and denser in situ measurements, the ability to close the carbon budget at spatial scales of about 100 km{sup 2} and daily time scales requires fossil fuel CO{sub 2} inventories at commensurate resolution. Additionally, the growing interest in U.S. climate change policy measures are best served by emissions that are tied to the driving processes in space and time. Here we introduce a high resolution data product (the 'Vulcan' inventory: www.purdue.edu/eas/carbon/vulcan/) that has quantified fossil fuel CO{sub 2} emissions for the contiguous U.S. at spatial scales less than 100 km{sup 2} and temporal scales as small as hours. This data product, completed for the year 2002, includes detail on combustion technology and 48 fuel types through all sectors of the U.S. economy. The Vulcan inventory is built from the decades of local/regional air pollution monitoring and complements these data with census, traffic, and digital road data sets. The Vulcan inventory shows excellent agreement with national-level Department of Energy inventories, despite the different approach taken by the DOE to quantify U.S. fossil fuel CO{sub 2} emissions. Comparison to the global 1{sup o} x 1{sup o} fossil fuel CO{sub 2} inventory, used widely by the carbon cycle and climate change community prior to the construction of the Vulcan inventory, highlights the space/time biases inherent in the population-based approach. 39 refs., 5 figs., 1 tab.

Kevin R. Gurney; Daniel L. Mendoza; Yuyu Zhou; Marc L. Fischer; Chris C. Miller; Sarath Geethakumar; Stephane de la Rue du Can [Purdue University, West Lafayette, IN (United States). Department of Earth and Atmospheric Sciences/Department of Agronomy

2009-07-15T23:59:59.000Z

248

LOW-TEMPERATURE, ANODE-SUPPORTED HIGH POWER DENSITY SOLID OXIDE FUEL CELLS WITH NANOSTRUCTURED ELECTRODES  

DOE Green Energy (OSTI)

Anode-supported solid oxide fuel cells with Ni + yttria-stabilized zirconia (YSZ) anode, YSZ-samaria-doped ceria (SDC) bi-layer electrolyte and Sr-doped LaCoO{sub 3} (LSC) + SDC cathode were fabricated. Fuel used consisted of H{sub 2} diluted with He, N{sub 2}, H{sub 2}O or CO{sub 2}, mixtures of H{sub 2} and CO, and mixtures of CO and CO{sub 2}. Cell performance was measured at 800 C with above-mentioned fuel gas mixtures and air as oxidant. For a given concentration of the diluent, the cell performance was higher with He as the diluent than with N{sub 2} as the diluent. Mass transport through porous Ni-YSZ anode for H{sub 2}-H{sub 2}O, CO-CO{sub 2} binary systems and H{sub 2}-H{sub 2}O-diluent gas ternary systems was analyzed using multicomponent gas diffusion theory. At high concentrations of the diluent, the maximum achievable current density was limited by the anodic concentration polarization. From this measured limiting current density, the corresponding effective gas diffusivity was estimated. Highest effective diffusivity was estimated for fuel gas mixtures containing H{sub 2}-H{sub 2}O-He mixtures ({approx}0.34 cm{sup 2}/s), and the lowest for CO-CO{sub 2} mixtures ({approx}0.07 cm{sup 2}/s). The lowest performance was observed with CO-CO{sub 2} mixture as a fuel, which in part was attributed to the lowest effective diffusivity of the fuels tested.

Anil V. Virkar

2001-09-26T23:59:59.000Z

249

High resolution fossil fuel combustion CO2 emission fluxes for the United States  

SciTech Connect

Quantification of fossil fuel CO{sub 2} emissions at fine space and time resolution is emerging as a critical need in carbon cycle and climate change research. As atmospheric CO{sub 2} measurements expand with the advent of a dedicated remote sensing platform and denser in situ measurements, the ability to close the carbon budget at spatial scales of {approx}100 km{sup 2} and daily time scales requires fossil fuel CO{sub 2} inventories at commensurate resolution. Additionally, the growing interest in U.S. climate change policy measures are best served by emissions that are tied to the driving processes in space and time. Here we introduce a high resolution data product (the 'Vulcan' inventory: www.purdue.edu/eas/carbon/vulcan/) that has quantified fossil fuel CO{sub 2} emissions for the contiguous U.S. at spatial scales less than 100 km{sup 2} and temporal scales as small as hours. This data product, completed for the year 2002, includes detail on combustion technology and 48 fuel types through all sectors of the U.S. economy. The Vulcan inventory is built from the decades of local/regional air pollution monitoring and complements these data with census, traffic, and digital road data sets. The Vulcan inventory shows excellent agreement with national-level Department of Energy inventories, despite the different approach taken by the DOE to quantify U.S. fossil fuel CO{sub 2} emissions. Comparison to the global 1{sup o} x 1{sup o} fossil fuel CO{sub 2} inventory, used widely by the carbon cycle and climate change community prior to the construction of the Vulcan inventory, highlights the space/time biases inherent in the population-based approach.

Gurney, Kevin R.; Mendoza, Daniel L.; Zhou, Yuyu; Fischer, Marc L.; Miller, Chris C.; Geethakumar, Sarath; de la Rue du Can, Stephane

2009-03-19T23:59:59.000Z

250

Oxidation of Fuel Cladding Candidate Materials in Steam Environments at High Temperature and Pressure  

SciTech Connect

Under certain severe accident conditions, the fuel rods of nuclear power plants are exposed to high temperature/pressure steam environments in which the Zr alloy cladding is rapidly oxidized. As alternative claddings, the oxidation resistances of SiC-based materials and stainless steels with high Cr and/or Al additions have been examined from 800-1200 C in high-pressure steam environments. Very low reaction kinetics were observed with alumina-forming FeCrAl alloys at 1200 C while Fe-Cr alloys with only 15-20% Cr were rapidly attacked.

Cheng, Ting [ORNL; Keiser, James R [ORNL; Brady, Michael P [ORNL; Terrani, Kurt A [ORNL; Pint, Bruce A [ORNL

2012-01-01T23:59:59.000Z

251

Air Shipment of Highly Enriched Uranium Spent Nuclear Fuel from Romania  

SciTech Connect

Romania safely air shipped 23.7 kilograms of Russian origin highly enriched uranium (HEU) spent nuclear fuel from the VVR S research reactor at Magurele, Romania, to the Russian Federation in June 2009. This was the world’s first air shipment of spent nuclear fuel transported in a Type B(U) cask under existing international laws without special exceptions for the air transport licenses. This shipment was coordinated by the Russian Research Reactor Fuel Return Program (RRRFR), part of the U.S. Department of Energy Global Threat Reduction Initiative (GTRI), in cooperation with the Romania National Commission for Nuclear Activities Control (CNCAN), the Horia Hulubei National Institute of Physics and Nuclear Engineering (IFIN-HH), and the Russian Federation State Corporation Rosatom. The shipment was transported by truck to and from the respective commercial airports in Romania and the Russian Federation and stored at a secure nuclear facility in Russia where it will be converted into low enriched uranium. With this shipment, Romania became the 3rd country under the RRRFR program and the 14th country under the GTRI program to remove all HEU. This paper describes the work, equipment, and approvals that were required to complete this spent fuel air shipment.

K. J. Allen; I. Bolshinsky; L. L. Biro; M. E. Budu; N. V. Zamfir; M. Dragusin

2010-07-01T23:59:59.000Z

252

Implications of Low Particulate Matter Emissions on System Fuel Efficiency for High Efficiency Clean Combustion  

DOE Green Energy (OSTI)

Advanced diesel combustion regimes such as High Efficiency Clean Combustion (HECC) offer the benefits of reduced engine out NOX and particulate matter (PM) emissions. Lower PM emissions during advanced combustion reduce the demand on diesel particulate filters (DPFs) and can, thereby, reduce the fuel penalty associated with DPF regeneration. In this study, a SiC DPF was loaded and regenerated on a 1.7-liter 4-cylinder diesel engine operated in conventional and advanced combustion modes at different speed and load conditions. A diesel oxidation catalyst (DOC) and a lean NOX trap (LNT) were also installed in the exhaust stream. Five steady-state speed and load conditions were weighted to estimate Federal Test Procedure (FTP) fuel efficiency. The DPF was loaded using lean-rich cycling with frequencies that resulted in similar levels of NOX emissions downstream of the LNT. The pressure drop across the DPF was measured at a standard point (1500 rpm, 5.0 bar) before and after loading, and a P rise rate was determined for comparison between conventional and advanced combustion modes. Higher PM emissions in conventional combustion resulted in a higher rate of backpressure rise across the DPF at all of the load points leading to more frequent DPF regenerations and higher fuel penalty. The fuel penalty during conventional combustion was 4.2% compared with 3.1% for a mixture of conventional and advanced modes.

Parks, II, James E [ORNL; Prikhodko, Vitaly Y [ORNL

2009-01-01T23:59:59.000Z

253

Guide for Identifying and Converting High-Potential Petroleum Brownfield Sites to Alternative Fuel Stations  

DOE Green Energy (OSTI)

Former gasoline stations that are now classified as brownfields can be good sites to sell alternative fuels because they are in locations that are convenient to vehicles and they may be seeking a new source of income. However, their success as alternative fueling stations is highly dependent on location-specific criteria. First, this report outlines what these criteria are, how to prioritize them, and then applies that assessment framework to five of the most popular alternative fuels--electricity, natural gas, hydrogen, ethanol, and biodiesel. The second part of this report delves into the criteria and tools used to assess an alternative fuel retail site at the local level. It does this through two case studies of converting former gasoline stations in the Seattle-Eugene area into electric charge stations. The third part of this report addresses steps to be taken after the specific site has been selected. This includes choosing and installing the recharging equipment, which includes steps to take in the permitting process and key players to include.

Johnson, C.; Hettinger, D.; Mosey, G.

2011-05-01T23:59:59.000Z

254

Investigation of Fuel Cell System Performance and Operation: A Fuel Cell as a Practical  

E-Print Network (OSTI)

The low-grade heat from the fuel cell is utilized at the domestic hot water storage tank with a double The low-grade fuel cell heat feeds a heat exchanger to supply domestic hot water requirementsInvestigation of Fuel Cell System Performance and Operation: A Fuel Cell as a Practical Distributed

255

High resolution neutron imaging of water in the polymer electrolyte fuel cell membrane  

Science Conference Proceedings (OSTI)

Water transport in the ionomeric membrane, typically Nafion{reg_sign}, has profound influence on the performance of the polymer electrolyte fuel cell, in terms of internal resistance and overall water balance. In this work, high resolution neutron imaging of the Nafion{reg_sign} membrane is presented in order to measure water content and through-plane gradients in situ under disparate temperature and humidification conditions.

Mukherjee, Partha P [Los Alamos National Laboratory; Makundan, Rangachary [Los Alamos National Laboratory; Spendelow, Jacob S [Los Alamos National Laboratory; Borup, Rodney L [Los Alamos National Laboratory; Hussey, D S [NIST; Jacobson, D L [NIST; Arif, M [NIST

2009-01-01T23:59:59.000Z

256

Neutronics and Depletion Methods for Parametric Studies of Fluoride Salt Cooled High Temperature Reactors with Slab Fuel Geometry and Multi-Batch Fuel Management Schemes  

SciTech Connect

The Advanced High Temperature Reactor (AHTR) is a 3400 MWth fluoride salt cooled high temperature reactor (FHR) that uses TRISO particle fuel compacted into slabs rather than spherical fuel pebbles or cylindrical fuel compacts. Simplified methods are required for parametric design studies such that analyzing the entire feasible design space for an AHTR is tractable. These simplifications include fuel homogenization techniques to increase the speed of neutron transport calculations in depletion analysis and equilibrium depletion analysis methods to analyze systems with multi-batch fuel management schemes. This paper presents three elements of significant novelty. First, the reactivity-equivalent physical transformation (RPT) methodology usually applied in systems with coated particle fuel in cylindrical and spherical geometries was extended to slab geometries. Secondly, based on this newly developed RPT method for slab geometries, a methodology that uses Monte Carlo depletion approaches was further developed to search for the maximum discharge burnup in a multi-batch system by iteratively estimating the beginning of equilibrium cycle composition and sampling different discharge burnups. This iterative equilibrium depletion search (IEDS) method fully defines an equilibrium fuel cycle (keff, power, flux and composition evolutions across space and time), but is computationally demanding, although feasible on single-processor workstations. Finally, an analytical method, the non-linear reactivity model, was developed by expanding the linear reactivity model to include an arbitrary number of higher order terms to extrapolate single-batch depletion results to estimate the maximum discharge burnup and BOEC keff in systems with multi-batch fuel management schemes. Results from this method were benchmarked against equilibrium depletion analysis results using the IEDS.

Cisneros, Anselmo T. [University of California, Berkeley; Ilas, Dan [ORNL

2012-01-01T23:59:59.000Z

257

New Mexico Hydrogen Fuels Challenge Program Description The New...  

NLE Websites -- All DOE Office Websites (Extended Search)

New Mexico Hydrogen Fuels Challenge Program Description The New Mexico Hydrogen Fuels Challenge is an event that provides a hands-on opportunity for middle school students (grades...

258

The ORNL High Flux Isotope Reactor and New Advanced Fuel Testing Capabilities  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy s High Flux Isotope Reactor (HFIR), located at the Oak Ridge National Laboratory (ORNL), was originally designed (in the 1960s) primarily as a part of the overall program to produce transuranic isotopes for use in the heavy-element research program of the United States. Today, the reactor is a highly versatile machine, producing medical and transuranic isotopes and performing materials test experimental irradiations and neutron-scattering experiments. The ability to test advanced fuels and cladding materials in a thermal neutron spectrum in the United States is limited, and a fast-spectrum irradiation facility does not currently exist in this country. The HFIR has a distinct advantage for consideration as a fuel/cladding irradiation facility because of the extremely high neutron fluxes that this reactor provides over the full thermal- to fast-neutron energy range. New test capabilities have been developed that will allow testing of advanced nuclear fuels and cladding materials in the HFIR under prototypic light-water reactor (LWR) and fast-reactor (FR) operating conditions.

Ott, Larry J [ORNL; McDuffee, Joel Lee [ORNL

2011-01-01T23:59:59.000Z

259

Foreign programs for the storage of spent nuclear power plant fuels, high-level waste canisters and transuranic wastes  

SciTech Connect

The various national programs for developing and applying technology for the interim storage of spent fuel, high-level radioactive waste, and TRU wastes are summarized. Primary emphasis of the report is on dry storage techniques for uranium dioxide fuels, but data are also provided concerning pool storage.

Harmon, K.M.; Johnson, A.B. Jr.

1984-04-01T23:59:59.000Z

260

Decay Heat Calculations for PWR and BWR Assemblies Fueled with Uranium and Plutonium Mixed Oxide Fuel using SCALE  

Science Conference Proceedings (OSTI)

In currently operating commercial nuclear power plants (NPP), there are two main types of nuclear fuel, low enriched uranium (LEU) fuel, and mixed-oxide uranium-plutonium (MOX) fuel. The LEU fuel is made of pure uranium dioxide (UO{sub 2} or UOX) and has been the fuel of choice in commercial light water reactors (LWRs) for a number of years. Naturally occurring uranium contains a mixture of different uranium isotopes, primarily, {sup 235}U and {sup 238}U. {sup 235}U is a fissile isotope, and will readily undergo a fission reaction upon interaction with a thermal neutron. {sup 235}U has an isotopic concentration of 0.71% in naturally occurring uranium. For most reactors to maintain a fission chain reaction, the natural isotopic concentration of {sup 235}U must be increased (enriched) to a level greater than 0.71%. Modern nuclear reactor fuel assemblies contain a number of fuel pins potentially having different {sup 235}U enrichments varying from {approx}2.0% to {approx}5% enriched in {sup 235}U. Currently in the United States (US), all commercial nuclear power plants use UO{sub 2} fuel. In the rest of the world, UO{sub 2} fuel is still commonly used, but MOX fuel is also used in a number of reactors. MOX fuel contains a mixture of both UO{sub 2} and PuO{sub 2}. Because the plutonium provides the fissile content of the fuel, the uranium used in MOX is either natural or depleted uranium. PuO{sub 2} is added to effectively replace the fissile content of {sup 235}U so that the level of fissile content is sufficiently high to maintain the chain reaction in an LWR. Both reactor-grade and weapons-grade plutonium contains a number of fissile and non-fissile plutonium isotopes, with the fraction of fissile and non-fissile plutonium isotopes being dependent on the source of the plutonium. While only RG plutonium is currently used in MOX, there is the possibility that WG plutonium from dismantled weapons will be used to make MOX for use in US reactors. Reactor-grade plutonium in MOX fuel is generally obtained from reprocessed irradiated nuclear fuel, whereas weapons-grade plutonium is obtained from decommissioned nuclear weapons material and thus has a different plutonium (and other actinides) concentration. Using MOX fuel instead of UOX fuel has potential impacts on the neutronic performance of the nuclear fuel and the design of the nuclear fuel must take these differences into account. Each of the plutonium sources (RG and WG) has different implications on the neutronic behavior of the fuel because each contains a different blend of plutonium nuclides. The amount of heat and the number of neutrons produced from fission of plutonium nuclides is different from fission of {sup 235}U. These differences in UOX and MOX do not end at discharge of the fuel from the reactor core - the short- and long-term storage of MOX fuel may have different requirements than UOX fuel because of the different discharged fuel decay heat characteristics. The research documented in this report compares MOX and UOX fuel during storage and disposal of the fuel by comparing decay heat rates for typical pressurized water reactor (PWR) and boiling water reactor (BWR) fuel assemblies with and without weapons-grade (WG) and reactor-grade (RG) MOX fuel.

Ade, Brian J [ORNL; Gauld, Ian C [ORNL

2011-10-01T23:59:59.000Z

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261

Deep Burn: Development of Transuranic Fuel for High-Temperature Helium-Cooled Reactors- Monthly Highlights September 2010  

SciTech Connect

The DB Program monthly highlights report for August 2010, ORNL/TM-2010/184, was distributed to program participants by email on September 17. This report discusses: (1) Core and Fuel Analysis - (a) Core Design Optimization in the HTR (high temperature helium-cooled reactor) Prismatic Design (Logos), (b) Core Design Optimization in the HTR Pebble Bed Design (INL), (c) Microfuel analysis for the DB HTR (INL, GA, Logos); (2) Spent Fuel Management - (a) TRISO (tri-structural isotropic) repository behavior (UNLV), (b) Repository performance of TRISO fuel (UCB); (3) Fuel Cycle Integration of the HTR (high temperature helium-cooled reactor) - Synergy with other reactor fuel cycles (GA, Logos); (4) TRU (transuranic elements) HTR Fuel Qualification - (a) Thermochemical Modeling, (b) Actinide and Fission Product Transport, (c) Radiation Damage and Properties; (5) HTR Spent Fuel Recycle - (a) TRU Kernel Development (ORNL), (b) Coating Development (ORNL), (c) Characterization Development and Support, (d) ZrC Properties and Handbook; and (6) HTR Fuel Recycle - (a) Graphite Recycle (ORNL), (b) Aqueous Reprocessing, (c) Pyrochemical Reprocessing METROX (metal recovery from oxide fuel) Process Development (ANL).

Snead, Lance Lewis [ORNL; Besmann, Theodore M [ORNL; Collins, Emory D [ORNL; Bell, Gary L [ORNL

2010-10-01T23:59:59.000Z

262

Low-Enriched Uranium Fuel Conversion Activities for the High Flux Isotope Reactor, Annual Report for FY 2011  

SciTech Connect

This report describes progress made during FY11 in ORNL activities to support converting the High Flux Isotope Reactor (HFIR) from high-enriched uranium (HEU) fuel to low-enriched uranium (LEU) fuel. Conversion from HEU to LEU will require a change in fuel form from uranium oxide to a uranium-molybdenum (UMo) alloy. With both radial and axial contouring of the fuel foil and an increase in reactor power to 100 MW, calculations indicate that the HFIR can be operated with LEU fuel with no degradation in performance to users from the current levels achieved with HEU fuel. Studies are continuing to demonstrate that the fuel thermal safety margins can be preserved following conversion. Studies are also continuing to update other aspects of the reactor steady state operation and accident response for the effects of fuel conversion. Technical input has been provided to Oregon State University in support of their hydraulic testing program. The HFIR conversion schedule was revised and provided to the GTRI program. In addition to HFIR conversion activities, technical support was provided directly to the Fuel Fabrication Capability program manager.

Renfro, David G [ORNL; Cook, David Howard [ORNL; Freels, James D [ORNL; Griffin, Frederick P [ORNL; Ilas, Germina [ORNL; Sease, John D [ORNL; Chandler, David [ORNL

2012-03-01T23:59:59.000Z

263

Progress on High Energy Delayed Gamma Spectroscopy for Direct Assay of Pu in Spent Fuel  

Science Conference Proceedings (OSTI)

The direct, nondestructive measurement of fissile and fissionable isotopes in spent fuel is not yet possible. Current methods which infer plutonium content through proxy measurements and confirmatory burnup calculations have relatively large uncertainty and do not satisfy the desire for a measurement that is independent of operator declarations. We are currently exploring the High Energy Delayed Gamma Spectroscopy (HEDGS) technique for direct, independent Pu measurement in light-water reactor fuels. HEDGS exploits the unique distribution of fission-product nuclei from each of the fissile isotopes. Fission is stimulated in the sample with a source of interrogating neutrons, and delayed gamma rays from the decay of the short-lived fission-product nuclei are measured. The measured gamma spectrum from the unknown sample is then fit with a linear combination of gamma spectra from pure U-235, Pu-239, and Pu-241, as deduced from the known fission-product yield curves and decay properties of the fission-product nuclei, to determine the original proportions of these fissile isotopes. In previous work, we performed preliminary modeling studies of HEDGS on idealized single fuel pins of various burnups. Here, we report progress on extending our GEANT-based modeling tools to efficiently model full pressurized water reactor (PWR) fuel assemblies using variance reduction techniques specific to the background emissions and induced signal, as appropriate. Predicted performance for a nominal HEDGS instrument design, is reported for the assay of U-235, Pu-239 and Pu-241 in spent fuel assemblies ranging from fresh to 60 GWd/MTU in burnup.

Campbell, Luke W.; Smith, Leon E.

2010-08-11T23:59:59.000Z

264

Co-firing high sulfur coal with refuse derived fuels. Final report  

DOE Green Energy (OSTI)

This project was designed to evaluate the combustion performance of and emissions from a fluidized bed combustor during the combustion of mixtures of high sulfur and/or high chlorine coals and municipal solid waste (MSW). The project included four major tasks, which were as follows: (1) Selection, acquisition, and characterization of raw materials for fuels and the determination of combustion profiles of combination fuels using thermal analytical techniques; (2) Studies of the mechanisms for the formation of chlorinated organics during the combustion of MSW using a tube furnace; (3) Investigation of the effect of sulfur species on the formation of chlorinated organics; and (4) Examination of the combustion performance of combination fuels in a laboratory scale fluidized bed combustor. Several kinds of coals and the major combustible components of the MSW, including PVC, newspaper, and cellulose were tested in this project. Coals with a wide range of sulfur and chlorine contents were used. TGA/MS/FTIR analyses were performed on the raw materials and their blends. The possible mechanism for the formation of chlorinated organics during combustion was investigated by conducting a series of experiments in a tube furnace. The effect of sulfur dioxide on the formation of molecular chlorine during combustion processes was examined in this study.

Pan, W.P.; Riley, J.T.; Lloyd, W.G.

1997-11-30T23:59:59.000Z

265

What are Spent Nuclear Fuel and High-Level Radioactive Waste ?  

Science Conference Proceedings (OSTI)

Spent nuclear fuel and high-level radioactive waste are materials from nuclear power plants and government defense programs. These materials contain highly radioactive elements, such as cesium, strontium, technetium, and neptunium. Some of these elements will remain radioactive for a few years, while others will be radioactive for millions of years. Exposure to such radioactive materials can cause human health problems. Scientists worldwide agree that the safest way to manage these materials is to dispose of them deep underground in what is called a geologic repository.

DOE

2002-12-01T23:59:59.000Z

266

STABLE HIGH CONDUCTIVITY BILAYERED ELECTROLYTES FOR LOW TEMPERATURE SOLID OXIDE FUEL CELLS  

DOE Green Energy (OSTI)

Solid oxide fuel cells (SOFCs) are the future of energy production in America. They offer great promise as a clean and efficient process for directly converting chemical energy to electricity while providing significant environmental benefits (they produce negligible CO, HC, or NOx and, as a result of their high efficiency, produce about one-third less CO{sub 2} per kilowatt hour than internal combustion engines). Unfortunately, the current SOFC technology, based on a stabilized zirconia electrolyte, must operate in the region of 1000 C to avoid unacceptably high ohmic losses. These high temperatures demand (a) specialized (expensive) materials for the fuel cell interconnects and insulation, (b) time to heat up to the operating temperature and (c) energy input to arrive at the operating temperature. Therefore, if fuel cells could be designed to give a reasonable power output at lower temperatures tremendous benefits may be accrued, not the least of which is reduced cost. The problem is, at lower temperatures the conductivity of the conventional stabilized zirconia electrolyte decreases to the point where it cannot supply electrical current efficiently to an external load. The primary objectives of the proposed research is to develop a stable high conductivity (>0.05 S cm{sup -1} at 550 C) electrolyte for lower temperature SOFCs. This objective is specifically directed toward meeting the lowest (and most difficult) temperature criteria for the 21st Century Fuel Cell Program. Meeting this objective provides a potential for future transportation applications of SOFCs, where their ability to directly use hydrocarbon fuels could permit refueling within the existing transportation infrastructure. In order to meet this objective we are developing a functionally gradient bilayer electrolyte comprised of bismuth oxide on the air side and ceria on the fuel side. Bismuth oxide and doped ceria are among the highest ionic conducting electrolytes and in fact bismuth oxide based electrolytes are the only known solid oxide electrolytes to have an ionic conductivity that meets the program conductivity goal. We have previously demonstrated that this concept works, that a bismuth oxide/ceria bilayer electrolyte provides near theoretical open circuit potential (OCP) and is stable for 1400 h of fuel cell operation under both open circuit and maximum power conditions. More recently, we developed a computer model to determine the defect transport in this bilayer and have found that a bilayer comprised primarily of the more conductive component (bismuth oxide) is stable for 500 C operation. In this first year of the project we are obtaining necessary thermochemical data to complete the computer model as well as initial SOFC results based on thick 1-2 mm single and bilayer ceria/bismuth oxide electrolytes. We will use the computer model to obtain the optimum relative layer thickness as a function of temperature and air/fuel conditions. SOFCs will be fabricated with 1-2 mm single and bilayer electrolytes based on the modeling results, tested for OCP, conductivity, and stability and compared against the predictions. The computer modeling is a continuation of previous work under support from GRI and the student was available at the inception of the contract. However, the experimental effort was delayed until the beginning of the Spring Semester because the contract was started in October, 2 months after the start of our Fall Semester, and after all of the graduate students were committed to other projects. The results from both of these efforts are described in the following two sections: (1) Experimental; and (2) Computer Modeling.

Eric D. Wachsman

2000-10-01T23:59:59.000Z

267

Assessment of innovative fuel designs for high performance light water reactors  

E-Print Network (OSTI)

To increase the power density and maximum allowable fuel burnup in light water reactors, new fuel rod designs are investigated. Such fuel is desirable for improving the economic performance light water reactors loaded with ...

Carpenter, David Michael

2006-01-01T23:59:59.000Z

268

Neutronics and Depletion Methods for Parametric Studies of Fluoride Salt Cooled High Temperature Reactors with Slab Fuel Geometry and Multi-Batch Fuel Management Schemes  

SciTech Connect

The Advanced High-Temperature Reactor (AHTR) is a 3400 MWth fluoride-salt-cooled high-temperature reactor (FHR) that uses TRISO particle fuel compacted into slabs rather than spherical or cylindrical fuel compacts. Simplified methods are required for parametric design studies such that analyzing the entire feasible design space for an AHTR is tractable. These simplifications include fuel homogenization techniques to increase the speed of neutron transport calculations in depletion analysis and equilibrium depletion analysis methods to analyze systems with multi-batch fuel management schemes. This paper presents three elements of significant novelty. First, the Reactivity-Equivalent Physical Transformation (RPT) methodology usually applied in systems with coated-particle fuel in cylindrical and spherical geometries has been extended to slab geometries. Secondly, based on this newly developed RPT method for slab geometries, a methodology that uses Monte Carlo depletion approaches was further developed to search for the maximum discharge burnup in a multi-batch system by iteratively estimating the beginning of equilibrium cycle (BOEC) composition and sampling different discharge burnups. This Iterative Equilibrium Depletion Search (IEDS) method fully defines an equilibrium fuel cycle (keff, power, flux, and composition evolutions) but is computationally demanding, although feasible on single-processor workstations. Finally, an analytical method, the Non-Linear Reactivity Model, was developed by expanding the linear reactivity model to include an arbitrary number of higher order terms so that single-batch depletion results could be extrapolated to estimate the maximum discharge burnup and BOEC keff in systems with multi-batch fuel management schemes. Results from this method were benchmarked against equilibrium depletion analysis results using the IEDS.

Cisneros, Anselmo T. [University of California, Berkeley; Ilas, Dan [ORNL

2013-01-01T23:59:59.000Z

269

High-Octane Fuel from Refinery Exhaust Gas: Upgrading Refinery Off-Gas to High-Octane Alkylate  

Science Conference Proceedings (OSTI)

Broad Funding Opportunity Announcement Project: Exelus is developing a method to convert olefins from oil refinery exhaust gas into alkylate, a clean-burning, high-octane component of gasoline. Traditionally, olefins must be separated from exhaust before they can be converted into another source of useful fuel. Exelus’ process uses catalysts that convert the olefin to alkylate without first separating it from the exhaust. The ability to turn up to 50% of exhaust directly into gasoline blends could result in an additional 46 million gallons of gasoline in the U.S. each year.

None

2009-12-01T23:59:59.000Z

270

LIQUID BIO-FUEL PRODUCTION FROM NON-FOOD BIOMASS VIA HIGH TEMPERATURE STEAM ELECTROLYSIS  

DOE Green Energy (OSTI)

Bio-Syntrolysis is a hybrid energy process that enables production of synthetic liquid fuels that are compatible with the existing conventional liquid transportation fuels infrastructure. Using biomass as a renewable carbon source, and supplemental hydrogen from high-temperature steam electrolysis (HTSE), bio-syntrolysis has the potential to provide a significant alternative petroleum source that could reduce US dependence on imported oil. Combining hydrogen from HTSE with CO from an oxygen-blown biomass gasifier yields syngas to be used as a feedstock for synthesis of liquid transportation fuels via a Fischer-Tropsch process. Conversion of syngas to liquid hydrocarbon fuels, using a biomass-based carbon source, expands the application of renewable energy beyond the grid to include transportation fuels. It can also contribute to grid stability associated with non-dispatchable power generation. The use of supplemental hydrogen from HTSE enables greater than 90% utilization of the biomass carbon content which is about 2.5 times higher than carbon utilization associated with traditional cellulosic ethanol production. If the electrical power source needed for HTSE is based on nuclear or renewable energy, the process is carbon neutral. INL has demonstrated improved biomass processing prior to gasification. Recyclable biomass in the form of crop residue or energy crops would serve as the feedstock for this process. A process model of syngas production using high temperature electrolysis and biomass gasification is presented. Process heat from the biomass gasifier is used to heat steam for the hydrogen production via the high temperature steam electrolysis process. Oxygen produced form the electrolysis process is used to control the oxidation rate in the oxygen-blown biomass gasifier. Based on the gasifier temperature, 94% to 95% of the carbon in the biomass becomes carbon monoxide in the syngas (carbon monoxide and hydrogen). Assuming the thermal efficiency of the power cycle for electricity generation is 50%, (as expected from GEN IV nuclear reactors), the syngas production efficiency ranges from 70% to 73% as the gasifier temperature decreases from 1900 K to 1500 K. Parametric studies of system pressure, biomass moisture content and low temperature alkaline electrolysis are also presented.

G. L. Hawkes; J. E. O'Brien; M. G. McKellar

2011-11-01T23:59:59.000Z

271

TEM Characterization of U-7Mo/Al-2Si Dispersion Fuel Irradiated to Intermediate and High Fission Densities  

SciTech Connect

This paper will discuss the results of TEM analysis that was performed on two samples taken from the low flux and high flux sides of the fuel plate with U-7Mo fuel particles dispersed in U-2Si matrix. The corresponding local fission density of the fuel particles and the peak fuel plate centerline temperature between the low flux and high flux samples are 3.32 x 10{sup 27} f/m{sup 3} and 90 C, and 6.31 x 10{sup 27} f/m{sup 3} and 120 C, respectively. The results of this work showed the presence of a bubble superlattice within the U-7Mo grains that accommodated fission gases (e.g., Xe). The presence of this structure helps the U-7Mo exhibit a stable swelling behavior during irradiation. The Si-rich interaction layers that develop around the fuel particles at the U-7Mo/matrix interface during fuel plate fabrication and irradiation become amorphous during irradiation. The change in bubble distribution at the high fission density suggests that the bubble superlattice is stable as the U-7Mo matrix remains crystalline. It appears that there is a threshold Si content in the fuel particle above which the U-Mo turns to amorphous under irradiation. The threshold Si content is approximately 8 at.% and 4 at.% for low flux and high flux condition, respectively.

J. Gan; D.D. Keiser, Jr.; B.D. Miller; A.B. Robinson; J-F. Jue; P.G. Medvedev; D.M. Wachs

2012-05-01T23:59:59.000Z

272

Prediction of Combustion Stability and Flashback in Turbines with High-Hydrogen Fuel - Georgia Institute of Technology  

NLE Websites -- All DOE Office Websites (Extended Search)

Prediction of Combustion Stability Prediction of Combustion Stability and Flashback in Turbines with High- Hydrogen Fuel-Georgia Institute of Technology Background Georgia Institute of Technology (Georgia Tech), in collaboration with Pennsylvania State University and gas turbine manufacturers, is conducting research to improve the state-of-the-art in understanding and modeling combustion instabilities, one of the most critical problems associated with burning high-hydrogen content (HHC) fuels in

273

US Department of Energy Storage of Spent Fuel and High Level Waste  

DOE Green Energy (OSTI)

ABSTRACT This paper provides an overview of the Department of Energy's (DOE) spent nuclear fuel (SNF) and high level waste (HLW) storage management. Like commercial reactor fuel, DOE's SNF and HLW were destined for the Yucca Mountain repository. In March 2010, the DOE filed a motion with the Nuclear Regulatory Commission (NRC) to withdraw the license application for the repository at Yucca Mountain. A new repository is now decades away. The default for the commercial and DOE research reactor fuel and HLW is on-site storage for the foreseeable future. Though the motion to withdraw the license application and delay opening of a repository signals extended storage, DOE's immediate plans for management of its SNF and HLW remain the same as before Yucca Mountain was designated as the repository, though it has expanded its research and development efforts to ensure safe extended storage. This paper outlines some of the proposed research that DOE is conducting and will use to enhance its storage systems and facilities.

Sandra M Birk

2010-10-01T23:59:59.000Z

274

Hydrogen as a zero-emission, high-efficiency fuel: Uniqueness, experiments and simulations  

DOE Green Energy (OSTI)

The planned use of hydrogen as the energy carrier of the future introduces new challenges and opportunities, especially to the engine design community. Hydrogen is a bio-friendly fuel that can be produced from renewable resources and has no carbon dioxide combustion products; and in a properly designed ICE, almost zero NO{sub x} and hydrocarbon emissions can be achieved. Because of the unique properties of hydrogen combustion - in particular the highly wrinkled nature of the laminar flame front due to the preferential diffusion instability - modeling approaches for hydrocarbon gaseous fuels are not generally applicable to hydrogen combustion. This paper reports on the current progress to develop an engine design capability based on the KIVA family of codes for hydrogen-fueled, spark-ignited engines in support of the National Hydrogen Program. A turbulent combustion model, based on a modified eddy-turnover model in conjunction with an intake flow valve model, is found to describe well the efficiency and NO{sub x} emissions for an experimental engine over a wide range of ignition timings. The NO{sub x} emissions of this engine satisfy the Equivalent Zero Vehicle (EZEV) standard established by the California Resource Board.

Johnson, N.L.

1997-11-01T23:59:59.000Z

275

A LOW COST AND HIGH QUALITY SOLID FUEL FROM BIOMASS AND COAL FINES  

SciTech Connect

Use of biomass wastes as fuels in existing boilers would reduce greenhouse gas emissions, SO2 and NOx emissions, while beneficially utilizing wastes. However, the use of biomass has been limited by its low energy content and density, high moisture content, inconsistent configuration and decay characteristics. If biomass is upgraded by conventional methods, the cost of the fuel becomes prohibitive. Altex has identified a process, called the Altex Fuel Pellet (AFP) process, that utilizes a mixture of biomass wastes, including municipal biosolids, and some coal fines, to produce a strong, high energy content, good burning and weather resistant fuel pellet, that is lower in cost than coal. This cost benefit is primarily derived from fees that are collected for accepting municipal biosolids. Besides low cost, the process is also flexible and can incorporate several biomass materials of interest The work reported on herein showed the technical and economic feasibility of the AFP process. Low-cost sawdust wood waste and light fractions of municipal wastes were selected as key biomass wastes to be combined with biosolids and coal fines to produce AFP pellets. The process combines steps of dewatering, pellet extrusion, drying and weatherizing. Prior to pilot-scale tests, bench-scale test equipment was used to produce limited quantities of pellets for characterization. These tests showed which pellet formulations had a high potential. Pilot-scale tests then showed that extremely robust pellets could be produced that have high energy content, good density and adequate weatherability. It was concluded that these pellets could be handled, stored and transported using equipment similar to that used for coal. Tests showed that AFP pellets have a high combustion rate when burned in a stoker type systems. While NOx emissions under stoker type firing conditions was high, a simple air staging approach reduced emissions to below that for coal. In pulverized-fuel-fired tests it was found that the ground pellets could be used as an effective NOx control agent for pulverized-coal-fired systems. NOx emissions reductions up to 63% were recorded, when using AFP as a NOx control agent. In addition to performance benefits, economic analyses showed the good economic benefits of AFP fuel. Using equipment manufacturer inputs, and reasonable values for biomass, biosolids and coal fines costs, it was determined that an AFP plant would have good profitability. For cases where biosolids contents were in the range of 50%, the after tax Internal Rates of Return were in the range of 40% to 50%. These are very attractive returns. Besides the baseline analysis for the various AFP formulations tested at pilot scale, sensitivity analysis showed the impact of important parameters on return. From results, it was clear that returns are excellent for a range of parameters that could be expected in practice. Importantly, these good returns are achieved even without incentives related to the emissions control benefits of biomass.

John T. Kelly; George Miller; Mehdi Namazian

2001-07-01T23:59:59.000Z

276

350 MW(t) design fuel cycle selection. Revision 1  

Science Conference Proceedings (OSTI)

This document discusses the results of this evaluation and a recommendation to retain the graded fuel cycle in which one-half of the fuel elements are exchanged at each refueling. This recommendation is based on the better performance of the graded cycle relative to the evaluation criteria of both economics and control margin. A choice to retain the graded cycle and a power density of 5.9 MW/m{sup 3} for the upcoming conceptual design phase was deemed prudent for the following reasons: the graded cycle has significantly better economics, and essentially the same expected availability factor as the batch design, when both are evaluated against the same requirements, including water ingress; and the reduction in maximum fuel pin power peaking in the batch design compared to the graded cycle is only a few percent and gas hot streaks are not improved by changing to a batch cycle. The preliminary 2-D power distribution studies for both designs showed that maximum fuel pin power peaking, particularly near the inner reflector, was high for both designs and nearly the same in magnitude. 10 figs., 9 tabs.

Lane, R.K.; Lefler, W.; Shirley, G.

1986-01-01T23:59:59.000Z

277

Irradiation performance of fast reactor MOX fuel pins with ferritic/martensitic cladding irradiated to high burnups  

Science Conference Proceedings (OSTI)

The ACO-3 irradiation test, which attained extremely high burnups of about 232 GWd/t and resisted a high neutron fluence (E > 0.1 MeV) of about 39 × 1026 n/m2 as one of the lead tests of the Core Demonstration Experiment in the Fast Flux Test Facility, demonstrated that the fuel pin cladding made of ferritic/martensitic HT-9 alloy had superior void swelling resistance. The measured diameter profiles of the irradiated ACO-3 fuel pins showed axially extensive incremental strain in the MOX fuel column region and localized incremental strain near the interfaces between the MOX fuel and upper blanket columns. These incremental strains were as low as 1.5% despite the extremely high level of the fast neutron fluence. Evaluation of the pin diametral strain indicated that the incremental strain in the MOX fuel column region was substantially due to cladding void swelling and irradiation creep caused by internal fission gas pressure, while the localized strain near the MOX fuel/upper blanket interface was likely the result of the pellet/cladding mechanical interaction (PCMI) caused by cesium/fuel reactions. The evaluation also suggested that the PCMI was effectively mitigated by a large gap size between the cladding and blanket column.

Tomoyuki Uwaba; Masahiro Ito; Kozo Katsuyama; Bruce J. Makenas; David W. Wootan; Jon Carmack

2011-05-01T23:59:59.000Z

278

Irradiation performance of fast reactor MOX fuel pins with ferritic/martensitic cladding irradiated to high burnups  

Science Conference Proceedings (OSTI)

The ACO-3 irradiation test, which attained extremely high burnups of about 232 GWd/t and resisted a high neutron fluence (E > 0.1 MeV) of about 39E26 n/m2 as one of the lead tests of the Core Demonstration Experiment in the Fast Flux Test Facility, demonstrated that the fuel pin cladding made of ferritic/martensitic HT-9 alloy had superior void swelling resistance. The measured diameter profiles of the irradiated ACO-3 fuel pins showed axially extensive incremental strain in the MOX fuel column region and localized incremental strain near the interfaces between the MOX fuel and upper blanket columns. These incremental strains were as low as 1.5% despite the extremely high level of the fast neutron fluence. Evaluation of the pin diametral strain indicated that the incremental strain in the MOX fuel column region was substantially due to cladding void swelling and irradiation creep caused by internal fission gas pressure, while the localized strain near the MOX fuel/upper blanket interface was likely the result of the pellet/cladding mechanical interaction (PCMI) caused by cesium/fuel reactions. The evaluation also suggested that the PCMI was effectively mitigated by a large gap size between the cladding and blanket column.

Uwaba, Tomoyuki; Ito, Masahiro; Mizuno, Tomoyasu; Katsuyama, Kozo; Makenas, Bruce J.; Wootan, David W.; Carmack, Jon

2011-06-16T23:59:59.000Z

279

Certification challenges in the development of an innovative high payload capacity spent fuel transportation cask  

SciTech Connect

The design approach and certification strategy used in the development of an innovative transportation cask for legal weight truck shipments of spent nuclear fuel is presented. The proposed approach represents a significant departure from conventional cask designs in that it uses titanium alloy, a material with a high strength-to-weight ratio which has no precedent in transportation cask certification. The significant increase in payload obtainable with the proposed approach, and the associated benefits such as reduced life cycle costs, lower personnel exposure, and lower transportation accident risks are discussed. 8 refs., 3 figs., 1 tab.

Mair, B.R.; Severson, M.J.; Ciez, A.P. (Westinghouse Electric Corp., Pittsburgh, PA (USA))

1990-01-01T23:59:59.000Z

280

Sealant materials for solid oxide fuels and other high-temperature ceramics  

DOE Green Energy (OSTI)

Glass-ceramic sealing materials have been developed with mechanical and chemical properties suitable for a variety of high-temperature applications. We have demonstrated the ability to tailor the thermal expansion coefficient between 8 and 12 x 10{sup -6}/{degrees}C, and the softening temperature can be adjusted such that the materials have suitable viscosities for a soft, compliant seal at temperatures ranging from 650 to 1000{degrees}C. These materials form excellent bonds to a variety of ceramics and metals during heating to the target operation temperature. They have limited reactivity with the fuel cell materials tested and are stable in both air and reducing environments.

Kueper, T.W.; Bloom, I.D.

1995-12-31T23:59:59.000Z

Note: This page contains sample records for the topic "high grade fuel" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


281

CSP Policies & Procedures Process for Grade Appeals  

E-Print Network (OSTI)

CSP Policies & Procedures Process for Grade Appeals Grade Appeals ­ Generally speaking, once grades

Leistikow, Bruce N.

282

Coal-fueled high-speed diesel engine development. Final report, September 28, 1990--November 30, 1993  

DOE Green Energy (OSTI)

The goal of this program was to study the feasibility of operating a Detroit Diesel Series 149 engine at high speeds using a Coal-Water-Slurry (CWS) fuel. The CWS-fueled 149 engine is proposed for the mine-haul off-highway truck and work boat marine markets. Economic analysis studies indicate that, for these markets, the use of CWS fuel could have sufficient operating cost savings, depending upon the future diesel fuel price, emission control system capital and operating costs, and maintenance and overhaul costs. A major portion of the maintenance costs is expected to be due to lower life and higher cost of the CWS injectors. Injection and combustion systems were specially designed for CWS, and were installed in one cylinder of a Detroit Diesel 8V-149TI engine for testing. The objective was to achieve engine operation for sustained periods at speeds up to 1,900 rpm with reasonable fuel economy and coal burnout rate. A computer simulation predicted autoignition of coal fuel at 1,900 rpm would require an average droplet size of 18 microns and 19:1 compression ratio, so the injection system, and pistons were designed accordingly. The injection system was capable of supplying the required volume of CWS/injection with a duration of approximately 25 crank angle degrees and peak pressures on the order of 100 mpa. In addition to the high compression ratio, the combustion system also utilized hot residual gases in the cylinder, warm inlet air admission and ceramic insulated engine components to enhance combustion. Autoignition of CWS fuel was achieved at 1900 rpm, at loads ranging from 20--80 percent of the rated load of diesel-fuel powered cylinders. Limited emissions data indicates coal burnout rates in excess of 99 percent. NO{sub x} levels were significantly lower, while unburned hydrocarbon levels were higher for the CWS fueled cylinder than for corresponding diesel-fuel powered cylinders.

Kakwani, R.M.; Winsor, R.E.; Ryan, T.W. III; Schwalb, J.A.; Wahiduzzaman, S.; Wilson, R.P. Jr.

1993-09-01T23:59:59.000Z

283

Multiphysics Simulations of the Complex 3D Geometry of the High Flux Isotope Reactor Fuel Elements Using COMSOL  

Science Conference Proceedings (OSTI)

A research and development project is ongoing to convert the currently operating High Flux Isotope Reactor (HFIR) of Oak Ridge National Laboratory (ORNL) from highly-enriched Uranium (HEU U3O8) fuel to low-enriched Uranium (LEU U-10Mo) fuel. Because LEU HFIR-specific testing and experiments will be limited, COMSOL is chosen to provide the needed multiphysics simulation capability to validate against the HEU design data and calculations, and predict the performance of the LEU fuel for design and safety analyses. The focus of this paper is on the unique issues associated with COMSOL modeling of the 3D geometry, meshing, and solution of the HFIR fuel plate and assembled fuel elements. Two parallel paths of 3D model development are underway. The first path follows the traditional route through examination of all flow and heat transfer details using the Low-Reynolds number k-e turbulence model provided by COMSOL v4.2. The second path simplifies the fluid channel modeling by taking advantage of the wealth of knowledge provided by decades of design and safety analyses, data from experiments and tests, and HFIR operation. By simplifying the fluid channel, a significant level of complexity and computer resource requirements are reduced, while also expanding the level and type of analysis that can be performed with COMSOL. Comparison and confirmation of validity of the first (detailed) and second (simplified) 3D modeling paths with each other, and with available data, will enable an expanded level of analysis. The detailed model will be used to analyze hot-spots and other micro fuel behavior events. The simplified model will be used to analyze events such as routine heat-up and expansion of the entire fuel element, and flow blockage. Preliminary, coarse-mesh model results of the detailed individual fuel plate are presented. Examples of the solution for an entire fuel element consisting of multiple individual fuel plates produced by the simplified model are also presented.

Freels, James D [ORNL; Jain, Prashant K [ORNL

2011-01-01T23:59:59.000Z

284

LOW-TEMPERATURE, ANODE-SUPPORTED HIGH POWER DENSITY SOLID OXIDE FUEL CELLS WITH NANOSTRUCTURED ELECTRODES  

DOE Green Energy (OSTI)

This report summarizes the work done during the entire project period, between October 1, 1999 and March 31, 2003, which includes a six-month no-cost extension. During the project, eight research papers have, either been, published, accepted for publication, or submitted for publication. In addition, several presentations have been made in technical meetings and workshops. The project also has provided support for four graduate students working towards advanced degrees. The principal technical objective of the project was to analyze the role of electrode microstructure on solid oxide fuel cell performance. Prior theoretical work conducted in our laboratory demonstrated that the particle size of composite electrodes has a profound effect on cell performance; the finer the particle size, the lower the activation polarization, the better the performance. The composite cathodes examined consisted of electronically conducting perovskites such as Sr-doped LaMnO{sub 3} (LSM) or Sr-doped LaCoO{sub 3} (LSC), which is also a mixed conductor, as the electrocatalyst, and yttria-stabilized zirconia (YSZ) or rare earth oxide doped CeO{sub 2} as the ionic conductor. The composite anodes examined were mixtures of Ni and YSZ. A procedure was developed for the synthesis of nanosize YSZ by molecular decomposition, in which unwanted species were removed by leaching, leaving behind nanosize YSZ. Anode-supported cells were made using the as-synthesized powders, or using commercially acquired powders. The electrolyte was usually a thin ({approx}10 microns), dense layer of YSZ, supported on a thick ({approx}1 mm), porous Ni + YSZ anode. The cathode was a porous mixture of electrocatalyst and an ionic conductor. Most of the cell testing was done at 800 C with hydrogen as fuel and air as the oxidant. Maximum power densities as high as 1.8 W/cm{sup 2} were demonstrated. Polarization behavior of the cells was theoretically analyzed. A limited amount of cell testing was done using liquid hydrocarbon fuels where reforming was achieved internally. Significant polarization losses also occur at the anode, especially at high fuel utilizations. An analysis of polarization losses requires that various contributions are isolated, and their dependence on pertinent parameters is quantitatively described. An investigation of fuel composition on gas transport through porous anodes was investigated and the role of fuel diluents was explored. This work showed that the molecular weight of the diluent has a significant effect on anode concentration polarization. This further showed that the presence of some molecular hydrogen is necessary to minimize polarization losses. Theoretical analysis has shown that the electrode microstructure has a profound effect on cell performance. In a series of experiments, cathode microstructural parameters were varied, without altering other parameters. Cathode microstructural parameters, especially three phase boundary (TPB) length, were estimated using techniques in quantitative stereology. Cell performance was quantitatively correlated with the relevant microstructural parameters, and charge transfer resistivity was explicitly evaluated. This is the first time that a fundamental parameter, which governs the activation polarization, has been quantitatively determined. An important parameter, which governs the cathodic activation polarization, and thus cell performance, is the ionic conductivity of the composite cathode. The traditional composite cathode is a mixture of LSM and YSZ. It is well known that Sr and Mg-doped LaGaO{sub 3} (LSGM), exhibits higher oxygen ion conductivity compared to YSZ. Cells were fabricated with composite cathodes comprising a mixture of LSM and LSGM. Studies demonstrated that LSGM-based composite cathodes exhibit excellent behavior. Studies have shown that Ni + YSZ is an excellent anode. In fact, in most cells, the principal polarization losses, at least at low fuel utilizations, are associated with the cathode. Theoretical analysis conducted in our group has also shown that anode-supported cells exhibi

Professor Anil V. Virkar

2003-05-23T23:59:59.000Z

285

Coal-fueled high-speed diesel engine development. Annual technical progress report, October 1990--September 1991  

DOE Green Energy (OSTI)

The objectives of this program are to study combustion feasibility by running Series 149 engine tests at high speeds with a fuel injection and combustion system designed for coal-water-slurry (CWS). The following criteria will be used to judge feasibility: (1) engine operation for sustained periods over the load range at speeds from 600 to 1900 rpm. The 149 engine for mine-haul trucks has a rated speed of 1900 rpm; (2) reasonable fuel economy and coal burnout rate; (3) reasonable cost of the engine design concept and CWS fuel compared to future oil prices.

Not Available

1991-11-01T23:59:59.000Z

286

Development and Demonstration of a New Generation High Efficiency 10kW Stationary Fuel Cell System  

SciTech Connect

The overall project objective is to develop and demonstrate a polymer electrolyte membrane fuel cell combined heat and power (PEMFC CHP) system that provides the foundation for commercial, mass produced units which achieve over 40% electrical efficiency (fuel to electric conversion) from 50-100% load, greater than 70% overall efficiency (fuel to electric energy + usable waste heat energy conversion), have the potential to achieve 40,000 hours durability on all major process components, and can be produced in high volumes at under $400/kW (revised to $750/kW per 2011 DOE estimates) capital cost.

Howell, Thomas Russell

2013-04-30T23:59:59.000Z

287

Fluoride-Salt-Cooled High-Temperature Reactor (FHR) with Silicon-Carbide-Matrix Coated-Particle Fuel  

Science Conference Proceedings (OSTI)

The FHR is a new reactor concept that uses coated-particle fuel and a low-pressure liquid-salt coolant. Its neutronics are similar to a high-temperature gas-cooled reactor (HTGR). The power density is 5 to 10 times higher because of the superior cooling properties of liquids versus gases. The leading candidate coolant salt is a mixture of {sup 7}LiF and BeF{sub 2} (FLiBe) possessing a boiling point above 1300 C and the figure of merit {rho}C{sub p} (volumetric heat capacity) for the salt slightly superior to water. Studies are underway to define a near-term base-line concept while understanding longer-term options. Near-term options use graphite-matrix coated-particle fuel where the graphite is both a structural component and the primary neutron moderator. It is the same basic fuel used in HTGRs. The fuel can take several geometric forms with a pebble bed being the leading contender. Recent work on silicon-carbide-matrix (SiCm) coated-particle fuel may create a second longer-term fuel option. SiCm coated-particle fuels are currently being investigated for use in light-water reactors. The replacement of the graphite matrix with a SiCm creates a new family of fuels. The first motivation behind the effort is to take advantage of the superior radiation resistance of SiC compared to graphite in order to provide a stable matrix for hosting coated fuel particles. The second motivation is a much more rugged fuel under accident, repository, and other conditions.

Forsberg, C. W. [Massachusetts Institute of Technology (MIT); Terrani, Kurt A [ORNL; Snead, Lance Lewis [ORNL; Katoh, Yutai [ORNL

2012-01-01T23:59:59.000Z

288

EPRI Review of Geologic Disposal for Used Fuel and High Level Radioactive Waste: Volume IV - Lessons Learned  

Science Conference Proceedings (OSTI)

The effective termination of the Yucca Mountain program by the U.S. Administration in 2009 has further delayed the construction and operation of a permanent disposal facility for used fuel and high level radioactive waste (HLW) in the United States. In concert with this decision, the President directed the Energy Secretary to establish the Blue Ribbon Commission on America's Nuclear Future to review and provide recommendations on options for managing used fuel and HLW. EPRI is uniquely positioned to prov...

2010-09-29T23:59:59.000Z

289

Co-firing high sulfur coal with refuse derived fuels. Technical progress report No. 6, January--March 1996  

DOE Green Energy (OSTI)

The objectives for this quarter of study on the co-firing of high sulfur coals with refuse derived fuels were two-fold. First, the effects of different experimental parameters such as temperature, flow rates and reaction times on the formation of chlorinated organic compounds were studied using the tubular furnace as a reactor followed by GC/MS analysis. Secondly, the effect of fuel/air ratio on the flue gas composition and combustion efficiency were studied with the AFBC system.

Pan, W.P.; Riley, J.T.; Lloyd, W.G.

1996-02-29T23:59:59.000Z

290

High Purity Americium-241 for Fuel Cycle R&D Program  

SciTech Connect

Previously the U.S. Department of Energy released Am-241 for various applications such as smoke detectors and Am-Be neutron sources for oil wells. At this date there is a shortage of usable, higher purity Am-241 in metal and oxide form available in the United States. Recently, the limited source of Am-241 has been from Russia with production being contracted to existing customers. The shortage has resulted in the price per gram rising dramatically over the last few years. DOE-NE currently has need for high purity Am-241 metal and oxide to fabricate fuel pellets for reactor testing in the Fuel Cycle R&D program. All the available high purity americium has been gathered from within the DOE system of laboratories. However, this is only a fraction of the projected needs of FCRD over the next 10 years. Therefore, FCR&D has proposed extraction and purification concepts to extract Am-241 from a mixed AmO2-PuO2 feedstock stored at the Savannah River Site. The most simple extraction system is based upon high temperature reduction using lanthanum metal with concurrent evaporation and condensation to produce high purity Am metal. Metallic americium has over a four order of magnitude higher vapor pressure than plutonium. Results from small-scale reduction experiments are presented. These results confirm thermodynamic predictions that at 1000 deg C metallic lanthanum reduces both PuO2 and AmO2. Faster kinetics are expected for temperatures up to about 1500 deg C.

Dr. Paul A. Lessing

2011-07-01T23:59:59.000Z

291

Application of Self-Propagating High Temperature Synthesis to the Fabrication of Actinide Bearing Nitride and Other Ceramic Nuclear Fuels  

SciTech Connect

The project uses an exothermic combustion synthesis reaction, termed self-propagating high-temperature synthesis (SHS), to produce high quality, reproducible nitride fuels and other ceramic type nuclear fuels (cercers and cermets, etc.) in conjunction with the fabrication of transmutation fuels. The major research objective of the project is determining the fundamental SHS processing parameters by first using manganese as a surrogate for americium to produce dense Zr-Mn-N ceramic compounds. These fundamental principles will then be transferred to the production of dense Zr-Am-N ceramic materials. A further research objective in the research program is generating fundamental SHS processing data to the synthesis of (i) Pu-Am-Zr-N and (ii) U-Pu-Am-N ceramic fuels. In this case, Ce will be used as the surrogate for Pu, Mn as the surrogate for Am, and depleted uranium as the surrogate for U. Once sufficient fundamental data has been determined for these surrogate systems, the information will be transferred to Idaho National Laboratory (INL) for synthesis of Zr-Am-N, Pu-Am-Zr-N and U-Pu-Am-N ceramic fuels. The high vapor pressures of americium (Am) and americium nitride (AmN) are cause for concern in producing nitride ceramic nuclear fuel that contains Am. Along with the problem of Am retention during the sintering phases of current processing methods, are additional concerns of producing a consistent product of desirable homogeneity, density and porosity. Similar difficulties have been experienced during the laboratory scale process development stage of producing metal alloys containing Am wherein compact powder sintering methods had to be abandoned. Therefore, there is an urgent need to develop a low-temperature or low–heat fuel fabrication process for the synthesis of Am-containing ceramic fuels. Self-propagating high temperature synthesis (SHS), also called combustion synthesis, offers such an alternative process for the synthesis of Am nitride fuels. Although SHS takes thermodynamic advantage of the high combustion temperatures of these exothermic SHS reactions to synthesize the required compounds, the very fast heating, reaction and cooling rates can kinetically generate extremely fast reaction rates and facilitate the retention of volatile species within the rapidly propagating SHS reaction front. The initial objective of the research program is to use Mn as the surrogate for Am to synthesize a reproducible, dense, high quality Zr-Mn-N ceramic compound. Having determined the fundamental SHS reaction parameters and optimized SHS processing steps using Mn as the surrogate for Am, the technology will be transferred to Idaho National Laboratory to successfully synthesize a high quality Zr-Am-N ceramic fuel.

John J. Moore, Marissa M. Reigel, Collin D. Donohoue

2009-04-30T23:59:59.000Z

292

High Efficiency Generation of Hydrogen Fuels using Nuclear Power Annual Report August, 2000 - July 2001  

DOE Green Energy (OSTI)

OAK B188 High Efficiency Generation of Hydrogen Fuels using Nuclear Power Annual Report August 2000 - July 2001. Currently no large scale, cost-effective, environmentally attractive hydrogen production process is available for commercialization nor has such a process been identified. Hydrogen is a promising energy carrier, which potentially could replace the fossil fuels used in the transportation sector of our economy. Carbon dioxide emissions from fossil fuel combustion are thought to be responsible for global warming. The purpose of this work is to determine the potential for efficient, cost-effective, large-scale production of hydrogen utilizing high temperature heat from an advanced nuclear power station. The benefits of this work will include the generation of a low-polluting transportable energy feedstock in an efficient method that has little or no implication for greenhouse gas emissions from a primary energy source whose availability and sources are domestically controlled. This will help to ensure energy for a future transportation/energy infrastructure that is not influenced/controlled by foreign governments. This report describes work accomplished during the second year (Phase 2) of a three year project whose objective is to ''define an economically feasible concept for production of hydrogen, by nuclear means, using an advanced high temperature nuclear reactor as the energy source.'' The emphasis of the first year (Phase 1) was to evaluate thermochemical processes which offer the potential for efficient, cost-effective, large-scale production of hydrogen from water, in which the primary energy input is high temperature heat from an advanced nuclear reactor and to select one (or, at most, three) for further detailed consideration. Phase 1 met its goals and did select one process, the sulfur-iodine process, for investigation in Phases 2 and 3. The combined goals of Phases 2 and 3 were to select the advanced nuclear reactor best suited to driving the selected thermochemical process and to define the selected reactor and process to the point that capital costs, operating costs and the resultant cost of hydrogen can be estimated. During original contract negotiation, it was necessary to reduce work scope to meet funding limits. As a result, the reactor interface and process will not be iterated to the point that only hydrogen is produced. Rather, hydrogen and electricity will be co-generated and the hydrogen cost will be stated as a function of the electricity sales price.

Brown, L.C.

2002-11-01T23:59:59.000Z

293

High Efficiency Generation of Hydrogen Fuels using Nuclear Power Annual Report August, 2000 - July 2001  

SciTech Connect

OAK B188 High Efficiency Generation of Hydrogen Fuels using Nuclear Power Annual Report August 2000 - July 2001. Currently no large scale, cost-effective, environmentally attractive hydrogen production process is available for commercialization nor has such a process been identified. Hydrogen is a promising energy carrier, which potentially could replace the fossil fuels used in the transportation sector of our economy. Carbon dioxide emissions from fossil fuel combustion are thought to be responsible for global warming. The purpose of this work is to determine the potential for efficient, cost-effective, large-scale production of hydrogen utilizing high temperature heat from an advanced nuclear power station. The benefits of this work will include the generation of a low-polluting transportable energy feedstock in an efficient method that has little or no implication for greenhouse gas emissions from a primary energy source whose availability and sources are domestically controlled. This will help to ensure energy for a future transportation/energy infrastructure that is not influenced/controlled by foreign governments. This report describes work accomplished during the second year (Phase 2) of a three year project whose objective is to ''define an economically feasible concept for production of hydrogen, by nuclear means, using an advanced high temperature nuclear reactor as the energy source.'' The emphasis of the first year (Phase 1) was to evaluate thermochemical processes which offer the potential for efficient, cost-effective, large-scale production of hydrogen from water, in which the primary energy input is high temperature heat from an advanced nuclear reactor and to select one (or, at most, three) for further detailed consideration. Phase 1 met its goals and did select one process, the sulfur-iodine process, for investigation in Phases 2 and 3. The combined goals of Phases 2 and 3 were to select the advanced nuclear reactor best suited to driving the selected thermochemical process and to define the selected reactor and process to the point that capital costs, operating costs and the resultant cost of hydrogen can be estimated. During original contract negotiation, it was necessary to reduce work scope to meet funding limits. As a result, the reactor interface and process will not be iterated to the point that only hydrogen is produced. Rather, hydrogen and electricity will be co-generated and the hydrogen cost will be stated as a function of the electricity sales price.

Brown, L.C.

2002-11-01T23:59:59.000Z

294

Assessment of helical-cruciform fuel rods for high power density LWRs  

E-Print Network (OSTI)

In order to significantly increase the power density of Light Water Reactors (LWRs), the helical-cruciform (HC) fuel rod assembly has been proposed as an alternative to traditional fuel geometry. The HC assembly is a ...

Conboy, Thomas M

2010-01-01T23:59:59.000Z

295

Design of high-ionic conductivity electrodes for direct methanol fuel cells  

E-Print Network (OSTI)

Carbon-supported porous electrodes are used in low-temperature fuel cells to provide maximum catalyst surface area, while taking up little volume and using minimum catalyst material. In Direct Methanol Fuel Cells (DMFCs), ...

Schrauth, Anthony J

2011-01-01T23:59:59.000Z

296

Highly porous platinum electrodes for the use in potentially implantable glucose fuel cells.  

E-Print Network (OSTI)

??Implantable glucose fuel cells are investigated as self-regenerative, long-term approach to power medical implants such as cardiac pacemakers. Such fuel cells use ambient energy of… (more)

Kloke, Arne

2012-01-01T23:59:59.000Z

297

Evaluation of high power density annular fuel application in the Korean OPR-1000 reactor  

E-Print Network (OSTI)

Compared to the traditional solid fuel geometry for PWRs, the internally and externally cooled annular fuel offers the potential to increase the core power density while maintaining or increasing safety margins. It is ...

Zhang, Liang, S.M. Massachusetts Institute of Technology

2009-01-01T23:59:59.000Z

298

Very High Temperature Reactor (VHTR) Deep Burn Core and Fuel Analysis -- Complete Design Selection for the Pebble Bed Reactor  

Science Conference Proceedings (OSTI)

The Deep-Burn (DB) concept focuses on the destruction of transuranic nuclides from used light water reactor fuel. These transuranic nuclides are incorporated into TRISO coated fuel particles and used in gas-cooled reactors with the aim of a fractional fuel burnup of 60 to 70% in fissions per initial metal atom (FIMA). This high performance is expected through the use of multiple recirculation passes of the fuel in pebble form without any physical or chemical changes between passes. In particular, the concept does not call for reprocessing of the fuel between passes. In principle, the DB pebble bed concept employs the same reactor designs as the presently envisioned low-enriched uranium core designs, such as the 400 MWth Pebble Bed Modular Reactor (PBMR-400). Although it has been shown in the previous Fiscal Year (2009) that a PuO2 fueled pebble bed reactor concept is viable, achieving a high fuel burnup, while remaining within safety-imposed prescribed operational limits for fuel temperature, power peaking and temperature reactivity feedback coefficients for the entire temperature range, is challenging. The presence of the isotopes 239-Pu, 240-Pu and 241-Pu that have resonances in the thermal energy range significantly modifies the neutron thermal energy spectrum as compared to a ”standard,” UO2-fueled core. Therefore, the DB pebble bed core exhibits a relatively hard neutron energy spectrum. However, regions within the pebble bed that are near the graphite reflectors experience a locally softer spectrum. This can lead to power and temperature peaking in these regions. Furthermore, a shift of the thermal energy spectrum with increasing temperature can lead to increased absorption in the resonances of the fissile Pu isotopes. This can lead to a positive temperature reactivity coefficient for the graphite moderator under certain operating conditions. The effort of this task in FY 2010 has focused on the optimization of the core to maximize the pebble discharge burnup level, while retaining its inherent safety characteristics. Using generic pebble bed reactor cores, this task will perform physics calculations to evaluate the capabilities of the pebble bed reactor to perform utilization and destruction of LWR used-fuel transuranics. The task will use established benchmarked models, and will introduce modeling advancements appropriate to the nature of the fuel considered (high TRU content and high burn-up).

B. Boer; A. M. Ougouag

2010-09-01T23:59:59.000Z

299

Introduction of Thorium-Based Fuels in High Conversion Pressurized Water Reactors  

Science Conference Proceedings (OSTI)

Regular Technical Paper / Special Issue on the Symposium on Radiation Effects in Ceramic Oxide and Novel LWR Fuels / Fission Reactors

V. Vallet; B. Gastaldi; J. Politello; A. Santamarina; L. Van Den Durpel

300

Tailored Macroporous SiCN and SiC Structures for High-Temperature Fuel Reforming**  

E-Print Network (OSTI)

. The catalytic reforming of hydrocarbons in a microreformer is an attractive approach to supply hydrogen to fuel

Kenis, Paul J. A.

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301

MODELING THE PERFORMANCE OF HIGH BURNUP THORIA AND URANIA PWR FUEL  

E-Print Network (OSTI)

Fuel performance models have been developed to assess the performance of ThO[subscript 2]-UO[subscript 2]

Long, Y.

302

Application of Self-Propagating High Temperature Synthesis to the Fabrication of Actinide Bearing Nitride and Other Ceramic Nuclear Fuels  

Science Conference Proceedings (OSTI)

The high vapor pressures of americium (Am) and americium nitride (AmN) are cause for concern in producing nitride ceramic nuclear fuel that contains Am. Along with the problem of Am retention during the sintering phases of current processing methods, are additional concerns of producing a consistent product of desirable homogeneity, density and porosity. Similar difficulties have been experienced during the laboratory scale process development stage of producing metal alloys containing Am wherein compact powder sintering methods had to be abandoned. Therefore, there is an urgent need to develop a low-temperature or low–heat fuel fabrication process for the synthesis of Am-containing ceramic fuels. Self-propagating high temperature synthesis (SHS), also called combustion synthesis, offers such an alternative process for the synthesis of Am nitride fuels. Although SHS takes thermodynamic advantage of the high combustion temperatures of these exothermic SHS reactions to synthesize the required compounds, the very fast heating, reaction and cooling rates can kinetically generate extremely fast reaction rates and facilitate the retention of volatile species within the rapidly propagating SHS reaction front. The initial objective of the research program is to use Mn as the surrogate for Am to synthesize a reproducible, dense, high quality Zr-Mn-N ceramic compound. Having determined the fundamental SHS reaction parameters and optimized SHS processing steps using Mn as the surrogate for Am, the technology will be transferred to Idaho National Laboratory to successfully synthesize a high quality Zr-Am-N ceramic fuel.

John J. Moore, Douglas E. Burkes, Collin D. Donohoue, Marissa M. Reigel, J. Rory Kennedy

2009-05-18T23:59:59.000Z

303

Development of high energy density fuels from mild gasification of coal. Final report  

SciTech Connect

METC has concluded that MCG technology has the potential to simultaneously satisfy the transportation and power generation fuel needs in the most cost-effective manner. MCG is based on low temperature pyrolysis, a technique known to the coal community for over a century. Most past pyrolysis developments were aimed at maximizing the liquids yield which results in a low quality tarry product requiring significant and capital intensive upgrading. By properly tailoring the pyrolysis severity to control the liquid yield-liquid quality relationship, it has been found that a higher quality distillate-boiling liquid can be readily ``skimmed`` from the coal. The resultant liquids have a much higher H/C ratio than conventional pyrolytic tars and therefore can be hydroprocessed at lower cost. These liquids are also extremely enriched in l-, 2-, and 3-ring aromatics. The co-product char material can be used in place of coal as a pulverized fuel (pf) for power generation in a coal combustor. In this situation where the original coal has a high sulfur content, the MCG process can be practiced with a coal-lime mixture and the calcium values retained on the char can tie up the unconverted coal sulfur upon pf combustion of the char. Lime has also been shown to improve the yield and quality of the MCG liquids.

Not Available

1991-12-01T23:59:59.000Z

304

High Temperature Fuel Cell (Phosphoric Acid) Manufacturing R&D  

NLE Websites -- All DOE Office Websites (Extended Search)

TEMPERATURE FUEL CELL TEMPERATURE FUEL CELL (PHOSPHORIC ACID) MANUFACTURING R&D Sridhar Kanuri Manager, Phosphoric acid fuel cells & fuel processing August 10 th , 2011 PAFC MANUFACTURING R&D Agenda PAFC cost challenge Manufacturing Cost reduction opportunities Summary PAFC SYSTEM OVERVIEW Overview Heaters Reactant manifolds Manifold adaptors Axial load system Pressure Plates Power take-off Coolant manifolds Insulation H frame Coolant hoses Cell stack Assembly Fuel Processing System Thermal Management System / Water Treatment System Power Supply System (CSA's) Electrical System Module Blower Skid Powerplant modules Cost reduction is being accomplished by incremental changes in technology and manufacturing Closing commercialization gap Continuous manufacturing

305

Lessons Learned from Practical Field Experience with High Pressure Gaseous Fuels  

NLE Websites -- All DOE Office Websites (Extended Search)

5/2010 5/2010 www.cleanvehicle.org 1 Lessons Learned from Practical Field Experience with High Pressure Gaseous Fuels DOE - DOT CNG - H 2 Workshop December 10, 2009 Douglas Horne, PE - CVEF President Rob Adams, P.Eng. - Marathon Technical Services The Facts  NGVs have been used in North America for over 30 years  Codes and Standards (C&S) provide opportunity for safe reliable operation of NGVs  C&S evolve with new technology and field experience  People make mistakes, continuous training is critical for safe operations  Cylinders have a limited life -track your cylinders! 2/25/2010 www.cleanvehicle.org 2 Incidents in North America  Since 1984 CVEF has recorded 97 incidents of which 67 involved CNG vehicles - 37 incidents involve either a CNG leak (15) or a

306

Mechanical properties of solid oxide fuel cell glass-ceramic seal at high temperatures  

DOE Green Energy (OSTI)

Mechanical properties of solid oxide fuel cell glass-ceramic seal material, G18, are studied at high temperatures. Samples of G18 are aged for either 4h or 100h, resulting in samples with different crystallinity. Reduced modulus, hardness, and time-dependent behavior are measured by nanoindentation. The nanoindentation is performed at room temperature, 550, 650, and 750°C, using loading rates of 5 mN/s and 25 mN/s. Results show a decrease in reduced modulus with increasing temperature, with significant decrease above the glass transition temperature (Tg). Hardness generally decreases with increasing temperature, with a slight increase before Tg for the 4h aged sample. Dwell tests show that creep increases with increasing temperature, but decrease with further aging.

Milhans, Jacqueline; Li, Dongsheng; Khaleel, Mohammad A.; Sun, Xin; Al-Haik, Marwan; Harris, Adrian; Garmestani, Hamid

2011-04-20T23:59:59.000Z

307

Method of Fabrication of High Power Density Solid Oxide Fuel Cells  

DOE Patents (OSTI)

A method for producing ultra-high power density solid oxide fuel cells (SOFCs). The method involves the formation of a multilayer structure cells wherein a buffer layer of doped-ceria is deposited intermediate a zirconia electrolyte and a cobalt iron based electrode using a colloidal spray deposition (CSD) technique. For example, a cobalt iron based cathode composed of (La,Sr)(Co,Fe)O(LSCF) may be deposited on a zirconia electrolyte via a buffer layer of doped-ceria deposited by the CSD technique. The thus formed SOFC have a power density of 1400 mW/cm.sup.2 at 600.degree. C. and 900 mW/cm.sup.2 at 700.degree. C. which constitutes a 2-3 times increased in power density over conventionally produced SOFCs.

Pham, Ai Quoc (San Jose, CA); Glass, Robert S. (Livermore, CA)

2008-09-09T23:59:59.000Z

308

Co-firing high sulfur coal with refuse derived fuels. Quarterly report, October - December 1996  

DOE Green Energy (OSTI)

The objectives of this quarter of study on the co-firing of high sulfur coal with refuse derived fuels project were two-fold. First, the effect of S0{sub 2} on the formation of chlorine during combustion processes was examined. To simulate the conditions used in the AFBC system, experiments were conducted in a quartz tube in an electrically heated furnace. The principle analytical technique used for identification of the products from this study was GC/MS. The evolved gas was trapped by an absorbent and analyzed with a GC/MS system. The preliminary results indicate an inhibiting effect of S0{sub 2} on the Deacon Reaction. Secondly, information on the evolution of chlorine, sulfur and organic compounds from coals 95031 and 95011 were studied with the AFBC system. 2 figs., 1 tab.

Pan, W.-P.; Riley, J.T.; Lloyd, W.G.

1996-12-01T23:59:59.000Z

309

Regenerative fuel cells for High Altitude Long Endurance Solar Powered Aircraft  

DOE Green Energy (OSTI)

High Altitude Long Endurance (HALE) unmanned missions appear to be feasible using a lightweight, high efficiency, span-loaded, Solar Powered Aircraft (SPA) which includes a Regenerative Fuel Cell (RFC) system and novel tankage for energy storage. An existing flightworthy electric powered flying wing design was modified to incorporate present and near-term technologies in energy storage, power electronics, aerodynamics, and guidance and control in order to design philosophy was to work with vendors to identify affordable near-term technological opportunities that could be applied to existing designs in order to reduce weight, increase reliability, and maintain adequate efficiency of components for delivery within 18 months. The energy storage subsystem for a HALE SPA is a key driver for the entire vehicle because it can represent up to half of the vehicle weight and most missions of interest require the specific energy to be considerably higher than 200 W-hr/kg for many cycles. This stringent specific energy requirement precludes the use of rechargeable batteries or flywheels and suggests examination of various RFC designs. An RFC system using lightweight tankage, a single fuel cell (FC) stack, and a single electrolyzer (EC) stack separated by the length of a spar segment (up to 39 ft), has specific energy of {approximately}300 W-hr/kg with 45% efficiency, which is adequate for HALE SPA requirements. However, this design has complexity and weight penalties associated with thermal management, electrical wiring, plumbing, and structural weight. A more elegant solution is to use unitized RFC stacks (reversible stacks that act as both FCs and ECs) because these systems have superior specific energy, scale to smaller systems more favorably, and have intrinsically simpler thermal management.

Mitlitsky, F.; Colella, N.J.; Myers, B. [Lawrence Livermore National Lab., CA (United States); Anderson, C.J. [Aero Vironment, Inc., Monrovia, CA (United States)

1993-06-02T23:59:59.000Z

310

Depletion Analysis of Modular High Temperature Gas-cooled Reactor Loaded with LEU/Thorium Fuel  

SciTech Connect

Thorium based fuel has been considered as an option to uranium-based fuel, based on considerations of resource utilization (Thorium is more widely available when compared to Uranium). The fertile isotope of Thorium (Th-232) can be converted to fissile isotope U-233 by neutron capture during the operation of a suitable nuclear reactor such as High Temperature Gas-cooled Reactor (HTGR). However, the fertile Thorium needs a fissile supporter to start and maintain the conversion process such as U-235 or Pu-239. This report presents the results of a study that analyzed the thorium utilization in a prismatic HTGR, namely Modular High Temperature Gas-Cooled Reactor (MHTGR) that was designed by General Atomics (GA). The collected for the modeling of this design come from Chapter 4 of MHTGR Preliminary Safety Information Document that GA sent to Department of Energy (DOE) on 1995. Both full core and unit cell models were used to perform this analysis using SCALE 6.1 and Serpent 1.1.18. Because of the long mean free paths (and migration lengths) of neutrons in HTRs, using a unit cell to represent a whole core can be non-trivial. The sizes of these cells were set to match the spectral index between unit cell and full core domains. It was found that for the purposes of this study an adjusted unit cell model is adequate. Discharge isotopics and one-group cross-sections were delivered to the transmutation analysis team. This report provides documentation for these calculations

Sonat Sen; Gilles Youinou

2013-02-01T23:59:59.000Z

311

Development and Evaluation of a Safeguards System Concept for a Pebble-Fueled High Temperature Gas-cooled Reactor  

E-Print Network (OSTI)

Pebble-fueled high temperature gas-cooled reactor (HTGR) technology was first developed by the Federal Republic of Germany in the 1950s. More recently, the design has been embraced by the People's Republic of China and the Republic of South Africa. Unlike light water reactors that generate heat from fuel assemblies comprised of fuel rods, pebble-fueled HTGRs utilize thousands of 60-mm diameter fuel spheres (pebbles) comprised of thousands of TRISO particles. As this reactor type is deployed across the world, adequate methods for safeguarding the reactor must be developed. Current safeguards methods for the pebble-fueled HTGR focus on extensive, redundant containment and surveillance (C/S) measures or a combination of item-type and bulk-type material safeguards measures to deter and detect the diversion of fuel pebbles. The disadvantages to these approaches are the loss of continuity of knowledge (CoK) when C/S systems fail, or are compromised, and the introduction of material unaccounted for (MUF). Either vulnerability can be exploited by an adversary to divert fuel pebbles from the reactor system. It was determined that a solution to maintaining CoK is to develop a system to identify each fuel pebble that is inserted and removed from the reactor. Work was performed to develop and evaluate the use of inert microspheres placed in each fuel pebble, whose random placement could be used as a fingerprint to identify the fuel pebble. Ultrasound imaging of 1 mm zirconium oxide microspheres was identified as a possible imaging system and microsphere material for the new safeguards system concept. The system concept was evaluated, and it was found that a minimum of three microspheres are necessary to create enough random fingerprints for 10,000,000 pebbles. It was also found that, over the lifetime of the reactor, less than 0.01% of fuel pebbles can be expected to have randomly the same microsphere fingerprint. From an MCNP 5.1 model, it was determined that less than fifty microspheres in each pebble will have no impact on the reactivity or temperature coefficient of reactivity of the reactor system. Finally, using an ultrasound system it was found that ultrasound waves can penetrate thin layers of graphite to image the microsphere fingerprint.

Gitau, Ernest Travis Ngure

2011-08-01T23:59:59.000Z

312

High Temperature Reactor (HTR) Deep Burn Core and Fuel Analysis: Design Selection for the Prismatic Block Reactor  

SciTech Connect

The Deep Burn (DB) Project is a U.S. Department of Energy sponsored feasibility study of Transuranic Management using high burnup fuel in the high temperature helium cooled reactor (HTR). The DB Project consists of seven tasks: project management, core and fuel analysis, spent fuel management, fuel cycle integration, TRU fuel modeling, TRU fuel qualification, and HTR fuel recycle. In the Phase II of the Project, we conducted nuclear analysis of TRU destruction/utilization in the HTR prismatic block design (Task 2.1), deep burn fuel/TRISO microanalysis (Task 2.3), and synergy with fast reactors (Task 4.2). The Task 2.1 covers the core physics design, thermo-hydraulic CFD analysis, and the thermofluid and safety analysis (low pressure conduction cooling, LPCC) of the HTR prismatic block design. The Task 2.3 covers the analysis of the structural behavior of TRISO fuel containing TRU at very high burnup level, i.e. exceeding 50% of FIMA. The Task 4.2 includes the self-cleaning HTR based on recycle of HTR-generated TRU in the same HTR. Chapter IV contains the design and analysis results of the 600MWth DB-HTR core physics with the cycle length, the average discharged burnup, heavy metal and plutonium consumptions, radial and axial power distributions, temperature reactivity coefficients. Also, it contains the analysis results of the 450MWth DB-HTR core physics and the analysis of the decay heat of a TRU loaded DB-HTR core. The evaluation of the hot spot fuel temperature of the fuel block in the DB-HTR (Deep-Burn High Temperature Reactor) core under full operating power conditions are described in Chapter V. The investigated designs are the 600MWth and 460MWth DB-HTRs. In Chapter VI, the thermo-fluid and safety of the 600MWth DB-HTRs has been analyzed to investigate a thermal-fluid design performance at the steady state and a passive safety performance during an LPCC event. Chapter VII describes the analysis results of the TRISO fuel microanalysis of the 600MWth and 450MWth DB-HTRs. The TRISO fuel microanalysis covers the gas pressure buildup in a coated fuel particle including helium production, the thermo-mechanical behavior of a CFP, the failure probabilities of CFPs, the temperature distribution in a CPF, and the fission product (FP) transport in a CFP and a graphite. In Chapter VIII, it contains the core design and analysis of sodium cooled fast reactor (SFR) with deep burn HTR reactor. It considers a synergistic combination of the DB-MHR and an SFR burner for a safe and efficient transmutation of the TRUs from LWRs. Chapter IX describes the design and analysis results of the self-cleaning (or self-recycling) HTR core. The analysis is considered zero and 5-year cooling time of the spent LWR fuels.

Francesco Venneri; Chang-Keun Jo; Jae-Man Noh; Yonghee Kim; Claudio Filippone; Jonghwa Chang; Chris Hamilton; Young-Min Kim; Ji-Su Jun; Moon-Sung Cho; Hong-Sik Lim; MIchael A. Pope; Abderrafi M. Ougouag; Vincent Descotes; Brian Boer

2010-09-01T23:59:59.000Z

313

High-bandwidth Modulation of H2/Syngas Fuel to Control Combustion Dynamics in Micro-Mixing Lean Premix Systems  

SciTech Connect

The goal of this program was to develop and demonstrate fuel injection technologies that will facilitate the development of cost-effective turbine engines for Integrated Gasification Combined Cycle (IGCC) power plants, while improving efficiency and reducing emissions. The program involved developing a next-generation multi-point injector with enhanced stability performance for lean premix turbine systems that burn hydrogen (H2) or synthesis gas (syngas) fuels. A previously developed injector that demonstrated superior emissions performance was improved to enhance static flame stability through zone staging and pilot sheltering. In addition, piezo valve technology was implemented to investigate the potential for enhanced dynamic stability through high-bandwidth modulation of the fuel supply. Prototype injector and valve hardware were tested in an atmospheric combustion facility. The program was successful in meeting its objectives. Specifically, the following was accomplished: Demonstrated improvement of lean operability of the Parker multi-point injector through staging of fuel flow and primary zone sheltering; Developed a piezo valve capable of proportional and high-bandwidth modulation of gaseous fuel flow at frequencies as high as 500 Hz; The valve was shown to be capable of effecting changes to flame dynamics, heat release, and acoustic signature of an atmospheric combustor. The latter achievement indicates the viability of the Parker piezo valve technology for use in future adaptively controlled systems for the mitigation of combustion instabilities, particularly for attenuating combustion dynamics under ultra-lean conditions.

Jeff Melzak; Tim Lieuwen; Adel Mansour

2012-01-31T23:59:59.000Z

314

New applications of high-temperature solar energy for the production of transportable fuels and chemicals and for energy storage  

DOE Green Energy (OSTI)

The solar fuels and chemicals study was limited to the examination of processes requiring temperatures in excess of 1000/sup 0/K since lower temperature processes had already been examined in studies concerned with the application of waste heat from nuclear power plants to industrial processes. In developing the carbon cycle processes, the primary activity included an extensive literature search and the thermodynamic evaluation of a number of candidate chemical cycles. Although both hydrogen and carbon closed- and open-loop chemical cycles were studied, it was concluded that the carbon cycles offered sufficient additional potential to warrant concentrating on them in subsequent work. The section on new ideas for transportable fuels presents the elements of a new concept for a carbon cycle recovery technique to produce transportable fuels. The elements discussed are sources of carbon dioxide, solar energy reduction of CO/sub 2/, potential carbon cycles, and use of carbon monoxide as fuel and feedstocks. Another section presents some new concepts for the use of high-temperature solar energy in the production of essential materials and for closed-loop chemical storage, as well as for the production of hydrogen as a fuel and open-loop applications. Potential problem areas pertinent to solar-derived fuels and chemicals have been identified. These problems are primarily associated with the limited high temperature experience in industry and include materials compatibility, separation of reaction products, development of solid electrolytes and high-temperature electrodes, selective emission of receiver coatings at high temperature, and a lack of chemical kinetics data, and high-temperature thermodynamic data.

Not Available

1979-01-19T23:59:59.000Z

315

Transmutation facility for weapons grade plutonium based on a tokamak fusion neutron source  

Science Conference Proceedings (OSTI)

It is suggested that weapons grade plutonium could be processed through a transmutation facility to build up sufficient actinide and fission product inventories to serve as a deterrent to diversion or theft, pending eventual use as nuclear reactor fuel. A transmutation facility consisting of a fusion neutron source surrounded by fuel assemblies containing the weapons grade plutonium in the form of PuO2 pebbles in a lithium slurry was investigated and found to be technically feasible. A design concept/operation scenario was developed for a facility which would be able to transmute the world's estimated inventory of weapons grade plutonium to 11% Pu-240 concentration in about 25 years. The fusion neutron source would be based on tokamak plasma operating conditions and magnet technology being qualified in ongoing R D programs, and the plutonium fuel would be based on existing technology. A new R D program would be required to qualify a refractory metal alloy structural material needed to handle the high heat fluxes. Extensions of existing technologies and acceleration of existing R D programs would seem to be adequate to qualify other technologies required for the facility.

Not Available

1994-09-01T23:59:59.000Z

316

Transmutation facility for weapons-grade plutonium disposition based on a tokamak fusion neutron source  

Science Conference Proceedings (OSTI)

It is suggested that weapons-grade plutonium could be processed through a transmutation facility to build up sufficient actinide and fission product inventories to serve as a deterrent to diversion or theft during subsequent storage, pending eventual use as fuel in commercial nuclear reactors. A transmutation facility consisting of a tokamak fusion neutron source surrounded by fuel assemblies containing the weapons-grade plutonium in the form of PuO{sub 2} pebbles in a lithium slurry is investigated. A design concept/operation scenario is developed for a facility that would be able to transmute the world`s estimated surplus inventory of weapons-grade plutonium to 11% {sup 240}Pu concentration in nearly 25 yr. The fusion neutron source would be based on plasma physics and plasma support technology being qualified in ongoing research and development (R&D) programs, and the plutonium fuel would be based on existing technology. A new R&D program would be required to qualify a refractory metal alloy structural material that would be needed to handle the high heat fluxes; otherwise, extensions of existing technologies and acceleration of existing R&D programs would seem to be adequate to qualify all required technologies. Such a facility might feasibly be deployed in 20 to 30 yr, or sooner with a crash program. 49 refs., 5 figs., 13 tabs.

Stacey, W.M.; Pilger, B.L.; Mowrey, J.A. [Georgia Inst. of Technology, Atlanta, GA (United States)] [and others

1995-05-01T23:59:59.000Z

317

Large-diameter, high-plutonium metallic fuel testing in EBR-II  

Science Conference Proceedings (OSTI)

The integral fast reactor (IFR) concept makes use of U-Pu-Zr metallic fuel alloys because of favorable core behavior characteristics and compatibility with a pyrometallurgical reprocessing scheme. Advanced reactor designs use U-x Pu-10 Zr (where 20 {le} x {le} 28). Most of the IFR fuel performance database was obtained with fuel containing {le}20 wt% Pu having a 0.439-cm diameter irradiated in cladding tubes having a 0.584-cm o.d. However, commercial implementations of the IFR concept (e.g., the advanced liquid-metal reactor by General Electric) will likely use fuel of larger diameter and plutonium contents {ge}20 wt%. The HT9 advanced driver fuel test, irradiated in Experimental Breeder Reactor II (EBR-II), was initiated to obtain irradiation performance data from larger diameter fuel cast with a range of plutonium compositions and clad in the reference cladding alloy HT9.

Crawford, D.C.; Hayes, S.L.; Pahl, R.G. [Argonne National Lab., Idaho Falls, ID (United States)

1994-12-31T23:59:59.000Z

318

Conceptual Process for the Manufacture of Low-Enriched Uranium/Molybdenum Fuel for the High Flux Isotope Reactor  

Science Conference Proceedings (OSTI)

The U.S. nonproliferation policy 'to minimize, and to the extent possible, eliminate the use of HEU in civil nuclear programs throughout the world' has resulted in the conversion (or scheduled conversion) of many of the U.S. research reactors from high-enriched uranium (HEU) to low-enriched uranium (LEU). A foil fuel appears to offer the best option for using a LEU fuel in the High Flux Isotope Reactor (HFIR) without degrading the performance of the reactor. The purpose of this document is to outline a proposed conceptual fabrication process flow sheet for a new, foil-type, 19.75%-enriched fuel for HFIR. The preparation of the flow sheet allows a better understanding of the costs of infrastructure modifications, operating costs, and implementation schedule issues associated with the fabrication of LEU fuel for HFIR. Preparation of a reference flow sheet is one of the first planning steps needed in the development of a new manufacturing capacity for low enriched fuels for U.S. research and test reactors. The flow sheet can be used to develop a work breakdown structure (WBS), a critical path schedule, and identify development needs. The reference flow sheet presented in this report is specifically for production of LEU foil fuel for the HFIR. The need for an overall reference flow sheet for production of fuel for all High Performance Research Reactors (HPRR) has been identified by the national program office. This report could provide a starting point for the development of such a reference flow sheet for a foil-based fuel for all HPRRs. The reference flow sheet presented is based on processes currently being developed by the national program for the LEU foil fuel when available, processes used historically in the manufacture of other nuclear fuels and materials, and processes used in other manufacturing industries producing a product configuration similar to the form required in manufacturing a foil fuel. The processes in the reference flow sheet are within the bounds of known technology and are adaptable to the high-volume production required to process {approx} 2.5 to 4 tons of U/Mo and produce {approx}16,000 flat plates for U.S. reactors annually ({approx}10,000 of which are needed for HFIR operations). The reference flow sheet is not intended to necessarily represent the best or the most economical way to manufacture a LEU foil fuel for HFIR but simply represents a 'snapshot' in time of technology and is intended to identify the process steps that will likely be required to manufacture a foil fuel. Changes in some of the process steps selected for the reference flow sheet are inevitable; however, no one step or series of steps dominates the overall flow sheet requirements. A result of conceptualizing a reference flow sheet was the identification of the greater number of steps required for a foil process when compared to the dispersion fuel process. Additionally, in most of the foil processing steps, bare uranium must be handled, increasing the complexity of these processing areas relative to current operations. Based on a likely total cost of a few hundred million dollars for a new facility, it is apparent that line item funding will be necessary and could take as much as 8 to 10 years to complete. The infrastructure cost could exceed $100M.

Sease, J.D.; Primm, R.T. III; Miller, J.H.

2007-09-30T23:59:59.000Z

319

Initial Screening of Thermochemical Water-Splitting Cycles for High Efficiency Generation of Hydrogen Fuels Using Nuclear Power  

DOE Green Energy (OSTI)

OAK B188 Initial Screening of Thermochemical Water-Splitting Cycles for High Efficiency Generation of Hydrogen Fuels Using Nuclear Power There is currently no large scale, cost-effective, environmentally attractive hydrogen production process, nor is such a process available for commercialization. Hydrogen is a promising energy carrier, which potentially could replace the fossil fuels used in the transportation sector of our economy. Fossil fuels are polluting and carbon dioxide emissions from their combustion are thought to be responsible for global warming. The purpose of this work is to determine the potential for efficient, cost-effective, large-scale production of hydrogen utilizing high temperature heat from an advanced nuclear power station. Almost 800 literature references were located which pertain to thermochemical production of hydrogen from water and over 100 thermochemical watersplitting cycles were examined. Using defined criteria and quantifiable metrics, 25 cycles have been selected for more detailed study.

Brown, L.C.; Funk, J.F.; Showalter, S.K.

1999-12-15T23:59:59.000Z

320

Dry Storage Demonstration for High-Burnup Spent Nuclear Fuel: Feasibility Study  

Science Conference Proceedings (OSTI)

Initially, casks for dry storage of spent fuel were licensed for assembly-average burnup of about 35 GWd/MTU. Over the last two decades, the discharge burnup of fuel has increased steadily and now routinely exceeds 45 GWd/MTU. This feasibility study examines the options available for conducting a confirmatory experimental program supporting regulatory acceptance of practical approaches for storing, and later transporting, spent fuel with burnup well in excess of 45 GWd/MTU under a dry, inert atmosphere.

2003-09-19T23:59:59.000Z

Note: This page contains sample records for the topic "high grade fuel" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


321

MEMS Fuel Cells--Low Temp--High Power Density - Energy Innovation ...  

Rechargeable batteries presently provide limited energy ... as well as to manufacture the fuel cell via a continuous integration ... Microfluidic systems with ...

322

Irradiation behavior of High-Burnup LWR-MOX (mixed-oxide) Fuels  

Science Conference Proceedings (OSTI)

About this Abstract. Meeting, 2014 TMS Annual Meeting & Exhibition. Symposium , Radiation Effects in Oxide Ceramics and Novel LWR Fuels. Presentation Title ...

323

P2-03: 3D Characterization of High Burn-up MOX Fuel  

Science Conference Proceedings (OSTI)

Currently fast reactor performance is largely defined by the limitations of the materials involved in reactors, especially the metallic or mixed oxide ((U, Pu)O2) fuel ...

324

A High Temperature Planar Solid Oxide Fuel Cell Operating on Phosphine Contaminated Coal Syngas.  

E-Print Network (OSTI)

??Solid oxide fuel cells that operate on phosphine contaminated coal syngas are subject to performance degradation due to alterations of the anode microstructure. Theoretical investigations… (more)

De Silva, Kandaudage Channa R.

2011-01-01T23:59:59.000Z

325

The selective catalytic cracking of Fischer-Tropsch liquids to high value transportation fuels. Final report  

DOE Green Energy (OSTI)

Amoco Oil Company, investigated a selective catalytic cracking process (FCC) to convert the Fischer-Tropsch (F-T) gasoline and wax fractions to high value transportation fuels. The primary tasks of this contract were to (1) optimize the catalyst and process conditions of the FCC process for maximum conversion of F-T wax into reactive olefins for later production of C{sub 4}{minus}C{sub 8} ethers, and (2) use the olefin-containing light naphtha obtained from FCC processing of the F-T wax as feedstock for the synthesis of ethers. The catalytic cracking of F-T wax feedstocks gave high conversions with low activity catalysts and low process severities. HZSM-5 and beta zeolite catalysts gave higher yields of propylene, isobutylene, and isoamylenes but a lower gasoline yield than Y zeolite catalysts. Catalyst selection and process optimization will depend on product valuation. For a given catalyst and process condition, Sasol and LaPorte waxes gave similar conversions and product selectivities. The contaminant iron F-T catalyst fines in the LaPorte wax caused higher coke and hydrogen yields.

Schwartz, M.M.; Reagon, W.J.; Nicholas, J.J.; Hughes, R.D.

1994-11-01T23:59:59.000Z

326

Experimental Investigation of the Effects of Fuel Characteristics on High Efficiency Clean Combustion (HECC) in a Light-Duty Diesel Engine  

Science Conference Proceedings (OSTI)

An experimental study was performed to understand fuel property effects on low temperature combustion (LTC) processes in a light-duty diesel engine. These types of combustion modes are often collectively referred to as high efficiency clean combustion (HECC). A statistically designed set of research fuels, the Fuels for Advanced Combustion Engines (FACE), were used for this study. Engine conditions consistent with low speed cruise (1500 rpm, 2.6 bar BMEP) were chosen for investigating fuel property effects on HECC operation in a GM 1.9-L common rail diesel engine. The FACE fuel matrix includes nine combinations of fuel properties including cetane number (30 to 55), aromatic contents (20 to 45 %), and 90 % distillation temperature (270 to 340 C). HECC operation was achieved with high levels of EGR and adjusting injection parameters, e.g. higher fuel rail pressure and single injection event, which is also known as Premixed Charge Compression Ignition (PCCI) combustion. Engine performance, pollutant emissions, and details of the combustion process are discussed in this paper. Cetane number was found to significantly affect the combustion process with variations in the start of injection (SOI) timing, which revealed that the ranges of SOI timing for HECC operation and the PM emission levels were distinctively different between high cetane number (55) and low cetane number fuels (30). Low cetane number fuels showed comparable levels of regulated gas emissions with high cetane number fuels and had an advantage in PM emissions.

Cho, Kukwon [ORNL; Han, Manbae [ORNL; Wagner, Robert M [ORNL; Sluder, Scott [ORNL

2009-01-01T23:59:59.000Z

327

High-silicon {sup 238}PuO{sub 2} fuel characterization study: Half module impact tests  

SciTech Connect

The General-Purpose Heat Source (GPHS) provides power for space missions by transmitting the heat of [sup 238]Pu decay to an array of thermoelectric elements. The modular GPHS design was developed to address both survivability during launch abort and return from orbit. Previous testing conducted in support of the Galileo and Ulysses missions documented the response of GPHSs to a variety of fragment- impact, aging, atmospheric reentry, and Earth-impact conditions. The evaluations documented in this report are part of an ongoing program to determine the effect of fuel impurities on the response of the heat source to conditions baselined during the Galileo/Ulysses test program. In the first two tests in this series, encapsulated GPHS fuel pellets containing high levels of silicon were aged, loaded into GPHS module halves, and impacted against steel plates. The results show no significant differences between the response of these capsules and the behavior of relatively low-silicon fuel pellets tested previously.

Reimus, M.A.H.

1997-01-01T23:59:59.000Z

328

Commercial Grade Dedication RM  

Energy.gov (U.S. Department of Energy (DOE))

The objective of this Standard Review Plan (SRP) on Commercial Grade Dedication (CGD) is to provide guidance for a uniform review of the CGD activities for office of Environmental Management...

329

Conversion of the University of Missouri-Rolla Reactor from high-enriched uranium to low-enriched uranium fuel  

SciTech Connect

The objectives of this project were to convert the UMR Reactor fuel from high-enriched uranium (HEU) to low-enriched uranium (LEU) fuel and to ship the HEU fuel back to the Department of Energy Savannah River Site. The actual core conversion was completed in the summer of 1992. The HEU fuel was offloaded to an onsite storage pit where it remained until July, 1996. In July, 1996, the HEU fuel was shipped to the DOE Savannah River Site. The objectives of the project have been achieved. DOE provided the following funding for the project. Several papers were published regarding the conversion project and are listed in the Attachment. In retrospect, the conversion project required much more time and effort than originally thought. Several difficulties were encountered including the unavailability of a shipping cask for several years. The authors are grateful for the generous funding provided by DOE for this project but wish to point out that much of their efforts on the conversion project went unfunded.

Bolon, A.E.; Straka, M.; Freeman, D.W.

1997-03-28T23:59:59.000Z

330

MOX Safety Fuels the Future  

E-Print Network (OSTI)

– Convert 34 metric tons of weapons-grade grade plutonium to mixed oxide (MOX) fuel for use in commercial power reactors • Positive Impact – Removes many warheads from the nuclear arsenal – Eliminates $500 million/year in security costs – Provides clean, carbon free energy that offsets over $21 billion in imported oil costs at $50/barrel

Walt Elliott; Cable Tray; Ap Reference Plant; La Hague

2007-01-01T23:59:59.000Z

331

Materials technology assessment of high-temperature solar receivers for fuels and chemicals production  

DOE Green Energy (OSTI)

Current interest in using solar thermal energy to produce fuels and chemicals has prompted an assessment of materials technology for five proposed designs of solar receivers. The principal process of interest is water splitting. Reaction schemes considered involve the high-temperature decomposition of sulfuric acid, and silicon carbide is the structural ceramic material usually considered most resistant to the conditions of this reaction. Hence we have assessed the fabricability of the designs from SiC for that reaction system, even though most designs envision use with air, helium, or nitrogen as a heat transfer medium. Honeycomb and hemispherical dome receivers have been fabricated from SiC. A receiver using planar coiled tubes has been fabricated from cordierite but not from SiC. Fabrication has not been demonstrated for helical coil and long tube designs. The last three of these should be fabricable with up to two years development. All lack the ultimate test: operational experience. The need for relable seals is common to all designs. Metallic gaskets are subject to corrosion, and ceramic and mechanical seals have not been demonstrated for the anticipated thermal cycling.

Tiegs, T.N.

1981-07-01T23:59:59.000Z

332

Co-firing high sulfur coal with refuse derived fuels. Technical report {number_sign}4  

DOE Green Energy (OSTI)

In order to study combustion performance under conditions similar to that in the AFBC system, the authors conducted a series of experiments at a heating rate of 100 C/min using the TGA/FTIR/MS system. Results indicate that more hydrocarbons are evolved at the faster heating rate, owing to incomplete combustion of the fuel. Chlorinated organic compounds can be formed at high heating rates. Certain oxidation products such as organic acids and alcohols are obtained at the slow heating rate. To simulate the conditions used in the atmospheric fluidized bed combustor (AFBC) at Western Kentucky University, studies were also conducted using a quartz tube in a tube furnace. The temperature conditions were kept identical to those of the combustor. The products evolved from the combustion of coal, PVC, and mixtures of the two were trapped in suitable solvents at different temperatures, and analyzed using the Shimadzu GC/MS system. The detection limits and the GC/MS analytical parameters were also established. The experiments were conducted keeping in mind the broader perspective; that of studying conditions conducive to the formation of chlorinated organic compounds from the combustion of coal/MSW blends. 32 figs., 16 tabs.

Pan, W.P.; Riley, J.T.; Lloyd, W.G.

1995-08-03T23:59:59.000Z

333

Safeguards-by-Design: Guidance for High Temperature Gas Reactors (HTGRs) With Pebble Fuel  

SciTech Connect

The following is a guidance document from a series prepared for the U.S. Department of Energy (DOE) National Nuclear Security Administration (NNSA), under the Next Generation Safeguards Initiative (NGSI), to assist facility designers and operators in implementing international Safeguards-by-Design (SBD). SBD has two main objectives: (1) to avoid costly and time consuming redesign work or retrofits of new nuclear fuel cycle facilities and (2) to make the implementation of international safeguards more effective and efficient at such facilities. In the long term, the attainment of these goals would save industry and the International Atomic Energy Agency (IAEA) time, money, and resources and be mutually beneficial. This particular safeguards guidance document focuses on pebble fuel high temperature gas reactors (HTGR). The purpose of the IAEA safeguards system is to provide credible assurance to the international community that nuclear material and other specified items are not diverted from peaceful nuclear uses. The safeguards system consists of the IAEA’s statutory authority to establish safeguards; safeguards rights and obligations in safeguards agreements and additional protocols; and technical measures implemented pursuant to those agreements. Of foremost importance is the international safeguards agreement between the country and the IAEA, concluded pursuant to the Treaty on the Non-Proliferation of Nuclear Weapons (NPT). According to a 1992 IAEA Board of Governors decision, countries must: notify the IAEA of a decision to construct a new nuclear facility as soon as such decision is taken; provide design information on such facilities as the designs develop; and provide detailed design information based on construction plans at least 180 days prior to the start of construction, and on "as-built" designs at least 180 days before the first receipt of nuclear material. Ultimately, the design information will be captured in an IAEA Design Information Questionnaire (DIQ), prepared by the facility operator, typically with the support of the facility designer. The IAEA will verify design information over the life of the project. This design information is an important IAEA safeguards tool. Since the main interlocutor with the IAEA in each country is the State Regulatory Authority/SSAC (or Regional Regulatory Authority, e.g. EURATOM), the responsibility for conveying this design information to the IAEA falls to the State Regulatory Authority/SSAC.

Philip Casey Durst; Mark Schanfein

2012-08-01T23:59:59.000Z

334

Turning Bacteria into Fuel: Cyanobacteria Designed for Solar-Powered Highly Efficient Production of Biofuels  

SciTech Connect

Broad Funding Opportunity Announcement Project: ASU is engineering a type of photosynthetic bacteria that efficiently produce fatty acids—a fuel precursor for biofuels. This type of bacteria, called Synechocystis, is already good at converting solar energy and carbon dioxide (CO2) into a type of fatty acid called lauric acid. ASU has modified the organism so it continuously converts sunlight and CO2 into fatty acids—overriding its natural tendency to use solar energy solely for cell growth and maximizing the solar-to-fuel conversion process. ASU’s approach is different because most biofuels research focuses on increasing cellular biomass and not on excreting fatty acids. The project has also identified a unique way to convert the harvested lauric acid into a fuel that can be easily blended with existing transportation fuels.

2010-01-01T23:59:59.000Z

335

Thermal-hydraulic analysis of cross-shaped spiral fuel in high power density BWRs  

E-Print Network (OSTI)

Preliminary analysis of the cross-shaped spiral (CSS) fuel assembly suggests great thermal-hydraulic upside. According to computational models, the increase in rod surface area, combined with an increase in coolant turbulence ...

Conboy, Thomas M

2007-01-01T23:59:59.000Z

336

Japan’s fossil-fueled generation remains high because of ...  

U.S. Energy Information Administration (EIA)

Japan's use of fossil-fueled generation—the combined amount of electricity generated from natural gas, oil, and coal—was up 21% in 2012, compared to the level in ...

337

Program on Technology Innovation: Advanced Fuel Cycles - Impact on High-Level Waste Disposal  

Science Conference Proceedings (OSTI)

This report presents the results of a dynamic simulation analysis for deployment of advanced light water reactors (LWRs) and fast burner reactors, as proposed by the Global Nuclear Energy Partnership (GNEP) program. Conditions for the analysis were selected for their potential to challenge the nuclear fuel simulation codes that were used, due to the large variations in nuclear fuel composition for the burner reactors before equilibrium conditions are approached. The analysis was performed in a U.S. conte...

2008-09-30T23:59:59.000Z

338

Used Fuel and High-Level Radioactive Waste Extended Storage Collaboration Program  

Science Conference Proceedings (OSTI)

The Electric Power Research Institute (EPRI) convened a workshop of over 40 representatives of the nuclear industry, federal government, national laboratories, and suppliers of used-fuel dry-storage systems to discuss the potential issues associated with extended dry storage of used fuel, that is, storage considerably beyond the term of current and recently proposed U.S. Nuclear Regulatory Commission (NRC) regulations. The workshop was held November 18-19, 2009, at EPRI's offices in Washington, DC.

2010-03-02T23:59:59.000Z

339

Ionic liquids and ionic liquid acids with high temperature stability for fuel cell and other high temperature applications, method of making and cell employing same  

DOE Patents (OSTI)

Disclosed are developments in high temperature fuel cells including ionic liquids with high temperature stability and the storage of inorganic acids as di-anion salts of low volatility. The formation of ionically conducting liquids of this type having conductivities of unprecedented magnitude for non-aqueous systems is described. The stability of the di-anion configuration is shown to play a role in the high performance of the non-corrosive proton-transfer ionic liquids as high temperature fuel cell electrolytes. Performance of simple H.sub.2(g) electrolyte/O.sub.2(g) fuel cells with the new electrolytes is described. Superior performance both at ambient temperature and temperatures up to and above 200.degree. C. are achieved. Both neutral proton transfer salts and the acid salts with HSO.sup.-.sub.4 anions, give good results, the bisulphate case being particularly good at low temperatures and very high temperatures. The performance of all electrolytes is improved by the addition of a small amount of involatile base of pK.sub.a value intermediate between those of the acid and base that make the bulk electrolyte. The preferred case is the imidazole-doped ethylammonium hydrogensulfate which yields behavior superior in all respects to that of the industry standard phosphoric acid electrolyte.

Angell, C. Austen (Mesa, AZ); Xu, Wu (Broadview Heights, OH); Belieres, Jean-Philippe (Chandler, AZ); Yoshizawa, Masahiro (Tokyo, JP)

2011-01-11T23:59:59.000Z

340

Composite Cathode for High-Power Density Solid Oxide Fuel Cells  

DOE Green Energy (OSTI)

Reduction of solid oxide fuel cell (SOFC) operating temperature will play a key role in reducing the stack cost by allowing the use of low-cost metallic interconnects and new approaches to sealing, while making applications such as transportation more feasible. Reported results for anode-supported SOFCs show that cathode polarization resistance is the primary barrier to achieving high power densities at operating temperatures of 700 C and lower. This project aims to identify and develop composite cathodes that could reduce SOFC operating temperatures below 700 C. This effort focuses on study and use of (La,Sr)(Co,Fe)O{sub 3} (LSCF) based composite cathodes, which have arguably the best potential to substantially improve on the currently-used, (La,Sr)MnO{sub 3}-Yttria-stabilized Zirconia. During this Phase I, it was successfully demonstrated that high performances can be achieved with LSCF/Gadolinium-Doped Ceria composite cathodes on Ni-based anode supported cells operating at 700 C or lower. We studied electrochemical reactions at LSCF/Yttria-stabilized Zirconia (YSZ) interfaces, and observed chemical reactions between LSCF and YSZ. By using ceria electrolytes or YSZ electrolytes with ceria diffusion barrier layers, the chemical reactions between LSCF and electrolytes were prevented under cathode firing conditions necessary for the optimal adhesion of the cathodes. The protection provided by ceria layer is expected to be adequate for stable long-term cathode performances, but more testing is needed to verify this. Using ceria-based barrier layers, high performance Ni-YSZ anode supported cells have been demonstrated with maximum power densities of 0.8W/cm2 at 700 C and 1.6W/cm{sup 2} at 800 C. Ni-SDC anode supported cells with SDC electrolytes yielded >1W/cm{sup 2} at 600 C. We speculate that the power output of Ni-YSZ anode supported cell at 700 C and lower, was limited by the quality of the Ceria and Ceria YSZ interface. Improvements in the low-temperature performances are expected based on further development of barrier layer fabrication processes and optimization of cathode microstructure.

Ilwon Kim; Scott Barnett; Yi Jiang; Manoj Pillai; Nikkia McDonald; Dan Gostovic; Zhongryang Zhan; Jiang Liu

2004-01-31T23:59:59.000Z

Note: This page contains sample records for the topic "high grade fuel" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

Feasibility analyses for HEU to LEU fuel conversion of the LAUE Langivin Institute (ILL) High Flux Reactor (RHF).  

SciTech Connect

The High Flux Reactor (RHF) of the Laue Langevin Institute (ILL) based in Grenoble, France is a research reactor designed primarily for neutron beam experiments for fundamental science. It delivers one of the most intense neutron fluxes worldwide, with an unperturbed thermal neutron flux of 1.5 x 10{sup 15} n/cm{sup 2}/s in its reflector. The reactor has been conceived to operate at a nuclear power of 57 MW but currently operates at 52 MW. The reactor currently uses a Highly Enriched Uranium (HEU) fuel. In the framework of its non-proliferation policies, the international community presently aims to minimize the amount of nuclear material available that could be used for nuclear weapons. In this geopolitical context, most worldwide research and test reactors have already started a program of conversion to the use of Low Enriched Uranium (LEU) fuel. A new type of LEU fuel based on a mixture of uranium and molybdenum (UMo) is expected to allow the conversion of compact high performance reactors like the RHF. This report presents the results of reactor design, performance and steady state safety analyses for conversion of the RHF from the use of HEU fuel to the use of UMo LEU fuel. The objective of this work was to show that is feasible, under a set of manufacturing assumptions, to design a new RHF fuel element that could safely replace the HEU element currently used. The new proposed design has been developed to maximize performance, minimize changes and preserve strong safety margins. Neutronics and thermal-hydraulics models of the RHF have been developed and qualified by benchmark against experiments and/or against other codes and models. The models developed were then used to evaluate the RHF performance if LEU UMo were to replace the current HEU fuel 'meat' without any geometric change to the fuel plates. Results of these direct replacement analyses have shown a significant degradation of the RHF performance, in terms of both neutron flux and cycle length. Consequently, ANL and ILL have collaborated to investigate alternative designs. A promising candidate design has been selected and studied, increasing the total amount of fuel without changing the external plate dimensions by relocating the burnable poison. In this way, changes required in the fuel element are reasonably small. With this new design, neutronics analyses have shown that performance could be maintained at a high level: 2 day decrease of cycle length (to 47.5 days at 58.3 MW) and 1-2% decrease of brightness in the cold and hot sources in comparison to the current typical operation. In addition, studies have shown that the thermal-hydraulic and shutdown margins for the proposed LEU design would satisfy technical specifications.

Stevens, J.; Tentner. A.; Bergeron, A.; Nuclear Engineering Division

2010-08-19T23:59:59.000Z

342

Expected environments in high-level nuclear waste and spent fuel repositories in salt  

SciTech Connect

The purpose of this report is to describe the expected environments associated with high-level waste (HLW) and spent fuel (SF) repositories in salt formations. These environments include the thermal, fluid, pressure, brine chemistry, and radiation fields predicted for the repository conceptual designs. In this study, it is assumed that the repository will be a room and pillar mine in a rock-salt formation, with the disposal horizon located approx. 2000 ft (610 m) below the surface of the earth. Canistered waste packages containing HLW in a solid matrix or SF elements are emplaced in vertical holes in the floor of the rooms. The emplacement holes are backfilled with crushed salt or other material and sealed at some later time. Sensitivity studies are presented to show the effect of changing the areal heat load, the canister heat load, the barrier material and thickness, ventilation of the storage room, and adding a second row to the emplacement configuration. The calculated thermal environment is used as input for brine migration calculations. The vapor and gas pressure will gradually attain the lithostatic pressure in a sealed repository. In the unlikely event that an emplacement hole will become sealed in relatively early years, the vapor space pressure was calculated for three scenarios (i.e., no hole closure - no backfill, no hole closure - backfill, and hole closure - no backfill). It was assumed that the gas in the system consisted of air and water vapor in equilibrium with brine. A computer code (REPRESS) was developed assuming that these changes occur slowly (equilibrium conditions). The brine chemical environment is outlined in terms of brine chemistry, corrosion, and compositions. The nuclear radiation environment emphasized in this report is the stored energy that can be released as a result of radiation damage or crystal dislocations within crystal lattices.

Claiborne, H.C.; Rickertsen, L.D., Graham, R.F.

1980-08-01T23:59:59.000Z

343

NEUTRALIZATIONS OF HIGH ALUMINUM LOW URANIUM USED NUCLEAR FUEL SOLUTIONS CONTAINING GADOLINIUM AS A NEUTRON POISON  

DOE Green Energy (OSTI)

H-Canyon will begin dissolving High Aluminum - Low Uranium (High Al/Low U) Used Nuclear Fuel (UNF) following approval by DOE which is anticipated in CY2011. High Al/Low U is an aluminum/enriched uranium UNF with small quantities of uranium relative to aluminum. The maximum enrichment level expected is 93% {sup 235}U. The High Al/Low U UNF will be dissolved in H-Canyon in a nitric acid/mercury/gadolinium solution. The resulting solution will be neutralized and transferred to Tank 39H in the Tank Farm. To confirm that the solution generated could be poisoned with Gd, neutralized, and discarded to the Savannah River Site (SRS) high level waste (HLW) system without undue nuclear safety concerns the caustic precipitation of simulant solutions was examined. Experiments were performed with three simulant solutions representative of the H-Canyon estimated concentrations in the final solutions after dissolution. The maximum U, Gd, and Al concentration were selected for testing from the range of solution compositions provided. Simulants were prepared in three different nitric acid concentrations, ranging from 0.5 to 1.5 M. The simulant solutions were neutralized to four different endpoints: (1) just before a solid phase was formed (pH 3.5-4), (2) the point where a solid phase was obtained, (3) 0.8 M free hydroxide, and (4) 1.2 M free hydroxide, using 50 wt % sodium hydroxide (NaOH). The settling behavior of the neutralized solutions was found to be slower compared to previous studies, with settling continuing over a one week period. Due to the high concentration of Al in these solutions, precipitation of solids was observed immediately upon addition of NaOH. Precipitation continued as additional NaOH was added, reaching a point where the mixture becomes almost completely solid due to the large amount of precipitate. As additional NaOH was added, some of the precipitate began to redissolve, and the solutions neutralized to the final two endpoints mixed easily and had expected densities of typical neutralized waste. Based on particle size and scanning electron microscopy analyses, the neutralized solids were found to be homogeneous and less than 20 microns in size. The majority of solids were less than 4 microns in size. Compared to previous studies, a larger percentage of the Gd was found to precipitate in the partially neutralized solutions (at pH 3.5-4). In addition the Gd:U mass ratio was found to be at least 1.0 in all of the solids obtained after partial or full neutralization. The hydrogen to U (H:U) molar ratios for two accident scenarios were also determined. The first was for transient neutralization and agitator failure. Experimentally this scenario was determined by measuring the H:U ratio of the settled solids. The minimum H:U molar ratio for solids from fully neutralized solutions was 388:1. The second accident scenario is for the solids drying out in an unagitiated pump box. Experimentally, this scenario was determined by measuring the H:U molar ratio in centrifuged solids. The minimum H:U atom ratios for centrifuged precipitated solids was 250:1. It was determined previously that a 30:1 H:Pu atom ratio was sufficient for a 1:1 Gd:Pu mass ratio. Assuming a 1:1 equivalence with {sup 239}Pu, the results of these experiments show Gd is a viable poison for neutralizing U/Gd solutions with the tested compositions.

Taylor-Pashow, K.

2011-06-08T23:59:59.000Z

344

Active region based on graded-gap InGaN/GaN superlattices for high-power 440- to 470-nm light-emitting diodes  

SciTech Connect

The structural and optical properties of light-emitting diode structures with an active region based on ultrathin InGaN quantum wells limited by short-period InGaN/GaN superlattices from both sides have been investigated. The dependences of the external quantum efficiency on the active region design are analyzed. It is shown that the use of InGaN/GaN structures as limiting graded-gap short-period superlattices may significantly increase the quantum efficiency.

Tsatsulnikov, A. F., E-mail: Andrew@beam.ioffe.ru; Lundin, W. V.; Sakharov, A. V.; Zavarin, E. E.; Usov, S. O.; Nikolaev, A. E.; Cherkashin, N. A.; Ber, B. Ya.; Kazantsev, D. Yu. [Russian Academy of Sciences, Ioffe Physicotechnical Institute (Russian Federation); Mizerov, M. N. [Russian Academy of Sciences, Center for Microelectronics, Ioffe Physicotechnical Institute (Russian Federation); Park, Hee Seok [Samsung Electro-Mechanics Co. Ltd. (Korea, Republic of); Hytch, M.; Hue, F. [National Center for Scientific Research, Center for Material Elaboration and Structural Studies (France)

2010-01-15T23:59:59.000Z

345

Accident source terms for light-water nuclear power plants using high-burnup or MOX fuel.  

Science Conference Proceedings (OSTI)

Representative accident source terms patterned after the NUREG-1465 Source Term have been developed for high burnup fuel in BWRs and PWRs and for MOX fuel in a PWR with an ice-condenser containment. These source terms have been derived using nonparametric order statistics to develop distributions for the timing of radionuclide release during four accident phases and for release fractions of nine chemical classes of radionuclides as calculated with the MELCOR 1.8.5 accident analysis computer code. The accident phases are those defined in the NUREG-1465 Source Term - gap release, in-vessel release, ex-vessel release, and late in-vessel release. Important differences among the accident source terms derived here and the NUREG-1465 Source Term are not attributable to either fuel burnup or use of MOX fuel. Rather, differences among the source terms are due predominantly to improved understanding of the physics of core meltdown accidents. Heat losses from the degrading reactor core prolong the process of in-vessel release of radionuclides. Improved understanding of the chemistries of tellurium and cesium under reactor accidents changes the predicted behavior characteristics of these radioactive elements relative to what was assumed in the derivation of the NUREG-1465 Source Term. An additional radionuclide chemical class has been defined to account for release of cesium as cesium molybdate which enhances molybdenum release relative to other metallic fission products.

Salay, Michael (U.S. Nuclear Regulatory Commission, Washington, D.C.); Gauntt, Randall O.; Lee, Richard Y. (U.S. Nuclear Regulatory Commission, Washington, D.C.); Powers, Dana Auburn; Leonard, Mark Thomas

2011-01-01T23:59:59.000Z

346

High Efficiency Generation of Hydrogen Fuels Using Nuclear Power - for the period August 1, 1999 through October 31, 1999  

DOE Green Energy (OSTI)

OAK B188 High Efficiency Generation of Hydrogen Fuels Using Nuclear Power - for the period August 1, 1999 through October 31, 1999. The highlights for this period are: (1) The methodologies for searching the literature for potentially attractive thermochemical water-splitting cycles, storing cycle and reference data, and screening the cycles have been established; and (2) The water-splitting cycle screening criteria were established on schedule.

L. C. Brown

2000-01-01T23:59:59.000Z

347

Upgrading Below Grade Spaces  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Patrick H. Huelman, Sam Breidenbach, Steve Schirber Patrick H. Huelman, Sam Breidenbach, Steve Schirber NorthernSTAR Building America Partnership Upgrading Below Grade Spaces Residential Energy Efficiency Stakeholder March 1, 2012 Austin, TX * Act 1: Technical Challenges & Opportunities - Pat Huelman, University of Minnesota * Act 2: Assessing Homeowner Priorities & Risks - Sam Breidenbach, TDS Custom Construction * Act 3: An Industry Perspective - Steve Schirber, Cocoon Act 1. Upgrade Below Grade * Basement Remodeling: It Doesn't Get Any Riskier! - Combustion safety - Foundation moisture - Radon (& other soil gases) - Biologicals (mold, dust mites, etc.) - Garage gases (if attached) * And front and center are uncontrolled... - negative pressures in basements (beyond stack)

348

Safeguards-by-Design:Guidance for High Temperature Gas Reactors (HTGRs) With Prismatic Fuel  

Science Conference Proceedings (OSTI)

Introduction and Purpose The following is a guidance document from a series prepared for the U.S. Department of Energy (DOE) National Nuclear Security Administration (NNSA), under the Next Generation Safeguards Initiative (NGSI), to assist facility designers and operators in implementing international Safeguards-by-Design (SBD). SBD has two main objectives: (1) to avoid costly and time consuming redesign work or retrofits of new nuclear fuel cycle facilities and (2) to make the implementation of international safeguards more effective and efficient at such facilities. In the long term, the attainment of these goals would save industry and the International Atomic Energy Agency (IAEA) time, money, and resources and be mutually beneficial. This particular safeguards guidance document focuses on prismatic fuel high temperature gas reactors (HTGR). The purpose of the IAEA safeguards system is to provide credible assurance to the international community that nuclear material and other specified items are not diverted from peaceful nuclear uses. The safeguards system consists of the IAEA’s statutory authority to establish safeguards; safeguards rights and obligations in safeguards agreements and additional protocols; and technical measures implemented pursuant to those agreements. Of foremost importance is the international safeguards agreement between the country and the IAEA, concluded pursuant to the Treaty on the Non-Proliferation of Nuclear Weapons (NPT). According to a 1992 IAEA Board of Governors decision, countries must: notify the IAEA of a decision to construct a new nuclear facility as soon as such decision is taken; provide design information on such facilities as the designs develop; and provide detailed design information based on construction plans at least 180 days prior to the start of construction, and on "as-built" designs at least 180 days before the first receipt of nuclear material. Ultimately, the design information will be captured in an IAEA Design Information Questionnaire (DIQ), prepared by the facility operator, typically with the support of the facility designer. The IAEA will verify design information over the life of the project. This design information is an important IAEA safeguards tool. Since the main interlocutor with the IAEA in each country is the State Regulatory Authority/SSAC (or Regional Regulatory Authority, e.g. EURATOM), the responsibility for conveying this design information to the IAEA falls to the State Regulatory Authority/SSAC. For the nuclear industry to reap the benefits of SBD (i.e. avoid cost overruns and construction schedule slippages), nuclear facility designers and operators should work closely with the State Regulatory Authority and IAEA as soon as a decision is taken to build a new nuclear facility. Ideally, this interaction should begin during the conceptual design phase and continue throughout construction and start-up of a nuclear facility. Such early coordination and planning could influence decisions on the design of the nuclear material processing flow-sheet, material storage and handling arrangements, and facility layout (including safeguards equipment), etc.

Mark Schanfein; Casey Durst

2012-11-01T23:59:59.000Z

349

Solar Thermal Energy Storage Device: Hybrid Nanostructures for High-Energy-Density Solar Thermal Fuels  

SciTech Connect

HEATS Project: MIT is developing a thermal energy storage device that captures energy from the sun; this energy can be stored and released at a later time when it is needed most. Within the device, the absorption of sunlight causes the solar thermal fuel’s photoactive molecules to change shape, which allows energy to be stored within their chemical bonds. A trigger is applied to release the stored energy as heat, where it can be converted into electricity or used directly as heat. The molecules would then revert to their original shape, and can be recharged using sunlight to begin the process anew. MIT’s technology would be 100% renewable, rechargeable like a battery, and emissions-free. Devices using these solar thermal fuels—called Hybrisol—can also be used without a grid infrastructure for applications such as de-icing, heating, cooking, and water purification.

None

2012-01-09T23:59:59.000Z

350

Demonstration of a Highly Efficient Solid Oxide Fuel Cell Power System Using Adiabatic Steam Reforming and Anode Gas Recirculation  

SciTech Connect

Solid oxide fuel cells (SOFC) are currently being developed for a wide variety of applications because of their high efficiency at multiple power levels. Applications for SOFCs encompass a large range of power levels including 1-2 kW residential combined heat and power applications, 100-250 kW sized systems for distributed generation and grid extension, and MW-scale power plants utilizing coal. This paper reports on the development of a highly efficient, small-scale SOFC power system operating on methane. The system uses adiabatic steam reforming of methane and anode gas recirculation to achieve high net electrical efficiency. The anode exit gas is recirculated and all of the heat and water required for the endothermic reforming reaction are provided by the anode gas emerging from the SOFC stack. Although the single-pass fuel utilization is only about 55%, because of the anode gas recirculation the overall fuel utilization is up to 93%. The demonstrated system achieved gross power output of 1650 to 2150 watts with a maximum net LHV efficiency of 56.7% at 1720 watts. Overall system efficiency could be further improved to over 60% with use of properly sized blowers.

Powell, Michael R.; Meinhardt, Kerry D.; Sprenkle, Vincent L.; Chick, Lawrence A.; Mcvay, Gary L.

2012-05-01T23:59:59.000Z

351

Direct conversion of surplus fissile materials, spent nuclear fuel, and other materials to high-level-waste glass  

SciTech Connect

With the end of the cold war the United States, Russia, and other countries have excess plutonium and other materials from the reductions in inventories of nuclear weapons. The United States Academy of Sciences (NAS) has recommended that these surplus fissile materials (SFMs) be processed so they are no more accessible than plutonium in spent nuclear fuel (SNF). This spent fuel standard, if adopted worldwide, would prevent rapid recovery of SFMs for the manufacture of nuclear weapons. The NAS recommended investigation of three sets of options for disposition of SFMs while meeting the spent fuel standard: (1) incorporate SFMs with highly radioactive materials and dispose of as waste, (2) partly burn the SFMs in reactors with conversion of the SFMs to SNF for disposal, and (3) dispose of the SFMs in deep boreholes. The US Government is investigating these options for SFM disposition. A new method for the disposition of SFMs is described herein: the simultaneous conversion of SFMs, SNF, and other highly radioactive materials into high-level-waste (HLW) glass. The SFMs include plutonium, neptinium, americium, and {sup 233}U. The primary SFM is plutonium. The preferred SNF is degraded SNF, which may require processing before it can be accepted by a geological repository for disposal.

Forsberg, C.W.; Elam, K.R.

1995-01-31T23:59:59.000Z

352

Program on Technology Innovation: Liquid Precursor High-Velocity Oxy-Fuel Spray Process for Making Fine Structured and Highly Bonded Alloy Coatings  

Science Conference Proceedings (OSTI)

High velocity oxygen-fuel (HVOF) thermal spray processes are used in applications requiring the highest density and adhesion strength, which is not achievable in most other thermal spray processes. Like other thermal spray processes, however, a normal HVOF process is not able to apply fine powders less than 10m via a conventional powder feeder like other thermal spray processes. The advantages of using smaller nano-sized particles in a HVOF process include uniform coating, uniform microstructure, higher ...

2007-03-28T23:59:59.000Z

353

High Energy Delayed Gamma Spectroscopy for Plutonium Assay of Spent Fuel  

Science Conference Proceedings (OSTI)

The direct measurement of plutonium in spent reactor fuel is an unmet challenge in international safeguards. In this simulation study, we investigate the use of the delayed gamma rays from fission product nuclei to determine the amount of fissile isotopes (Pu-239, Pu-241, and U-235) in irradiated light water reactor fuel assemblies. Fission is stimulated with an interrogating neutron source, and the radiation from the short lived fission products is measured. This measured gamma spectrum is then fit to a linear combination of spectra from pure Pu-239, Pu-241, and U-235 to determine the proportion of fissile isotopes present. In this paper, we describe the modelling and analysis methods used to represent the background of radioemissions from long-lived isotopes originally present in the spent fuel and the short time scale delayed gamma signal. Results are presented for simulations using a nominal instrument design on a library of fuel assemblies with burnups ranging from 0 to 60 GWd/MTU.

Campbell, Luke W.; Misner, Alex C.; Smith, Leon E.; Reese, Steve; Robinson, Joshua

2010-11-05T23:59:59.000Z

354

A carbon riveted Pt/Graphene catalyst with high stability for direct methanol fuel cell  

Science Conference Proceedings (OSTI)

Pt/Graphene catalyst was prepared by microwave-assisted polyol process, and carbonization was riveted onto the catalyst surface to enhance the catalyst stability. The physical properties of the obtained catalysts were characterized by X-ray diffraction ... Keywords: Direct methanol fuel cell, Methanol electrooxidation, Pt/Graphene, Stability

Xiaowei Liu, Jialin Duan, Hailong Chen, Yufeng Zhang, Xuelin Zhang

2013-10-01T23:59:59.000Z

355

Closed DTU fuel cycle with Np recycle and waste transmutation  

Science Conference Proceedings (OSTI)

A nuclear energy scenario for the 21st century that included a denatured thorium-uranium-oxide (DTU) fuel cycle and new light water reactors (LWRs) supported by accelerator-driven transmutation of waste (ATW) systems was previously described. This coupled system with the closed DTU fuel cycle provides several improvements beyond conventional LWR (CLWR) (once-through, UO{sub 2} fuel) nuclear technology: increased proliferation resistance, reduced waste, and efficient use of natural resources. However, like CLWR fuel cycles, the spent fuel in the first one-third core discharged after startup contains higher-quality Pu than the equilibrium fuel cycle. To eliminate this high-grade Pu, Np is separated and recycled with Th and U--rather than with higher actinides [(HA) including Pu]. The presence of Np in the LWR feed greatly increases the production of {sup 238}Pu so that a few kilograms of Pu generated enough alpha-decay heat that the separated Pu is highly resistant to proliferation. This alternate process also simplifies the pyrochemical separation of fuel elements (Th and U) from HAs. To examine the advantages of this concept, the authors modeled a US deployment scenario for nuclear energy that includes DTU-LWRs plus ATW`s to burn the actinides produced by these LWRs and to close the back-end of the DTU fuel cycle.

Beller, D.E.; Sailor, W.C.; Venneri, F. [Los Alamos National Lab., NM (United States); Herring, J.S. [Idaho National Engineering and Environmental Lab., ID (United States)

1999-09-01T23:59:59.000Z

356

Criticality Safety of Low-Enriched Uranium and High-Enriched Uranium Fuel Elements in Heavy Water Lattices  

Science Conference Proceedings (OSTI)

The RB reactor was designed as a natural-uranium, heavy water, nonreflected critical assembly in the Vinca Institute of Nuclear Sciences, Belgrade, Yugoslavia, in 1958. From 1962 until 2002, numerous critical experiments were carried out with low-enriched uranium and high-enriched uranium fuel elements of tubular shape, known as the Russian TVR-S fuel assembly type, placed in various heavy water square lattices within the RB cylindrical aluminum tank. Some of these well-documented experiments were selected, described, evaluated, and accepted for inclusion in the 'International Handbook of Evaluated Criticality Safety Benchmark Experiments', contributing to the preservation of a rather small number of heavy water benchmark critical experiments.

Pesic, Milan P

2003-10-15T23:59:59.000Z

357

Advanced High-Temperature Reactor for Production of Electricity and Hydrogen: Molten-Salt-Coolant, Graphite-Coated-Particle-Fuel  

DOE Green Energy (OSTI)

The objective of the Advanced High-Temperature Reactor (AHTR) is to provide the very high temperatures necessary to enable low-cost (1) efficient thermochemical production of hydrogen and (2) efficient production of electricity. The proposed AHTR uses coated-particle graphite fuel similar to the fuel used in modular high-temperature gas-cooled reactors (MHTGRs), such as the General Atomics gas turbine-modular helium reactor (GT-MHR). However, unlike the MHTGRs, the AHTR uses a molten salt coolant with a pool configuration, similar to that of the PRISM liquid metal reactor. A multi-reheat helium Brayton (gas-turbine) cycle, with efficiencies >50%, is used to produce electricity. This approach (1) minimizes requirements for new technology development and (2) results in an advanced reactor concept that operates at essentially ambient pressures and at very high temperatures. The low-pressure molten-salt coolant, with its high heat capacity and natural circulation heat transfer capability, creates the potential for (1) exceptionally robust safety (including passive decay-heat removal) and (2) allows scaling to large reactor sizes [{approx}1000 Mw(e)] with passive safety systems to provide the potential for improved economics.

Forsberg, C.W.

2002-02-21T23:59:59.000Z

358

MATERIAL AND PROCESS DEVELOPMENT LEADING TO ECONOMICAL HIGH-PERFORMANCE THIN-FILM SOLID OXIDE FUEL CELLS  

DOE Green Energy (OSTI)

This report summarizes the results of the work conducted under the program: ''Material and Process Development Leading to Economical High-Performance Thin-Film Solid Oxide Fuel Cells'' under contract number DE-AC26-00NT40711. The program goal is to advance materials and processes that can be used to produce economical, high-performance solid oxide fuel cells (SOFC) capable of achieving extraordinary high power densities at reduced temperatures. Under this program, anode-supported thin electrolyte based on lanthanum gallate (LSMGF) has been developed using tape-calendering process. The fabrication parameters such as raw materials characteristics, tape formulations and sintering conditions have been evaluated. Dense anode supported LSGMF electrolytes with thickness range of 10-50 micron have been fabricated. High performance cathode based on Sr{sub 0.5}Sm{sub 0.5}CoO{sub 3} (SSC) has been developed. Polarization of {approx}0.23 ohm-cm{sup 2} has been achieved at 600 C with Sr{sub 0.5}Sm{sub 0.5}CoO{sub 3}cathode. The high-performance SSC cathode and thin gallate electrolyte have been integrated into single cells and cell performance has been characterized. Tested cells to date generally showed low performance because of low cell OCVs and material interactions between NiO in the anode and lanthanum gallate electrolyte.

Jie Guan; Nguyen Minh

2003-12-01T23:59:59.000Z

359

Aviation turbine fuels, 1985  

Science Conference Proceedings (OSTI)

Samples of this report are typical 1985 production and were analyzed in the laboratories of 17 manufactures of aviation turbine (jet) fuels. The data were submitted for study, calculation, and compilation under a cooperative agreement between the National Institute for Petroleum and Energy Research (NIPER), Bartlesville, Oklahoma, the American Petroleum Institute (API), and the United States Department of Energy (DOE), Bartlesville Project Office. results for certain properties of 88 samples of aviation turbine fuels are included in the report for military grades JP-4 and JP-5, and commercial type Jet A. Previous aviation fuel survey reports are listed.

Dickson, C.L.; Woodward, P.W.

1986-05-01T23:59:59.000Z

360

Aviation turbine fuels, 1982  

Science Conference Proceedings (OSTI)

Properties of some aviation turbine fuels marketed in the United States during 1982 are presented in this report. The samples represented are typical 1982 production and were analyzed in the laboratories of 14 manufacturers of aviation turbine (jet) fuels. The data were submitted for study, calculation, and compilation under a cooperative agreement between the Department of Energy (DOE), Bartlesville Energy Technology Center (BETC), Bartlesville, Oklahoma, and the American Petroleum Institute (API). Results for the properties of 90 samples of aviation turbine fuels are included in the report for military grades JP-4 and HP-5, and commercial type Jet A.

Shelton, E.M.; Dickson, C.L.

1983-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "high grade fuel" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


361

Advanced Use of the OWL Grade Book  

E-Print Network (OSTI)

Advanced Use of the OWL Grade Book #12;Notes Overview The Grade Book has many features to help you organize, release, and compile grades. This manualette will discuss the following advanced Grade Book the Grade Book, creating columns or adding and releasing grades, please see the Basic Use of the OWL Grade

Lennard, William N.

362

Using MMS with the OWL Grade Book  

E-Print Network (OSTI)

Using MMS with the OWL Grade Book #12;Notes Overview While MMS provides you with an easy way to maintain and manage your students'grades, the OWL Grade Book offers a simple and secure method into the OWL Grade Book, as well as export grades from the OWL Grade Book into MMS. Page 2 Transfer Grades from

Lennard, William N.

363

Program on Technology Innovation: Advanced Fuel Cycles--Impact on High-Level Waste Disposal  

Science Conference Proceedings (OSTI)

The aim of advanced fuel cycles is to improve the sustainability of nuclear energy by enhancing the effectiveness of natural uranium resource utilization and by mitigating waste disposal issues, while keeping the costs of energy products, in particular electricity, economically viable. In addition, this aim has to be achieved under conditions that minimize the risks of diversion of separated fissile materials and their possible misuse for non-peaceful ends. The report presents results from recently publi...

2007-12-21T23:59:59.000Z

364

Post-Irradiation Examination of Fuel Cladding Surfaces Exposed to High Lithium in Ringhals-2  

Science Conference Proceedings (OSTI)

Lithium is used to control the pH in pressurized water reactor primary coolant at slightly alkaline levels. Lithium is also known to induce corrosion in zirconium alloys at elevated concentrations temperatures. Utility chemistry programs seek to increase the maximum lithium concentration at the beginning of cycle to maintain a higher pH for expected corrosion and radiation field benefits, but to do so the margin for fuel performance needs to be quantified.This report has been prepared ...

2012-10-30T23:59:59.000Z

365

High performance metal/air fuel cells. Part 1. General review. [Li, Al, Ca, Cd, Mg  

SciTech Connect

Metal/air fuel cells are reviewed in terms of their potential application in electric vehicles. Attention is focused on those metals (light alkali and alkaline earth metals, and aluminum) which, in combination with oxygen, have theoretical energy densities (2--13 kWh/kg-metal) exceeding that of gasoline (utilized in automobiles at 2--3 kWh/kg). Lithium and aluminum have yielded 8- and 4 kWh/kg, respectively, in laboratory experimental cells. The slurry Zn/air system achieves 0.85 kWh/kg-Zn in prototype vehicle cells and is reviewed for comparison. Calcium can probably yield 1.8 kWh/kg-Ca, but its potential as a fuel has not yet been fully explored. The remaining metals appear to be unsuitable for use in aqueous electrolyte fuel cells. The discharge characteristics of lithium, aluminum, and (possibly) calcium/air cells indicate the potential for electric vehicles of the highway performance and minimum range (300 miles) of subcompact automobiles, rapid refueling for unlimited range extension, and the storage in the fuel cell of sufficient metal for ranges in excess of 1000 miles. Barriers to the concept are the economic necessity of recycling cell reaction products (except in the case of calcium), the expansion or creation of vast metal production industries, and the change-over of existing service station infrastructures to allow electric vehicle servicing. The energy efficiency of a transportation system using aluminum was estimated using data on the current aluminum production industry. The total estimated cost of ownership and operation of an aluminum/air cell was 3.0--3.6 cents/km. The relative rarity of lithium would complicate its use. 6 tables.

Cooper, J. F.

1977-08-15T23:59:59.000Z

366

Fuel Effects on Combustion and Emissions of a Direct-Inection Diesel Engine Operating at Moderate to High Engine Speed and Load  

Science Conference Proceedings (OSTI)

It is advantageous to increase the specific power output of diesel engines and to operate them at higher load for a greater portion of a driving cycle to achieve better thermal efficiency and thus reduce vehicle fuel consumption. Such operation is limited by excessive smoke formation at retarded injection timing and high rates of cylinder pressure rise at more advanced timing. Given this window of operation, it is desired to understand the influence of fuel properties such that optimum combustion performance and emissions can be retained over the range of fuels commonly available in the marketplace. It has been shown in previous studies that varying cetane number (CN) of diesel fuel has little effect on ignition delay at high engine load due to the domination of high cylinder temperature on ignition kinetics. The work here experimentally confirms that finding but also shows that emissions and combustion performance vary according to fuel reactivity. Data are examined from a direct-injection single cylinder research engine for eight common diesel fuels including soy-based biodiesel blends at two high load operating points with no exhaust gas recirculation (EGR) and at a moderate load with four levels of EGR. It is shown in the work that at high engine load where combustion is controlled by mixing processes, CN and other fuel properties have little effect on engine performance, although lower CN fuels produce a small increase in noise, smoke and CO emissions. Biodiesel blends increase NOX emissions and decreases CO and smoke emissions at high load, but otherwise have little effect on performance. At moderate load, higher CN fuels are more tolerant to EGR due to their better chemical reactivity at retarded injection timing, but all fuels produce comparable thermal efficiency at advanced combustion phasing regardless of EGR. In contrast to the high load conditions, there was no increase in NOX emissions for biodiesel at the moderate load condition. It is concluded that although higher CN does not significantly alter ignition delay at moderate to high loads it has a dominant influence on the acceptable injection timing range. Apart from CN effects, fuel oxygen content plays an independent role in reducing some emissions. It is therefore recommended that compensation for fuel ignitability and oxygen content be included in combustion control strategies to optimize emissions and performance of future diesel engines.

Szybist, James P [ORNL; Szymkowicz, Patrick G. [General Motors Corporation; Northrop, William F [General Motors Corporation

2012-01-01T23:59:59.000Z

367

Assumptions and criteria for performing a feasibility study of the conversion of the high flux isotope reactor core to use low-enriched uranium fuel  

SciTech Connect

This paper provides a preliminary estimate of the operating power for the High Flux Isotope Reactor when fuelled with low enriched uranium (LEU). Uncertainties in the fuel fabrication and inspection processes are reviewed for the current fuel cycle [highly enriched uranium (HEU)] and the impact of these uncertainties on the proposed LEU fuel cycle operating power is discussed. These studies indicate that for the power distribution presented in a companion paper in these proceedings, the operating power for an LEU cycle would be close to the current operating power. (authors)

Primm Iii, R. T. [Oak Ridge National Laboratory, P. O. Box 2008, Oak Ridge, TN 37831-6399 (United States); Ellis, R. J.; Gehin, J. C. [Oak Ridge National Laboratory, P. O. Box 2008, Oak Ridge, TN 37831-6172 (United States); Moses, D. L. [Oak Ridge National Laboratory, P. O. Box 2008, Oak Ridge, TN 37831-6050 (United States); Binder, J. L. [Oak Ridge National Laboratory, P. O. Box 2008, Oak Ridge, TN 37831-6162 (United States); Xoubi, N. [Univ. of Cincinnati, Rhodes Hall, ML 72, PO Box 210072, Cincinnati, OH 45221-0072 (United States)

2006-07-01T23:59:59.000Z

368

Mechanisms Underpinning Degradation of Protective Oxides and Thermal Barrier Coatings in High Hydrogen Content-Fueled Turbines - University of California, Irvine  

NLE Websites -- All DOE Office Websites (Extended Search)

Mechanisms Underpinning Degradation Mechanisms Underpinning Degradation of Protective Oxides and Thermal Barrier Coatings in High Hydrogen Content-Fueled Turbines-University of California, Irvine Background Thermal barrier coatings (TBCs) and components in the hot section of gas turbines are degraded by coal-derived high hydrogen content (HHC) synthesis gas (syngas). In this project the University of California, Irvine (UCI) will provide an improved mechanistic understanding of the degradation of critical turbine system materials in HHC-fueled

369

Design, Operation, and Performance Data for High Burnup PWR Fuel from the H. B. Robinson Plant for Use in the NRC Experimental Progr am at Argonne National Laboratory  

Science Conference Proceedings (OSTI)

This report presents the background information -- design, irradiation history, and performance data -- for twelve high-burnup pressurized water reactor (PWR) fuel rods that are being provided to the U.S. Nuclear Regulatory Commission (NRC) for use in experiments designed to study the response of highly irradiated fuel to transient accidents and long-term storage conditions. This information will establish the starting conditions needed to correctly interpret future experimental results.

2001-05-04T23:59:59.000Z

370

Alternative Fuels Data Center: Alternative Fuel Production Tax Credits  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Alternative Fuel Alternative Fuel Production Tax Credits to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel Production Tax Credits on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel Production Tax Credits on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel Production Tax Credits on Google Bookmark Alternative Fuels Data Center: Alternative Fuel Production Tax Credits on Delicious Rank Alternative Fuels Data Center: Alternative Fuel Production Tax Credits on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuel Production Tax Credits on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Alternative Fuel Production Tax Credits The Enterprise Zone Program and the High Quality Jobs Program offer state

371

Aviation fuels, 1983  

Science Conference Proceedings (OSTI)

Properties of some aviation gasolines and aviation turbine fuels marketed in the United States during 1983 are presented in this report. The samples represented are typical 1983 production and were analyzed in the laboratories of 12 manufacturers of aviation gasolines and 18 producers of aviation turbine (jet) fuels. The data were submitted for study, calculation, and compilation under a cooperative agreement between the National Institute for Petroleum and Energy Research (NIPER), Bartlesville, Oklahoma, and the American Petroleum Institute (API). Results for properties of 34 samples of grades 80/87, 100/130, and 100LL for aviation gasolines, and 104 samples of military grades JP-4 and JP-5, and commercial type Jet A for aviation turbine fuels are included in this report.

Shelton, E.M.; Dickson, C.L.

1984-04-01T23:59:59.000Z

372

Oxidation Protection of Uranium Nitride Fuel using Liquid Phase Sintering  

SciTech Connect

Two methods are proposed to increase the oxidation resistance of uranium nitride (UN) nuclear fuel. These paths are: (1) Addition of USi{sub x} (e.g. U3Si2) to UN nitride powder, followed by liquid phase sintering, and (2) 'alloying' UN nitride with various compounds (followed by densification via Spark Plasma Sintering or Liquid Phase Sintering) that will greatly increase oxidation resistance. The advantages (high thermal conductivity, very high melting point, and high density) of nitride fuel have long been recognized. The sodium cooled BR-10 reactor in Russia operated for 18 years on uranium nitride fuel (UN was used as the driver fuel for two core loads). However, the potential advantages (large power up-grade, increased cycle lengths, possible high burn-ups) as a Light Water Reactor (LWR) fuel are offset by uranium nitride's extremely low oxidation resistance (UN powders oxidize in air and UN pellets decompose in hot water). Innovative research is proposed to solve this problem and thereby provide an accident tolerant LWR fuel that would resist water leaks and high temperature steam oxidation/spalling during an accident. It is proposed that we investigate two methods to increase the oxidation resistance of UN: (1) Addition of USi{sub x} (e.g. U{sub 3}Si{sub 2}) to UN nitride powder, followed by liquid phase sintering, and (2) 'alloying' UN nitride with compounds (followed by densification via Spark Plasma Sintering) that will greatly increase oxidation resistance.

Dr. Paul A. Lessing

2012-03-01T23:59:59.000Z

373

Fuel processing for fuel cell powered vehicles.  

DOE Green Energy (OSTI)

A number of auto companies have announced plans to have fuel cell powered vehicles on the road by the year 2004. The low-temperature polymer electrolyte fuel cells to be used in these vehicles require high quality hydrogen. Without a hydrogen-refueling infrastructure, these vehicles need to convert the available hydrocarbon fuels into a hydrogen-rich gas on-board the vehicle. Earlier analysis has shown that fuel processors based on partial oxidation reforming are well suited to meet the size and weight targets and the other performance-related needs of on-board fuel processors for light-duty fuel cell vehicles (1).

Ahmed, S.; Wilkenhoener, R.; Lee, S. H. D.; Carter, J. D.; Kumar, R.; Krumpelt, M.

1999-01-22T23:59:59.000Z

374

Energy Fuels Nuclear, Inc. Arizona Strip Operations  

Science Conference Proceedings (OSTI)

Founded in 1975 by uranium pioneer, Robert W. Adams, Energy Fuels Nuclear, Inc. (EFNI) emerged as the largest US uranium mining company by the mid-1980s. Confronting the challenges of declining uranium market prices and the development of high-grade ore bodies in Australia and Canada, EFNI aggressively pursued exploration and development of breccia-pipe ore bodies in Northwestern Arizona. As a result, EFNI's production for the Arizona Strip of 18.9 million pounds U[sub 3]O[sub 8] over the period 1980 through 1991, maintained the company's status as a leading US uranium producer.

Pool, T.C.

1993-05-01T23:59:59.000Z

375

LOW-TEMPERATURE, ANODE-SUPPORTED HIGH POWER DENSITY SOLID OXIDE FUEL CELLS WITH NANOSTRUCTURED ELECTRODES  

DOE Green Energy (OSTI)

A simple, approximate analysis of the effect of differing cathode and anode areas on the measurement of cell performance on anode-supported solid oxide fuel cells, wherein the cathode area is smaller than the anode area, is presented. It is shown that the effect of cathode area on cathode polarization, on electrolyte contribution, and on anode resistance, as normalized on the basis of the cathode area, is negligible. There is a small but measurable effect on anode polarization, which results from concentration polarization. Effectively, it is the result of a greater amount of fuel transported to the anode/electrolyte interface in cases wherein the anode area is larger than the cathode area. Experiments were performed on cells made with differing cathode areas and geometries. Cathodic and anodic overpotentials measured using reference electrodes, and the measured ohmic area specific resistances by current interruption, were in good agreement with expectations based on the analysis presented. At 800 C, the maximum power density measured with a cathode area of {approx}1.1 cm{sup 2} was {approx}1.65 W/cm{sup 2} compared to {approx}1.45 W/cm{sup 2} for cathode area of {approx}2 cm{sup 2}, for anode thickness of {approx}1.3 mm, with hydrogen as the fuel and air as the oxidant. At 750 C, the measured maximum power densities were {approx}1.3 W/cm{sup 2} for the cell with cathode area {approx}1.1 cm{sup 2}, and {approx}1.25 W/cm{sup 2} for the cell with cathode area {approx}2 cm{sup 2}.

Anil V. Virkar

2001-06-21T23:59:59.000Z

376

Numerical and Experimental Study of Mixing Processes Associated with Hydrogen and High Hydrogen Content Fuels  

Science Conference Proceedings (OSTI)

As simulation capability improves exponentially with increasingly more cost effective CPUs and hardware, it can be used “routinely” for engineering applications. Many commercial products are available and they are marketed as increasingly powerful and easy to use. The question remains as to the overall accuracy of results obtained. To support the validation of the CFD, a hierarchical experiment was established in which the type of fuel injection (radial, axial) as well as level of swirl (non-swirling, swirling) could be systematically varied. The effort was limited to time efficient approaches (i.e., generally RANS approaches) although limited assessment of time resolved methods (i.e., unsteady RANS and LES) were considered. Careful measurements of the flowfield velocity and fuel concentration were made using both intrusive and non-intrusive methods. This database was then used as the basis for the assessment of the CFD approach. The numerical studies were carried out with a statistically based matrix. As a result, the effect of turbulence model, fuel type, axial plane, turbulent Schmidt number, and injection type could be studied using analysis of variance. The results for the non-swirling cases could be analyzed as planned, and demonstrate that turbulence model selection, turbulence Schmidt number, and the type of injection will strongly influence the agreement with measured values. Interestingly, the type of fuel used (either hydrogen or methane) has no influence on the accuracy of the simulations. For axial injection, the selection of proper turbulence Schmidt number is important, whereas for radial injection, the results are relatively insensitive to this parameter. In general, it was found that the nature of the flowfield influences the performance of the predictions. This result implies that it is difficult to establish a priori the “best” simulation approach to use. However, the insights from the relative orientation of the jet and flow do offer some guidance for which approach to take. Overall, the results underscore the importance of model “anchoring” (i.e., “tuning” the model to provide “reasonable” agreement with a well characterized geometry/flow). Finally, the results obtained have been carefully compiled into a standalone database following a standard format that is contained in an Appendix. This database is thus available for use by others for CFD modeling evaluations.

McDonell, Vincent; Hill, Scott; Akbari, Amin; McDonell, Vincent

2011-09-30T23:59:59.000Z

377

Performance assessment of the direct disposal in unsaturated tuff or spent nuclear fuel and high-level waste owned by USDOE: Volume 2, Methodology and results  

SciTech Connect

This assessment studied the performance of high-level radioactive waste and spent nuclear fuel in a hypothetical repository in unsaturated tuff. The results of this 10-month study are intended to help guide the Office of Environment Management of the US Department of Energy (DOE) on how to prepare its wastes for eventual permanent disposal. The waste forms comprised spent fuel and high-level waste currently stored at the Idaho National Engineering Laboratory (INEL) and the Hanford reservations. About 700 metric tons heavy metal (MTHM) of the waste under study is stored at INEL, including graphite spent nuclear fuel, highly enriched uranium spent fuel, low enriched uranium spent fuel, and calcined high-level waste. About 2100 MTHM of weapons production fuel, currently stored on the Hanford reservation, was also included. The behavior of the waste was analyzed by waste form and also as a group of waste forms in the hypothetical tuff repository. When the waste forms were studied together, the repository was assumed also to contain about 9200 MTHM high-level waste in borosilicate glass from three DOE sites. The addition of the borosilicate glass, which has already been proposed as a final waste form, brought the total to about 12,000 MTHM.

Rechard, R.P. [ed.

1995-03-01T23:59:59.000Z

378

Mathematical modeling of solid oxide fuel cells using hydrocarbon fuels  

E-Print Network (OSTI)

Solid oxide fuel cells (SOFCs) are high efficiency conversion devices that use hydrogen or light hydrocarbon (HC) fuels in stationary applications to produce quiet and clean power. While successful, HC-fueled SOFCs face ...

Lee, Won Yong, Ph. D. Massachusetts Institute of Technology

2012-01-01T23:59:59.000Z

379

Development of Commodity Grade, Lower Cost Carbon Fiber - Commercial Applications  

SciTech Connect

In pursuit of the goal to produce ultra-lightweight fuel efficient vehicles, there has been great excitement during the last few years about the potential for using carbon fiber reinforced composites in high volume applications. Currently, the greatest hurdle that inhibits wider implementation of carbon fiber composites in transportation is the high cost of the fiber when compared to other candidate materials. As part of the United States Department of Energy s FreedomCAR initiative, significant research is being conducted to develop lower cost, high volume technologies for producing carbon fiber. This paper will highlight the on-going research in this area. Through Department of Energy (DOE) sponsorship, Oak Ridge National Laboratory (ORNL) and its partners have been working with the US Automotive Composites Consortium (ACC) to develop technologies that would enable the production of carbon fiber at 5-7 dollars per pound. Achievement of this cost goal would allow the introduction of carbon fiber based composites into a greater number of applications for future vehicles. The approach has necessitated the development of both alternative precursors and more efficient production methods. Alternative precursors under investigation include textile grade polyacrylonitrile (PAN) fibers and fibers from lignin-based feedstocks. Previously, as part of the research program, Hexcel Corporation developed the science necessary to allow textile grade PAN to be used as a precursor rather than typical carbon fiber grade precursors. Efforts are also underway to develop carbon fiber precursors from lignin-based feedstocks. ORNL and its partners are working on this effort with domestic pulp and paper producers. In terms of alternative production methods, ORNL has developed a microwave-based carbonization unit that can process pre-oxidized fiber at over 200 inches per minute. ORNL has also developed a new method of high speed oxidation and a new method for precursor stabilization. Additionally, novel methods of activating carbon fiber surfaces have been developed which allow atomic oxygen concentrations as high as 25-30% to be achieved rather than the more typical 4-8% achieved by the standard industrial ozone treatment.

Warren, Charles David [ORNL; Paulauskas, Felix L [ORNL; Baker, Frederick S [ORNL; Eberle, Cliff [ORNL; Naskar, Amit K [ORNL

2009-01-01T23:59:59.000Z

380

Locations of spent nuclear fuel and high-level radioactive waste ultimately destined for geologic disposal  

Science Conference Proceedings (OSTI)

Since the late 1950s, Americans have come to rely more and more on energy generated from nuclear reactors. Today, 109 commercial nuclear reactors supply over one-fifth of the electricity used to run our homes, schools, factories, and farms. When the nuclear fuel can no longer sustain a fission reaction in these reactors it becomes `spent` or `used` and is removed from the reactors and stored onsite. Most of our Nation`s spent nuclear fuel is currently being stored in specially designed deep pools of water at reactor sites; some is being stored aboveground in heavy thick-walled metal or concrete structures. Sites currently using aboveground dry storage systems include Virginia Power`s Surry Plant, Carolina Power and Light`s H.B. Robinson Plant, Duke Power`s Oconee Nuclear Station, Colorado Public Service Company`s shutdown reactor at Fort St. Vrain, Baltimore Gas and Electric`s Calvert Cliffs Plant, and Michigan`s Consumer Power Palisades Plant.

Not Available

1994-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "high grade fuel" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


381

Treatment of high-level wastes from the IFR fuel cycle  

SciTech Connect

The Integral Fast Reactor (IFR) is being developed as a future commercial power source that promises to have important advantages over present reactors, including improved resource conservation and waste management. The spent metal alloy fuels from an IFR will be processed in an electrochemical cell operating at 500{degree}C with a molten chloride salt electrolyte and cadmium metal anode. After the actinides have been recovered from several batches of core and blanket fuels, the salt cadmium in this electrorefiner will be treated to separate fission products from residual transuranic elements. This treatment produces a waste salt that contains the alkali metal, alkaline earth, and halide fission products; some of the rare earths; and less than 100 nCi/g of alpha activity. The treated metal wastes contain the rest of the fission products (except T, Kr, and Xe) small amounts of uranium, and only trace amounts of transuranic elements. The current concept for the salt waste form is an aluminosilicate matrix, and the concept for the metal waste form is a corrosion-resistant metal alloy. The processes and equipment being developed to treat and immobilize the salt and metal wastes are described.

Johnson, T.R.; Lewis, M.A.; Newman, A.E.; Laidler, J.J.

1992-01-01T23:59:59.000Z

382

Treatment of high-level wastes from the IFR fuel cycle  

Science Conference Proceedings (OSTI)

The Integral Fast Reactor (IFR) is being developed as a future commercial power source that promises to have important advantages over present reactors, including improved resource conservation and waste management. The spent metal alloy fuels from an IFR will be processed in an electrochemical cell operating at 500{degree}C with a molten chloride salt electrolyte and cadmium metal anode. After the actinides have been recovered from several batches of core and blanket fuels, the salt cadmium in this electrorefiner will be treated to separate fission products from residual transuranic elements. This treatment produces a waste salt that contains the alkali metal, alkaline earth, and halide fission products; some of the rare earths; and less than 100 nCi/g of alpha activity. The treated metal wastes contain the rest of the fission products (except T, Kr, and Xe) small amounts of uranium, and only trace amounts of transuranic elements. The current concept for the salt waste form is an aluminosilicate matrix, and the concept for the metal waste form is a corrosion-resistant metal alloy. The processes and equipment being developed to treat and immobilize the salt and metal wastes are described.

Johnson, T.R.; Lewis, M.A.; Newman, A.E.; Laidler, J.J.

1992-08-01T23:59:59.000Z

383

Feasibility of low-cost, high-volume production of silane and pyrolysis of silane to semiconductor-grade silicon. Quarterly progress report, April--June 1978. Low cost silicon solar array project  

DOE Green Energy (OSTI)

The purpose of the silane production program is to determine the feasibility and practicality of high-volume, low-cost production of silane (SiH/sub 4/) as an intermediate for obtaining solar-grade silicon metal. The process is based on the synthesis of SiH/sub 4/ by the catalytic disproportionation of chlorosilanes resulting from the reaction of hydrogen, metallurgical silicon, and silicon tetrachloride. The goal is to demonstrate the feasibility of a silane production cost of under $4.00/kg at a production rate of 1000 MT/year. The objective of the silicon production program is to establish the feasibility and cost of manufacturing semiconductor grade polycrystalline silicon through the pyrolysis of silane. The silane-to-silicon conversion is to be investigated in a fluid bed reactor and in a free space reactor. The process design program is to provide JPL with engineering and economic parameters for an experimental unit sized for 25 metric tons of silicon per year and a product-cost estimate for silicon produced on a scale of 100 metric tons per year. The purpose of the capacitive fluid-bed heating program is to explore the feasibility of using electrical capacitive heating to control the fluidized silicon-bed temperature during the heterogeneous decomposition of silane. In addition, a theoretical fluid-bed silicon deposition model was developed for use in the design of a fluid-bed pyrolysis scheme. Progress is reported in each of these areas. (WHK)

Breneman, W.C.; Farrier, E.G.; Morihara, H.

1978-01-01T23:59:59.000Z

384

Basic Use of the OWL Grade Book  

E-Print Network (OSTI)

Basic Use of the OWL Grade Book #12;Notes Overview The Grade Book tool provides an easy and convenient way for instructors to manage grades and distribute them to students. Using the Grade Book. This handout will show you how to: · Access the Grade Book · Create a column in the Grade Book · Add

Lennard, William N.

385

MATERIAL AND PROCESS DEVELOPMENT LEADING TO ECONOMICAL HIGH-PERFORMANCE THIN-FILM SOLID OXIDE FUEL CELLS  

DOE Green Energy (OSTI)

This document summarizes the technical progress from April to September 2003 for the program, Material and Process Development Leading to Economical High-Performance Thin-Film Solid Oxide Fuel Cells, contract number DE-AC26-00NT40711. Characteristics of doped lanthanum gallate (LSGMF) powder suitable for thin electrolyte fabrication have been defined. Bilayers with thin LSGMF electrolyte supported on an anode were fabricated and the fabrication process was improved. Preliminary performance was characterized. High performance cathode material Sr{sub 0.5}Sm{sub 0.5}CoO{sub 3} has been down-selected and is being optimized by modifying materials characteristics and processing parameters. The selected cathode exhibited excellent performance with cathode polarization of {approx}0.23 ohm-cm{sup 2} at 600 C.

Jie Guan; Nguyen Minh

2003-10-01T23:59:59.000Z

386

Fuel injector system  

DOE Patents (OSTI)

A fuel injection system particularly adapted for injecting coal slurry fuels at high pressures includes an accumulator-type fuel injector which utilizes high-pressure pilot fuel as a purging fluid to prevent hard particles in the fuel from impeding the opening and closing movement of a needle valve, and as a hydraulic medium to hold the needle valve in its closed position. A fluid passage in the injector delivers an appropriately small amount of the ignition-aiding pilot fuel to an appropriate region of a chamber in the injector's nozzle so that at the beginning of each injection interval the first stratum of fuel to be discharged consists essentially of pilot fuel and thereafter mostly slurry fuel is injected.

Hsu, Bertrand D. (Erie, PA); Leonard, Gary L. (Schenctady, NY)

1988-01-01T23:59:59.000Z

387

DOCUMENTATION OF NATIONAL WEATHER CONDITIONS AFFECTING LONG-TERM DEGRADATION OF COMMERCIAL SPENT NUCLEAR FUEL AND DOE SPENT NUCLEAR FUEL AND HIGH-LEVEL WASTE  

SciTech Connect

The U.S. Department of Energy (DOE) is preparing a proposal to construct, operate 2nd monitor, and eventually close a repository at Yucca Mountain in Nye County, Nevada, for the geologic disposal of spent nuclear fuel (SNF) and high-level radioactive waste (HLW). As part of this effort, DOE has prepared a viability assessment and an assessment of potential consequences that may exist if the repository is not constructed. The assessment of potential consequences if the repository is not constructed assumes that all SNF and HLW would be left at the generator sites. These include 72 commercial generator sites (three commercial facility pairs--Salem and Hope Creek, Fitzpatrick and Nine Mile Point, and Dresden and Morris--would share common storage due to their close proximity to each other) and five DOE sites across the country. DOE analyzed the environmental consequences of the effects of the continued storage of these materials at these sites in a report titled Continued Storage Analysis Report (CSAR; Reference 1 ) . The CSAR analysis includes a discussion of the degradation of these materials when exposed to the environment. This document describes the environmental parameters that influence the degradation analyzed in the CSAR. These include temperature, relative humidity, precipitation chemistry (pH and chemical composition), annual precipitation rates, annual number of rain-days, and annual freeze/thaw cycles. The document also tabulates weather conditions for each storage site, evaluates the degradation of concrete storage modules and vaults in different regions of the country, and provides a thermal analysis of commercial SNF in storage.

W. L. Poe, Jr.; P.F. Wise

1998-11-01T23:59:59.000Z

388

Obstacles to US ability to control and track weapons-grade uranium supplied abroad  

SciTech Connect

The United States has exported over 16,000 kilograms of highly enriched uranium for use in research reactors in over 40 nations. GAO learned that the central computerized system used for tracking such exports is incomplete and inaccurate. Intended users also consider it inadequate and unreliable. In addition, three other systems gather information on highly enriched uranium. GAO recommends streamlining and consolidating the information maintained on this material in a more accurate, comprehensive, and flexible manner. GAO believes that reducing the use of highly enriched uranium is a sound non-proliferation objective. A number of obstacles, however, must be overcome if the conversion of research reactors to non-weapons grade fuels is to become a reality in the next few years. In the meantime, US ability to ensure adequate physical protection of highly enriched uranium supplied abroad is limited and international safeguards of nuclear material need further improvement.

Bowsher, C.A.

1982-08-02T23:59:59.000Z

389

Fuel processor for fuel cell power system  

DOE Patents (OSTI)

A catalytic organic fuel processing apparatus, which can be used in a fuel cell power system, contains within a housing a catalyst chamber, a variable speed fan, and a combustion chamber. Vaporized organic fuel is circulated by the fan past the combustion chamber with which it is in indirect heat exchange relationship. The heated vaporized organic fuel enters a catalyst bed where it is converted into a desired product such as hydrogen needed to power the fuel cell. During periods of high demand, air is injected upstream of the combustion chamber and organic fuel injection means to burn with some of the organic fuel on the outside of the combustion chamber, and thus be in direct heat exchange relation with the organic fuel going into the catalyst bed.

Vanderborgh, Nicholas E. (Los Alamos, NM); Springer, Thomas E. (Los Alamos, NM); Huff, James R. (Los Alamos, NM)

1987-01-01T23:59:59.000Z

390

Design of an Online Fission Gas Monitoring System for Post-irradiation Examination Heating Tests of Coated Fuel Particles for High-Temperature Gas-Cooled Reactors  

Science Conference Proceedings (OSTI)

A new Fission Gas Monitoring System (FGMS) has been designed at the Idaho National Laboratory (INL) for use of monitoring online fission gas-released during fuel heating tests. The FGMS will be used with the Fuel Accident Condition Simulator (FACS) at the Hot Fuels Examination Facility (HFEF) located at the Materials and Fuels Complex (MFC) within the INL campus. Preselected Advanced Gas Reactor (AGR) TRISO (Tri-isotropic) fuel compacts will undergo testing to assess the fission product retention characteristics under high temperature accident conditions. The FACS furnace will heat the fuel to temperatures up to 2,000ºC in a helium atmosphere. Released fission products such as Kr and Xe isotopes will be transported downstream to the FGMS where they will accumulate in cryogenically cooledcollection traps and monitored with High Purity Germanium (HPGe) detectors during the heating process. Special INL developed software will be used to monitor the accumulated fission products and will report data in near real-time. These data will then be reported in a form that can be readily available to the INL reporting database. This paper describes the details of the FGMS design, the control and acqusition software, system calibration, and the expected performance of the FGMS. Preliminary online data may be available for presentation at the High Temperature Reactor (HTR) conference.

Dawn Scates

2010-10-01T23:59:59.000Z

391

The Development of Microfabricated Microbial Fuel Cell Array as a High Throughput Screening Platform for Electrochemically Active Microbes  

E-Print Network (OSTI)

Microbial fuel cells (MFCs) are novel green technologies that convert chemical energy stored in biomass into electricity through microbial metabolisms. Both fossil fuel depletion and environmental concern have fostered significant interest in MFCs for both wastewater treatment and electricity generation. However, MFCs have not yet been used for practical applications due to their low power outputs and challenges associated with scale-up. High throughput screening devices for parallel studies are highly necessary to significantly improve and optimize MFC working conditions for future practical applications. Here in this research, microfabricated platforms of microbial fuel cell array as high throughput screening devices for MFC parallel studies have been developed. Their utilities were described with environmental sample screening to uncover electricigens with higher electrochemical activities. The first version of the MFC arrays is a batch-mode miniaturized 24-well MFC array using ferricyanide as catholyte. Several environmental species that showed higher electricity generation capabilities than Shewanella oneidensis MR-1 (SO) were uncovered using the developed MFC array, with one environmental electricigen, Shewanella sp. Hac353 (dq307734.1)(7Ca), showing 2.3-fold higher power output than SO. The second MFC array platform developed is an air-cathode MFC array using oxygen in air as electron acceptor, which is sustainable compared to ferricyanide that depletes over time. Environmental electricigen screenings were also conducted, showing parallel comparison capabilities of the developed array. The third MFC array platform is a microfluidic-cathode MFC array that enables long-term operations of miniature MFC arrays with improved power generation abilities. The capability of the microfluidic-cathode MFC array to support long-term parallel analysis was demonstrated by characterizing power generation of SO and 7Ca, proving extended operation time and improved power outputs compared to batch-mode MFC array. The fourth MFC array platform enables both catholyte and anolyte replenishments for long-term characterization of various carbon substrate performances. Finally, the 24-well microfluidic MFC array was further scaled up to 96 wells, which greatly increased the throughput of MFC parallel studies. The developed MFC arrays as high throughput screening platforms are expected to greatly impact how current MFC studies are conducted and ultimately lead to significant improvement in MFC power output.

Hou, Huijie

2011-12-01T23:59:59.000Z

392

Disposition of weapons-grade plutonium in Westinghouse reactors  

E-Print Network (OSTI)

We have studied the feasibility of using weapons-grade plutonium in the form of mixed-oxide (MOX) fuel in existing Westinghouse reactors. We have designed three transition cycles from an all LEU core to a partial MOX core. We found that four-loop Westinghouse reactors such as the Vogtle power plant are capable of handling up to 45 percent weapons-grade MOX loading without any modifications. We have also designed two kinds of weapons-grade MOX assemblies with three enrichments per assembly and four enrichments total. Wet annular burnable absorber (WABA) rods were used in all the feed and some burned MOX assemblies and some LEU feed assemblies. Integral fuel burnable absorber (IFBA) was used in the rest of the LEU feed assemblies. The average discharge burnup of MOX assemblies was over 47,000 MWD/MTM, which is more than enough to meet the "spent fuel standard." One unit is capable of consuming 0.462 MT of weapons-grade plutonium a year. Preliminary analyses showed that important reactor physics parameters for the three transitions cycles are comparable to those of LEU cores including boron levels, reactivity coefficients, peaking factors, and shutdown margins. Further transient analyses need to be performed.

Alsaed, Abdelhalim Ali

1996-01-01T23:59:59.000Z

393

Disposition of Weapons-Grade Plutonium in Westinghouse Reactors  

E-Print Network (OSTI)

Disposition of Weapons-Grade Plutonium in Westinghouse Reactors Abdelhalim Ali Alsaed and Marvin Adams We have studied the feasibility of using weapons-grade plutonium in the form of mixed-oxide (MOX) fuel in existing Westinghouse reactors. We have designed three transition cycles from an all LEU core to a partial MOX core. We found that four-loop Westinghouse reactors such as the Vogtle power plant are capable of handling up to 45 percent weapons-grade MOX loading without any modifications. We have also designed two kinds of weapons-grade MOX assemblies with three enrichments per assembly and four total enrichments. Wet annular burnable absorber (WABA) rods were used in all the MOX feed assemblies, some burned MOX assemblies, and some LEU feed assemblies. Integral fuel burnable absorber (IFBA) was used in the rest of the LEU feed assemblies. The average discharge burnup of MOX assemblies was over 47,000 MWD/MTM, which is more than enough to meet the "spent fuel standard." One unit is ...

No. De-fc-al; Abdelhalim Ali Alsaed; Abdelhalim Ali Alsaed; Marvin Adams; Marvin Adams

1998-01-01T23:59:59.000Z

394

A neutronic feasibility study for LEU conversion of the high flux isotope reactor (HFIR).  

SciTech Connect

A neutronic feasibility study was performed to determine the uranium densities that would be required to convert the High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory (ORNL) from HEU (93%) to LEU (<20%)fuel. The LEU core that was studied is the same as the current HEU core, except for potential changes in the design of the fuel plates. The study concludes that conversion of HFIR from HEU to LEU fuel would require an advanced fuel with a uranium density of 6-7 gU/cm{sup 3} in the inner fuel element and 9-10 gU/cm{sup 3} in the outer fuel element to match the cycle length of the HEU core. LEU fuel with uranium density up to 4.8 gU/cm{sup 3} is currently qualified for research reactor use. Modifications in fuel grading and burnable poison distribution are needed to produce an acceptable power distribution.

Mo, S. C.

1998-01-14T23:59:59.000Z

395

Weapons-grade plutonium dispositioning. Volume 2: Comparison of plutonium disposition options  

Science Conference Proceedings (OSTI)

The Secretary of Energy requested the National Academy of Sciences (NAS) Committee on International Security and Arms Control to evaluate disposition options for weapons-grade plutonium. The Idaho National Engineering Laboratory (INEL) offered to assist the NAS in this evaluation by investigating the technical aspects of the disposition options and their capability for achieving plutonium annihilation levels greater than 90%. This report was prepared for the NAS to document the gathered information and results from the requested option evaluations. Evaluations were performed for 12 plutonium disposition options involving five reactor and one accelerator-based systems. Each option was evaluated in four technical areas: (1) fuel status, (2) reactor or accelerator-based system status, (3) waste-processing status, and (4) waste disposal status. Based on these evaluations, each concept was rated on its operational capability and time to deployment. A third rating category of option costs could not be performed because of the unavailability of adequate information from the concept sponsors. The four options achieving the highest rating, in alphabetical order, are the Advanced Light Water Reactor with plutonium-based ternary fuel, the Advanced Liquid Metal Reactor with plutonium-based fuel, the Advanced Liquid Metal Reactor with uranium-plutonium-based fuel, and the Modular High Temperature Gas-Cooled Reactor with plutonium-based fuel. Of these four options, the Advanced Light Water Reactor and the Modular High Temperature Gas-Cooled Reactor do not propose reprocessing of their irradiated fuel. Time constraints and lack of detailed information did not allow for any further ratings among these four options. The INEL recommends these four options be investigated further to determine the optimum reactor design for plutonium disposition.

Brownson, D.A.; Hanson, D.J.; Blackman, H.S. [and others

1993-06-01T23:59:59.000Z

396

Benchmarking of the MIT High Temperature Gas-cooled Reactor TRISO-coated particle fuel performance model  

E-Print Network (OSTI)

MIT has developed a Coated Particle Fuel Performance Model to study the behavior of TRISO nuclear fuels. The code, TIMCOAT, is designed to assess the mechanical and chemical condition of populations of coated particles and ...

Stawicki, Michael A

2006-01-01T23:59:59.000Z

397

Connected gradings and fundamental group.  

E-Print Network (OSTI)

The main purpose of this paper is to provide explicit computations of the fundamental group of several algebras. For this purpose, given a $k$-algebra $A$, we consider the category of all connected gradings of $A$ by a group $G$ and we study the relation between gradings and Galois coverings. This theoretical tool gives information about the fundamental group of $A$, which allows its computation using complete lists of gradings.

Claude Cibils (I3M); Maria Julia Redondo (Departamento De Matematica UNS); Andrea Solotar (Departamento De Matematica UBA)

398