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Note: This page contains sample records for the topic "fuel pellet fabrication" 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.


1

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

2

Pellet Fueling Technology Development S. K. Combs  

E-Print Network [OSTI]

Pellet Fueling Technology Development S. K. Combs Fusion Energy Division, Oak Ridge National/10/00 Pellet Sizes Are Relevant for Fueling Applications on Any Present Experimental Fusion Device and Future pellet injector technology ¥ Hydrogen properties ¥ Ice/pellet formation techniques ¥ Acceleration

3

Manufacturing Fuel Pellets from Biomass Introduction  

E-Print Network [OSTI]

Manufacturing Fuel Pellets from Biomass Introduction Wood pellets have increased tremendously pellet stoves or boilers over traditional wood-fired equipment due to their relative ease of use. As a result, the demand for fuel pellets has also grown quickly. However, wood is not the only suitable

Boyer, Elizabeth W.

4

Fuel Fabrication Facility  

National Nuclear Security Administration (NNSA)

Construction of the Mixed Oxide Fuel Fabrication Facility Construction of the Mixed Oxide Fuel Fabrication Facility November 2005 May 2007 June 2008 May 2012...

5

Energex Pellet Fuel Inc | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 NoPublic Utilities Address:011-DNA Jump37. It is classifiedProject)EnerVault Corporation JumpHelenaEnergex Pellet

6

Fabrication of thorium bearing carbide fuels  

DOE Patents [OSTI]

Thorium-uranium carbide and thorium-plutonium carbide fuel pellets have been fabricated by the carbothermic reduction process. Temperatures of 1750.degree. C. and 2000.degree. C. were used during the reduction cycle. Sintering temperatures of 1800.degree. C. and 2000.degree. C. were used to prepare fuel pellet densities of 87% and >94% of theoretical, respectively. The process allows the fabrication of kilogram quantities of fuel with good reproducibility of chemicals and phase composition. Methods employing liquid techniques that form carbide microspheres or alloying-techniques which form alloys of thorium-uranium or thorium-plutonium suffer from limitation on the quantities processed of because of criticality concerns and lack of precise control of process conditions, respectively.

Gutierrez, Rueben L. (Los Alamos, NM); Herbst, Richard J. (Los Alamos, NM); Johnson, Karl W. R. (Los Alamos, NM)

1981-01-01T23:59:59.000Z

7

annular fuel pellet: Topics by E-print Network  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Manufacturing Fuel Pellets from Biomass Introduction Geosciences Websites Summary: are not suitable for burning...

8

Fuel pins with both target and fuel pellets in an isotope-production reactor  

DOE Patents [OSTI]

A method is described for producing tritium in a fast breeder reactor cooled with liquid metal. Lithium target pellets are placed in close contact with fissile fuel pellets in order to increase the tritium production rate.

Cawley, W.E.; Omberg, R.P.

1982-08-19T23:59:59.000Z

9

DEPOSITION OF FUEL PELLETS INJECTED INTO TOKAMAK PLASMAS Larry R. Baylor, T. C. Jernigan C. Hsieh  

E-Print Network [OSTI]

DEPOSITION OF FUEL PELLETS INJECTED INTO TOKAMAK PLASMAS Larry R. Baylor, T. C. Jernigan C. Hsieh Diego, CA 92138 (423) 574-1164 (619) 455- 4491 ABSTRACT Pellet injection has been used on tokamak deposition of these fuel pellets, defined as the change in density profile caused by the pellet, has been

10

Apparatus and method for classifying fuel pellets for nuclear reactor  

DOE Patents [OSTI]

Control for the operation of a mechanical handling and gauging system for nuclear fuel pellets. The pellets are inspected for diameters, lengths, surface flaws and weights in successive stations. The control includes, a computer for commanding the operation of the system and its electronics and for storing and processing the complex data derived at the required high rate. In measuring the diameter, the computer enables the measurement of a calibration pellet, stores that calibration data and computes and stores diameter-correction factors and their addresses along a pellet. To each diameter measurement a correction factor is applied at the appropriate address. The computer commands verification that all critical parts of the system and control are set for inspection and that each pellet is positioned for inspection. During each cycle of inspection, the measurement operation proceeds normally irrespective of whether or not a pellet is present in each station. If a pellet is not positioned in a station, a measurement is recorded, but the recorded measurement indicates maloperation. In measuring diameter and length a light pattern including successive shadows of slices transverse for diameter or longitudinal for length are projected on a photodiode array. The light pattern is scanned electronically by a train of pulses. The pulses are counted during the scan of the lighted diodes. For evaluation of diameter the maximum diameter count and the number of slices for which the diameter exceeds a predetermined minimum is determined. For acceptance, the maximum must be less than a maximum level and the minimum must exceed a set number. For evaluation of length, the maximum length is determined. For acceptance, the length must be within maximum and minimum limits.

Wilks, Robert S. (Plum Borough, PA); Sternheim, Eliezer (Pittsburgh, PA); Breakey, Gerald A. (Penn Township, Allegheny County, PA); Sturges, Jr., Robert H. (Plum Borough, PA); Taleff, Alexander (Churchill Borough, PA); Castner, Raymond P. (Monroeville, PA)

1984-01-01T23:59:59.000Z

11

1EPS Jun-1999 -LRB A Comparison of Fueling with Deuterium Pellet Injection  

E-Print Network [OSTI]

1EPS Jun-1999 - LRB A Comparison of Fueling with Deuterium Pellet Injection from Different DIII-D Pellet Injection Program q Modifications to injector (that was installed on JET 1987-91): » All three guns fire 2.7 mm pellets » Punch mechanism on one gun to reliably generate slower pellets (

12

Mechanical modeling of porous oxide fuel pellet A Test Problem  

SciTech Connect (OSTI)

A poro-elasto-plastic material model has been developed to capture the response of oxide fuels inside the nuclear reactors under operating conditions. Behavior of the oxide fuel and variation in void volume fraction under mechanical loading as predicted by the developed model has been reported in this article. The significant effect of void volume fraction on the overall stress distribution of the fuel pellet has also been described. An important oxide fuel issue that can have significant impact on the fuel performance is the mechanical response of oxide fuel pellet and clad system. Specifically, modeling the thermo-mechanical response of the fuel pellet in terms of its thermal expansion, mechanical deformation, swelling due to void formation and evolution, and the eventual contact of the fuel with the clad is of significant interest in understanding the fuel-clad mechanical interaction (FCMI). These phenomena are nonlinear and coupled since reduction in the fuel-clad gap affects thermal conductivity of the gap, which in turn affects temperature distribution within the fuel and the material properties of the fuel. Consequently, in order to accurately capture fuel-clad gap closure, we need to account for fuel swelling due to generation, retention, and evolution of fission gas in addition to the usual thermal expansion and mechanical deformation. Both fuel chemistry and microstructure also have a significant effect on the nucleation and growth of fission gas bubbles. Fuel-clad gap closure leading to eventual contact of the fuel with the clad introduces significant stresses in the clad, which makes thermo-mechanical response of the clad even more relevant. The overall aim of this test problem is to incorporate the above features in order to accurately capture fuel-clad mechanical interaction. Because of the complex nature of the problem, a series of test problems with increasing multi-physics coupling features, modeling accuracy, and complexity are defined with the objective of accurate simulation of fuel-clad mechanical interaction subjected to a wide-range of thermomechanical stimuli.

Nukala, Phani K [ORNL; Barai, Pallab [ORNL; Simunovic, Srdjan [ORNL; Ott, Larry J [ORNL

2009-10-01T23:59:59.000Z

13

Pellet Fueling Technology Development Leading to Efficient Fueling of ITER Burning Plasmas  

SciTech Connect (OSTI)

Pellet injection is the primary fueling technique planned for central fueling of the ITER burning plasma, which is a requirement for achieving high fusion gain. Injection of pellets from the inner wall has been shown on present day tokamaks to provide efficient fueling and is planned for use on ITER [1,2]. Significant development of pellet fueling technology has occurred as a result of the ITER R&D process. Extrusion rates with batch extruders have reached more than 1/2 of the ITER design specification of 1.3 cm3/s [3] and the ability to fuel efficiently from the inner wall by injecting through curved guide tubes has been demonstrated on several fusion devices. Modeling of the fueling deposition from inner wall pellet injection has been done using the Parks et al. ExB drift model [4] shows that inside launched pellets of 3mm size and speeds of 300 m/s have the capability to fuel well inside the separatrix. Gas fueling on the other hand is calculated to have very poor fueling efficiency due to the high density and wide scrape off layer compared to current machines. Isotopically mixed D/T pellets can provide efficient tritium fueling that will minimize tritium wall loading when compared to gas puffing of tritium. In addition, the use of pellets as an ELM trigger has been demonstrated and continues to be investigated as an ELM mitigation technique. During the ITER CDA and EDA the U.S. was responsible for ITER fueling system design and R&D and is in good position to resume this role for the ITER pellet fueling system. Currently the performance of the ITER guide tube design is under investigation. A mockup is being built that will allow tests with different pellet sizes and repetition rates. The results of these tests and their implication for fueling efficiency and central fueling will be discussed. The ITER pellet injection technology developments to date, specified requirements, and remaining development issues will be presented along with a plan to reach the design goal in time for employment on ITER.

Baylor, Larry R [ORNL; Combs, Stephen Kirk [ORNL; Jernigan, Thomas C [ORNL; Houlberg, Wayne A [ORNL; Maruyama, S. [ITER International Team, Garching, Germany; Owen, Larry W [ORNL; Parks, P. B. [General Atomics; Rasmussen, David A [ORNL

2005-01-01T23:59:59.000Z

14

Neutronic fuel element fabrication  

DOE Patents [OSTI]

This disclosure describes a method for metallurgically bonding a complete leak-tight enclosure to a matrix-type fuel element penetrated longitudinally by a multiplicity of coolant channels. Coolant tubes containing solid filler pins are disposed in the coolant channels. A leak-tight metal enclosure is then formed about the entire assembly of fuel matrix, coolant tubes and pins. The completely enclosed and sealed assembly is exposed to a high temperature and pressure gas environment to effect a metallurgical bond between all contacting surfaces therein. The ends of the assembly are then machined away to expose the pin ends which are chemically leached from the coolant tubes to leave the coolant tubes with internal coolant passageways. The invention described herein was made in the course of, or under, a contract with the U.S. Atomic Energy Commission. It relates generally to fuel elements for neutronic reactors and more particularly to a method for providing a leak-tight metal enclosure for a high-performance matrix-type fuel element penetrated longitudinally by a multiplicity of coolant tubes. The planned utilization of nuclear energy in high-performance, compact-propulsion and mobile power-generation systems has necessitated the development of fuel elements capable of operating at high power densities. High power densities in turn require fuel elements having high thermal conductivities and good fuel retention capabilities at high temperatures. A metal clad fuel element containing a ceramic phase of fuel intimately mixed with and bonded to a continuous refractory metal matrix has been found to satisfy the above requirements. Metal coolant tubes penetrate the matrix to afford internal cooling to the fuel element while providing positive fuel retention and containment of fission products generated within the fuel matrix. Metal header plates are bonded to the coolant tubes at each end of the fuel element and a metal cladding or can completes the fuel-matrix enclosure by encompassing the sides of the fuel element between the header plates.

Korton, George (Cincinnati, OH)

2004-02-24T23:59:59.000Z

15

Synthesis and Analysis of Alpha Silicon Carbide Components for Encapsulation of Fuel Rods and Pellets  

SciTech Connect (OSTI)

The chemical, mechanical and thermal properties of silicon carbide (SiC) along with its low neutron activation and stability in a radiation field make it an attractive material for encapsulating fuel rods and fuel pellets. The alpha phase (6H) is particularly stable. Unfortunately, it requires very high temperature processing and is not readily available in fibers or near-net shapes. This paper describes an investigation to fabricate a-SiC as thin films, fibers and near-net-shape products by direct conversion of carbon using silicon monoxide vapor at temperatures less than 1700 C. In addition, experiments to nucleate the alpha phase during pyrolysis of polysilazane, are also described. Structure and composition were characterized using scanning electron microscopy, energy dispersive spectroscopy and X-ray diffraction. Preliminary tensile property analysis of fibers was also performed.

Kevin M. McHugh; John E. Garnier; George W. Griffith

2011-09-01T23:59:59.000Z

16

Integrated Recycling Test Fuel Fabrication  

SciTech Connect (OSTI)

The Integrated Recycling Test is a collaborative irradiation test that will electrochemically recycle used light water reactor fuel into metallic fuel feedstock. The feedstock will be fabricated into a metallic fast reactor type fuel that will be irradiation tested in a drop in capsule test in the Advanced Test Reactor on the Idaho National Laboratory site. This paper will summarize the fuel fabrication activities and design efforts. Casting development will include developing a casting process and system. The closure welding system will be based on the gas tungsten arc burst welding process. The settler/bonder system has been designed to be a simple system which provides heating and controllable impact energy to ensure wetting between the fuel and cladding. The final major pieces of equipment to be designed are the weld and sodium bond inspection system. Both x-radiography and ultrasonic inspection techniques have been examine experimentally and found to be feasible, however the final remote system has not been designed. Conceptual designs for radiography and an ultrasonic system have been made.

R.S. Fielding; K.H. Kim; B. Grover; J. Smith; J. King; K. Wendt; D. Chapman; L. Zirker

2013-03-01T23:59:59.000Z

17

Contact Detection and Constraints Enforcement for the Simulation of Pellet/Clad Thermo-Mechanical Contact in Nuclear Fuel Rods  

E-Print Network [OSTI]

As fission process heats up the fuel rods, UO2 pellets stacked on top of each other swell both radially and axially, while the surrounding Zircaloy cladding creeps down, so that the pellets eventually come into contact with the clad...

Lebrun-Grandi, Damien Thomas

2014-03-05T23:59:59.000Z

18

Fuel Fabrication Capability Research and Development Plan  

SciTech Connect (OSTI)

The purpose of this document is to provide a comprehensive review of the mission of the Fuel Fabrication Capability (FFC) within the Global Threat Reduction Initiative (GTRI) Convert Program, along with research and development (R&D) needs that have been identified as necessary to ensuring mission success. The design and fabrication of successful nuclear fuels must be closely linked endeavors.

Senor, David J.; Burkes, Douglas

2013-06-28T23:59:59.000Z

19

Determination of Gd concentration profile in UO2-Gd2O3 fuel pellets  

E-Print Network [OSTI]

A transversal mapping of the Gd concentration was measured in UO2-Gd2O3 nuclear fuel pellets by electron paramagnetic resonance spectroscopy (EPR). The quantification was made from the comparison with a Gd2O3 reference sample. The nominal concentration in the pellets is UO2: 7.5 % Gd2O3. A concentration gradient was found, which indicates that the Gd2O3 amount diminishes towards the edges of the pellets. The concentration varies from (9.3 +/- 0.5)% in the center to (5.8 +/- 0.3)% in one of the edges. The method was found to be particularly suitable for the precise mapping of the distribution of Gd3+ ions in the UO2 matrix.

D. Tobia; E. L. Winkler; J. Milano; A. Butera; R. Kempf; L. Bianchi; F. Kaufmann

2014-02-28T23:59:59.000Z

20

Determination of Gd concentration profile in UO2-Gd2O3 fuel pellets  

E-Print Network [OSTI]

A transversal mapping of the Gd concentration was measured in UO2-Gd2O3 nuclear fuel pellets by electron paramagnetic resonance spectroscopy (EPR). The quantification was made from the comparison with a Gd2O3 reference sample. The nominal concentration in the pellets is UO2: 7.5 % Gd2O3. A concentration gradient was found, which indicates that the Gd2O3 amount diminishes towards the edges of the pellets. The concentration varies from (9.3 +/- 0.5)% in the center to (5.8 +/- 0.3)% in one of the edges. The method was found to be particularly suitable for the precise mapping of the distribution of Gd3+ ions in the UO2 matrix.

Tobia, D; Milano, J; Butera, A; Kempf, R; Bianchi, L; Kaufmann, F

2014-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "fuel pellet fabrication" 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

Fuel injector Holes (Fabrication of Micro-Orifices for Fuel Injectors...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

injector Holes (Fabrication of Micro-Orifices for Fuel Injectors) Fuel injector Holes (Fabrication of Micro-Orifices for Fuel Injectors) 2009 DOE Hydrogen Program and Vehicle...

22

Method for producing sintered ceramic, layered, circular fuel pellets  

DOE Patents [OSTI]

A compacting die wherein the improvement comprises providing a screen in the die cavity, the screen being positioned parallel to the side walls of said die and dividing the die cavity into center and annular compartments. In addition, the use of this die in a method for producing an annular clad ceramic fuel material is disclosed.

Harlow, John L. (East Berne, NY)

1983-01-01T23:59:59.000Z

23

Validation of the BISON 3D Fuel Performance Code: Temperature Comparisons for Concentrically and Eccentrically Located Fuel Pellets  

SciTech Connect (OSTI)

BISON is a modern finite-element based nuclear fuel performance code that has been under development at the Idaho National Laboratory (USA) since 2009. The code is applicable to both steady and transient fuel behaviour and is used to analyse either 2D axisymmetric or 3D geometries. BISON has been applied to a variety of fuel forms including LWR fuel rods, TRISO-coated fuel particles, and metallic fuel in both rod and plate geometries. Code validation is currently in progress, principally by comparison to instrumented LWR fuel rods. Halden IFA experiments constitute a large percentage of the current BISON validation base. The validation emphasis here is centreline temperatures at the beginning of fuel life, with comparisons made to seven rods from the IFA-431 and 432 assemblies. The principal focus is IFA-431 Rod 4, which included concentric and eccentrically located fuel pellets. This experiment provides an opportunity to explore 3D thermomechanical behaviour and assess the 3D simulation capabilities of BISON. Analysis results agree with experimental results showing lower fuel centreline temperatures for eccentric fuel with the peak temperature shifted from the centreline. The comparison confirms with modern 3D analysis tools that the measured temperature difference between concentric and eccentric pellets is not an artefact and provides a quantitative explanation for the difference.

J. D. Hales; D. M. Perez; R. L. Williamson; S. R. Novascone; B. W. Spencer

2013-03-01T23:59:59.000Z

24

Fuel Fabrication Capability Research and Development Plan  

SciTech Connect (OSTI)

The purpose of this document is to provide a comprehensive review of the mission of the Fuel Fabrication Capability (FFC) within the Global Threat Reduction Initiative Convert Program, along with research and development (R&D) needs that have been identified as necessary to ensuring mission success. The design and fabrication of successful nuclear fuels must be closely linked endeavors. Therefore, the overriding motivation behind the FFC R&D program described in this plan is to foster closer integration between fuel design and fabrication to reduce programmatic risk. These motivating factors are all interrelated, and progress addressing one will aid understanding of the others. The FFC R&D needs fall into two principal categories, 1) baseline process optimization, to refine the existing fabrication technologies, and 2) manufacturing process alternatives, to evaluate new fabrication technologies that could provide improvements in quality, repeatability, material utilization, or cost. The FFC R&D Plan examines efforts currently under way in regard to coupon, foil, plate, and fuel element manufacturing, and provides recommendations for a number of R&D topics that are of high priority but not currently funded (i.e., knowledge gaps). The plan ties all FFC R&D efforts into a unified vision that supports the overall Convert Program schedule in general, and the fabrication schedule leading up to the MP-1 and FSP-1 irradiation experiments specifically. The fabrication technology decision gates and down-selection logic and schedules are tied to the schedule for fabricating the MP-1 fuel plates, which will provide the necessary data to make a final fuel fabrication process down-selection. Because of the short turnaround between MP-1 and the follow-on FSP-1 and MP-2 experiments, the suite of specimen types that will be available for MP-1 will be the same as those available for FSP-1 and MP-2. Therefore, the only opportunity to explore parameter space and alternative processing is between now and 2016 when the candidate processes are down-selected in preparation for the MP-1, FSP-1, and MP-2 plate manufacturing campaigns. A number of key risks identified by the FFC are discussed in this plan, with recommended mitigating actions for those activities within FFC, and identification of risks that are impacted by activities in other areas of the Convert Program. The R&D Plan does not include discussion of FFC initiatives related to production-scale manufacturing of fuel (e.g., establishment of the Pilot Line Production Facility), rather, the goal of this plan is to document the R&D activities needed ultimately to enable high-quality and cost-effective production of the fuel by the commercial fuel fabricator. The intent is for this R&D Plan to be a living document that will be reviewed and updated on a regular basis (e.g., annually) to ensure that FFC R&D activities remain properly aligned to the needs of the Convert Program. This version of the R&D Plan represents the first annual review and revision.

Senor, David J.; Burkes, Douglas

2014-04-17T23:59:59.000Z

25

Automated catalyst processing for cloud electrode fabrication for fuel cells  

DOE Patents [OSTI]

A process for making dry carbon/polytetrafluoroethylene floc material, particularly useful in the manufacture of fuel cell electrodes, comprises of the steps of floccing a co-suspension of carbon particles and polytetrafluoroethylene particles, filtering excess liquids from the co-suspension, molding pellet shapes from the remaining wet floc solids without using significant pressure during the molding, drying the wet floc pellet shapes within the mold at temperatures no greater than about 150.degree. F., and removing the dry pellets from the mold.

Goller, Glen J. (West Springfield, MA); Breault, Richard D. (Coventry, CT)

1980-01-01T23:59:59.000Z

26

Automated fabrication, characterization and transport of ICF pellets. Final report, March 1, 1979-October 31, 1980  

SciTech Connect (OSTI)

The near-term objectives of the contract were threefold: (1) evaluate techniques for the production of frozen hydrogen microspheres and demonstrate concepts for coating them; (2) develop and demonstrate an optical characterization system which could lead to automated pellet inspection; and (3) develop and demonstrate a preliminary electrostatic pellet transport control system. This report describes the equipment assembled for these experiments and the results obtained.

Clifford, D W; Boyd, B A; Lilienkamp, R H

1980-12-01T23:59:59.000Z

27

Advanced Pellet Cladding Interaction Modeling Using the US DOE CASL Fuel Performance Code: Peregrine  

SciTech Connect (OSTI)

The US DOEs Consortium for Advanced Simulation of LWRs (CASL) program has undertaken an effort to enhance and develop modeling and simulation tools for a virtual reactor application, including high fidelity neutronics, fluid flow/thermal hydraulics, and fuel and material behavior. The fuel performance analysis efforts aim to provide 3-dimensional capabilities for single and multiple rods to assess safety margins and the impact of plant operation and fuel rod design on the fuel thermomechanical- chemical behavior, including Pellet-Cladding Interaction (PCI) failures and CRUD-Induced Localized Corrosion (CILC) failures in PWRs. [1-3] The CASL fuel performance code, Peregrine, is an engineering scale code that is built upon the MOOSE/ELK/FOX computational FEM framework, which is also common to the fuel modeling framework, BISON [4,5]. Peregrine uses both 2-D and 3-D geometric fuel rod representations and contains a materials properties and fuel behavior model library for the UO2 and Zircaloy system common to PWR fuel derived from both open literature sources and the FALCON code [6]. The primary purpose of Peregrine is to accurately calculate the thermal, mechanical, and chemical processes active throughout a single fuel rod during operation in a reactor, for both steady state and off-normal conditions.

Jason Hales; Various

2014-06-01T23:59:59.000Z

28

Chemical aspects of pellet-cladding interaction in light water reactor fuel elements  

SciTech Connect (OSTI)

In contrast to the extensive literature on the mechanical aspects of pellet-cladding interaction (PCI) in light water reactor fuel elements, the chemical features of this phenomenon are so poorly understood that there is still disagreement concerning the chemical agent responsible. Since the earliest work by Rosenbaum, Davies and Pon, laboratory and in-reactor experiments designed to elucidate the mechanism of PCI fuel rod failures have concentrated almost exclusively on iodine. The assumption that this is the reponsible chemical agent is contained in models of PCI which have been constructed for incorporation into fuel performance codes. The evidence implicating iodine is circumstantial, being based primarily upon the volatility and significant fission yield of this element and on the microstructural similarity of the failed Zircaloy specimens exposed to iodine in laboratory stress corrosion cracking (SCC) tests to cladding failures by PCI.

Olander, D.R.

1982-01-01T23:59:59.000Z

29

Update on US High Density Fuel Fabrication Development  

SciTech Connect (OSTI)

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 encompassesfuel powder to monolithic foil and binary fuel systems to multiple element additionssignificant 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

30

LIBS Spectral Data for a Mixed Actinide Fuel Pellet Containing Uranium, Plutonium, Neptunium and Americium  

SciTech Connect (OSTI)

Laser-induced breakdown spectroscopy (LIBS) was used to analyze a mixed actinide fuel pellet containing 75% UO{sub 2}/20% PuO{sub 2}/3% AmO{sub 2}/2% NpO{sub 2}. The preliminary data shown here is the first report of LIBS analysis of a mixed actinide fuel pellet, to the authors knowledge. The LIBS spectral data was acquired in a plutonium facility at Los Alamos National Laboratory where the sample was contained within a glove box. The initial installation of the glove box was not intended for complete ultraviolet (UV), visible (VIS) and near infrared (NIR) transmission, therefore the LIBS spectrum is truncated in the UV and NIR regions due to the optical transmission of the window port and filters that were installed. The optical collection of the emission from the LIBS plasma will be optimized in the future. However, the preliminary LIBS data acquired is worth reporting due to the uniqueness of the sample and spectral data. The analysis of several actinides in the presence of each other is an important feature of this analysis since traditional methods must chemically separate uranium, plutonium, neptunium, and americium prior to analysis. Due to the historic nature of the sample fuel pellet analyzed, the provided sample composition of 75% UO{sub 2}/20% PuO{sub 2}/3% AmO{sub 2}/2% NpO{sub 2} cannot be confirm without further analytical processing. Uranium, plutonium, and americium emission lines were abundant and easily assigned while neptunium was more difficult to identify. There may be several reasons for this observation, other than knowing the exact sample composition of the fuel pellet. First, the atomic emission wavelength resources for neptunium are limited and such techniques as hollow cathode discharge lamp have different dynamics than the plasma used in LIBS which results in different emission spectra. Secondly, due to the complex sample of four actinide elements, which all have very dense electronic energy levels, there may be reactions and interactions occurring within the plasma, such as collisional energy transfer, that might be a factor in the reduction in neptunium emission lines. Neptunium has to be analyzed alone using LIBS to further understand the dynamics that may be occurring in the plasma of the mixed actinide fuel pellet sample. The LIBS data suggests that the emission spectrum for the mixed actinide fuel pellet is not simply the sum of the emission spectra of the pure samples but is dependent on the species present in the plasma and the interactions and reactions that occur within the plasma. Finally, many of the neptunium lines are in the near infrared region which is drastically reduced in intensity by the current optical setup and possibly the sensitivity of the emission detector in the spectral region. Once the optics are replaced and the optical collection system is modified and optimized, the probability of observing emission lines for neptunium might be increased significantly. The mixed actinide fuel pellet was analyzed under the experimental conditions listed in Table 1. The LIBS spectra of the fuel pellet are shown in Figures 1-49. The spectra are labeled with the observed wavelength and atomic species (both neutral (I) and ionic (II)). Table 2 is a complete list of the observed and literature based emission wavelengths. The literature wavelengths have references including NIST Atomic Spectra Database (NIST), B.A. Palmer et al. 'An Atlas of Uranium Emission Intensities in a Hollow Cathode Discharge' taken at the Kitt Peak National Observatory (KPNO), R.L. Kurucz 1995 Atomic Line Data from the Smithsonian Astrophysical Observatory (SAO), J. Blaise et al. 'The Atomic Spectrum of Plutonium' from Argonne National Laboratory (BFG), and M. Fred and F.S. Tomkins, 'Preliminary Term Analysis of Am I and Am II Spectra' (FT). The dash (-) shown under Ionic State indicates that the ionic state of the transition was not available. In the spectra, the dash (-) is replaced with a question mark (?). Peaks that are not assigned are most likely real features and not noise but cannot be confidently assi

Judge, Elizabeth J. [Los Alamos National Laboratory; Berg, John M. [Los Alamos National Laboratory; Le, Loan A. [Los Alamos National Laboratory; Lopez, Leon N. [Los Alamos National Laboratory; Barefield, James E. [Los Alamos National Laboratory

2012-06-18T23:59:59.000Z

31

The Asian Wood Pellet Markets  

E-Print Network [OSTI]

The Asian Wood Pellet Markets Joseph A. Roos and Allen M. Brackley United States Department Wood Pellet plant in North Pole, Alaska. Clockwise from upper left: pelleting machine; pellets bagged for home use; a Superior Pellet Fuels bag; inventory of product ready for shipment to retailers. Upper

32

Handbook for Small-Scale Densified Biomass Fuel (Pellets) Manufacturing for Local Markets.  

SciTech Connect (OSTI)

Wood pellet manufacturing in the Intermountain West is a recently founded and rapidly expanding energy industry for small-scale producers. Within a three-year period, the total number of manufacturers in the region has increased from seven to twelve (Folk et al., 1988). Small-scale industry development is evolving because a supply of raw materials from small and some medium-sized primary and secondary wood processors that has been largely unused. For the residue producer considering pellet fuel manufacturing, the wastewood generated from primary products often carries a cost associated with residue disposal when methods at-e stockpiling, landfilling or incinerating. Regional processors use these methods for a variety of reasons, including the relatively small amounts of residue produced, residue form, mixed residue types, high transportation costs and lack of a local market, convenience and absence of regulation. Direct costs associated with residue disposal include the expenses required to own and operate residue handling equipment, costs for operating and maintaining a combustor and tipping fees charged to accept wood waste at public landfills. Economic and social costs related to environmental concerns may also be incurred to include local air and water quality degradation from open-air combustion and leachate movement into streams and drinking water.

Folk, Richard L.; Govett, Robert L.

1992-07-01T23:59:59.000Z

33

Assured Fuel Supply: Potential Conversion and Fabrication Bottlenecks  

E-Print Network [OSTI]

Assured Fuel Supply: Potential Conversion and Fabrication Bottlenecks PNNL-16951 DRAFT Authors bottlenecks that may arise in the conversion and fuel fabrication steps when used in conjunction with the U.S.-sponsored Reliable Fuel Supply (RFS) reserve. Paper is also intended to identify pathways for assessing the magnitude

34

Evaluation of Gas, Oil and Wood Pellet Fueled Residential Heating System Emissions Characteristics  

SciTech Connect (OSTI)

This study has measured the emissions from a wide range of heating equipment burning different fuels including several liquid fuel options, utility supplied natural gas and wood pellet resources. The major effort was placed on generating a database for the mass emission rate of fine particulates (PM 2.5) for the various fuel types studied. The fine particulates or PM 2.5 (less than 2.5 microns in size) were measured using a dilution tunnel technique following the method described in US EPA CTM-039. The PM 2.5 emission results are expressed in several units for the benefit of scientists, engineers and administrators. The measurements of gaseous emissions of O{sub 2}, CO{sub 2}, CO, NO{sub x} and SO{sub 2} were made using a combustion analyzer based on electrochemical cells These measurements are presented for each of the residential heating systems tested. This analyzer also provides a steady state efficiency based on stack gas and temperature measurements and these values are included in the report. The gaseous results are within the ranges expected from prior emission studies with the enhancement of expanding these measurements to fuels not available to earlier researchers. Based on measured excess air levels and ultimate analysis of the fuel's chemical composition the gaseous emission results are as expected and fall within the range provided for emission factors contained in the US-EPA AP 42, Emission Factors Volume I, Fifth Edition. Since there were no unexpected findings in these gaseous measurements, the bulk of the report is centered on the emissions of fine particulates, or PM 2.5. The fine particulate (PM 2.5) results for the liquid fuel fired heating systems indicate a very strong linear relationship between the fine particulate emissions and the sulfur content of the liquid fuels being studied. This is illustrated by the plot contained in the first figure on the next page which clearly illustrates the linear relationship between the measured mass of fine particulate per unit of energy, expressed as milligrams per Mega-Joule (mg/MJ) versus the different sulfur contents of four different heating fuels. These were tested in a conventional cast iron boiler equipped with a flame retention head burner. The fuels included a typical ASTM No. 2 fuel oil with sulfur below 0.5 percent (1520 average ppm S), an ASTM No. 2 fuel oil with very high sulfur content (5780 ppm S), low sulfur heating oil (322 ppm S) and an ultra low sulfur diesel fuel (11 ppm S). Three additional oil-fired heating system types were also tested with normal heating fuel, low sulfur and ultralow sulfur fuel. They included an oil-fired warm air furnace of conventional design, a high efficiency condensing warm air furnace, a condensing hydronic boiler and the conventional hydronic boiler as discussed above. The linearity in the results was observed with all of the different oil-fired equipment types (as shown in the second figure on the next page). A linear regression of the data resulted in an Rsquared value of 0.99 indicating that a very good linear relationship exits. This means that as sulfur decreases the PM 2.5 emissions are reduced in a linear manner within the sulfur content range tested. At the ultra low sulfur level (15 ppm S) the amount of PM 2.5 had been reduced dramatically to an average of 0.043 mg/MJ. Three different gas-fired heating systems were tested. These included a conventional in-shot induced draft warm air furnace, an atmospheric fired hydronic boiler and a high efficiency hydronic boiler. The particulate (PM 2.5) measured ranged from 0.011 to 0.036 mg/MJ. depending on the raw material source used in their manufacture. All three stoves tested were fueled with premium (low ash) wood pellets obtained in a single batch to provide for uniformity in the test fuel. Unlike the oil and gas fired systems, the wood pellet stoves had measurable amounts of particulates sized above the 2.5-micron size that defines fine particulates (less than 2.5 microns). The fine particulate emissions rates ranged from 22 to 30 mg/ MJ with an average value

McDonald, R.

2009-12-01T23:59:59.000Z

35

Demonstration of fuel resistant to pellet-cladding interaction: Phase 2. Second semiannual report, July-December 1979  

SciTech Connect (OSTI)

This program has as its ultimate objective the demonstration of an advanced fuel design that is resistant to the failure mechanism known as fuel pellet-cladding interaction (PCI). Two fuel concepts are being developed for possible demonstration within this program: (a) Cu-barrier fuel and (b) Zr-liner fuel. In the current report period the nuclear design of the demonstration was begun. The design calls for 132 bundles of barrier fuel to be inserted into the core of Quad Cities Unit 2 at the beginning of Cycle 6. Laboratory and in-reactor tests were started to evaluate the stability of Zr-liner fuel which remains in service after a defect has occurred which allows water to enter the rod. Results to date on intentionally defected fuel indicate that the Zr-liner fuel is not rapidly degraded despite ingress of water.

Rosenbaum, H.S. (comp.)

1980-03-01T23:59:59.000Z

36

Advanced Safeguards Approaches for New TRU Fuel Fabrication Facilities  

SciTech Connect (OSTI)

This second report in a series of three reviews possible safeguards approaches for the new transuranic (TRU) fuel fabrication processes to be deployed at AFCF specifically, the ceramic TRU (MOX) fuel fabrication line and the metallic (pyroprocessing) line. The most common TRU fuel has been fuel composed of mixed plutonium and uranium dioxide, referred to as MOX. However, under the Advanced Fuel Cycle projects custom-made fuels with higher contents of neptunium, americium, and curium may also be produced to evaluate if these minor actinides can be effectively burned and transmuted through irradiation in the ABR. A third and final report in this series will evaluate and review the advanced safeguards approach options for the ABR. In reviewing and developing the advanced safeguards approach for the new TRU fuel fabrication processes envisioned for AFCF, the existing international (IAEA) safeguards approach at the Plutonium Fuel Production Facility (PFPF) and the conceptual approach planned for the new J-MOX facility in Japan have been considered as a starting point of reference. The pyro-metallurgical reprocessing and fuel fabrication process at EBR-II near Idaho Falls also provided insight for safeguarding the additional metallic pyroprocessing fuel fabrication line planned for AFCF.

Durst, Philip C.; Ehinger, Michael H.; Boyer, Brian; Therios, Ike; Bean, Robert; Dougan, A.; Tolk, K.

2007-12-15T23:59:59.000Z

37

MONOLITHIC FUEL FABRICATION PROCESS DEVELOPMENT AT THE IDAHO NATIONAL LABORATORY  

SciTech Connect (OSTI)

Within the Reduced Enrichment for Research and Test Reactors (RERTR) program directed by the US Department of Energy (DOE), UMo fuel-foils are being developed in an effort to realize high density monolithic fuel plates for use in high-flux research and test reactors. Namely, targeted are reactors that are not amenable to Low Enriched Uranium (LEU) fuel conversion via utilization of high density dispersion-based fuels, i.e. 8-9 gU/cc. LEU conversion of reactors having a need for >8-9 gU/cc fuel density will only be possible by way of monolithic fuel forms. The UMo fuel foils under development afford fuel meat density of ~16 gU/cc and thus have the potential to facilitate LEU conversions without any significant reactor-performance penalty. Two primary challenges have been established with respect to UMo monolithic fuel development; namely, fuel element fabrication and in-reactor fuel element performance. Both issues are being addressed concurrently at the Idaho National Laboratory. An overview is provided of the ongoing monolithic UMo fuel development effort at the Idaho National Laboratory (INL); including development of complex/graded fuel foils. Fabrication processes to be discussed include: UMo alloying and casting, foil fabrication via hot rolling, fuel-clad interlayer application via co-rolling and thermal spray processes, clad bonding via Hot Isostatic Pressing (HIP) and Friction Bonding (FB), and fuel plate finishing.

Glenn A. Moore; Francine J. Rice; Nicolas E. Woolstenhulme; W. David SwanK; DeLon C. Haggard; Jan-Fong Jue; Blair H. Park; Steven E. Steffler; N. Pat Hallinan; Michael D. Chapple; Douglas E. Burkes

2008-10-01T23:59:59.000Z

38

Fabrication of Small Diesel Fuel Injector Orifices  

Broader source: Energy.gov (indexed) [DOE]

nozzles. - Improved fuel atomization reduces sootparticulate formation and improves air entrainment thereby improving combustion efficiency Multiple approaches were examined...

39

Comments on Americium Volatilization during Fuel Fabrication for Fast Reactors  

SciTech Connect (OSTI)

The physical processes relevant to the fabrication of metallic and ceramic nuclear fuels are analyzed, with attention to recycling of fuels containing U, Pu, and minor volatile actinides for the use in fast reactors. This analysis is relevant to the development of a process model that can be used for the numerical simulation and prediction of the spatial distribution of composition in the fuel, an important factor in fuel performance.

Sabau, Adrian S [ORNL; Ohriner, Evan Keith [ORNL

2008-01-01T23:59:59.000Z

40

Coated U(Mo) Fuel: As-Fabricated Microstructures  

SciTech Connect (OSTI)

As part of the development of low-enriched uranium fuels, fuel plates have recently been tested in the BR-2 reactor as part of the SELENIUM experiment. These fuel plates contained fuel particles with either Si or ZrN thin film coating (up to 1 m thickness) around the U-7Mo fuel particles. In order to best understand irradiation performance, it is important to determine the starting microstructure that can be observed in as-fabricated fuel plates. To this end, detailed microstructural characterization was performed on ZrN and Si-coated U-7Mo powder in samples taken from AA6061-clad fuel plates fabricated at 500C. Of interest was the condition of the thin film coatings after fabrication at a relatively high temperature. Both scanning electron microscopy and transmission electron microscopy were employed. The ZrN thin film coating was observed to consist of columns comprised of very fine ZrN grains. Relatively large amounts of porosity could be found in some areas of the thin film, along with an enrichment of oxygen around each of the the ZrN columns. In the case of the pure Si thin film coating sample, a (U,Mo,Al,Si) interaction layer was observed around the U-7Mo particles. Apparently, the Si reacted with the U-7Mo and Al matrix during fuel plate fabrication at 500C to form this layer. The microstructure of the formed layer is very similar to those that form in U-7Mo versus Al-Si alloy diffusion couples annealed at higher temperatures and as-fabricated U-7Mo dispersion fuel plates with Al-Si alloy matrix fabricated at 500C.

Emmanuel Perez; Dennis D. Keiser, Jr.; Ann Leenaers; Sven Van den Berghe; Tom Wiencek

2014-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "fuel pellet fabrication" 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

MONOLITHIC FUEL FABRICATION PROCESS DEVELOPMENT AT THE IDAHO NATIONAL LABORATORY_  

SciTech Connect (OSTI)

Full-size/prototypic U10Mo monolithic fuel-foils and aluminum clad fuel plates are being developed at the Idaho National Laboratorys (INL) Materials and Fuels Complex (MFC). These efforts are focused on realizing Low Enriched Uranium (LEU) high density monolithic fuel plates for use in High Performance Research and Test Reactors. The U10Mo fuel foils under development afford a fuel meat density of ~16 gU/cc and thus have the potential to facilitate LEU conversions without any significant reactor-performance penalty. An overview is provided of the ongoing monolithic UMo fuel development effort, including application of a zirconium barrier layer on fuel foils, fabrication scale-up efforts, and development of complex/graded fuel foils. Fuel plate clad bonding processes to be discussed include: Hot Isostatic Pressing (HIP) and Friction Bonding (FB).

G. A. Moore; F. J. Rice; N. E. Woolstenhulme; J-F. Jue; B. H. Park; S. E. Steffler; N. P. Hallinan; M. D. Chapple; M. C. Marshall; B. L. Mackowiak; C. R. Clark; B. H. Rabin

2009-11-01T23:59:59.000Z

42

Fabrication and Characterization of Fully Ceramic Microencapsulated Fuels  

SciTech Connect (OSTI)

The current generation of fully ceramic microencapsulated fuels, consisting of Tristructural Isotropic fuel particles embedded in a silicon carbide matrix, is fabricated by hot pressing. Matrix powder feedstock is comprised of alumina - yttria additives thoroughly mixed with silicon carbide nanopowder using polyethyleneimine as a dispersing agent. Fuel compacts are fabricated by hot pressing the powder - fuel particle mixture at a temperature of 1800-1900 C using compaction pressures of 10-20 MPa. Detailed microstructural characterization of the final fuel compacts shows that oxide additives are limited in extent and are distributed uniformly at silicon carbide grain boundaries, at triple joints between silicon carbide grains, and at the fuel particle-matrix interface.

Terrani, Kurt A [ORNL; Kiggans, Jim [ORNL; Katoh, Yutai [ORNL; Shimoda, Kazuya [Kyoto University, Japan; Montgomery, Fred C [ORNL; Armstrong, Beth L [ORNL; Parish, Chad M [ORNL; Hinoki, Tatsuya [Kyoto University, Japan; Hunn, John D [ORNL; Snead, Lance Lewis [ORNL

2012-01-01T23:59:59.000Z

43

Redundancy of Supply in the International Nuclear Fuel Fabrication Market: Are Fabrication Services Assured?  

SciTech Connect (OSTI)

For several years, Pacific Northwest National Laboratory (PNNL) has been assessing the reliability of nuclear fuel supply in support of the U.S. Department of Energy/National Nuclear Security Administration. Three international low enriched uranium reserves, which are intended back up the existing and well-functioning nuclear fuel market, are currently moving toward implementation. These backup reserves are intended to provide countries credible assurance that of the uninterrupted supply of nuclear fuel to operate their nuclear power reactors in the event that their primary fuel supply is disrupted, whether for political or other reasons. The efficacy of these backup reserves, however, may be constrained without redundant fabrication services. This report presents the findings of a recent PNNL study that simulated outages of varying durations at specific nuclear fuel fabrication plants. The modeling specifically enabled prediction and visualization of the reactors affected and the degree of fuel delivery delay. The results thus provide insight on the extent of vulnerability to nuclear fuel supply disruption at the level of individual fabrication plants, reactors, and countries. The simulation studies demonstrate that, when a reasonable set of qualification criteria are applied, existing fabrication plants are technically qualified to provide backup fabrication services to the majority of the world's power reactors. The report concludes with an assessment of the redundancy of fuel supply in the nuclear fuel market, and a description of potential extra-market mechanisms to enhance the security of fuel supply in cases where it may be warranted. This report is an assessment of the ability of the existing market to respond to supply disruptions that occur for technical reasons. A forthcoming report will address political disruption scenarios.

Seward, Amy M.; Toomey, Christopher; Ford, Benjamin E.; Wood, Thomas W.; Perkins, Casey J.

2011-11-14T23:59:59.000Z

44

Greenfield Alternative Study LEU-Mo Fuel Fabrication Facility  

SciTech Connect (OSTI)

This report provides the initial first look of the design of the Greenfield Alternative of the Fuel Fabrication Capability (FFC); a facility to be built at a Greenfield DOE National Laboratory site. The FFC is designed to fabricate LEU-Mo monolithic fuel for the 5 US High Performance Research Reactors (HPRRs). This report provides a pre-conceptual design of the site, facility, process and equipment systems of the FFC; along with a preliminary hazards evaluation, risk assessment as well as the ROM cost and schedule estimate.

Washington Division of URS

2008-07-01T23:59:59.000Z

45

Determination of Radial Power Profiles in Thorium-Plutonium Mixed Oxide Fuel Pellets.  

E-Print Network [OSTI]

??To be able to license fuel for use in commercial nuclear reactors its thermomechanical behavior needs to be well known. For this, fuel performance codes (more)

fredriksson, patrik

2014-01-01T23:59:59.000Z

46

FABRICATION OF URANIUM OXYCARBIDE KERNELS AND COMPACTS FOR HTR FUEL  

SciTech Connect (OSTI)

As part of the program to demonstrate tristructural isotropic (TRISO)-coated fuel for the Next Generation Nuclear Plant (NGNP), Advanced Gas Reactor (AGR) fuel is being irradiation tested in the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL). This testing has led to improved kernel fabrication techniques, the formation of TRISO fuel particles, and upgrades to the overcoating, compaction, and heat treatment processes. Combined, these improvements provide a fuel manufacturing process that meets the stringent requirements associated with testing in the AGR experimentation program. Researchers at Idaho National Laboratory (INL) are working in conjunction with a team from Babcock and Wilcox (B&W) and Oak Ridge National Laboratory (ORNL) to (a) improve the quality of uranium oxycarbide (UCO) fuel kernels, (b) deposit TRISO layers to produce a fuel that meets or exceeds the standard developed by German researches in the 1980s, and (c) develop a process to overcoat TRISO particles with the same matrix material, but applies it with water using equipment previously and successfully employed in the pharmaceutical industry. A primary goal of this work is to simplify the process, making it more robust and repeatable while relying less on operator technique than prior overcoating efforts. A secondary goal is to improve first-pass yields to greater than 95% through the use of established technology and equipment. In the first test, called AGR-1, graphite compacts containing approximately 300,000 coated particles were irradiated from December 2006 to November 2009. The AGR-1 fuel was designed to closely replicate many of the properties of German TRISO-coated particles, thought to be important for good fuel performance. No release of gaseous fission product, indicative of particle coating failure, was detected in the nearly 3-year irradiation to a peak burn up of 19.6% at a time-average temperature of 10381121C. Before fabricating AGR-2 fuel, each fabrication process was improved and changed. Changes to the kernel fabrication process included replacing the carbon black powder feed with a surface-modified carbon slurry and shortening the sintering schedule. AGR-2 TRISO particles were produced in a 6-inch diameter coater using a charge size about 21-times that of the 2-inch diameter coater used to coat AGR-1 particles. The compacting process was changed to increase matrix density and throughput by increasing the temperature and pressure of pressing and using a different type of press. AGR-2 fuel began irradiation in the ATR in late spring 2010.

Dr. Jeffrey A. Phillips; Eric L. Shaber; Scott G. Nagley

2012-10-01T23:59:59.000Z

47

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

48

Fabrication of small-orifice fuel injectors for diesel engines.  

SciTech Connect (OSTI)

Diesel fuel injector nozzles with spray hole diameters of 50-75 {micro}m have been fabricated via electroless nickel plating of conventionally made nozzles. Thick layers of nickel are deposited onto the orifice interior surfaces, reducing the diameter from {approx}200 {micro}m to the target diameter. The nickel plate is hard, smooth, and adherent, and covers the orifice interior surfaces uniformly.

Woodford, J. B.; Fenske, G. R.

2005-04-08T23:59:59.000Z

49

Discrete Element Model for Simulations of Early-Life Thermal Fracturing Behaviors in Ceramic Nuclear Fuel Pellets  

SciTech Connect (OSTI)

A discrete element Model (DEM) representation of coupled solid mechanics/fracturing and heat conduction processes has been developed and applied to explicitly simulate the random initiations and subsequent propagations of interacting thermal cracks in a ceramic nuclear fuel pellet during initial rise to power and during power cycles. The DEM model clearly predicts realistic early-life crack patterns including both radial cracks and circumferential cracks. Simulation results clearly demonstrate the formation of radial cracks during the initial power rise, and formation of circumferential cracks as the power is ramped down. In these simulations, additional early-life power cycles do not lead to the formation of new thermal cracks. They do, however clearly indicate changes in the apertures of thermal cracks during later power cycles due to thermal expansion and shrinkage. The number of radial cracks increases with increasing power, which is consistent with the experimental observations.

Hai Huang; Ben Spencer; Jason Hales

2014-10-01T23:59:59.000Z

50

E-Print Network 3.0 - abb-2901 fuel pellet Sample Search Results  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

P.O. Box 1663, Los Alamos, NM 87545 USA... fueling systems in support of magnetic fusion energy, particularly the International Thermonuclear... - tritium (D-T) gas puffing...

51

E-Print Network 3.0 - advanced-feature fuel pellet Sample Search...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

P.O. Box 1663, Los Alamos, NM 87545 USA... fueling systems in support of magnetic fusion energy, particularly the International Thermonuclear... - tritium (D-T) gas puffing...

52

E-Print Network 3.0 - advanced fuel pellet Sample Search Results  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

P.O. Box 1663, Los Alamos, NM 87545 USA... fueling systems in support of magnetic fusion energy, particularly the International Thermonuclear... - tritium (D-T) gas puffing...

53

Pelletizing lignite  

DOE Patents [OSTI]

Lignite is formed into high strength pellets having a calorific value of at least 9,500 Btu/lb by blending a sufficient amount of an aqueous base bituminous emulsion with finely-divided raw lignite containing its inherent moisture to form a moistened green mixture containing at least 3 weight % of the bituminous material, based on the total dry weight of the solids, pelletizing the green mixture into discrete green pellets of a predetermined average diameter and drying the green pellets to a predetermined moisture content, preferrably no less than about 5 weight %. Lignite char and mixture of raw lignite and lignite char can be formed into high strength pellets in the same general manner.

Goksel, Mehmet A. (Houghton, MI)

1983-11-01T23:59:59.000Z

54

FULL SIZE U-10MO MONOLITHIC FUEL FOIL AND FUEL PLATE FABRICATION-TECHNOLOGY DEVELOPMENT  

SciTech Connect (OSTI)

Full-size U10Mo foils are being developed for use in high density LEU monolithic fuel plates. The application of a zirconium barrier layer too the foil is applied using a hot co-rolling process. Aluminum clad fuel plates are fabricated using Hot Isostatic Pressing (HIP) or a Friction Bonding (FB) process. An overview is provided of ongoing technology development activities, including: the co-rolling process, foil shearing/slitting and polishing, cladding bonding processes, plate forming, plate-assembly swaging, and fuel plate characterization. Characterization techniques being employed include, Ultrasonic Testing (UT), radiography, and microscopy.

G. A. Moore; J-F Jue; B. H. Rabin; M. J. Nilles

2010-03-01T23:59:59.000Z

55

Successful biomass (wood pellets ) implementation in  

E-Print Network [OSTI]

Successful biomass (wood pellets ) implementation in Estonia Biomass Utilisation of Local of primary energy in Estonia ! Wood fuels production ! Pellet firing projects in Estonia ­ SIDA Demo East Production of wood fuels in Estonia in 2002 Regional Energy Centres in Estonia Wood pellets production

56

Premium Fuel Production From Mining and Timber Waste Using Advanced Separation and Pelletizing Technologies  

SciTech Connect (OSTI)

The Commonwealth of Kentucky is one of the leading states in the production of both coal and timber. As a result of mining and processing coal, an estimated 3 million tons of fine coal are disposed annually to waste-slurry impoundments with an additional 500 million tons stored at a number of disposal sites around the state due to past practices. Likewise, the Kentucky timber industry discards nearly 35,000 tons of sawdust on the production site due to unfavorable economics of transporting the material to industrial boilers for use as a fuel. With an average heating value of 6,700 Btu/lb, the monetary value of the energy disposed in the form of sawdust is approximately $490,000 annually. Since the two industries are typically in close proximity, one promising avenue is to selectively recover and dewater the fine-coal particles and then briquette them with sawdust to produce a high-value fuel. The benefits are i) a premium fuel product that is low in moisture and can be handled, transported, and utilized in existing infrastructure, thereby avoiding significant additional capital investment and ii) a reduction in the amount of fine-waste material produced by the two industries that must now be disposed at a significant financial and environmental price. As such, the goal of this project was to evaluate the feasibility of producing a premium fuel with a heating value greater than 10,000 Btu/lb from waste materials generated by the coal and timber industries. Laboratory and pilot-scale testing of the briquetting process indicated that the goal was successfully achieved. Low-ash briquettes containing 5% to 10% sawdust were produced with energy values that were well in excess of 12,000 Btu/lb. A major economic hurdle associated with commercially briquetting coal is binder cost. Approximately fifty binder formulations, both with and without lime, were subjected to an extensive laboratory evaluation to assess their relative technical and economical effectiveness as binding agents for the briquetting of 90% coal and 10% sawdust blends. Guar gum, wheat starch, and a multi-component formulation were identified as most cost-effective for the production of briquettes targeted for the pulverized-coal market with costs being around $8 per ton of the coal-sawdust blend. REAX/lime and a second multi-component formulation were identified as the most cost-effective for the production of briquettes targeted for the stoker-coal market. Various sources of sawdust generated from different wood types were also investigated to determine their chemical properties and to evaluate their relative performance when briquetted with clean coal to form a premium fuel. The highest heating values, approaching 7,000 Btu/lb, were obtained from oak. Sawdusts from higher-density, red oak, white oak, hickory, and beech trees provided higher quality briquettes relative to their lower-density counterparts. In addition to sawdust type, a number of other parameters were evaluated to characterize their impact on briquette properties. The parameters that exhibited the greatest impact on briquette performance were binder concentration; sawdust concentration and particle size; cure temperature; and ash content. Parameters that had the least impact on briquette properties, at least over the ranges studied, were moisture content, briquetting force, and briquetting dwell time. The continuous production of briquettes from a blend of coal and sawdust was evaluated using a 200 lbs/hr Komarek Model B-100 briquetter. The heating values of briquettes produced by the unit exceeded the goal of the project by a large margin. A significant observation was the role of feed moisture on the stability of the mass flow rate through the briquetter and on briquette strength. Excessive feed moisture levels caused inconsistent or stoppage of material flow through the feed hopper and resulted in the production of variable-quality briquettes. Obviously, the limit on feed moisture content has a significant impact on the economics of coal-sawdust briquetting since it will ultimately dictate dew

Honaker, R. Q.; Taulbee, D.; Parekh, B. K.; Tao, D.

2005-12-05T23:59:59.000Z

57

Fabrication of solid oxide fuel cell by electrochemical vapor deposition  

DOE Patents [OSTI]

In a high temperature solid oxide fuel cell (SOFC), the deposition of an impervious high density thin layer of electrically conductive interconnector material, such as magnesium doped lanthanum chromite, and of an electrolyte material, such as yttria stabilized zirconia, onto a porous support/air electrode substrate surface is carried out at high temperatures (/approximately/1100/degree/ /minus/ 1300/degree/C) by a process of electrochemical vapor deposition. In this process, the mixed chlorides of the specific metals involved react in the gaseous state with water vapor resulting in the deposit of an impervious thin oxide layer on the support tube/air electrode substrate of between 20--50 microns in thickness. An internal heater, such as a heat pipe, is placed within the support tube/air electrode substrate and induces a uniform temperature profile therein so as to afford precise and uniform oxide deposition kinetics in an arrangement which is particularly adapted for large scale, commercial fabrication of SOFCs.

Riley, B.; Szreders, B.E.

1988-04-26T23:59:59.000Z

58

Fabrication of solid oxide fuel cell by electrochemical vapor deposition  

DOE Patents [OSTI]

In a high temperature solid oxide fuel cell (SOFC), the deposition of an impervious high density thin layer of electrically conductive interconnector material, such as magnesium doped lanthanum chromite, and of an electrolyte material, such as yttria stabilized zirconia, onto a porous support/air electrode substrate surface is carried out at high temperatures (approximately 1100.degree.-1300.degree. C.) by a process of electrochemical vapor deposition. In this process, the mixed chlorides of the specific metals involved react in the gaseous state with water vapor resulting in the deposit of an impervious thin oxide layer on the support tube/air electrode substrate of between 20-50 microns in thickness. An internal heater, such as a heat pipe, is placed within the support tube/air electrode substrate and induces a uniform temperature profile therein so as to afford precise and uniform oxide deposition kinetics in an arrangement which is particularly adapted for large scale, commercial fabrication of SOFCs.

Brian, Riley (Willimantic, CT); Szreders, Bernard E. (Oakdale, CT)

1989-01-01T23:59:59.000Z

59

Fabrication of carbon-aerogel electrodes for use in phosphoric acid fuel cells .  

E-Print Network [OSTI]

??An experiment was done to determine the ability to fabricate carbon aerogel electrodes for use in a phosphoric acid fuel cell (PAFC). It was found (more)

Tharp, Ronald S

2005-01-01T23:59:59.000Z

60

An Investigation of Different Methods of Fabricating Membrane Electrode Assemblies for Methanol Fuel Cells  

E-Print Network [OSTI]

Methanol fuel cells are electrochemical conversion devices that produce electricity from methanol fuel. The current process of fabricating membrane electrode assemblies (MEAs) is tedious and if it is not sufficiently ...

Hall, Kwame (Kwame J.)

2009-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "fuel pellet fabrication" 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

Production of zinc pellets  

DOE Patents [OSTI]

Uniform zinc pellets are formed for use in batteries having a stationary or moving slurry zinc particle electrode. The process involves the cathodic deposition of zinc in a finely divided morphology from battery reaction product onto a non-adhering electrode substrate. The mossy zinc is removed from the electrode substrate by the action of gravity, entrainment in a flowing electrolyte, or by mechanical action. The finely divided zinc particles are collected and pressed into pellets by a mechanical device such as an extruder, a roller and chopper, or a punch and die. The pure zinc pellets are returned to the zinc battery in a pumped slurry and have uniform size, density and reactivity. Applications include zinc-air fuel batteries, zinc-ferricyanide storage batteries, and zinc-nickel-oxide secondary batteries.

Cooper, John F. (Oakland, CA)

1996-01-01T23:59:59.000Z

62

Production of zinc pellets  

DOE Patents [OSTI]

Uniform zinc pellets are formed for use in batteries having a stationary or moving slurry zinc particle electrode. The process involves the cathodic deposition of zinc in a finely divided morphology from battery reaction product onto a non-adhering electrode substrate. The mossy zinc is removed from the electrode substrate by the action of gravity, entrainment in a flowing electrolyte, or by mechanical action. The finely divided zinc particles are collected and pressed into pellets by a mechanical device such as an extruder, a roller and chopper, or a punch and die. The pure zinc pellets are returned to the zinc battery in a pumped slurry and have uniform size, density and reactivity. Applications include zinc-air fuel batteries, zinc-ferricyanide storage batteries, and zinc-nickel-oxide secondary batteries. 6 figs.

Cooper, J.F.

1996-11-26T23:59:59.000Z

63

Fabrication of Microfluidic Devices with Application to Membraneless Fuel Cells Jon McKechnie  

E-Print Network [OSTI]

Fabrication of Microfluidic Devices with Application to Membraneless Fuel Cells by Jon McKechnie B, by photocopy or other means, without the permission of the author. #12;ii Fabrication of Microfluidic Devices of microfluidic membraneless fuel cells. A primary goal of this particular work is the establishment

Victoria, University of

64

Safety Criticality Standards Using the French CRISTAL Code Package: Application to the AREVA NP UO{sub 2} Fuel Fabrication Plant  

SciTech Connect (OSTI)

Criticality safety evaluations implement requirements to proof of sufficient sub critical margins outside of the reactor environment for example in fuel fabrication plants. Basic criticality data (i.e., criticality standards) are used in the determination of sub critical margins for all processes involving plutonium or enriched uranium. There are several criticality international standards, e.g., ARH-600, which is one the US nuclear industry relies on. The French Nuclear Safety Authority (DGSNR and its advising body IRSN) has requested AREVA NP to review the criticality standards used for the evaluation of its Low Enriched Uranium fuel fabrication plants with CRISTAL V0, the recently updated French criticality evaluation package. Criticality safety is a concern for every phase of the fabrication process including UF{sub 6} cylinder storage, UF{sub 6}-UO{sub 2} conversion, powder storage, pelletizing, rod loading, assembly fabrication, and assembly transportation. Until 2003, the accepted criticality standards were based on the French CEA work performed in the late seventies with the APOLLO1 cell/assembly computer code. APOLLO1 is a spectral code, used for evaluating the basic characteristics of fuel assemblies for reactor physics applications, which has been enhanced to perform criticality safety calculations. Throughout the years, CRISTAL, starting with APOLLO1 and MORET 3 (a 3D Monte Carlo code), has been improved to account for the growth of its qualification database and for increasing user requirements. Today, CRISTAL V0 is an up-to-date computational tool incorporating a modern basic microscopic cross section set based on JEF2.2 and the comprehensive APOLLO2 and MORET 4 codes. APOLLO2 is well suited for criticality standards calculations as it includes a sophisticated self shielding approach, a P{sub ij} flux determination, and a 1D transport (S{sub n}) process. CRISTAL V0 is the result of more than five years of development work focusing on theoretical approaches and the implementation of user-friendly graphical interfaces. Due to its comprehensive physical simulation and thanks to its broad qualification database with more than a thousand benchmark/calculation comparisons, CRISTAL V0 provides outstanding and reliable accuracy for criticality evaluations for configurations covering the entire fuel cycle (i.e. from enrichment, pellet/assembly fabrication, transportation, to fuel reprocessing). After a brief description of the calculation scheme and the physics algorithms used in this code package, results for the various fissile media encountered in a UO{sub 2} fuel fabrication plant will be detailed and discussed. (authors)

Doucet, M.; Durant Terrasson, L.; Mouton, J. [AREVA-NP (France)

2006-07-01T23:59:59.000Z

65

Ash pelletization  

SciTech Connect (OSTI)

Ash pelletization is outlined under the following topics: projects with CSX involvement; US Generating (Cedar Bay), Jacksonville, FL; Hydra-Co (Salt City Project), Solvay, NY; Virginia Power, Yorktown Plant; US Generating; Indiantown, FL; Future Projects; Development of ash disposal site;s Reuse of ash product; and Utility Survey.

Woodall, M.

1994-12-31T23:59:59.000Z

66

Fabrication of Micro-Orifices for Diesel Fuel Injectors  

Broader source: Energy.gov (indexed) [DOE]

G. Fenske, J. Wang, and E. El- Hannouny (ANL), R Schaefer and F. Hamady (NVFEL) US DOE - Vehicle Technologies Propulsion Materials Jerry Gibbs Fabrication of Micro-orifices for...

67

An Overview of Current and Past W-UO[2] CERMET Fuel Fabrication Technology  

SciTech Connect (OSTI)

Studies dating back to the late 1940s performed by a number of different organizations and laboratories have established the major advantages of Nuclear Thermal Propulsion (NTP) systems, particularly for manned missions. A number of NTP projects have been initiated since this time; none have had any sustained fuel development work that appreciably contributed to fuel fabrication or performance data from this era. As interest in these missions returns and previous space nuclear power researchers begin to retire, fuel fabrication technologies must be revisited, so that established technologies can be transferred to young researchers seamlessly and updated, more advanced processes can be employed to develop successful NTP fuels. CERMET fuels, specifically W-UO2, are of particular interest to the next generation NTP plans since these fuels have shown significant advantages over other fuel types, such as relatively high burnup, no significant failures under severe transient conditions, capability of accommodating a large fission product inventory during irradiation and compatibility with flowing hot hydrogen. Examples of previous fabrication routes involved with CERMET fuels include hot isostatic pressing (HIPing) and press and sinter, whereas newer technologies, such as spark plasma sintering, combustion synthesis and microsphere fabrication might be well suited to produce high quality, effective fuel elements. These advanced technologies may address common issues with CERMET fuels, such as grain growth, ductile to brittle transition temperature and UO2 stoichiometry, more effectively than the commonly accepted traditional fabrication routes. Bonding of fuel elements, especially if the fabrication process demands production of smaller element segments, must be investigated. Advanced brazing techniques and compounds are now available that could produce a higher quality bond segment with increased ease in joining. This paper will briefly address the history of CERMET fuel fabrication technology as related to the GE 710 and ANL Nuclear Rocket Programs, in addition to discussing future plans, viable alternatives and preliminary investigations for W-UO2 CERMET fuel fabrication. The intention of the talk is to provide the brief history and tie in an overview of current programs and investigations as related to NTP based W-UO2 CERMET fuel fabrication, and hopefully peak interest in advanced fuel fabrication technologies.

Douglas E. Burkes; Daniel M. Wachs; James E. Werner; Steven D. Howe

2007-06-01T23:59:59.000Z

68

Fabrication procedures for manufacturing High Flux Isotope Reactor fuel elements - 2  

SciTech Connect (OSTI)

The original fabrication procedures written in 1968 delineated the manufacturing procedures at that time. Since 1968, there have been a number of procedural changes. This rewrite of the fabrication procedures incorporates these changes. The entire fuel core of this reactor is made up of two fuel elements. Each element consists of one annular array of fuel plates. These annuli are identified as the inner and outer fuel elements, since one fits inside the other. The inner element consists of 171 identical fuel plates, and the outer element contains 369 identical fuel plates differing slightly from those in the inner element. Both sets of fuel plates contain U{sub 3}O{sub 8} powder as the fuel, dispersed in an aluminum powder matrix and clad with aluminum. Procedures for manufacturing and inspection of the fuel elements are described and illustrated.

Knight, R.W.; Morin, R.A.

1999-12-01T23:59:59.000Z

69

EA-0534: Radioisotope Heat Source Fuel Processing and Fabrication, Los Alamos, New Mexico  

Broader source: Energy.gov [DOE]

This EA evaluates the environmental impacts of a proposal to operate existing Pu-238 processing facilities at Savannah River Site, and fabricate a limited quantity of Pu-238 fueled heat sources at...

70

Fabrication and Testing of Full-Length Single-Cell Externally Fueled Converters for Thermionic Reactors  

SciTech Connect (OSTI)

Paper presented at the 29th IECEC in Monterey, CA in August 1994. The present paper describes the fabrication and testing of full-length prototypcial converters, both unfueled and fueled, and presents parametric results of electrically heated tests.

Schock, Alfred

1995-08-01T23:59:59.000Z

71

Fabrication of carbon-aerogel electrodes for use in phosphoric acid fuel cells  

E-Print Network [OSTI]

An experiment was done to determine the ability to fabricate carbon aerogel electrodes for use in a phosphoric acid fuel cell (PAFC). It was found that the use of a 25% solution of the surfactant Cetyltrimethylammonium ...

Tharp, Ronald S

2005-01-01T23:59:59.000Z

72

Fabrication of Small Diesel Fuel Injector Orifices | Department of Energy  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-UpHeat PumpRecord ofESPCofConstructionofFY 2011 Report toAnnuAl ProgressEnergySmall

73

Fabrication of Small-Orifice Fuel Injectors | Department of Energy  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-UpHeat PumpRecord ofESPCofConstructionofFY 2011 Report toAnnuAl

74

Mixed Oxide (MOX) Fuel Fabrication Facility Project Lessons Learned - Scott  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankCombustion | Department ofT ib l L d F S i DOE TribaltheMyMinutes from DecemberCannon, MOX Federal

75

Development of an Innovative High-Thermal Conductivity UO2 Ceramic Composites Fuel Pellets with Carbon Nano-Tubes Using Spark Plasma Sintering  

SciTech Connect (OSTI)

Uranium dioxide (UO2) is the most common fuel material in commercial nuclear power reactors. Despite its numerous advantages such as high melting point, good high-temperature stability, good chemical compatibility with cladding and coolant, and resistance to radiation, it suffers from low thermal conductivity that can result in large temperature gradients within the UO2 fuel pellet, causing it to crack and release fission gases. Thermal swelling of the pellets also limits the lifetime of UO2 fuel in the reactor. To mitigate these problems, we propose to develop novel UO2 fuel with uniformly distributed carbon nanotubes (CNTs) that can provide high-conductivity thermal pathways and can eliminate fuel cracking and fission gas release due to high temperatures. CNTs have been investigated extensively for the past decade to explore their unique physical properties and many potential applications. CNTs have high thermal conductivity (6600 W/mK for an individual single- walled CNT and >3000 W/mK for an individual multi-walled CNT) and high temperature stability up to 2800C in vacuum and about 750C in air. These properties make them attractive candidates in preparing nano-composites with new functional properties. The objective of the proposed research is to develop high thermal conductivity of UO2CNT composites without affecting the neutronic property of UO2 significantly. The concept of this goal is to utilize a rapid sintering method (515 min) called spark plasma sintering (SPS) in which a mixture of CNTs and UO2 powder are used to make composites with different volume fractions of CNTs. Incorporation of these nanoscale materials plays a fundamentally critical role in controlling the performance and stability of UO2 fuel. We will use a novel in situ growth process to grow CNTs on UO2 particles for rapid sintering and develop UO2-CNT composites. This method is expected to provide a uniform distribution of CNTs at various volume fractions so that a high thermally conductive UO2-CNT composite is obtained with a minimal volume fraction of CNTs. The mixtures are sintered in the SPS facility at a range of temperatures, pressures, and time durations so as to identify the optimal processing conditions to obtain the desired microstructure of sintered UO2-CNT pellets. The second objective of the proposed work is to identify the optimal volume fraction of CNTs in the microstructure of the composites that provides the desired high thermal conductivity yet retaining the mechanical strength required for efficient function as a reactor fuel. We will systematically study the resulting microstructure (grain size, porosity, distribution of CNTs, etc.) obtained at various SPS processing conditions using optical microscopy, scanning electron microscopy (SEM), and transmission electron microscope (TEM). We will conduct indentation hardness measurements and uniaxial strength measurements as a function of volume fraction of CNTs to determine the mechanical strength and compare them to the properties of UO2. The fracture surfaces will be studied to determine the fracture characteristics that may relate to the observed cracking during service. Finally, we will perform thermal conductivity measurements on all the composites up to 1000 C. This study will relate the microstructure, mechanical properties, and thermal properties at various volume fractions of CNTs. The overall intent is to identify optimal processing conditions that will provide a well-consolidated compact with optimal microstructure and thermo-mechanical properties. The deliverables include: (1) fully characterized UO2-CNT composite with optimal CNT volume fraction and high thermal conductivity and (2) processing conditions for production of UO2-CNT composite pellets using SPS method.

Subhash, Ghatu; Wu, Kuang-Hsi; Tulenko, James

2014-03-10T23:59:59.000Z

76

FUEL & TARGET FABRICATION Aiken County, South Carolina  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-Series toESnet4:Epitaxial ThinFOR IMMEDIATE RELEASE1 FreedomUniversity,NERSC

77

Design, fabrication, and characterization of a micro fuel processor  

E-Print Network [OSTI]

The development of portable-power systems employing hydrogen-driven solid oxide fuel cells continues to garner significant interest among applied science researchers. The technology can be applied in fields ranging from ...

Blackwell, Brandon S. (Brandon Shaw)

2008-01-01T23:59:59.000Z

78

A microfluidic microbial fuel cell fabricated by soft lithography Fang Qian a,b,  

E-Print Network [OSTI]

A microfluidic microbial fuel cell fabricated by soft lithography Fang Qian a,b, , Zhen He c microfluidic microbial fuel cell (MFC) platform built by soft-lithography tech- niques. The MFC design includes a unique sub-5 lL polydimethylsiloxane soft chamber featuring carbon cloth electrodes and microfluidic

79

Operation of N Reactor and Fuels Fabrication Facilities, Hanford Reservation, Richland, Benton County, Washington: Environmental assessment  

SciTech Connect (OSTI)

Environmental data, calculations and analyses show no significant adverse radiological or nonradiological impacts from current or projected future operations resulting from N Reactor, Fuels Fabrication and Spent Fuel Storage Facilities. Nonoccupational radiation exposures resulting from 1978 N Reactor operations are summarized and compared to allowable exposure limits.

Not Available

1980-08-01T23:59:59.000Z

80

Standard specification for sintered gadolinium oxide-uranium dioxide pellets  

E-Print Network [OSTI]

1.1 This specification is for finished sintered gadolinium oxide-uranium dioxide pellets for use in light-water reactors. It applies to gadolinium oxide-uranium dioxide pellets containing uranium of any 235U concentration and any concentration of gadolinium oxide. 1.2 This specification recognizes the presence of reprocessed uranium in the fuel cycle and consequently defines isotopic limits for gadolinium oxide-uranium dioxide pellets made from commercial grade UO2. Such commercial grade UO2 is defined so that, regarding fuel design and manufacture, the product is essentially equivalent to that made from unirradiated uranium. UO2 falling outside these limits cannot necessarily be regarded as equivalent and may thus need special provisions at the fuel fabrication plant or in the fuel design. 1.3 This specification does not include (1) provisions for preventing criticality accidents or (2) requirements for health and safety. Observance of this specification does not relieve the user of the obligation to be aw...

American Society for Testing and Materials. Philadelphia

2008-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "fuel pellet fabrication" 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

Characterization of candidate DOE sites for fabricating MOX fuel for lead assemblies  

SciTech Connect (OSTI)

The Office of Fissile Materials Disposition (MD) of the Department of Energy (DOE) is directing the program to disposition US surplus weapons-usable plutonium. For the reactor option for disposition of this surplus plutonium, MD is seeking to contract with a consortium, which would include a mixed-oxide (MOX) fuel fabricator and a commercial US reactor operator, to fabricate and burn MOX fuel in existing commercial nuclear reactors. This option would entail establishing a MOX fuel fabrication facility under the direction of the consortium on an existing DOE site. Because of the lead time required to establish a MOX fuel fabrication facility and the need to qualify the MOX fuel for use in a commercial reactor, MD is considering the early fabrication of lead assemblies (LAs) in existing DOE facilities under the technical direction of the consortium. The LA facility would be expected to produce a minimum of 1 metric ton heavy metal per year and must be operational by June 2003. DOE operations offices were asked to identify candidate sites and facilities to be evaluated for suitability to fabricate MOX fuel LAs. Savannah River Site, Argonne National Laboratory-West, Hanford, Lawrence Livermore National Laboratory, and Los Alamos National Laboratory were identified as final candidates to host the LA project. A Site Evaluation Team (SET) worked with each site to develop viable plans for the LA project. SET then characterized the suitability of each of the five plans for fabricating MOX LAs using 28 attributes and documented the characterization to aid DOE and the consortium in selecting the site for the LA project. SET concluded that each option has relative advantages and disadvantages in comparison with other options; however, each could meet the requirements of the LA project as outlined by MD and SET.

Holdaway, R.F.; Miller, J.W.; Sease, J.D.; Moses, R.J.; O`Connor, D.G. [Oak Ridge National Lab., TN (United States); Carrell, R.D. [Technical Resources International, Inc., Richland, WA (United States); Jaeger, C.D. [Sandia National Labs., Albuquerque, NM (United States); Thompson, M.L.; Strasser, A.A. [Delta-21 Resources, Inc., Oak Ridge, TN (United States)

1998-03-01T23:59:59.000Z

82

Safety issues in fabricating mixed oxide fuel using surplus weapons plutonium  

SciTech Connect (OSTI)

This paper presents an assessment of the safety issues and implications of fabricating mixed oxide (MOX) fuel using surplus weapons plutonium. The basis for this assessment is the research done at Los Alamos National Laboratory (LANL) in identifying and resolving the technical issues surrounding the production of PuO{sub 2} feed, removal of gallium from the PuO{sub 2} feed, the fabrication of test fuel, and the work done at the LANL plutonium processing facility. The use of plutonium in MOX fuel has been successfully demonstrated in Europe, where the experience has been almost exclusively with plutonium separated from commercial spent nuclear fuel. This experience in safely operating MOX fuel fabrication facilities directly applies to the fabrication and irradiation of MOX fuel made from surplus weapons plutonium. Consequently, this paper focuses on the technical difference between plutonium from surplus weapons, and light-water reactor recycled plutonium. Preliminary assessments and research lead to the conclusion that no new process or product safety concerns will arise from using surplus weapons plutonium in MOX fuel.

Buksa, J.; Badwan, F.; Barr, M.; Motley, F.

1998-07-01T23:59:59.000Z

83

Method of fabricating a monolithic solid oxide fuel cell  

DOE Patents [OSTI]

In a two-step densifying process of making a monolithic solid oxide fuel cell, a limited number of anode-electrolyte-cathode cells separated by an interconnect layer are formed and partially densified. Subsequently, the partially densified cells are stacked and further densified to form a monolithic array.

Minh, Nguyen Q. (Fountain Valley, CA); Horne, Craig R. (Redondo Beach, CA)

1994-01-01T23:59:59.000Z

84

Method of fabricating a monolithic solid oxide fuel cell  

DOE Patents [OSTI]

In a two-step densifying process of making a monolithic solid oxide fuel cell, a limited number of anode-electrolyte-cathode cells separated by an interconnect layer are formed and partially densified. Subsequently, the partially densified cells are stacked and further densified to form a monolithic array. 10 figures.

Minh, N.Q.; Horne, C.R.

1994-03-01T23:59:59.000Z

85

Microstructural Examination to Aid in Understanding Friction Bonding Fabrication Technique for Monolithic Nuclear Fuel  

SciTech Connect (OSTI)

Monolithic nuclear fuel is currently being developed for use in research reactors, and friction bonding (FB) is a technique being developed to help in this fuels fabrication. Since both FB and monolithic fuel are new concepts, research is needed to understand the impact of varying FB fabrication parameters on fuel plate characteristics. This thesis research provides insight into the FB process and its application to the monolithic fuel design by recognizing and understanding the microstructural effects of varying fabrication parameters (a) FB tool load, and (b) FB tool face alloy. These two fabrication parameters help drive material temperature during fabrication, and thus the material properties, bond strength, and possible formation of interface reaction layers. This study analyzed temperatures and tool loads measured during those FB processes and examined microstructural characteristics of materials and bonds in samples taken from the resulting fuel plates. This study shows that higher tool load increases aluminum plasticization and forging during FB, and that the tool face alloy helps determine the tools heat extraction efficacy. The study concludes that successful aluminum bonds can be attained in fuel plates using a wide range of FB tool loads. The range of tool loads yielding successful uranium-aluminum bonding was not established, but it was demonstrated that such bonding can be attained with FB tool load of 48,900 N (11,000 lbf) when using a FB tool faced with a tungsten alloy. This tool successfully performed FB, and with better results than tools faced with other materials. Results of this study correlate well with results reported for similar aluminum bonding techniques. This studys results also provide support and validation for other nuclear fuel development studies and conclusions. Recommendations are offered for further research.

Karen L. Shropshire

2008-04-01T23:59:59.000Z

86

The Role of Friction Stir Welding in Nuclear Fuel Plate Fabrication  

SciTech Connect (OSTI)

The friction bonding process combines desirable attributes of both friction stir welding and friction stir processing. The development of the process is spurred on by the need to fabricate thin, high density, reduced enrichment fuel plates for nuclear research reactors. The work seeks to convert research and test reactors currently operating on highly enriched uranium fuel to operate on low enriched uranium fuel without significant loss in reactor performance, safety characteristics, or significant increase in cost. In doing so, the threat of global nuclear material proliferation will be reduced. Feasibility studies performed on the process show that this is a viable option for mass production of plate-type nuclear fuel. Adapting the friction stir weld process for nuclear fuel fabrication has resulted in the development of several unique ideas and observations. Preliminary results of this adaptation and process model development are discussed.

D Burkes; P Medvedev; M Chapple; A Amritkar; P Wells; I Charit

2009-02-01T23:59:59.000Z

87

Conductivity fuel cell collector plate and method of fabrication  

DOE Patents [OSTI]

An improved method of manufacturing a PEM fuel cell collector plate is disclosed. During molding a highly conductive polymer composite is formed having a relatively high polymer concentration along its external surfaces. After molding the polymer rich layer is removed from the land areas by machining, grinding or similar process. This layer removal results in increased overall conductivity of the molded collector plate. The polymer rich surface remains in the collector plate channels, providing increased mechanical strength and other benefits to the channels. The improved method also permits greater mold cavity thickness providing a number of advantages during the molding process.

Braun, James C. (Juno Beach, FL)

2002-01-01T23:59:59.000Z

88

Fabrication of fuel cell electrodes and other catalytic structures  

DOE Patents [OSTI]

A porous layer of catalyst material suitable for use as an electrode in a molten carbonate fuel cell includes elongated pores substantially extending across the layer thickness. The catalyst layer is prepared by depositing particulate catalyst material into polymeric flocking on a substrate surface by a procedure such as tape casting. The loaded substrate is heated in a series of steps with rising temperatures to set the tape, thermally decompose the substrate with flocking and sinter bond the catalyst particles into a porous catalytic layer with elongated pores across its thickness. Employed as an electrode, the elongated pores provide distribution of reactant gas into contact with catalyst particles wetted by molten electrolyte. 1 fig.

Smith, J.L.

1987-02-11T23:59:59.000Z

89

Thermomechanical Loading Applied on the Cladding Tube During the Pellet Cladding  

E-Print Network [OSTI]

Thermomechanical Loading Applied on the Cladding Tube During the Pellet Cladding Mechanical the evolution of the ther- momechanical loading applied on the cladding tube during the Pellet- Cladding fuel pellets [1]. As a conse- quence, the pellets from the surrounding fuel rods expand suddenly, which

90

Graphene sheets fabricated from disposable paper cups as a catalyst support material for fuel cells  

E-Print Network [OSTI]

Graphene sheets fabricated from disposable paper cups as a catalyst support material for fuel cells Hong Zhao and T. S. Zhao* Disposable paper-cups are used for the formation of graphene sheets with Fe2+ as a catalyst. The proposed synthesis strategy not only enables graphene sheets to be produced in high yield

Zhao, Tianshou

91

Fuel injector Holes (Fabrication of Micro-Orifices for Fuel Injectors...  

Broader source: Energy.gov (indexed) [DOE]

nozzles. - Improved fuel atomization reduces sootparticulate formation and improves air entrainment thereby improving combustion efficiency Multiple approaches were examined...

92

Fabrication of advanced oxide fuels containing minor actinide for use in fast reactors  

SciTech Connect (OSTI)

R and D of advanced fuel containing minor actinide for use in fast reactors is described related to the composite fuel with MgO matrix. Fabrication tests of MgO composite fuels containing Am were done by a practical process that could be adapted to the presently used commercial manufacturing technology. Am-containing MgO composite fuels having good characteristics, i.e., having no defects, a high density, a homogeneous dispersion of host phase, were obtained. As related technology, burn-up characteristics of a fast reactor core loaded with the present MgO composite fuel were also analyzed, mainly in terms of core criticality. Furthermore, phase relations of MA oxide which was assumed to be contained in MgO matrix fuel were experimentally investigated. (authors)

Miwa, Shuhei; Osaka, Masahiko; Tanaka, Kosuke; Ishi, Yohei; Yoshimochi, Hiroshi; Tanaka, Kenya [Oarai Research and Development Center, Japan Atomic Energy Agency, 4002 Oarai-machi, Higashi-ibaraki-gun, Ibaraki, 311-1393 (Japan)

2007-07-01T23:59:59.000Z

93

Fuel injector Holes (Fabrication of Micro-Orifices for Fuel Injectors) |  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-UpHeatMulti-Dimensional ElectricalEnergyQuality Challenges An OEMLife10andDepartment

94

Fabrication and characterization of micro-orifices for diesel fuel injectors.  

SciTech Connect (OSTI)

Stringent emission standards are driving the development of diesel-fuel injection concepts to mitigate in-cylinder formation of particulates. While research has demonstrated significant reduction in particulate formation using micro-orifice technology, implementation requires development of industrial processes to fabricate micro-orifices with diameters as low as 50 gmm and with large length-to-diameter ratios. This paper reviews the different processes being pursued to fabricate micro-orifices and the advanced techniques applied to characterize the performance of micro-orifices. The latter include the use of phase-contrast x-ray imaging of electroless nickel-plated, micro-orifices and laser imaging of fuel sprays at elevated pressures. The experimental results demonstrate an industrially viable process to create small uniform orifices that improve spray formation for fuel injection.

Fenske, G.; Woodford, J.; Wang, J.; El-Hannouny, E.; Schaefer, R.; Hamady, F.; National Vehicle and Fuel Emissions Lab.

2007-04-01T23:59:59.000Z

95

Pellet Production Wood Pellets are made by compressing  

E-Print Network [OSTI]

Pellet Production Wood Pellets are made by compressing clean dry sawdust, under very high pressure into a pellet as it cools. The material used for producing pellets usually comes from industries who are already pellets reduces the volume of material they have to treat as waste, reducing landfill. Pellets have

96

PRELIMINARY DATA CALL REPORT ADVANCED BURNER REACTOR START UP FUEL FABRICATION FACILITY  

SciTech Connect (OSTI)

The purpose of this report is to provide data for preparation of a NEPA Environmental Impact Statement in support the U. S. Department of Energy (DOE) Global Nuclear Energy Partnership (GNEP). One of the GNEP objectives is to reduce the inventory of long lived actinide from the light water reactor (LWR) spent fuel. The LWR spent fuel contains Plutonium (Pu) -239 and other transuranics (TRU) such as Americium-241. One of the options is to transmute or burn these actinides in fast neutron spectra as well as generate the electricity. A sodium-cooled Advanced Recycling Reactor (ARR) concept has been proposed to achieve this goal. However, fuel with relatively high TRU content has not been used in the fast reactor. To demonstrate the utilization of TRU fuel in a fast reactor, an Advanced Burner Reactor (ABR) prototype of ARR is proposed, which would necessarily be started up using weapons grade (WG) Pu fuel. The WG Pu is distinguished by relatively highest proportions of Pu-239 and lesser amount of other actinides. The WG Pu will be used as the startup fuel along with TRU fuel in lead test assemblies. Because such fuel is not currently being produced in the US, a new facility (or new capability in an existing facility) is being considered for fabrication of WG Pu fuel for the ABR. This report is provided in response to Data Call for the construction of startup fuel fabrication facility. It is anticipated that the facility will provide the startup fuel for 10-15 years and will take to 3 to 5 years to construct.

S. T. Khericha

2007-04-01T23:59:59.000Z

97

An International Pellet Ablation Database L.R. Baylor, A. Geraud*, W.A. Houlberg,  

E-Print Network [OSTI]

An International Pellet Ablation Database L.R. Baylor, A. Geraud*, W.A. Houlberg, D. Frigione+, M of an international pellet ablation database (IPADBASE) that has been assembled to enable studies of pellet ablation theories that are used to describe the physics of an ablating fuel pellet in a tokamak plasma. The database

98

A Blueprint for GNEP Advanced Burner Reactor Startup Fuel Fabrication Facility  

SciTech Connect (OSTI)

The purpose of this article is to identify the requirements and issues associated with design of GNEP Advanced Burner Reactor Fuel Facility. The report was prepared in support of providing data for preparation of a NEPA Environmental Impact Statement in support the U. S. Department of Energy (DOE) Global Nuclear Energy Partnership (GNEP). One of the GNEP objectives was to reduce the inventory of long lived actinide from the light water reactor (LWR) spent fuel. The LWR spent fuel contains Plutonium (Pu) -239 and other transuranics (TRU) such as Americium-241. One of the options is to transmute or burn these actinides in fast neutron spectra as well as generate the electricity. A sodium-cooled Advanced Recycling Reactor (ARR) concept was proposed to achieve this goal. However, fuel with relatively high TRU content has not been used in the fast reactor. To demonstrate the utilization of TRU fuel in a fast reactor, an Advanced Burner Reactor (ABR) prototype of ARR was proposed, which would necessarily be started up using weapons grade (WG) Pu fuel. The WG Pu is distinguished by relatively highest proportions of Pu-239 and lesser amount of other actinides. The WG Pu was assumed to be used as the startup fuel along with TRU fuel in lead test assemblies. Because such fuel is not currently being produced in the US, a new facility (or new capability in an existing facility) was being considered for fabrication of WG Pu fuel for the ABR. It was estimated that the facility will provide the startup fuel for 10-15 years and would take 3 to 5 years to construct.

S. Khericha

2010-12-01T23:59:59.000Z

99

Cryogenic pellet production developments for long-pulse plasma operation  

SciTech Connect (OSTI)

Long pulse plasma operation on large magnetic fusion devices require multiple forms of cryogenically formed pellets for plasma fueling, on-demand edge localized mode (ELM) triggering, radiative cooling of the divertor, and impurity transport studies. The solid deuterium fueling and ELM triggering pellets can be formed by extrusions created by helium cooled, twin-screw extruder based injection system that freezes deuterium in the screw section. A solenoid actuated cutter mechanism is activated to cut the pellets from the extrusion, inserting them into the barrel, and then fired by the pneumatic valve pulse of high pressure gas. Fuel pellets are injected at a rate up to 10 Hz, and ELM triggering pellets are injected at rates up to 20 Hz. The radiative cooling and impurity transport study pellets are produced by introducing impurity gas into a helium cooled section of a pipe gun where it deposits in-situ. A pneumatic valve is opened and propellant gas is released downstream where it encounters a passive punch which initially accelerates the pellet before the gas flow around the finishes the pellet acceleration. This paper discusses the various cryogenic pellet production techniques based on the twin-screw extruder, pipe gun, and pellet punch designs.

Meitner, S. J.; Baylor, L. R.; Combs, S. K.; Fehling, D. T.; McGill, J. M.; Duckworth, R. C.; McGinnis, W. D.; Rasmussen, D. A. [Oak Ridge National Laboratory, 1Bethel Valley Rd Oak Ridge, TN 37831 (United States)

2014-01-29T23:59:59.000Z

100

Pelletization of fine coals. Final report  

SciTech Connect (OSTI)

Coal is one of the most abundant energy resources in the US with nearly 800 million tons of it being mined annually. Process and environmental demands for low-ash, low-sulfur coals and economic constraints for high productivity are leading the coal industry to use such modern mining methods as longwall mining and such newer coal processing techniques as froth flotation, oil agglomeration, chemical cleaning and synthetic fuel production. All these processes are faced with one common problem area--fine coals. Dealing effectively with these fine coals during handling, storage, transportation, and/or processing continues to be a challenge facing the industry. Agglomeration by the unit operation of pelletization consists of tumbling moist fines in drums or discs. Past experimental work and limited commercial practice have shown that pelletization can alleviate the problems associated with fine coals. However, it was recognized that there exists a serious need for delineating the fundamental principles of fine coal pelletization. Accordingly, a research program has been carried involving four specific topics: (i) experimental investigation of coal pelletization kinetics, (ii) understanding the surface principles of coal pelletization, (iii) modeling of coal pelletization processes, and (iv) simulation of fine coal pelletization circuits. This report summarizes the major findings and provides relevant details of the research effort.

Sastry, K.V.S.

1995-12-31T23:59:59.000Z

Note: This page contains sample records for the topic "fuel pellet fabrication" 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

Fabrication and Testing of Full-Length Single-Cell Externally Fueled Converters for Thermionic Reactors  

SciTech Connect (OSTI)

The preceding paper described designs and analyses of thermionic reactors employing full-core-length single-cell converters with their heated emitters located on the outside of their internally cooled collectors, and it presented results of detailed parametric analyses which illustrate the benefits of this unconventional design. The present paper describes the fabrication and testing of full-length prototypical converters, both unfueled and fueled, and presents parametric results of electrically heated tests. The unfueled converter tests demonstrated the practicality of operating such long converters without shorting across a 0.3-mm interelectrode gap. They produced a measured peak output of 751 watts(e) from a single diode and a peak efficiency of 15.4%. The fueled converter tests measured the parametric performance of prototypic UO(subscript 2)-fueled converters designed for subsequent in-pile testing. They employed revolver-shaped tungsten elements with a central emitter hole surrounded by six fuel chambers. The full-length converters were heated by a water-cooled RF-induction coil inside an ion-pumped vacuum chamber. This required development of high-vacuum coaxial RF feedthroughs. In-pile test rules required multiple containment of the UO (subscript 2)-fuel, which complicated the fabrication of the test article and required successful development of techniques for welding tungsten and other refractory components. The test measured a peak power output of 530 watts(e) or 7.1 watts/cm (superscript 2) at an efficiency of 11.5%. There are three copies in the file. Cross-Reference a copy FSC-ESD-217-94-529 in the ESD files with a CID #8574.

Schock, Alfred

1994-06-01T23:59:59.000Z

102

US-Russian collaboration in MPC & A enhancements at the Elektrostal Uranium Fuel-Fabrication Plant  

SciTech Connect (OSTI)

Enhancement of the nuclear materials protection, control, and accounting of (MPC&A) at the Elektrostal Machine-Building Plant (ELEMASH) has proceeded in two phases. Initially, Elektrostal served as the model facility at which to test US/Russian collaboration and to demonstrate MPC&A technologies available for safeguards enhancements at Russian facilities. This phase addressed material control and accounting (MC&A) in the low-enriched uranium (LEU) fuel-fabrication processes and the physical protection (PP) of part of the (higher-enrichment) breeder-fuel process. The second phase, identified later in the broader US/Russian agreement for expanded MPC&A cooperation. includes implementation of appropriate MC&A and PP systems in the breeder-fuel fabrication processes. Within the past year, an automated physical protection system has been installed and demonstrated in building 274, and an automated MC&A system has been designed and is being installed and will be tested in the LEU process. Attention has now turned to assuring longterm sustainability for the first phase and beginning MPC&A upgrades for the second phase. Sustainability measures establish the infrastructure for operation, maintenance, and repair of the installed systems-with US support for the lifetime of the US/Russian Agreement, but evolving toward full Russian operation of the system over the long term. For phase 2, which will address higher enrichments, projects have been identified to characterize the facilities, design MPC&A systems, procure appropriate equipment, and install and test final systems. One goal in phase 2 will be to build on initial work to create shared, plant-wide MPC&A assets for operation, maintenance, and evaluation of all safeguards systems.

Smith, H.; Murray, W.; Whiteson, R. [and others

1997-11-01T23:59:59.000Z

103

Lignite pellets and methods of agglomerating or pelletizing  

DOE Patents [OSTI]

The specification discloses lignite pellets which are relatively hard, dust resistant, of generally uniform size and free from spontaneous ignition and general degradation. Also disclosed are methods for making such pellets which involve crushing as mined lignite, mixing said lignite with a binder such as asphalt, forming the lignite binder mixture into pellets, and drying the pellets.

Baker, Albert F. (Pittsburgh, PA); Blaustein, Eric W. (Pittsburgh, PA); Deurbrouck, Albert W. (Pittsburgh, PA); Garvin, John P. (Pittsburgh, PA); McKeever, Robert E. (Pittsburgh, PA)

1981-01-01T23:59:59.000Z

104

Radation shielding pellets  

DOE Patents [OSTI]

Radiation pellets having an outer shell, preferably, of Mo, W or depleted U nd an inner filling of lithium hydride wherein the outer shell material has a greater melting point than does the inner filling material.

Coomes, Edmund P. (Richland, WA); Luksic, Andrzej T. (Pasco, WA)

1988-01-01T23:59:59.000Z

105

Mobile Biomass Pelletizing System  

SciTech Connect (OSTI)

This grant project examines multiple aspects of the pelletizing process to determine the feasibility of pelletizing biomass using a mobile form factor system. These aspects are: the automatic adjustment of the die height in a rotary-style pellet mill, the construction of the die head to allow the use of ceramic materials for extreme wear, integrating a heat exchanger network into the entire process from drying to cooling, the use of superheated steam for adjusting the moisture content to optimum, the economics of using diesel power to operate the system; a break-even analysis of estimated fixed operating costs vs. tons per hour capacity. Initial development work has created a viable mechanical model. The overall analysis of this model suggests that pelletizing can be economically done using a mobile platform.

Thomas Mason

2009-04-16T23:59:59.000Z

106

Conversion of hydrocarbons for fuel-cell applications. Part I. Autothermal reforming of sulfur-free and sulfur-containing hydrocarbon liquids. Part II. Steam reforming of n-hexane on pellet and monolithic catalyst beds. Final report  

SciTech Connect (OSTI)

Experimental autothermal reforming (ATR) results obtained in the previous phase of this work with sulfur-free pure hydrocarbon liquids are summarized. Catalyst types and configuration used were the same as in earlier tests with No. 2 fuel oil to facilitate comparisons. Fuel oil has been found to form carbon in ATR at conditions much milder than those predicted by equilibrium. Reactive differences between paraffins and aromatics in ATR, and thus the formation of different carbon precursors, have been shown to be responsible for the observed carbon formation characteristics (fuel-specific). From tests with both light and heavy paraffins and aromatics, it is concluded that high boiling point hydrocarbons and polynuclear aromatics enhance the propensity for carbon formation in ATR. Effects of olefin (propylene) addition on the ATR performance of benzene are described. In ATR tests with mixtures of paraffins and aromatics (n-tetradecane and benzene) synergistic effects on conversion characteristics were identified. Comparisons of the No. 2 fuel oil data with the experimental results from this work with pure (and mixed) sulfur-free hydrocarbons indicate that the sulfur content of the fuel may be the limiting factor for efficient ATR operation. Steam reforming of hydrocarbons in conventional reformers is heat transfer limited. Steam reforming tasks performed have included performance comparisons between conventional pellet beds and honeycomb monolith catalysts. Metal-supported monoliths offer higher structural stability than ceramic supports, and have a higher thermal conductivity. Data from two metal monoliths of different catalyst (nickel) loading were compared to pellets under the same operating conditions.

Flytzani-Stephanopoulos, M.; Voecks, G.E.

1981-10-01T23:59:59.000Z

107

Key Differences in the Fabrication, Irradiation, and Safety Testing of U.S. and German TRISO-coated Particle Fuel and Their Implications on Fuel Performance  

SciTech Connect (OSTI)

High temperature gas reactor technology is achieving a renaissance around the world. This technology relies on high quality production and performance of coated particle fuel. Historically, the irradiation performance of TRISO-coated gas reactor particle fuel in Germany has been superior to that in the United States. German fuel generally displayed in-pile gas release values that were three orders of magnitude lower than U.S. fuel. Thus, we have critically examined the TRISO-coated fuel fabrication processes in the U.S. and Germany and the associated irradiation database with a goal of understanding why the German fuel behaves acceptably, why the U.S. fuel has not faired as well, and what process/ production parameters impart the reliable performance to this fuel form. The postirradiation examination results are also reviewed to identify failure mechanisms that may be the cause of the poorer U.S. irradiation performance. This comparison will help determine the roles that particle fuel process/product attributes and irradiation conditions (burnup, fast neutron fluence, temperature, and degree of acceleration) have on the behavior of the fuel during irradiation and provide a more quantitative linkage between acceptable processing parameters, as-fabricated fuel properties and subsequent in-reactor performance.

Petti, David Andrew; Maki, John Thomas; Buongiorno, Jacopo; Hobbins, Richard Redfield

2002-06-01T23:59:59.000Z

108

Surplus weapons plutonium: Technologies for pit disassembly/conversion and MOX fuel fabrication  

SciTech Connect (OSTI)

This paper will provide a description of the technologies involved in the disposition of plutonium from surplus nuclear weapon components (pits), based on pit disassembly and conversion and on fabrication of mixed oxide (MOX) fuel for disposition through irradiation in nuclear reactors. The MOX/Reactor option is the baseline disposition plan for both the US and russian for plutonium from pits and other clean plutonium metal and oxide. In the US, impure plutonium in various forms will be converted to oxide and immobilized in glass or ceramic, surrounded by vitrified high level waste to provide a radiation barrier. A similar fate is expected for impure material in Russia as well. The immobilization technologies will not be discussed. Following technical descriptions, a discussion of options for monitoring the plutonium during these processes will be provided.

Toevs, J.W.

1997-12-31T23:59:59.000Z

109

Standard specification for nuclear-grade aluminum oxide pellets  

E-Print Network [OSTI]

1.1 This specification applies to pellets of aluminum oxide that may be ultimately used in a reactor core, for example, as filler or spacers within fuel, burnable poison, or control rods. In order to distinguish between the subject pellets and burnable poison pellets, it is established that the subject pellets are not intended to be used as neutron-absorbing material. 1.2 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered standard.

American Society for Testing and Materials. Philadelphia

2008-01-01T23:59:59.000Z

110

Special Analysis for the Disposal of the Idaho National Laboratory Unirradiated Light Water Breeder Reactor Rods and Pellets Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada  

SciTech Connect (OSTI)

The purpose of this special analysis (SA) is to determine if the Idaho National Laboratory (INL) Unirradiated Light Water Breeder Reactor (LWBR) Rods and Pellets waste stream (INEL103597TR2, Revision 2) is suitable for disposal by shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS). The INL Unirradiated LWBR Rods and Pellets waste stream consists of 24 containers with unirradiated fabricated rods and pellets composed of uranium oxide (UO2) and thorium oxide (ThO2) fuel in zirconium cladding. The INL Unirradiated LWBR Rods and Pellets waste stream requires an SA because the 229Th, 230Th, 232U, 233U, and 234U activity concentrations exceed the Nevada National Security Site (NNSS) Waste Acceptance Criteria (WAC) Action Levels.

Shott, Gregory [NSTec

2014-08-31T23:59:59.000Z

111

Supplemental information for a notice of construction for the Fueled Clad Fabrication System, the Radioisotope Power Systems Facility, and the Fuel Assembly Area  

SciTech Connect (OSTI)

This ''Notice of Construction'' has been submitted by the US Department of Energy-Richland Operations Office (P.O. Box 550, Richland, Washington 99352), pursuant to WAC 402-80-070, for three new sources of radionuclide emissions at the Hanford Site in Washington State (Figure 1). The three new sources, the Fueled Clad Fabrication System (FCFS) the Radioisotope Power Systems Facility (RPSF) and the Fuel Assembly Area (FAA) will be located in one facility, the Fuels and materials Examination Facility (FMEF) of the 400 Area. The FMEF was originally designed to provide for post- irradiation examination and fabrication of breeder reactor fuels. These FMEF missions were cancelled before the introduction of any fuel materials or any irradiated material. The current plans are to use the facility to fabricate power supplies to be used in space applications and to produce Fast Flux Test Facility (FFTF) fuel and target assemblies. The FCFS and the RPSF will produce materials and assemblies for application in space. The FAA project will produce FFTF fuel and target assemblies. The FCFS and the RPSF will share the same building, stack, and, in certain cases, the same floor space. Given this relationship, to the extent possible, these systems will be dealt with separately. The FAA is a comparatively independent operation though it will share the FMEF complex.

Not Available

1989-08-01T23:59:59.000Z

112

Application for approval for construction of the Fueled Clad Fabrication System, the Radioisotope Power Systems Facility, and the Fuel Assembly Area  

SciTech Connect (OSTI)

The following ''Application for Approval of Construction'' is being submitted by the US Department of Energy-Richland Operations Office, pursuant to 40 CFR 61.07, for three new sources of airborne radionuclide emissions at the Hanford Site in Washington State. The three new sources, the Fueled Clad Fabrication System (FCFS), the Radioisotope Power Systems Facility (RPSF), and the Fuel Assembly Area (FAA), will be located in one facility, the Fuels and Materials Examination Facility (FMEF) of the 400 Area. The FMEF was originally designed to provide for post-irradiation examination and fabrication of breeder reactor fuels. These FMEF missions were canceled before the introduction of any fuel materials or any irradiated material. The current plans are to use the facility to fabricate power supplies to be used in space applications and to produce Fast Flux Test Facility (FFTF) fuel and target assemblies. The FCFS and the RPSF will produce materials and assemblies for application in space. The FAA project will produce FFTF fuel and target assemblies. The FCFS and the RPSF will share the same building and stack and, in certain cases, the same floor space. Given this relationship, these systems will be dealt with separately to the extent possible. The FAA is a comparatively independent operation though it will share the FMEF complex. 2 refs., 16 figs., 12 tabs.

Not Available

1989-08-01T23:59:59.000Z

113

Prevention of significant deterioration permit application for the Fueled Clad Fabrication System, the Radioisotope Power Systems Facility, and the Fuel Assembly Area  

SciTech Connect (OSTI)

This New Source Review'' has been submitted by the US Department of Energy-Richland Operations Office (PO Box 550, Richland, Washington 99352), pursuant to WAC 173-403-050 and in compliance with the Department of Ecology Guide to Processing A Prevention Of Significant Deterioration (PSD) Permit'' for three new sources of radionuclide emissions at the Hanford Site in Washington State. The three new sources, the Fueled Clad Fabrication System (FCFS), the Radioisotope Power Systems Facility (RPSF), and the Fuel Assembly Area (FAA), will be located in one facility, the Fuels and Materials Examination Facility (FMEF) of the 400 Area. The FMEF was originally designed to provide for post-irradiation examination and fabrication of breeder reactor fuels. These FMEF missions were cancelled before the introduction of any fuel materials or any irradiated material. The current plans are to use the facility to fabricate power supplies for use in space applications and to produce Fast Flux Test Facility (FFTF) fuel and target assemblies. The FCFS and the RPSF will produce materials and assemblies for application in space. The FAA project will produce FFTF fuel and target assemblies. The FCFS and the RPSF will share the same building, stack, and, in certain cases, the same floor space. Given this relationship, these systems will be dealt with separately to the extent possible. The FAA is a comparatively independent operation though it will share the FMEF complex.

Not Available

1989-08-01T23:59:59.000Z

114

Options for converting excess plutonium to feed for the MOX fuel fabrication facility  

SciTech Connect (OSTI)

The storage and safekeeping of excess plutonium in the United States represents a multibillion-dollar lifecycle cost to the taxpayers and poses challenges to National Security and Nuclear Non-Proliferation. Los Alamos National Laboratory is considering options for converting some portion of the 13 metric tons of excess plutonium that was previously destined for long-term waste disposition into feed for the MOX Fuel Fabrication Facility (MFFF). This approach could reduce storage costs and security ri sks, and produce fuel for nuclear energy at the same time. Over the course of 30 years of weapons related plutonium production, Los Alamos has developed a number of flow sheets aimed at separation and purification of plutonium. Flow sheets for converting metal to oxide and for removing chloride and fluoride from plutonium residues have been developed and withstood the test oftime. This presentation will address some potential options for utilizing processes and infrastructure developed by Defense Programs to transform a large variety of highly impure plutonium into feedstock for the MFFF.

Watts, Joe A [Los Alamos National Laboratory; Smith, Paul H [Los Alamos National Laboratory; Psaras, John D [Los Alamos National Laboratory; Jarvinen, Gordon D [Los Alamos National Laboratory; Costa, David A [Los Alamos National Laboratory; Joyce, Jr., Edward L [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

115

Safeguards and security concept for the Secure Automated Fabrication (SAF) and Liquid Metal Reactor (LMR) fuel cycle, SAF line technical support  

SciTech Connect (OSTI)

This report is a safeguards and security concept system review for the secure automated fabrication (SAF) and national liquid metal reactor (LMR) fuel programs.

Schaubert, V.J.; Remley, M.E.; Grantham, L.F.

1986-02-21T23:59:59.000Z

116

Plan offered to revive nukes. [US DOE would fabricate fuel from weapons for WNP-1 and 3  

SciTech Connect (OSTI)

This article discusses a new plan that would allow work to resume on two uncompleted nuclear power units in Washington state at a cost of $3.3 billion under an agreement with the federal government. If approved, the Department of Energy would fabricate plutonium from US and former Soviet Union weapons into fuel.

Not Available

1993-09-20T23:59:59.000Z

117

Recycling Of Uranium- And Plutonium-Contaminated Metals From Decommissioning Of The Hanau Fuel Fabrication Plant  

SciTech Connect (OSTI)

Decommissioning of a nuclear facility comprises not only actual dismantling but also, above all, management of the resulting residual materials and waste. Siemens Decommissioning Projects (DP) in Hanau has been involved in this task since 1995 when the decision was taken to decommission and dismantle the Hanau Fuel Fabrication Plant. Due to the decommissioning, large amounts of contaminated steel scrap have to be managed. The contamination of this metal scrap can be found almost exclusively in the form of surface contamination. Various decontamination technologies are involved, as there are blasting and wiping. Often these methods are not sufficient to meet the free release limits. In these cases, SIEMENS has decided to melt the scrap at Siempelkamp's melting plant. The plant is licensed according to the German Radiation Protection Ordinance Section 7 (issue of 20.07.2001). The furnace is a medium frequency induction type with a load capacity of 3.2 t and a throughput of 2 t/h for steel melting. For safety reasons, the furnace is widely operated by remote handling. A highly efficient filter system of cyclone, bag filter and HEPA-filter in two lines retains the dust and aerosol activity from the off-gas system. The slag is solidified at the surface of the melt and gripped before pouring the liquid iron into a chill. Since 1989, in total 15,000 t have been molten in the plant, 2,000 t of them having been contaminated steel scrap from the decommissioning of fuel fabrication plants. Decontamination factors could be achieved between 80 and 100 by the high affinity of the uranium to the slag former. The activity is transferred to the slag up to nearly 100 %. Samples taken from metal, slag and dust are analyzed by gamma measurements of the 186 keV line of U235 and the 1001 keV line of Pa234m for U238. All produced ingots showed a remaining activity less than 1 Bq/g and could be released for industrial reuse.

Kluth, T.; Quade, U.; Lederbrink, F. W.

2003-02-26T23:59:59.000Z

118

MICROBIAL POPULATIONS FECAL PELLETS AND  

E-Print Network [OSTI]

MICROBIAL POPULATIONS FECAL PELLETS AND AND BIOLU}IINESCENCEOF OCEANIC SEDII,IENTTRAP PARTICLES activities of microbial populations associated with fecal pellets col-Lecteo from oceanic zooplankton were (indicators of microbial growth and reproduction rates, respectively) were monitored in fecal pellets at time

Luther, Douglas S.

119

MARKETING PLAN PELLETED AND CRUMBLED  

E-Print Network [OSTI]

#12;MARKETING PLAN FOR PELLETED AND CRUMBLED COMPOSTED muLTRY MANURE PRODUCT JUNE, 1995 Prepared by should not be consideredto reflect the policy or position of I!aviromnentCanada. #12;Pelleted. Roger McNeill, Environment Canada I Zbeetnofl Consulting, 1995 #12;Pelleted and Crumbled, Composted

120

Uranium-233 purification and conversion to stabilized ceramic grade urania for LWBR fuel fabrication (LWBR Development Program)  

SciTech Connect (OSTI)

High purity ceramic grade urania (/sup 233/UO/sub 2/) used in manufacturing the fuel for the Light Water Breeder Reactor (LWBR) core was made from uranium-233 that was obtained by irradiating thoria under special conditions to result in not more than 10 ppM of uranium-232 in the recovered uranium-233 product. A developmental study established the operating parameters of the conversion process for transforming the uranium-233 into urania powder with the appropriate chemical and physical attributes for use in fabricating the LWBR core fuel. This developmental study included the following: (a) design of an ion exchange purification process for removing the gamma-emitting alpha-decay daughters of uranium-232, to reduce the gamma-radiation field of the uranium-233 during LWBR fuel manufacture; (b) definition of the parameters for precipitating the uranium-233 as ammonium uranate (ADU) and for reducing the ADU with hydrogen to yield a urania conversion product of the proper particle size, surface area and sinterability for use in manufacturing the LWBR fuel; (c) establishment of parameters and design of equipment for stabilizing the urania conversion product to prevent it from undergoing excessive oxidation on exposure to the air during LWBR fuel manufacturing operations; and (d) development of a procedure and a facility to reprocess the unirradiated thoria-urania fuel scrap from the LWBR core manufacturing operations to recover the uranium-233 and convert it into high purity ceramic grade urania for LWBR core fabrication.

Lloyd, R.

1980-10-01T23:59:59.000Z

Note: This page contains sample records for the topic "fuel pellet fabrication" 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

Pellet imaging techniques on ASDEX  

SciTech Connect (OSTI)

As part of a USDOE/ASDEX collaboration, a detailed examination of pellet ablation in ASDEX with a variety of diagnostics has allowed a better understanding of a number of features of hydrogen ice pellet ablation in a plasma. In particular, fast gated photos with an intensified Xybion CCD video camera allow in-situ velocity measurements of the pellet as it penetrates the plasma. With time resolution of typically 100 nanoseconds and exposures every 50 microseconds, the evolution of each pellet in a multi-pellet ASDEX tokamak plasma discharge can be followed. When the pellet cloud track has striations, the light intensity profile through the cloud is hollow (dark near the pellet), whereas at the beginning or near the end of the pellet trajectory the track is typically smooth (without striations) and has a gaussian-peaked light emission profile. New, single pellet Stark broadened D{sub {alpha}}D{sub {beta}}, and D{sub {gamma}} spectra, obtained with a tangentially viewing scanning mirror/spectrometer with Reticon array readout, are consistent with cloud densities of 2 {times} 10{sup 17}cm{sup {minus}3} or higher in the regions of strongest light emission. A spatially resolved array of D{sub {alpha}} detectors shows that the light variations during the pellet ablation are not caused solely by a modulation of the incoming energy flux as the pellet crosses rational q-surfaces, but instead are a result of a dynamic, non-stationary, ablation process. 20 refs., 4 figs.

Wurden, G.A. (Los Alamos National Lab., NM (USA)); Buechl, K.; Hofmann, J.; Lang, R.; Loch, R.; Rudyj, A.; Sandmann, W. (Max-Planck-Institut fuer Plasmaphysik, Garching (Germany, F.R.))

1990-01-01T23:59:59.000Z

122

Comparative Study of Laboratory-Scale and Prototypic Production-Scale Fuel Fabrication Processes and Product Characteristics  

SciTech Connect (OSTI)

Abstract An objective of the High Temperature Gas Reactor fuel development and qualification program for the United States Department of Energy has been to qualify fuel fabricated in prototypic production-scale equipment. The quality and characteristics of the tristructural isotropic coatings on fuel kernels are influenced by the equipment scale and processing parameters. Some characteristics affecting product quality were suppressed while others have become more significant in the larger equipment. Changes to the composition and method of producing resinated graphite matrix material has eliminated the use of hazardous, flammable liquids and enabled it to be procured as a vendor-supplied feed stock. A new method of overcoating TRISO particles with the resinated graphite matrix eliminates the use of hazardous, flammable liquids, produces highly spherical particles with a narrow size distribution, and attains product yields in excess of 99%. Compact fabrication processes have been scaled-up and automated with relatively minor changes to compact quality to manual laboratory-scale processes. The impact on statistical variability of the processes and the products as equipment was scaled are discussed. The prototypic production-scale processes produce test fuels that meet fuel quality specifications.

Douglas W. Marshall

2014-10-01T23:59:59.000Z

123

Overview of Recent Developments in Pellet Injection for ITER  

SciTech Connect (OSTI)

Pellet injection is the primary fueling technique planned for core fueling of ITER burning plasmas. Also, the injection of relatively small pellets to purposely trigger rapid small edge localized modes (ELMs) has been proposed as a possible solution to the heat flux damage from larger natural ELMs likely to be an issue on the ITER divertor surfaces. The ITER pellet injection system is designed to inject pellets into the plasma through both inner and outer wall guide tubes. The inner wall guide tubes will provide high throughput pellet fueling while the outerwall guide tubes will be used primarily to trigger ELMs at a high frequency (>15 Hz). The pellet fueling rate ofeach injector is to be up to 120 Pa-m3/s, which will require the formation of solid D-T at a volumetric rate of ~1500 mm3/s. Two injectors are to be provided for ITER at the startup with a provision for up to six injectorsduring the D-T phase. The required throughput of each injector is greater than that of any injector built to date, and a novel twin-screw continuous extrusion system is being developed to meet the challenging design parameters. Status of the development activities will be presented, highlighting recent progress.

Combs, Stephen Kirk [ORNL; Baylor, Larry R [ORNL; Meitner, Steven J [ORNL; Caughman, John B [ORNL; Rasmussen, David A [ORNL; Maruyama, So [ITER Organization, Cadarache, France

2012-01-01T23:59:59.000Z

124

Transmutation, Burn-Up and Fuel Fabrication Trade-Offs in Reduced-Moderation Water Reactor Thorium Fuel Cycles - 13502  

SciTech Connect (OSTI)

Multiple recycle of long-lived actinides has the potential to greatly reduce the required storage time for spent nuclear fuel or high level nuclear waste. This is generally thought to require fast reactors as most transuranic (TRU) isotopes have low fission probabilities in thermal reactors. Reduced-moderation LWRs are a potential alternative to fast reactors with reduced time to deployment as they are based on commercially mature LWR technology. Thorium (Th) fuel is neutronically advantageous for TRU multiple recycle in LWRs due to a large improvement in the void coefficient. If Th fuel is used in reduced-moderation LWRs, it appears neutronically feasible to achieve full actinide recycle while burning an external supply of TRU, with related potential improvements in waste management and fuel utilization. In this paper, the fuel cycle of TRU-bearing Th fuel is analysed for reduced-moderation PWRs and BWRs (RMPWRs and RBWRs). RMPWRs have the advantage of relatively rapid implementation and intrinsically low conversion ratios. However, it is challenging to simultaneously satisfy operational and fuel cycle constraints. An RBWR may potentially take longer to implement than an RMPWR due to more extensive changes from current BWR technology. However, the harder neutron spectrum can lead to favourable fuel cycle performance. A two-stage fuel cycle, where the first pass is Th-Pu MOX, is a technically reasonable implementation of either concept. The first stage of the fuel cycle can therefore be implemented at relatively low cost as a Pu disposal option, with a further policy option of full recycle in the medium term. (authors)

Lindley, Benjamin A.; Parks, Geoffrey T. [University of Cambridge, Cambridge (United Kingdom)] [University of Cambridge, Cambridge (United Kingdom); Franceschini, Fausto [Westinghouse Electric Company LLC, Cranberry Township, PA (United States)] [Westinghouse Electric Company LLC, Cranberry Township, PA (United States)

2013-07-01T23:59:59.000Z

125

Wood and Pellet Heating Basics | Department of Energy  

Energy Savers [EERE]

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankCombustion |Energyon ArmedWaste and Materials Disposition InformationWindWood and Pellet Heating Basics

126

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

SciTech Connect (OSTI)

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 lowheat 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

127

Interim Action Determination Flexible Manufacturing Capability for the Mixed Fuel Fabrication Facility (MFFF)  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAX POLICIES7.pdfFuel2007 | Department7 U.S. Department ofAboutWAPAInterim

128

Fabrication of Micro-Orifices for Diesel Fuel Injectors | Department of  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-UpHeat PumpRecord ofESPCofConstructionofFY 2011 Report toAnnuAl ProgressEnergy

129

Technique for controlling shrinkage distortion in cold-pressed annular pellets  

DOE Patents [OSTI]

A process and apparatus are described for the production of annular fuel pellets comprising locating particulate fuel material in a compaction chamber having side walls, a moveable punch located opposite a fixed member and a frustoconical element having a taper of between about 0.010 to 0.015 inches/inch located in about the center of the chamber. The punch is moved toward the fixed surface to compact the particulate material. The compacted pellet is fired to produce sintered pellets having substantially straight inner side walls essentially parallel to the pellet axis.

Johnson, R.G.R.; Burke, T.J.

1982-06-28T23:59:59.000Z

130

Microwave drying of ferric oxide pellets  

SciTech Connect (OSTI)

The application of microwave energy for the drying of ferric oxide pellets has been investigated and evaluated. It is shown that the microwave drying rates are much higher than those observed in the conventional process. Also there is some potential for improved quality of the product. As a stand-alone technology it is unlikely that microwave drying would be economical for pellets due to the low cost of conventional fuels. However, based on an understanding of the drying mechanisms in the conventional process and in the microwave process, it is shown that microwave-assisted drying offers considerable potential. In this hybrid process, the advantages of the two drying techniques are combined to provide an improved drying process.

Pickles, C.A.; Xia, D.K. [Queens` Univ., Kingston, Ontario (Canada). Dept. of Materials and Metallurgical Engineering

1997-12-31T23:59:59.000Z

131

Co-Rolled U10Mo/Zirconium-Barrier-Layer Monolithic Fuel Foil Fabrication Process  

SciTech Connect (OSTI)

Integral to the current UMo fuel foil processing scheme being developed at Idaho National Laboratory (INL) is the incorporation of a zirconium barrier layer for the purpose of controlling UMo-Al interdiffusion at the fuel-meat/cladding interface. A hot co-rolling process is employed to establish a ~25-m-thick zirconium barrier layer on each face of the ~0.3-mm-thick U10Mo fuel foil.

G. A. Moore; M. C. Marshall

2010-01-01T23:59:59.000Z

132

Computational design, fabrication, and characterization of microarchitectured solid oxide fuel cells with improved energy efficiency.  

E-Print Network [OSTI]

??Electrodes in a solid oxide fuel cell (SOFC) must possess both adequate porosity and electronic conductivity to perform their functions in the cell. They must (more)

Yoon, Chan

2010-01-01T23:59:59.000Z

133

E-Print Network 3.0 - atr fuel fabrication Sample Search Results  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Collection: Environmental Management and Restoration Technologies 3 2003 Hydrogen and Fuel Cells Merit Review Meeting May 19-22, 2003, Berkeley, CA Summary: Argonne...

134

E-Print Network 3.0 - ag fuel fabrication Sample Search Results  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

in this ... Source: DOE Office of Energy Efficiency and Renewable Energy, Hydrogen, Fuel Cells and Infrastructure Technologies Program Collection: Energy Storage, Conversion...

135

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

SciTech Connect (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 lowheat 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

136

Standard specification for sintered (Uranium-Plutonium) dioxide pellets  

E-Print Network [OSTI]

1.1 This specification covers finished sintered and ground (uranium-plutonium) dioxide pellets for use in thermal reactors. It applies to uranium-plutonium dioxide pellets containing plutonium additions up to 15 % weight. This specification may not completely cover the requirements for pellets fabricated from weapons-derived plutonium. 1.2 This specification does not include (1) provisions for preventing criticality accidents or (2) requirements for health and safety. Observance of this specification does not relieve the user of the obligation to be aware of and conform to all applicable international, federal, state, and local regulations pertaining to possessing, processing, shipping, or using source or special nuclear material. Examples of U.S. government documents are Code of Federal Regulations Title 10, Part 50Domestic Licensing of Production and Utilization Facilities; Code of Federal Regulations Title 10, Part 71Packaging and Transportation of Radioactive Material; and Code of Federal Regulations Tit...

American Society for Testing and Materials. Philadelphia

2001-01-01T23:59:59.000Z

137

Fire loading calculations for 300 Area N Reactor Fuel Fabrication and Storage Facility  

SciTech Connect (OSTI)

Fire loading analyses were provided for the N Reactor Fuel Supply Buildings 3712, 3716, 303A, 303B, 303E, 303G, and 303K. Fire loading calculations, maximum temperatures, and fire durations were provided to support the safety analyses documentation. The ``combustibles`` for this document include: wood, cardboard, cloth, and plastic, and does not include the uranium and fuel assembly loading. The information in this document will also be used to support the fire hazard analysis for the same buildings, therefore, it is assumed that sprinkler systems do not work, or the maximum possible fire loss is assumed.

Myott, C.F.

1994-01-24T23:59:59.000Z

138

A microfluidic microbial fuel cell fabricated by soft lithography Fang Qian a,b,  

E-Print Network [OSTI]

Microbial fuel cells (MFC) utilize microbial consumption of or- ganic feed stocks to produce electricity, and have significant poten- tial for applications in energy conversion and environmental science to the loss of electron transport capabilities (Rich- ter et al., 2008). Many studies in the mL-to-L regime

Li, Yat

139

Development of advanced mixed oxide fuels for plutonium management  

SciTech Connect (OSTI)

A number of advanced Mixed Oxide (MOX) fuel forms are currently being investigated at Los Alamos National Laboratory that have the potential to be effective plutonium management tools. Evolutionary Mixed Oxide (EMOX) fuel is a slight perturbation on standard MOX fuel, but achieves greater plutonium destruction rates by employing a fractional nonfertile component. A pure nonfertile fuel is also being studied. Initial calculations show that the fuel can be utilized in existing light water reactors and tailored to address different plutonium management goals (i.e., stabilization or reduction of plutonium inventories residing in spent nuclear fuel). In parallel, experiments are being performed to determine the feasibility of fabrication of such fuels. Initial EMOX pellets have successfully been fabricated using weapons-grade plutonium.

Eaton, S.; Beard, C.; Buksa, J.; Butt, D.; Chidester, K.; Havrilla, G.; Ramsey, K.

1997-06-01T23:59:59.000Z

140

SPS Fabrication of Tungsten-Rhenium Alloys in Support of NTR Fuels Development  

SciTech Connect (OSTI)

Abstract. Tungsten metal slugs were fabricated via Spark Plasma Sintering (SPS) of powdered metals at temperatures ranging from 1575 K to 1975 K and hold times of 5 minutes to 30 minutes, using powders with an average diameter of 7.8 ?m. Sintered tungsten specimens were found to have relative densities ranging from 83 % to 94 % of the theoretical density for tungsten. Consolidated specimens were also tested for their Vickers Hardness Number (VHN), which was fitted as a function of relative density; the fully consolidated VHN was extrapolated to be 381.45 kg/mm2. Concurrently, tungsten and rhenium powders with average respective diameters of 0.5 ?m and 13.3 ?m were pre-processed either by High-Energy-Ball-Milling (HEBM) or by homogeneous mixing to yield W-25at.%Re mixtures. The powder batches were sintered at temperatures of 1975 K and 2175 K for hold times ranging from 0 minutes to 60 minutes yielding relative densities ranging from 94% to 97%. The combination of HEBM and sintering showed a significant decrease in the inter-metallic phases compared to that of the homogenous mixing and sintering.

Jonathan A. Webb; Indrajit Charit; Cory Sparks; Darryl P. Butt; Megan Frary; Mark Carroll

2011-02-01T23:59:59.000Z

Note: This page contains sample records for the topic "fuel pellet fabrication" 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

Hot Isostatic Press Manufacturing Process Development for Fabrication of RERTR Monolithic Fuel Plates  

SciTech Connect (OSTI)

We use experimentation and finite element modeling to study a Hot Isostatic Press (HIP) manufacturing process for U-10Mo Monolithic Fuel Plates. Finite element simulations are used to identify the material properties affecting the process and improve the process geometry. Accounting for the high temperature material properties and plasticity is important to obtain qualitative agreement between model and experimental results. The model allows us to improve the process geometry and provide guidance on selection of material and finish conditions for the process strongbacks. We conclude that the HIP can must be fully filled to provide uniform normal stress across the bonding interface.

Crapps, Justin M. [Los Alamos National Laboratory; Clarke, Kester D. [Los Alamos National Laboratory; Katz, Joel D. [Los Alamos National Laboratory; Alexander, David J. [Los Alamos National Laboratory; Aikin, Beverly [Los Alamos National Laboratory; Vargas, Victor D. [Los Alamos National Laboratory; Montalvo, Joel D. [Los Alamos National Laboratory; Dombrowski, David E. [Los Alamos National Laboratory; Mihaila, Bogdan [Los Alamos National Laboratory

2012-06-06T23:59:59.000Z

142

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

143

Development and transfer of fuel fabrication and utilization technology for research reactors  

SciTech Connect (OSTI)

Approximately 300 research reactors supplied with US-enriched uranium are currently in operation in about 40 countries, with a variety of types, sizes, experiment capabilities and applications. Despite the usefulness and popularity of research reactors, relatively few innovations in their core design have been made in the last fifteen years. The main reason can be better understood by reviewing briefly the history of research reactor fuel technology and enrichment levels. Stringent requirements on the enrichment of the uranium to be used in research reactors were considered and a program was launched to assist research reactors in continuing their operation with the new requirements and with minimum penalties. The goal of the new program, the Reduced Enrichment Research and Test Reactor (RERTR) Program, is to develop the technical means to utilize LEU instead of HEU in research reactors without significant penalties in experiment performance, operating costs, reactor modifications, and safety characteristics. This paper reviews briefly the RERTR Program activities with special emphasis on the technology transfer aspects of interest to this conference.

Travelli, A.; Domagala, R.F.; Matos, J.E.; Snelgrove, J.L.

1982-01-01T23:59:59.000Z

144

A REVIEW OF THORIUM FUEL REPROCESSING EX  

Office of Scientific and Technical Information (OSTI)

oxide pellet fuel from this reactor was re- processed at the privately owned and operated Nuclear Fuel Services plant at West Valley, New York. Other reactor programs involving...

145

Method for making spherical binderless pellets  

DOE Patents [OSTI]

A method for making spherical binderless pellets using a rotating drum mixer whereby at least a portion of the particles comprising the pellets is comprised of coking coal particles.

Grubbs, Donald K. (Rector, PA); Kochanowski, Andrew T. (Spring Church, PA)

1983-01-01T23:59:59.000Z

146

U.S. Pellet Industry Analysis  

SciTech Connect (OSTI)

This report is a survey of the U.S. Pellet Industry, its current capacity, economic drivers, and projected demand for biomass pellets to meet future energy consumption needs. Energy consumption in the US is projected to require an ever increasing portion of renewable energy sources including biofuels, among which are wood, and agrictulrual biomass. Goals set by federal agencies will drive an ever increasing demand for biomass. The EIA projections estimate that renewable energy produced by 2035 will be roughly 10% of all US energy consumption. Further analysis of the biofuels consumption in the US shows that of the renewable energy sources excluding biofuels, nearly 30% are wood or biomass waste. This equates to roughly 2% of the total energy consumption in the US coming from biomass in 2009, and the projections for 2035 show a strong increase in this amount. As of 2009, biomass energy production equates to roughly 2-2.5 quadrillion Btu. The EIA projections also show coal as providing 21% of energy consumed. If biomass is blended at 20% to co-fire coal plants, this will result in an additional 4 quadrillion Btu of biomass consumption. The EISA goals aim to produce 16 billion gal/year of cellulosic biofuels, and the US military has set goals for biofuels production. The Air Force has proposed to replace 50% of its domestic fuel requirements with alternative fuels from renewable sources by 2016. The Navy has likewise set a goal to provide 50% of its energy requirements from alternative sources. The Department of Energy has set similarly ambitious goals. The DOE goal is to replace 40% of 2004 gasoline use with biofuels. This equates to roughly 60 billion gal/year, of which, 45 billion gal/year would be produced from lignocellulosic resources. This would require 530 million dry tons of herbaceous and woody lignocellulosic biomass per year.

Corrie I. Nichol; Jacob J. Jacobsen; Richard D. Boardman

2011-06-01T23:59:59.000Z

147

Light water reactor mixed-oxide fuel irradiation experiment  

SciTech Connect (OSTI)

The United States Department of Energy Office of Fissile Materials Disposition is sponsoring and Oak Ridge National Laboratory (ORNL) is leading an irradiation experiment to test mixed uranium-plutonium oxide (MOX) fuel made from weapons-grade (WG) plutonium. In this multiyear program, sealed capsules containing MOX fuel pellets fabricated at Los Alamos National Laboratory (LANL) are being irradiated in the Advanced Test Reactor (ATR) at the Idaho National Engineering and Environmental Laboratory (INEEL). The planned experiments will investigate the utilization of dry-processed plutonium, the effects of WG plutonium isotopics on MOX performance, and any material interactions of gallium with Zircaloy cladding.

Hodge, S.A.; Cowell, B.S. [Oak Ridge National Lab., TN (United States); Chang, G.S.; Ryskamp, J.M. [Lockheed Martin Idaho Technologies Co., Idaho Falls, ID (United States). Idaho National Engineering and Environmental Lab.

1998-06-01T23:59:59.000Z

148

25 years of pelletizing at CVRD  

SciTech Connect (OSTI)

This paper presents the evolution of the iron ore pelletizing activities at Companhia Vale do Rio Doce (CVRD), since the start-up of the first plant in the Tubarao area (Brazil), in 1969. The main features of CVRD`s pelletizing activities are described, focusing on the development of different types of pellets for the blast furnace and direct reduction markets, on the actions taken to face the urging necessity of cutting down energetic costs and on the handling of several different types of raw material. The profile of process control, quality management and environmental control at CVRD`s pelletizing plants is also presented.

Bandeira de Mello, L.A.; Mourao, J.M.; Cunha, J.M.; Piccolo, A.L.; Klein, M.S. [Companhia Vale do Rio Doce, Vitoria, Espirito Santo (Brazil)

1996-12-31T23:59:59.000Z

149

Pellet injector development at ORNL* S. K. Combs,a S. L. Milora,a L. R. Baylor,a P. W. Fisher,a C. A. Foster,a C. R. Foust,a M. J. Gouge,a  

E-Print Network [OSTI]

Pellet injector development at ORNL* S. K. Combs,a S. L. Milora,a L. R. Baylor,a P. W. Fisher,a C developing pellet injection systems for plasma fueling experiments on magnetic fusion confinement devices will use a combination of deuterium-tritium (D-T) gas puffing and pellet injection to achieve and maintain

150

High Thermal Conductivity UO2-BeO Nulcear Fuel: Neutronic Performance Assessments and Overview of Fabrication  

E-Print Network [OSTI]

The objective of this work was to evaluate a new high conductivity nuclear fuel form. Uranium dioxide (UO2) is a very effective nuclear fuel, but its performance is limited by its low thermal conductivity. The fuel concept considered here is a...

Naramore, Michael J

2010-08-03T23:59:59.000Z

151

AFIP-6 Fabrication Summary Report  

SciTech Connect (OSTI)

The AFIP-6 (ATR Full-size plate In center flux trap Position) experiment was designed to evaluate the performance of monolithic fuels at a scale prototypic of research reactor fuel plates. Two qualified fueled plates were fabricated for the AFIP-6 experiment; to be irradiated in the INL Advanced Test Reactor (ATR). This report provides details of the fuel fabrication efforts, including material selection, fabrication processes, and fuel plate qualification.

Glenn A. Moore; M. Craig Marshall

2011-09-01T23:59:59.000Z

152

AFIP-2 Fabrication Summary Report  

SciTech Connect (OSTI)

The Advanced Test Reactor (ATR) Full-size Plate In Center Flux Trap Position (AFIP)-2 experiment was designed to evaluate the performance of monolithic fuels at a scale prototypic of research reactor fuel plates. Two qualified fueled plates were fabricated for the AFIP 2 experiment to be irradiated in the Idaho National Laboratory ATR. This report provides details of the fuel fabrication efforts, including material selection, fabrication processes, and fuel plate qualification.

Glenn Moore

2010-02-01T23:59:59.000Z

153

AFIP-4 Fabrication Summary Report  

SciTech Connect (OSTI)

The AFIP-4 (ATR Full size-plate In center flux trap Position) experiment was designed to evaluate the performance of monolithic fuels at a scale prototypic of research reactor fuel plates. Twelve qualified fueled plates were fabricated for the AFIP-4 experiment; to be irradiated in the INL Advanced Test Reactor (ATR). This report provides details of the fuel fabrication efforts; including material selection, fabrication processes, and fuel plate qualification.

Glenn A. Moore

2010-02-01T23:59:59.000Z

154

LLNL MOX fuel lead assemblies data report for the surplus plutonium disposition environmental impact statement  

SciTech Connect (OSTI)

The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement. This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. The DOE Office of Fissile Materials Disposition (DOE-MD) has developed a dual-path strategy for disposition of surplus weapons-grade plutonium. One of the paths is to disposition surplus plutonium through irradiation of MOX fuel in commercial nuclear reactors. MOX fuel consists of plutonium and uranium oxides (PuO{sub 2} and UO{sub 2}), typically containing 95% or more UO{sub 2}. DOE-MD requested that the DOE Site Operations Offices nominate DOE sites that meet established minimum requirements that could produce MOX LAs. LLNL has proposed an LA MOX fuel fabrication approach that would be done entirely inside an S and S Category 1 area. This includes receipt and storage of PuO{sub 2} powder, fabrication of MOX fuel pellets, assembly of fuel rods and bundles, and shipping of the packaged fuel to a commercial reactor site. Support activities will take place within a Category 1 area. Building 332 will be used to receive and store the bulk PuO{sub 2} powder, fabricate MOX fuel pellets, and assemble fuel rods. Building 334 will be used to assemble, store, and ship fuel bundles. Only minor modifications would be required of Building 332. Uncontaminated glove boxes would need to be removed, petition walls would need to be removed, and minor modifications to the ventilation system would be required.

O`Connor, D.G.; Fisher, S.E.; Holdaway, R. [and others

1998-08-01T23:59:59.000Z

155

Fracture behavior of zircaloy spent-fuel cladding  

SciTech Connect (OSTI)

The Zircaloy cladding of water reactor fuel rods is susceptible to local breach-type failure, commonly known as pellet-cladding interaction (PCI) failure, during operational and off-normal power transients after the fuel has achieved a sufficiently high burnup. An optimization of power ramp procedures or fuel rod fabrication to minimize the cladding failure would result in a significant decrease in radiation exposure of plant personnel due to background and airborne radioactivity as well as an extension of core life in terms of allowable off-gas radioactivity. As part of a program to provide a better understanding of the fuel rod faiure phenomenon and to facilitate the formulation of a better failure criterion, a mechanistic study of the deformation and fracture behavior of high-burnup spent-fuel cladding is in progress under simulated PCI conditions.

Chung, H.M.; Yaggee, F.L.; Kassner, T.F.

1983-10-01T23:59:59.000Z

156

Design, Fabrication, and Operation of Innovative Microalgae Culture Experiments for the Purpose of Producing Fuels: Final Report, Phase I  

SciTech Connect (OSTI)

A conceptual design was developed for a 1000-acre (water surface) algae culture facility for the production of fuels. The system is modeled after the shallow raceway system with mixing foils that is now being operated at the University of Hawaii. A computer economic model was created to calculate the discounted breakeven price of algae or fuels produced by the culture facility. A sensitivity analysis was done to estimate the impact of changes in important biological, engineering, and financial parameters on product price.

Not Available

1985-01-01T23:59:59.000Z

157

Fuel performance improvement program: description and characterization of HBWR Series H-2, H-3, and H-4 test rods  

SciTech Connect (OSTI)

The fabrication process and as-built characteristics of the HBWR Series H-2 and H-3 test rods, as well as the three packed-particle (sphere-pac) rods in HBWR Series H-4 are described. The HBWR Series H-2, H-3, and H-4 tests are part of the irradiation test program of the Fuel Performance Improvement Program. Fifteen rods were fabricated for the three test series. Rod designs include: (1) a reference dished pellet design incorporating chamfered edges, (2) a chamfered, annular pellet design combined with graphite-coated cladding, and (3) a sphere-pac design. Both the annular-coated and sphere-pac designs include internal pressurization using helium.

Guenther, R.J.; Barner, J.O.; Welty, R.K.

1980-03-01T23:59:59.000Z

158

LANL MOX fuel lead assemblies data report for the surplus plutonium disposition environmental impact statement  

SciTech Connect (OSTI)

The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement. This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. LANL has proposed an LA MOX fuel fabrication approach that would be done entirely inside an S and S Category 1 area. This includes receipt and storage of PuO{sub 2} powder, fabrication of MOX fuel pellets, assembly of fuel rods and bundles, and shipping of the packaged fuel to a commercial reactor site. Support activities will take place within both Category 1 and 2 areas. Technical Area (TA) 55/Plutonium Facility 4 will be used to store the bulk PuO{sub 2} powder, fabricate MOX fuel pellets, assemble rods, and store fuel bundles. Bundles will be assembled at a separate facility, several of which have been identified as suitable for that activity. The Chemistry and Metallurgy Research Building (at TA-3) will be used for analytical chemistry support. Waste operations will be conducted in TA-50 and TA-54. Only very minor modifications will be needed to accommodate the LA program. These modifications consist mostly of minor equipment upgrades. A commercial reactor operator has not been identified for the LA irradiation. Postirradiation examination (PIE) of the irradiated fuel will take place at either Oak Ridge National Laboratory or ANL-W. The only modifications required at either PIE site would be to accommodate full-length irradiated fuel rods. Results from this program are critical to the overall plutonium distribution schedule.

Fisher, S.E.; Holdaway, R.; Ludwig, S.B. [and others

1998-08-01T23:59:59.000Z

159

Commonwealth Small Pellet Boiler Grant Program  

Broader source: Energy.gov [DOE]

The Massachusetts Clean Energy Center (MassCEC) and the Department of Energy Resources (DOER) are offering the Commonwealth Small Pellet Boiler Pilot Grant Program to provide grants to residents...

160

Hydrogen Uptake of DPB Getter Pellets  

SciTech Connect (OSTI)

The physical and chemical properties of 1,4-diphenylbutadiyne (DPB) blended with carbon-supported Pd (DPB-Pd/C) in the form of pellets during hydrogenation were investigated. A thermogravimetric analyzer (TGA) was employed to measure the kinetics of the hydrogen uptake by the DPB getter pellets. The kinetics obtained were then used to develop a semi-empirical model, based on gas diffusion into solids, to predict the performance of the getter pellets under various conditions. The accuracy of the prediction model was established by comparing the prediction models with independent experimental data on hydrogen pressure buildup in sealed systems containing DPB getter pellets and subjected to known rates of hydrogen input. The volatility of the hydrogenated DPB products and its effects on the hydrogen uptake kinetics were also analyzed.

Dinh, L N; Schildbach, M A; Herberg, J L; Saab, A P; Weigle, J; Chinn, S C; Maxwell, R S; McLean II, W

2008-05-30T23:59:59.000Z

Note: This page contains sample records for the topic "fuel pellet fabrication" 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

An economical and market analysis of Canadian wood pellets.  

SciTech Connect (OSTI)

This study systematically examined the current and future wood pellet market, estimated the cost of Canadian torrefied pellets, and compared the torrefied pellets with the conventional pellets based on literature and industrial data. The results showed that the wood pellet industry has been gaining significant momentum due to the European bioenergy incentives and the rising oil and natural gas prices. With the new bioenergy incentives in USA, the future pellets market may shift to North America, and Canada can potentially become the largest pellet production centre, supported by the abundant wood residues and mountain pine beetle (MPB) infested trees.

Peng, J. [University of British Columbia, Vancouver

2010-08-01T23:59:59.000Z

162

High Performance Fuel Desing for Next Generation Pressurized Water Reactors  

SciTech Connect (OSTI)

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

163

Technical recommendations in the design and operation of a plutonium fuel fabrication facility to facilitate decontamination and decommissioning  

SciTech Connect (OSTI)

Sequoyah Fuels Corporation (formerly Kerr-McGee Nuclear Corporation) is in the process of decontaminating and decommissioning the Cimarron Plutonium Facility. This facility was designed to produce mixed oxide (Pu-U)O{sub 2} fuel using the co-precipitation process. This report is intended to address three topics: (1) identify problem areas which were revealed during the first phase of the decontamination and decommissioning (D&D) effort which could have been minimized by use of different design criteria; (2) provide recommendations which would have minimized Pu hold-up or made non-destructive assay (NDA) for inventory more accurate and less difficult; and (3) identify the limitations of the current NDA equipment being used at the Cimarron Plutonium Facility. The major problem areas uncovered to date and possible resolutions are identified.

Not Available

1994-05-01T23:59:59.000Z

164

An improved structural mechanics model for the FRAPCON nuclear fuel performance code  

E-Print Network [OSTI]

In order to provide improved predictions of Pellet Cladding Mechanical Interaction (PCMI) for the FRAPCON nuclear fuel performance code, a new model, the FRAPCON Radial-Axial Soft Pellet (FRASP) model, was developed. This ...

Mieloszyk, Alexander James

2012-01-01T23:59:59.000Z

165

The enhanced ASDEX Upgrade pellet centrifuge launcher  

SciTech Connect (OSTI)

Pellets played an important role in the program of ASDEX Upgrade serving both for investigations on efficient particle fuelling and high density scenarios but also for pioneering work on Edge Localised Mode (ELM) pacing and mitigation. Initially designed for launching fuelling pellets from the magnetic low field side, the system was converted already some time ago to inject pellets from the magnetic high field side as much higher fuelling efficiency was found using this configuration. In operation for more than 20 years, the pellet launching system had to undergo a major revision and upgrading, in particular of its control system. Furthermore, the control system installed adjacent to the launcher had to be transferred to a more distant location enforcing a complete galvanic separation from torus potential and a fully remote control solution. Changing from a hybrid system consisting of PLC S5/S7 and some hard wired relay control to a state of the art PLC system allowed the introduction of several new operational options enabling more flexibility in the pellet experiments. This article describes the new system architecture of control hardware and software, the operating procedure, and the extended operational window. First successful applications for ELM pacing and triggering studies are presented as well as utilization for the development of high density scenarios.

Plckl, B.; Lang, P. T. [Max Planck Institute for Plasma Physics, EURATOM Association, Boltzmannstr. 2, 85748 Garching (Germany)] [Max Planck Institute for Plasma Physics, EURATOM Association, Boltzmannstr. 2, 85748 Garching (Germany)

2013-10-15T23:59:59.000Z

166

International Trade of Wood Pellets (Brochure)  

SciTech Connect (OSTI)

The production of wood pellets has increased dramatically in recent years due in large part to aggressive emissions policy in the European Union; the main markets that currently supply the European market are North America and Russia. However, current market circumstances and trade dynamics could change depending on the development of emerging markets, foreign exchange rates, and the evolution of carbon policies. This fact sheet outlines the existing and potential participants in the wood pellets market, along with historical data on production, trade, and prices.

Not Available

2013-05-01T23:59:59.000Z

167

Property:Building/SPPurchasedEngyPerAreaKwhM2Pellets | Open Energy  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 No revision hasInformationInyo County,InformationInformation Pellets Jump to: navigation, search This is

168

SciTech Connect: ABRASION TEST OF THORIA PELLETS  

Office of Scientific and Technical Information (OSTI)

ABRASION TEST OF THORIA PELLETS Citation Details In-Document Search Title: ABRASION TEST OF THORIA PELLETS Authors: Spiewak, I.; Hafford, J. A. Publication Date: 1954-03-01 OSTI...

169

Cryogenic neutron moderator on mesitylene pellets for IBR-2 reactor  

E-Print Network [OSTI]

Cryogenic neutron moderator on mesitylene pellets for IBR-2 reactor Anan'ev V., Belyakov A the camera is 40 K Temperature inside the camera is 160 K (pellets stick to the baffle) #12;Fulfillment

Titov, Anatoly

170

RUMEN DIGESTION PARAMETERS IN LAMBS FED WITH PELLETED DIET  

E-Print Network [OSTI]

RUMEN DIGESTION PARAMETERS IN LAMBS FED WITH PELLETED DIET A. PETKOV E.I. ENEV Department of animal with pelleted feed containing 25 % alfalfa meal, 35 % maize, 9.9 % barley, 7.2 % wheat, 21.5 % sunflower oil ration was 0.200 kg pelleted feed and at the age of 4 months, 0.400 kg. The pelleted feed was given twice

Paris-Sud XI, Université de

171

Preliminary Investigation of Candidate Materials for Use in Accident Resistant Fuel  

SciTech Connect (OSTI)

As part of a Collaborative Research and Development Agreement (CRADA) with industry, Idaho National Laboratory (INL) is investigating several options for accident resistant uranium compounds including silicides, and nitrides for use in future light water reactor (LWR) fuels. This work is part of a larger effort to create accident tolerant fuel forms where changes to the fuel pellets, cladding, and cladding treatment are considered. The goal fuel form should have a resistance to water corrosion comparable to UO2, have an equal to or larger thermal conductivity than uranium dioxide, a melting temperature that allows the material to stay solid under power reactor conditions, and a uranium loading that maintains or improves current LWR power densities. During the course of this research, fuel fabricated at INL will be characterized, irradiated at the INL Advanced Test Reactor, and examined after irradiation at INL facilities to help inform industrial partners on candidate technologies.

Jason M. Harp; Paul A. Lessing; Blair H. Park; Jakeob Maupin

2013-09-01T23:59:59.000Z

172

Pellet ELM Pacing Developments DIII-D December Experiment Highlights  

E-Print Network [OSTI]

Pellet ELM Pacing Developments ­ DIII-D December Experiment Highlights L.R. Baylor1, T.C. Jernigan1 issue for ITER. ELM Pacing has been shown to reduce the ELM size. · In support of ITER, the pellet injector gun design has been modified to produce small pellets at slow speeds. · The new injector gun

173

Pellet Driven Disruptions in Tokamaks H.R. Strauss  

E-Print Network [OSTI]

Pellet Driven Disruptions in Tokamaks H.R. Strauss Courant Institute of Mathematical Sciences New York University W. Park Princeton Plasma Physics Laboratory Abstract Pellet injection can trigger ballooning like instability in tokamaks, driven by the large pressure perturbation of the pellet cloud

Strauss, Hank

174

Quantitative Changes in Hydrocarbons over Time in Fecal Pellets of Incisitermes minor May Predict Whether Colonies Are Alive or Dead  

E-Print Network [OSTI]

Food utilization and fecal pellet production by drywoodexploring seasonality in pellet production and hydrocarbon

Lewis, Vernard R.; Nelson, Lori J.; Haverty, Michael I.; Baldwin, James A.

2010-01-01T23:59:59.000Z

175

LMFBR fuel component costs  

SciTech Connect (OSTI)

A significant portion of the cost of fabricating LMFBR fuels is in the non-fuel components such as fuel pin cladding, fuel assembly ducts and end fittings. The contribution of these to fuel fabrication costs, based on FFTF experience and extrapolated to large LMFBR fuel loadings, is discussed. The extrapolation considers the expected effects of LMFBR development programs in progress on non-fuel component costs.

Epperson, E.M.; Borisch, R.R.; Rice, L.H.

1981-10-29T23:59:59.000Z

176

Cotton-pellet, Inflammation Correspondence to author:  

E-Print Network [OSTI]

Inflammation is a biological reaction attributed with several acute and chronic pathological conditions. The study revealed the pharmacological effect of Tecomella undulate: bark against carrageenan induced paw edema and cotton pellet induced granuloma in rat. Wistar albino rats of either sex (180-240 g) were employed into the study. Acute inflammation was induced by injecting carrageenan (1%) in rat paw and estimated using plethysmograph. Chronic inflammation was induced by cotton pellet induced granuloma method. Serum nitrate/nitrate estimation was also done as an index of inflammatory reactions. Acute toxicity study was also done using Swiss albino mice. Butanolic and water fractions of Tecomella undulate (200 & 400 mg/kg) and indomethacin (10 mg/kg) were used as test drugs. Carrageennan caused a marked increase in rat paw volume due to edema formation. T. undulate: butanolic fraction significantly inhibited paw volume in successive hours similar to indomethacin. Interscapular implanted cotton caused significant increase in granuloma wt. and serum nitrate/nitrite level in control group. However, the test drugs lowered the effects of cotton pellet induced chronic inflammation. Therefore, the results may conclude that the bark of T. undulate is having a pharmacological potential to treat acute and chronic inflammation in rat. Available online on www.ijpsr.com 108ISSN: 0975-8232 INTRODUCTION: Inflammation

Rohit Goyal; P. L. Sharma; Manjeet Singh; Rohit Goyal

177

Novel Accident-Tolerant Fuel Meat and Cladding  

SciTech Connect (OSTI)

A novel accident-tolerant fuel meat and cladding are here proposed. The fuel meat design incorporates annular fuel with inserts and discs that are fabricated from a material having high thermal conductivity, for example niobium. The inserts are rods or tubes. Discs separate the fuel pellets. Using the BISON fuel performance code it was found that the peak fuel temperature can be lowered by more than 600 degrees C for one set of conditions with niobium metal as the thermal conductor. In addition to improved safety margin, several advantages are expected from the lower temperature such as decreased fission gas release and fuel cracking. Advantages and disadvantages are discussed. An enrichment of only 7.5% fully compensates the lost reactivity of the displaced UO2. Slightly higher enrichments, such as 9%, allow uprates and increased burnups to offset the initial costs for retooling. The design has applications for fast reactors and transuranic burning, which may accelerate its development. A zirconium silicide coating is also described for accident tolerant applications. A self-limiting degradation behavior for this coating is expected to produce a glassy, self-healing layer that becomes more protective at elevated temperature, with some similarities to MoSi2 and other silicides. Both the fuel and coating may benefit from the existing technology infrastructure and the associated wide expertise for a more rapid development in comparison to other, more novel fuels and cladding.

Robert D. Mariani; Pavel G Medvedev; Douglas L Porter; Steven L Hayes; James I. Cole; Xian-Ming Bai

2013-09-01T23:59:59.000Z

178

Operating experience with 100% pellet burden on Amanda blast furnace  

SciTech Connect (OSTI)

A number of significant changes in operations at the Ashland Works of the Armco Steel Company occurred in 1992 which directly impacted the Amanda Blast Furnace operation. These changes included the shutdown of the hot strip mill which resulted in coke oven gas enrichment of the Amanda stoves and an increase of 75 C in hot blast temperature, transition to 100% continuous cast operation which resulted in increased variation of the hot metal demand, and the July idling of the sinter plant. Historically, the Amanda Blast Furnace burden was 30% fluxed sinter and 70% acid pellet. It was anticipated that the change to 100% pellet burden would require changes in charging practice and alter furnace performance. The paper gives a general furnace description and then describes the burden characteristics, operating practice with 30% sinter/70% acid pellet burden, preparations for the 100% acid pellet burden operation, the 100% acid pellet operation, and the 100% fluxed pellet burden operation.

Keaton, D.E.; Minakawa, T. (Armco Steel Co., Middletown, OH (United States). Ironmaking Dept.)

1993-01-01T23:59:59.000Z

179

Pellet injectors for the tokamak fusion test reactor  

SciTech Connect (OSTI)

The repeating pneumatic injector is a device from the ORNL development program. A new eight-shot deuterium pellet injector has been designed and constructed specifically for the TFTR application and is scheduled to replace the repeating injector this year. The new device combines a cryogenic extruder and a cold wheel rotary mechanism to form and chamber eight pellets in a batch operation; the eight pellets can then be delivered in any time sequence. Another unique feature of the device is the variable pellet size with three pellets each of 3.0 and 3.5 mm diam and two each of 4.0 mm diam. The experience and technology that have been developed on previous injectors at ORNL have been utilized in the design of this latest pellet injection system.

Combs, S.K.

1986-01-01T23:59:59.000Z

180

Rig designed to study effect of vibration on spent nuclear fuel...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

precipitation and high levels of irradiation-induced damage to cladding and fuel pellets. Each of these HBU phenomena has the potential to impact the mechanical behavior of...

Note: This page contains sample records for the topic "fuel pellet fabrication" 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

Durable zinc ferrite sorbent pellets for hot coal gas desulfurization  

DOE Patents [OSTI]

Durable, porous sulfur sorbents useful in removing hydrogen sulfide from hot coal gas are prepared by water pelletizing a mixture of fine zinc oxide and fine iron oxide with inorganic and organic binders and small amounts of activators such as sodium carbonate and molybdenite; the pellets are dried and then indurated at a high temperature, e.g., 1800.degree. C., for a time sufficient to produce crush-resistant pellets.

Jha, Mahesh C. (Arvada, CO); Blandon, Antonio E. (Thornton, CO); Hepworth, Malcolm T. (Edina, MN)

1988-01-01T23:59:59.000Z

182

SciTech Connect: ABRASION TEST OF THORIA PELLETS  

Office of Scientific and Technical Information (OSTI)

BREEDING; PELLETS; REACTORS; TESTING; THERMAL NEUTRONS; THORIUM; THORIUM OXIDES Word Cloud More Like This Full Text preview image File size NAView Full Text View Full Text DOI:...

183

Assessment of Biomass Pelletization Options for Greensburg, Kansas: Executive Summary  

SciTech Connect (OSTI)

This executive summary provides an overview of an NREL assessment to identify potential opportunities to develop a biomass pelletization or briquetting plant in the region around Greensburg, Kansas.

Haase, S.

2009-11-01T23:59:59.000Z

184

Study of fueling requirements for the Engineering Test Reactor  

SciTech Connect (OSTI)

An assessment of the fueling requirement for the TIBER Engineering Test Reactor is studied. The neutral shielding pellet ablation model with the inclusion of the effects of the alpha particles is used for our study. The high electron temperature in a reactor-grade plasma makes pellet penetration very difficult. The launch length has to be very large (several tens of meters) in order to avoid pellet breakage due to the low inertial strength of DT ''ice.'' The minimum repetition rate corresponding to the largest allowable pellet, is found to be about 1 Hz. A brief survey is done on the various operational and conceptual pellet injection schemes for plasma fueling. The underlying conclusion is that an alternative fueling scheme of coaxial compact-toroid plasma gun is very likely needed for effective central fueling of reactor-grade plasmas. 16 refs.

Ho, S.K.; Perkins, L.J.

1987-10-16T23:59:59.000Z

185

Fabrication and Characterization of Uranium-based High Temperature...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Fabrication and Characterization of Uranium-based High Temperature Reactor Fuel June 01, 2013 The Uranium Fuel Development Laboratory is a modern R&D scale lab for the fabrication...

186

Salmon Carcasses Increase Stream Productivity More than Inorganic Fertilizer Pellets: A Test on Multiple Trophic Levels  

E-Print Network [OSTI]

Salmon Carcasses Increase Stream Productivity More than Inorganic Fertilizer Pellets: A Test experiment, we examined the short-term (6 weeks) comparative effects of artificial nutrient pellets pellet treatment was soluble reactive phosphorus (SRP) concentration. Ammonium-nitrogen concentration

Wagner, Diane

187

absorber pellets: Topics by E-print Network  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

absorber pellets First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 I Investigation of Pellet Acceleration...

188

Fabrication technology for ODS Alloy MA957  

SciTech Connect (OSTI)

A successful fabrication schedule has been developed at Carpenter Technology Corporation for the production of MA957 fuel and blanket cladding. Difficulties with gun drilling, plug drawing and recrystallization were overcome to produce a pilot lot of tubing. This report documents the fabrication efforts of two qualified vendors and the support studies performed at WHC to develop the fabrication-schedule.

ML Hamilton; DS Gelles; RJ Lobsinger; MM Paxton; WF Brown

2000-03-16T23:59:59.000Z

189

Material Fabrication  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Recycling Nuclear fuel recycling technologies could help make use of the valuable energy resource residing inside used fuel rods and minimize the final volume of nuclear waste. To...

190

Pellet Zone Ltd | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data CenterFranconia, Virginia: Energy ResourcesLoading map...(UtilityCounty,OrleansPassadumkeag, Maine:PawneeAS Address:Pelican Utility

191

SRS MOX fuel lead assemblies data report for the surplus plutonium disposition environmental impact statement  

SciTech Connect (OSTI)

The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement. This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. DOE-MD requested that the DOE Site Operations Offices nominate DOE sites that meet established minimum requirements that could produce MOX LAs. Six initial site combinations were proposed: (1) Argonne National Laboratory-West (ANL-W) with support from Idaho National Engineering and Environmental Laboratory (INEEL), (2) Hanford, (3) Los Alamos National Laboratory (LANL) with support from Pantex, (4) Lawrence Livermore National Laboratory (LLNL), (5) Oak Ridge Reservation (ORR), and (6) Savannah River Site(SRS). After further analysis by the sites and DOE-MD, five site combinations were established as possible candidates for producing MOX LAs: (1) ANL-W with support from INEEL, (2) Hanford, (3) LANL, (4) LLNL, and (5) SRS. SRS has proposed an LA MOX fuel fabrication approach that would be done entirely inside an S and S Category 1 area. An alternate approach would allow fabrication of fuel pellets and assembly of fuel rods in an S and S Category 2 or 3 facility with storage of bulk PuO{sub 2} and assembly, storage, and shipping of fuel bundles in an S and S Category 1 facility. The total Category 1 approach, which is the recommended option, would be done in the 221-H Canyon Building. A facility that was never in service will be removed from one area, and a hardened wall will be constructed in another area to accommodate execution of the LA fuel fabrication. The non-Category 1 approach would require removal of process equipment in the FB-Line metal production and packaging glove boxes, which requires work in a contamination area. The Immobilization Hot Demonstration Program equipment in the Savannah River Technology Center would need to be removed to accommodate pellet fabrication. This work would also be in a contaminated area.

O`Connor, D.G.; Fisher, S.E.; Holdaway, R. [and others

1998-08-01T23:59:59.000Z

192

apex nuclear fuel: Topics by E-print Network  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

fuel fabrication, in-core physics and fuel management of uranium, thorium and other fuel types, ... Kazimi, Mujid S. 19 Nuclear Waste Imaging and Spent Fuel Verification by...

193

Fabrication and Pre-irradiation Characterization of a Minor Actinide and Rare Earth Containing Fast Reactor Fuel Experiment for Irradiation in the Advanced Test Reactor  

SciTech Connect (OSTI)

The United States Department of Energy, seeks to develop and demonstrate the technologies needed to transmute the long-lived transuranic actinide isotopes contained in spent nuclear fuel into shorter lived fission products, thereby decreasing the volume of material requiring disposal and reducing the long-term radiotoxicity and heat load of high-level waste sent to a geologic repository. This transmutation of the long lived actinides plutonium, neptunium, americium and curium can be accomplished by first separating them from spent Light Water Reactor fuel using a pyro-metalurgical process, then reprocessing them into new fuel with fresh uranium additions, and then transmuted to short lived nuclides in a liquid metal cooled fast reactor. An important component of the technology is developing actinide-bearing fuel forms containing plutonium, neptunium, americium and curium isotopes that meet the stringent requirements of reactor fuels and materials.

Timothy A. Hyde

2012-06-01T23:59:59.000Z

194

Pellet injection in the RFP (Reversed Field Pinch)  

SciTech Connect (OSTI)

Observation of pellets injected into the ZT-40M Reversed Field Pinch has allowed a new twist on the usual tokamak ablation physics modeling. The RFP provides a strong ohmic heating regime with relatively high electron drift parameter (xi/sub drift/ /approximately/ 0.2), in the presence of a highly sheared magnetic field geometry. In situ photos of the pellet ablation cloud using a grated-intensified CCD camera, as well as two-view integrated photos of the pellet trajectory show substantial modification of the original pellet trajectory, in both direction and speed. Depending on the launch geometry, increases in the initial 500 m/s pellet speed by 50% have been observed, and a ski jump deflector plate in the launch port has been used to counteract strong poloidal curvature. In contrast to the tokamak, the D/sub ..cap alpha../ light signature is strongest near the edge, and weaker in the plasma center. Additional information on ion temperature response to pellet injection with 20 ..mu..sec time resolution has been obtained using a 5-channel neutral particle analyzer (NPA). The energy confinement is transiently degraded while the beta is largely unchanged. This may be indicative of pellet injection into a high-beta plasma operating at fixed beta. 10 refs., 6 figs.

Wurden, G.A.; Weber, P.G.; Munson, C.P.; Cayton, T.E.; Bunting, C.A.; Carolan, P.G.

1988-01-01T23:59:59.000Z

195

Consolidated waste forms: glass marbles and ceramic pellets  

SciTech Connect (OSTI)

Glass marbles and ceramic pellets have been developed at Pacific Northwest Laboratory as part of the multibarrier concept for immobilizing high-level radioactive waste. These consolidated waste forms served as substrates for the application of various inert coatings and as ideal-sized particles for encapsulation in protective matrices. Marble and pellet formulations were based on existing defense wastes at Savannah River Plant and proposed commercial wastes. To produce marbles, glass is poured from a melter in a continuous stream into a marble-making device. Marbles were produced at PNL on a vibratory marble machine at rates as high as 60 kg/h. Other marble-making concepts were also investigated. The marble process, including a lead-encapsulation step, was judged as one of the more feasible processes for immobilizing high-level wastes. To produce ceramic pellets, a series of processing steps are required, which include: spray calcining - to dry liquid wastes to a powder; disc pelletizing - to convert waste powders to spherical pellets; sintering - to densify pellets and cause desired crystal formation. These processing steps are quite complex, and thereby render the ceramic pellet process as one of the least feasible processes for immobilizing high-level wastes.

Treat, R.L.; Rusin, J.M.

1982-05-01T23:59:59.000Z

196

POTENTIAL IMPACT OF INTERFACIAL BONDING EFFICIENCY ON USED NUCLEAR FUEL VIBRATION INTEGRITY DURING NORMAL TRANSPORTATION  

SciTech Connect (OSTI)

Finite element analysis (FEA) was used to investigate the impacts of interfacial bonding efficiency at pellet pellet and pellet clad interfaces on surrogate of used nuclear fuel (UNF) vibration integrity. The FEA simulation results were also validated and benchmarked with reversible bending fatigue test results on surrogate rods consisting of stainless steel (SS) tubes with alumina-pellet inserts. Bending moments (M) are applied to the FEA models to evaluate the system responses of the surrogate rods. From the induced curvature, , the flexural rigidity EI can be estimated as EI=M/ . The impacts of interfacial bonding efficiency include the moment carrying capacity distribution between pellets and clad and cohesion influence on the flexural rigidity of the surrogate rod system. The result also indicates that the immediate consequences of interfacial de-bonding are a load carrying capacity shift from the fuel pellets to the clad and a reduction of the composite rod flexural rigidity. Therefore, the flexural rigidity of the surrogate rod and the bending moment bearing capacity between the clad and fuel pellets are strongly dependent on the efficiency of interfacial bonding at the pellet pellet and pellet clad interfaces. FEA models will be further used to study UNF vibration integrity.

Jiang, Hao [ORNL] [ORNL; Wang, Jy-An John [ORNL] [ORNL; Wang, Hong [ORNL] [ORNL

2014-01-01T23:59:59.000Z

197

Wood and Pellet Heating | Department of Energy  

Energy Savers [EERE]

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankCombustion |Energy UsageAUDITVehiclesTankless or Demand-TypeWelcome toFarm Growth ThroughWomen @

198

Appling County Pellets | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 NoPublic Utilities Address: 160 East 300AlgoilEnergy Information the Army Permit:FilmsSolar TechnologiesAppling

199

Arbuthnott Wood Pellets Ltd | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 NoPublic Utilities Address: 160 East 300AlgoilEnergy Information theDevelopmentAgroindustrial

200

Jmtland County Energy Agency Comfortable use of wood pellets in one-family houses in  

E-Print Network [OSTI]

Jämtland County Energy Agency Sweden 1 Comfortable use of wood pellets in one-family houses-operation with the Swedish Energy Agency, carried through the project "Comfortable use of wood pellets in one-family houses of one-family houses to start using wood pellets and an increase of the use of wood pellets in one

Note: This page contains sample records for the topic "fuel pellet fabrication" 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

Estimating low-density snowshoe hare populations using fecal pellet counts  

E-Print Network [OSTI]

Estimating low-density snowshoe hare populations using fecal pellet counts Dennis L. Murray, James americanus) populations found at high densities can be estimated using fecal pellet densities on rectangular of fecal pellet plots for estimating hare populations by correlating pellet densities with estimated hare

202

Low Velocity Boron Micro-Pellet Injector For Edge And Core Impurity Transport Measurements  

E-Print Network [OSTI]

1 Low Velocity Boron Micro-Pellet Injector For Edge And Core Impurity Transport Measurements H. W, Baltimore, Maryland 21218 Abstract A simple Low Velocity Boron Micro-Pellet Injector has been under High velocity, pneumatic, pellet injection systems are applied routinely for injecting frozen pellets

203

Benchmark of SCALE (SAS2H) isotopic predictions of depletion analyses for San Onofre PWR MOX fuel  

SciTech Connect (OSTI)

The isotopic composition of mixed-oxide (MOX) fuel, fabricated with both uranium and plutonium, after discharge from reactors is of significant interest to the Fissile Materials Disposition Program. The validation of the SCALE (SAS2H) depletion code for use in the prediction of isotopic compositions of MOX fuel, similar to previous validation studies on uranium-only fueled reactors, has corresponding significance. The EEI-Westinghouse Plutonium Recycle Demonstration Program examined the use of MOX fuel in the San Onofre PWR, Unit 1, during cycles 2 and 3. Isotopic analyses of the MOX spent fuel were conducted on 13 actinides and {sup 148}Nd by either mass or alpha spectrometry. Six fuel pellet samples were taken from four different fuel pins of an irradiated MOX assembly. The measured actinide inventories from those samples has been used to benchmark SAS2H for MOX fuel applications. The average percentage differences in the code results compared with the measurement were {minus}0.9% for {sup 235}U and 5.2% for {sup 239}Pu. The differences for most of the isotopes were significantly larger than in the cases for uranium-only fueled reactors. In general, comparisons of code results with alpha spectrometer data had extreme differences, although the differences in the calculations compared with mass spectrometer analyses were not extremely larger than that of uranium-only fueled reactors. This benchmark study should be useful in estimating uncertainties of inventory, criticality and dose calculations of MOX spent fuel.

Hermann, O.W.

2000-02-01T23:59:59.000Z

204

Assessment of Biomass Pelletization Options for Greensburg, Kansas: Executive Summary  

Office of Energy Efficiency and Renewable Energy (EERE)

This executive summary provides an overview of a technical report on an assessment NREL conducted in Greensburg, Kansas, to identify potential opportunities to develop a biomass pelletization or briquetting plant in the region.

205

advanced doped pellet: Topics by E-print Network  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

and Resources Websites Summary: , and K.-V. Weisberg Abstract. Deep penetration of pellets into the JET plasma may prove to be a useful tool for density and profile control. In...

206

Lithium pellet injection into high pressure magnetically confined plasmas  

E-Print Network [OSTI]

The ablation of solid pellets injected into high temperature magnetically confined plasmas is characterized by rapid oscillations in the ablation rate, and the formation of field aligned filaments in the ablatant. High ...

Bse, Brock (Brock Darrel)

2010-01-01T23:59:59.000Z

207

Evaluating the ignition sensitivity of thermal battery heat pellets  

SciTech Connect (OSTI)

Thermal batteries are activated by the ignition of heat pellets. If the heat pellets are not sensitive enough to the ignition stimulus, the thermal battery will not activate, resulting in a dud. Thus, to assure reliable thermal batteries, it is important to demonstrate that the pellets have satisfactory ignition sensitivity by testing a number of specimens. There are a number of statistical methods for evaluating the sensitivity of a device to some stimulus. Generally, these methods are applicable to the situation in which a single test is destructive to the specimen being tested, independent of the outcome of the test. In the case of thermal battery heat pellets, however, tests that result in a nonresponse do not totally degrade the specimen. This peculiarity provides opportunities to efficiently evaluate the ignition sensitivity of heat pellets. In this paper, a simple strategy for evaluating heat pellet ignition sensitivity (including experimental design and data analysis) is described. The relatively good asymptotic and small-sample efficiencies of this strategy are demonstrated.

Thomas, E.V.

1993-09-01T23:59:59.000Z

208

advanced uo2 fuel: Topics by E-print Network  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Last Page Topic Index 1 Determination of Gd concentration profile in UO2-Gd2O3 fuel pellets CERN Preprints Summary: A transversal mapping of the Gd concentration was measured in...

209

Metal Matrix Microencapsulated (M3) fuel neutronics performance in PWRs  

SciTech Connect (OSTI)

Metal Matrix Microencapsulated (M3) fuel consists of TRISO or BISO coated fuel particles directly dispersed in a matrix of zirconium metal to form a solid rod (Fig. 1). In this integral fuel concept the cladding tube and the failure mechanisms associated with it have been eliminated. In this manner pellet-clad-interactions (PCI), thin tube failure due to oxidation and hydriding, and tube pressurization and burst will be absent. M3 fuel, given the high stiffness of the integral rod design, could as well improve grid-to-rod wear behavior. Overall M3 fuel, compared to existing fuel designs, is expected to provide greatly improved operational performance. Multiple barriers to fission product release (ceramic coating layers in the coated fuel particle and te metal matrix) and the high thermal conductivity zirconium alloy metal matrix contribute to the enhancement in fuel behavior. The discontinuous nature of fissile material encapsulated in coated particles provides additional assistance; for instance if the M3 fuel rod is snapped into multiple pieces, only the limited number of fuel particles at the failure cross section are susceptible to release fission products. This is in contrast to the conventional oxide fuel where the presence of a small opening in the cladding provides the pathway for release of the entire inventory of fission products from the fuel rod. While conventional metal fuels (e.g. U-Zr and U-Mo) are typically expected to experience large swelling under irradiation due to the high degree of damage from fission fragments and introduction of fission gas into the lattice, this is not the case for M3 fuels. The fissile portion of the fuel is contained within the coated particle where enough room is available to accommodate fission gases and kernel swelling. The zirconium metal matrix will not be exposed to fission products and its swelling is known to be very limited when exposed solely to neutrons. Under design basis RIA and LOCA, fuel performance will be superior to the conventional oxide fuel since PCMI and rod burst, respectively, have been mitigated. Under beyond design basis accident scenarios where the fuel is exposed to high temperature steam for prolonged periods, larger inventory of zirconium metal in the core could negatively affect the accident progression. A thin steam resistant layer (e.g. alumina forming alloy steel), integrated into the solid rod during fabrication by co-extrusion or hot-isostatic-pressing, offers the potential to provide additional fuel protection from steam interaction: blanketing under a range of boiling regimes and under severe accident conditions up to high temperatures well beyond what is currently possible in the conventional fuel. A crucial aspect to the viability of M3 fuel in light water reactors is the reduced heavy metal load compared to standard pellet fuel. This study evaluated the design requirements to operate a Pressurized Water Reactor (PWR) with M3 fuel in order to obtain fuel cycle length, reactivity coefficients, and power peaking factors comparable to that of standard fuel.

Fratoni, Massimiliano [Pennsylvania State University] [Pennsylvania State University; Terrani, Kurt A [ORNL] [ORNL

2012-01-01T23:59:59.000Z

210

Hanford MOX fuel lead assemblies data report for the surplus plutonium disposition environmental impact statement  

SciTech Connect (OSTI)

The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement. This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. DOE-MD requested that the DOE Site Operations Offices nominate DOE sites that meet established minimum requirements that could produce MOX LAs. Six initial site combinations were proposed: (1) Argonne National Laboratory-West (ANL-W) with support from Idaho National Engineering and Environmental Laboratory (INEEL), (2) Hanford, (3) Los Alamos National Laboratory (LANL) with support from Pantex, (4) Lawrence Livermore National Laboratory (LLNL), (5) Oak Ridge Reservation (ORR), and (6) Savannah River Site (SRS). After further analysis by the sites and DOE-MD, five site combinations were established as possible candidates for producing MOX LAs: (1) ANL-W with support from INEEL, (2) Hanford, (3) LANL, (4) LLNL, and (5) SRS. Hanford has proposed an LA MOX fuel fabrication approach that would be done entirely inside an S and S Category 1 area. An alternate approach would allow fabrication of fuel pellets and assembly of fuel rods in an S and S Category 1 facility. In all, a total of three LA MOX fuel fabrication options were identified by Hanford that could accommodate the program. In every case, only minor modification would be required to ready any of the facilities to accept the equipment necessary to accomplish the LA program.

O`Connor, D.G.; Fisher, S.E.; Holdaway, R. [and others

1998-08-01T23:59:59.000Z

211

Electrically heated ex-reactor pellet-cladding interaction (PCI) simulations utilizing irradiated Zircaloy cladding. [PWR  

SciTech Connect (OSTI)

In a program sponsored by the Fuel Systems Research Branch of the US Nuclear Regulatory Commission, a series of six electrically heated fuel rod simulation tests were conducted at Pacific Northwest Laboratory. The primary objective of these tests was to determine the susceptibility of irradiated pressurized-water reactor (PWR) Zircaloy-4 cladding to failures caused by pellet-cladding mechanical interaction (PCMI). A secondary objective was to acquire kinetic data (e.g., ridge growth or relaxation rates) that might be helpful in the interpretation of in-reactor performance results and/or the modeling of PCMI. No cladding failures attributable to PCMI occurred during the six tests. This report describes the testing methods, testing apparatus, fuel rod diametral strain-measuring device, and test matrix. Test results are presented and discussed.

Barner, J.O.; Fitzsimmons, D.E.

1985-02-01T23:59:59.000Z

212

ACS Division of Fuel Chemistry, 44:4, 1011-1015 (August, 1999). PREDICTING EFFECTIVENESS FACTOR FOR M-TH ORDER AND LANGMUIR RATE  

E-Print Network [OSTI]

ACS Division of Fuel Chemistry, 44:4, 1011-1015 (August, 1999). PREDICTING EFFECTIVENESS FACTOR catalytic pellets and solid fuel particles. The effectiveness factor is defined as the ratio of the reaction catalytic pellet or a solid fuel particle) may be expressed as: d2 C dr2 + 2 r dC dr - r De = 0 (1) where r

Fletcher, Thomas H.

213

LMFBR fuel assembly design for HCDA fuel dispersal  

DOE Patents [OSTI]

A fuel assembly for a liquid metal fast breeder reactor having an upper axial blanket region disposed in a plurality of zones within the fuel assembly. The characterization of a zone is dependent on the height of the axial blanket region with respect to the active fuel region. The net effect of having a plurality of zones is to establish a dispersal flow path for the molten materials resulting during a core meltdown accident. Upward flowing molten material can escape from the core region and/or fuel assembly without solidifying on the surface of fuel rods due to the heat sink represented by blanket region pellets.

Lacko, Robert E. (North Huntingdon, PA); Tilbrook, Roger W. (Monroeville, PA)

1984-01-01T23:59:59.000Z

214

Biomass gasification for liquid fuel production  

SciTech Connect (OSTI)

In our old fix-bed autothermal gasifier we tested wood chips and wood pellets. We make experiments for Czech company producing agro pellets - pellets made from agricultural waste and fastrenewable natural resources. We tested pellets from wheat and rice straw and hay. These materials can be very perspective, because they do?t compete with food production, they were formed in sufficient quantity and in the place of their treatment. New installation is composed of allothermal biomass fixed bed gasifier with conditioning and using produced syngas for Fischer - Tropsch synthesis. As a gasifying agent will be used steam. Gas purification will have two parts - separation of dust particles using a hot filter and dolomite reactor for decomposition of tars. In next steps, gas will be cooled, compressed and removed of sulphur and chlorine compounds and carbon dioxide. This syngas will be used for liquid fuel synthesis.

Najser, Jan, E-mail: jan.najser@vsb.cz, E-mail: vaclav.peer@vsb.cz; Peer, Vclav, E-mail: jan.najser@vsb.cz, E-mail: vaclav.peer@vsb.cz [VSB - Technical university of Ostrava, Energy Research Center, 17. listopadu 15/2172, 708 33 Ostrava-Poruba (Czech Republic); Vantuch, Martin [University of Zilina, Faculty of Mechanical Engineering, Department of Power Engineering, Univerzitna 1, 010 26 Zilina (Slovakia)

2014-08-06T23:59:59.000Z

215

Valve for fuel pin loading system  

DOE Patents [OSTI]

A cyclone valve surrounds a wall opening through which cladding is projected. An axial valve inlet surrounds the cladding. Air is drawn through the inlet by a cyclone stream within the valve. An inflatable seal is included to physically engage a fuel pin subassembly during loading of fuel pellets.

Christiansen, D.W.

1984-01-01T23:59:59.000Z

216

Valve for fuel pin loading system  

DOE Patents [OSTI]

A cyclone valve surrounds a wall opening through which cladding is projected. An axial valve inlet surrounds the cladding. Air is drawn through the inlet by a cyclone stream within the valve. An inflatable seal is included to physically engage a fuel pin subassembly during loading of fuel pellets.

Christiansen, David W. (Kennewick, WA)

1985-01-01T23:59:59.000Z

217

Production, oxygen respiration rates, and sinking velocity of copepod fecal pellets: Direct measurements of ballasting by opal and calcite  

E-Print Network [OSTI]

Production, oxygen respiration rates, and sinking velocity of copepod fecal pellets: Direct of copepod fecal pellets egested by Temora longicornis were measured using a nanoflagellate (Rhodomonas sp pellet production varied between 0.8 pellets ind21 h21 and 3.8 pellets ind21 h21 and was significantly

Matthews, Adrian

218

Coaxial pellets for metallic impurity injection on the large helical device  

SciTech Connect (OSTI)

Two coaxial pellets with tungsten inserted into graphite carbon and polyethylene (PE) tubes are compared for tungsten spectroscopic study in the Large Helical Device. The tungsten pellet with carbon tube causes plasma collapse, while that with PE tube smoothly ablates without collapse. The deposition profile of the pellets is analyzed with a help of pellet ablation spectroscopy. It is found that the tungsten pellet with carbon tube can significantly penetrate into the core plasma and leads to the plasma collapse. A tungsten spectrum with radial profile is successfully observed when the tungsten pellet with PE tube is used.

Huang, X. L., E-mail: huang.xianli@nifs.ac.jp; Zhang, H. M. [Department of Fusion Science, Graduate University for Advanced Studies, Toki 509-5292, Gifu (Japan); Morita, S.; Oishi, T.; Goto, M. [Department of Fusion Science, Graduate University for Advanced Studies, Toki 509-5292, Gifu (Japan); National Institute for Fusion Science, Toki 509-5292, Gifu (Japan)

2014-11-15T23:59:59.000Z

219

Fabrication of CeO2 by sol-gel process based on microfluidic technology as an analog preparation of ceramic nuclear fuel microspheres  

E-Print Network [OSTI]

Microfluidics integrated with sol-gel processes is introduced in preparing monodispersed MOX nuclear fuel microspheres using nonactive cerium as a surrogate for uranium or plutonium. The detailed information about microfluidic devices and sol-gel processes are provided. The effects of viscosity and flow rate of continuous and dispersed phase on size and size distribution of CeO2 microspheres have been investigated. A comprehensive characterization of the CeO2 microspheres has been conducted, including XRD pattern, SEM, density, size and size distribution. The size of prepared monodisperse particles can be controlled precisely in range of 10{\\mu}m to 1000{\\mu}m and the particle CV is below 3%.

Bin Ye; Jilang Miao; Jiaolong Li; Zichen Zhao; Zhenqi Chang; Christophe A. Serra

2012-12-15T23:59:59.000Z

220

Organic binders for iron ore pelletization and steelmaking  

SciTech Connect (OSTI)

Historically, bentonite has been used in the agglomeration process in North American iron ore plants. In 1986, Eveleth Mines replaced bentonite with Peridur, a carboxy methyl cellulose organic binder used in conjunction with 1% limestone. Since May of 1993, Allied Colloids` Alcotac FE8 has been used by Eveleth as the replacement for bentonite. This paper discusses the performance benefits obtained when bentonite was replaced with an organic binder. These totally synthetic binders are used in conjunction with limestone. The benefits of organic binders are: improved metallurgical parameters of the fired pellet, especially the reducibility, which results in more efficient use of gases in the blast furnace; reduced silica in the pellet, in the case of Eveleth Mines this was a reduction of 0.5%, a lower silica pellet reduces slag in the blast furnace; increased production in both the agglomeration/induration and steelmaking processes; and a decrease in coke consumption.

Karkoska, D.; Sankey, E. [Allied Colloids, Suffolk, VA (United States); Anderson, R. [Eveleth Mines, MN (United States)

1995-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "fuel pellet fabrication" 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

Microwave measurement of the mass of frozen hydrogen pellets  

DOE Patents [OSTI]

A nondestructive apparatus and method for measuring the mass of a moving object, based on the perturbation of the dielectric character of a resonant microwave cavity caused by the object passing through the cavity. An oscillator circuit is formed with a resonant cavity in a positive feedback loop of a microwave power amplifier. The moving object perturbs the resonant characteristics of the cavity causing a shift in the operating frequency of the oscillator proportional to the ratio of the pellet volume to the volume of the cavity. Signals from the cavity oscillation are mixed with a local oscillator. Then the IF frequency from the mixer is measured thereby providing a direct measurement of pellet mass based upon known physical properties and relationships. This apparatus and method is particularly adapted for the measurement of frozen hydrogen pellets.

Talanker, Vera (Golden, CO); Greenwald, Martin (Belmont, MA)

1990-01-01T23:59:59.000Z

222

Wall conditioning experiments on TFTR using impurity pellet injection  

SciTech Connect (OSTI)

This work describes experiments intended to optimize the limiter conditioning for TFTR supershots. It is shown that deposition of thin layers of lithium on the limiters by impurity pellet injection changes the plasma-wall interaction and improves supershot performance. Series of up to ten Ohmic plasmas each with two lithium pellets were useful in preconditioning the limiter. Generally, plasma performance increased with the amount of lithium deposited up to the maximal amount which could be deposited. Experiments were performed with different materials being deposited (carbon, boron and lithium) and with different methods of deposition.

Strachan, J.D.; Mansfield, D.K.; Bell, M.G. [and others

1993-11-01T23:59:59.000Z

223

Vacuum Predictions and Measurements for an Internal Pellet Target  

E-Print Network [OSTI]

Measurements with low Z targets at internal experiments typically imply a gas load which deteriorates the ring vacuum. Future experiments need reliable estimates for the expected vacuum conditions in order to design 4-pi detectors closely surrounding the interaction area. We present a method for the calculation of the resulting vacuum of such a complex system using a Pellet Target. In order to test the method, a vacuum system with diagnostic tools has been set up and a Pellet Target was operated under realistic conditions. The results for the absolute vacuum agree within factors of two with the expected pressures.

Lehmann, I; Friden, C J; Norman, G; Ekstrm, C; Johansson, T; Wiedner, U; Lehmann, Inti; Nordhage, Orjan; Friden, Carl-Johan; Norman, Gunar; Ekstrom, Curt; Johansson, Tord; Wiedner, Ulrich

2007-01-01T23:59:59.000Z

224

Vacuum Predictions and Measurements for an Internal Pellet Target  

E-Print Network [OSTI]

Measurements with low Z targets at internal experiments typically imply a gas load which deteriorates the ring vacuum. Future experiments need reliable estimates for the expected vacuum conditions in order to design 4-pi detectors closely surrounding the interaction area. We present a method for the calculation of the resulting vacuum of such a complex system using a Pellet Target. In order to test the method, a vacuum system with diagnostic tools has been set up and a Pellet Target was operated under realistic conditions. The results for the absolute vacuum agree within factors of two with the expected pressures.

Inti Lehmann; Orjan Nordhage; Carl-Johan Friden; Gunar Norman; Curt Ekstrom; Tord Johansson; Ulrich Wiedner

2007-01-04T23:59:59.000Z

225

Durable regenerable sorbent pellets for removal of hydrogen sulfide from coal gas  

DOE Patents [OSTI]

Pellets for removing hydrogen sulfide from a coal gasification stream at an elevated temperature are prepared in durable form usable over repeated cycles of absorption and regeneration. The pellets include a material reactive with hydrogen sulfide, in particular zinc oxide, a binder, and an inert material, in particular calcium sulfate (drierite), having a particle size substantially larger than other components of the pellets. A second inert material and a promoter may also be included. Preparation of the pellets may be carried out by dry, solid-state mixing of components, moistening the mixture, and agglomerating it into pellets, followed by drying and calcining. Pellet size is selected, depending on the type of reaction bed for which the pellets are intended. The use of inert material with a large particle size provides a stable pellet structure with increased porosity, enabling effective gas contact and prolonged mechanical durability.

Siriwardane, Ranjani V. (Morgantown, WV)

1997-01-01T23:59:59.000Z

226

Durable regenerable sorbent pellets for removal of hydrogen sulfide from coal gas  

DOE Patents [OSTI]

Pellets for removing hydrogen sulfide from a coal gasification stream at an elevated temperature are prepared in durable form usable over repeated cycles of absorption and regeneration. The pellets include a material reactive with hydrogen sulfide, in particular zinc oxide, a binder, and an inert material, in particular calcium sulfate (drierite), having a particle size substantially larger than other components of the pellets. A second inert material and a promoter may also be included. Preparation of the pellets may be carried out by dry, solid-state mixing of components, moistening the mixture, and agglomerating it into pellets, followed by drying and calcining. Pellet size is selected, depending on the type of reaction bed for which the pellets are intended. The use of inert material with a large particle size provides a stable pellet structure with increased porosity, enabling effective gas contact and prolonged mechanical durability.

Siriwardane, R.V.

1997-12-30T23:59:59.000Z

227

Fixing and pelleting chromatin/nuclei from extracts onto coverslips for immunofluorescence  

E-Print Network [OSTI]

Fixing and pelleting chromatin/nuclei from extracts onto coverslips for immunofluorescence Arshad. poly-lysine coated coverslips. 4. spin down tubes (or equivalent method to pellet onto coverslips; our

Mitchison, Tim

228

Durable regenerable sorbent pellets for removal of hydrogen sulfide from coal gas  

DOE Patents [OSTI]

Pellets for removing hydrogen sulfide from a coal gasification stream at an elevated temperature are prepared in durable form, usable over repeated cycles of absorption and regeneration. The pellets include a material reactive with hydrogen sulfide, in particular zinc oxide, a binder, and an inert material, in particular calcium sulfate (drierite), having a particle size substantially larger than other components of the pellets. A second inert material and a promoter may also be included. Preparation of the pellets may be carried out by dry, solid-state mixing of components, moistening the mixture, and agglomerating it into pellets, followed by drying and calcining. Pellet size is selected, depending on the type of reaction bed for which the pellets are intended. The use of inert material with a large particle size provides a stable pellet structure with increased porosity, enabling effective gas contact and prolonged mechanical durability.

Siriwardane, R.V.

1999-02-02T23:59:59.000Z

229

2D-Modelling of pellet injection in the poloidal plane: results of numerical tests  

E-Print Network [OSTI]

2D-Modelling of pellet injection in the poloidal plane: results of numerical tests P. Lalousis developed for computing the expansion of pellet-produced clouds in the poloidal plane. The expansion

Paris-Sud XI, Université de

230

Durable regenerable sorbent pellets for removal of hydrogen sulfide coal gas  

DOE Patents [OSTI]

Pellets for removing hydrogen sulfide from a coal gasification stream at an elevated temperature are prepared in durable form, usable over repeated cycles of absorption and regeneration. The pellets include a material reactive with hydrogen sulfide, in particular zinc oxide, a binder, and an inert material, in particular calcium sulfate (drierite), having a particle size substantially larger than other components of the pellets. A second inert material and a promoter may also be included. Preparation of the pellets may be carried out by dry, solid-state mixing of components, moistening the mixture, and agglomerating it into pellets, followed by drying and calcining. Pellet size is selected, depending on the type of reaction bed for which the pellets are intended. The use of inert material with a large particle size provides a stable pellet structure with increased porosity, enabling effective gas contact and prolonged mechanical durability.

Siriwardane, Ranjani V. (Morgantown, WV)

1999-01-01T23:59:59.000Z

231

Woodfuel Usage Update 1 I Wood fuel use in Scotland 2011 I Hudson Consulting I September 2011  

E-Print Network [OSTI]

in forecast demand for wood to be used for pellet production of 140k odt/yr in 2011. 9. The total of wood usage by fuel category 3.3. Pellet plants 3.4. Greenhouse gas emissions 3.5. Projects in planning 4 by 2012 and beyond. The use of recycled fibre is forecast to increase to 40% in 2012. 8. Four wood pellet

232

Assessment of Biomass Pelletization Options for Greensburg, Kansas  

SciTech Connect (OSTI)

This report provides an overview of a technical report on an assessment NREL conducted in Greensburg, Kansas, to identify potential opportunities to develop a biomass pelletization or briquetting plant in the region. See NREL/TP-7A2-45843 for the Executive Summary of this report.

Haase, S.

2010-05-01T23:59:59.000Z

233

Standard specification for nuclear-Grade boron carbide pellets  

E-Print Network [OSTI]

1.1 This specification applies to boron carbide pellets for use as a control material in nuclear reactors. 1.2 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.

American Society for Testing and Materials. Philadelphia

2007-01-01T23:59:59.000Z

234

Method for producing pellets for use in a cryoblasting process  

DOE Patents [OSTI]

A cryoblasting process having a centrifugal accelerator for accelerating frozen pellets of argon or carbon dioxide toward a target area utilizes an accelerator throw wheel designed to induce, during operation, the creation of a low-friction gas bearing within internal passages of the wheel which would otherwise retard acceleration of the pellets as they move through the passages. An associated system and method for removing paint from a surface with cryoblasting techniques involves the treating, such as a preheating, of the painted surface to soften the paint prior to the impacting of frozen pellets thereagainst to increase the rate of paint removal. A system and method for producing large quantities of frozen pellets from a liquid material, such as liquid argon or carbon dioxide, for use in a cryoblasting process utilizes a chamber into which the liquid material is introduced in the form of a jet which disintegrates into droplets. A non-condensible gas, such as inert helium or air, is injected into the chamber at a controlled rate so that the droplets freeze into bodies of relatively high density.

Foster, Christopher A. (Clinton, TN); Fisher, Paul W. (Heiskell, TN)

1997-01-01T23:59:59.000Z

235

Standard Specification for Nuclear Grade Zirconium Oxide Pellets  

E-Print Network [OSTI]

1.1 This specification applies to pellets of stabilized zirconium oxide used in nuclear reactors. 1.2 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.

American Society for Testing and Materials. Philadelphia

2009-01-01T23:59:59.000Z

236

absorber bna pellets: Topics by E-print Network  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

absorber bna pellets First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Reproduced with permission from...

237

Updated 2-13-06 Grass Pelleting The Process  

E-Print Network [OSTI]

is transferred by auger or vacuum system to the hammer mill. A cyclone mounted above the hammer mill separates feeding and fine grinding. Some method of separating any metal or stones from the feedstock prior mesh screen. Ground material again needs to be separated from air prior to pelleting

Pawlowski, Wojtek

238

Cell Fabrication Facility Team Production and Research Activities...  

Broader source: Energy.gov (indexed) [DOE]

Cell Fabrication Facility Team Production and Research Activities 2013 DOE Hydrogen and Fuel Cells Program and Vehicle Technologies Program Annual Merit Review and Peer...

239

Designing fecal pellet surveys for snowshoe hares K.E. Hodges *, L.S. Mills  

E-Print Network [OSTI]

Designing fecal pellet surveys for snowshoe hares K.E. Hodges *, L.S. Mills Wildlife Biology, 2003), some popular indices, like counts of fecal pellets, have been used to answer basic ecological pellets to examine long-term population dynamics at individual sites (Malloy, 2000; Krebs et al., 2001

Mills, L. Scott

240

Comment on Li pellet conditioning in tokamak fusion test reactor R. V. Budny  

E-Print Network [OSTI]

Comment on Li pellet conditioning in tokamak fusion test reactor R. V. Budny Princeton Plasma; published online 9 September 2011) Li pellet conditioning in TFTR results in a reduction of the edge technique for introducing Li is via pellet injection. This was pioneered in ALCATOR- CMOD where it was first

Budny, Robert

Note: This page contains sample records for the topic "fuel pellet fabrication" 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

4June2013 Page 1 of 8 Sodium Hydroxide (Pellets) SOP Standard Operating Procedures  

E-Print Network [OSTI]

4June2013 Page 1 of 8 Sodium Hydroxide (Pellets) SOP Standard Operating Procedures Strong Corrosives ­ Strong Bases (SB) Sodium Hydroxide (Pellets) PrintOH Form: pellets Color: white Melting point/freezing point: 318 °C (604 °F

Cohen, Ronald C.

242

RIS0-M-2294 HANDLING OF DEUTERIUM PELLETS FOR PLASMA REFUELLING  

E-Print Network [OSTI]

RIS0-M-2294 HANDLING OF DEUTERIUM PELLETS FOR PLASMA REFUELLING P.s. Jensen and V. Andersen Association Euratom - Ris0 National Laboratory Abstract. The use of a guide tube technique to inject pellets in pellet-plasma experiments guide tube on the mass and (v ~ 150 m/s) is negligible. jectories

243

BIOLOGICAL CONTROL 2,278-281 (1992) Production of Conidia of Alternaria cassiae with Alginate Pellets  

E-Print Network [OSTI]

Pellets D. J. DAIGLE AND P. J. COTTY Southern Regional Research Center, ARS, USDA, P.O. Box 19687, New yield from pellets. Optimal sporulation resulted from mycelia produced during a 60- to 70-h fermentation in 2.4% dehydrated potato dextrose broth and 14% V-S vegetable juice and en- trapped in pellets

Cotty, Peter J.

244

New data on the characterization of humic substances extracted from phosphatised faecal "pellets" (Tunisia)  

E-Print Network [OSTI]

New data on the characterization of humic substances extracted from phosphatised faecal "pellets, Université Tunis El Manar, 1060, Tunis, Tunisie Humic substances (HS) were extracted from faecal "pellets of the organic matter within the pellets, both from a qualitative and quantitative point of view. The elemental

Paris-Sud XI, Université de

245

Cylindrical Pellet Pose Estimation in Clutter using a Single Robot Mounted Camera  

E-Print Network [OSTI]

Cylindrical Pellet Pose Estimation in Clutter using a Single Robot Mounted Camera Punit Tiwan estimation of cylindrical pellet using a single camera-in-hand configuration of a robot is discussed in this paper. Approaches to estimate pose in both isolated and an occluded environment is discussed. The pellet

Roy, Sumantra Dutta

246

Steady improved confinement in FTU high field plasmas sustained by deep pellet injection  

E-Print Network [OSTI]

Steady improved confinement in FTU high field plasmas sustained by deep pellet injection D to the maximum nominal toroidal field (8 T) by deep multiple pellet injection. These plasmas also feature high to the input power due to particle concentration in the well confined hot core. Deep pellet injection (e

Vlad, Gregorio

247

Monitoring Butterfly Abundance: Beyond Pollard Walks Jero^ me Pellet1,2  

E-Print Network [OSTI]

Monitoring Butterfly Abundance: Beyond Pollard Walks Je´ro^ me Pellet1,2 *, Jason T. Bried3 , David to the characteristics of the species under scrutiny and resources availability. Citation: Pellet J, Bried JT, Parietti D Copyright: ? 2012 Pellet et al. This is an open-access article distributed under the terms of the Creative

Richner, Heinz

248

Effects of corticosterone pellets on baseline and stress-induced corticosterone and corticosteroid-binding-globulin  

E-Print Network [OSTI]

Effects of corticosterone pellets on baseline and stress-induced corticosterone and corticosteroid-degradable corticosterone pellets (implanted under the skin) in elevating plasma corticosterone levels. We monitored to handling in Eurasian kestrel Falco tinnunculus and barn owl Tyto alba nestlings. Corticosterone pellets

Alvarez, Nadir

249

PPPL-3173 -Preprint: May 1996, UC-420, 426 Design and Operation of the Pellet Charge Exchange  

E-Print Network [OSTI]

PPPL-3173 - Preprint: May 1996, UC-420, 426 Design and Operation of the Pellet Charge Exchange-T experiments on TFTR are being measured by active neutral particle analysis using low-Z impurity pellet injection. When injected into a high temperature plasma, an impurity pellet (e.g. Lithium or Boron) rapidly

250

Lithium Pellet Injection Experiments on the Alcator C-Mod Tokamak  

E-Print Network [OSTI]

Lithium Pellet Injection Experiments on the Alcator C-Mod Tokamak by Darren Thomas Garnier A by .. . . .. . . .. . . .. . . .. . . .. . . .. . . .. . . .. . . .. . . .. . . .. . . .. . . .. . . . Prof. George Koster Chairman, Departmental Committee on Graduate Students #12;2 #12;Lithium Pellet in Physics Abstract A pellet enhanced performance (PEP) mode, showing significantly reduced core trans- port

Garnier, Darren T.

251

MHD Effects on Pellet Injection in Tokamaks H.R. Strauss  

E-Print Network [OSTI]

MHD Effects on Pellet Injection in Tokamaks H.R. Strauss Courant Institute of Mathematical Sciences New York University W. Park Princeton Plasma Physics Laboratory Abstract The location at which pellets are injected into a plasma can have a significant effect on what fraction of the pellet mass remains

Strauss, Hank

252

ORIGINAL PAPER Sedimentary pellets as an ice-cover proxy in a High Arctic  

E-Print Network [OSTI]

ORIGINAL PAPER Sedimentary pellets as an ice-cover proxy in a High Arctic ice-covered lake Jessica-cover extent and dynamics on this perennially ice-covered, High Arctic lake. These pellets are interpreted growth. The pellets remain frozen in the ice until a summer or series of summers with reduced ice cover

Vincent, Warwick F.

253

Ultrasonic backscatter coefficient quantitative estimates from Chinese hamster ovary cell pellet biophantoms  

E-Print Network [OSTI]

Ultrasonic backscatter coefficient quantitative estimates from Chinese hamster ovary cell pellet August 2010; accepted 6 August 2010 A cell pellet biophantom technique is introduced, and applied verification purposes. BSC estimates from CHO cell pellet biophantoms of known number density were performed

Illinois at Urbana-Champaign, University of

254

Streamlined LCA of Wood Pellets: Export and Possible Utilization in UBC  

E-Print Network [OSTI]

Streamlined LCA of Wood Pellets: Export and Possible Utilization in UBC Boiler House CHBE 573 Ann Pa May 15, 2009 #12;2 | P a g e INTRODUCTION Wood pellets are a type of biofuels and are often made. Like all biofuels, wood pellets are carbon- neutral and renewable and are very popular in Europe

255

Steady Improved Confinement in FTU High Field Plasmas Sustained by Deep Pellet Injection  

E-Print Network [OSTI]

Steady Improved Confinement in FTU High Field Plasmas Sustained by Deep Pellet Injection D at the maximum nominal toroidal field (8 T), and lower, by deep multiple pellet injection. These plasmas featured due to particle concentration in the well confined hot core. Deep pellet injection in Alcator C high

Vlad, Gregorio

256

Abundance, Composition, and Sinking Rates of Fish Fecal Pellets in the Santa  

E-Print Network [OSTI]

Abundance, Composition, and Sinking Rates of Fish Fecal Pellets in the Santa Barbara Channel Grace.O. Box 1346, Gloucester Point, Virginia 23062, USA. Rapidly sinking fecal pellets are an important composition, particulate organic carbon/nitrogen (POC/PON), and sinking rates of fecal pellets produced

257

ASSESSMENT OF POTENTIAL BIAS WITH SNOWSHOE HARE FECAL PELLET-PLOT COUNTS  

E-Print Network [OSTI]

385 ASSESSMENT OF POTENTIAL BIAS WITH SNOWSHOE HARE FECAL PELLET-PLOT COUNTS DENNIS MURRAY, 1 National Forest, Coeur d'Alene, ID 83815, USA Abstract: The fecal pellet-plot method has been used biases associated with the technique have not been addressed ade- quately. We studied hare pellet

258

Imaging of lithium pellet ablation trails and measurement of g profiles in TFTR  

E-Print Network [OSTI]

Imaging of lithium pellet ablation trails and measurement of g profiles in TFTR J. L. Terry, E. S March 1992) Video images with 2 ps exposures of the Li+ emission in Li pellet ablation clouds have been obtained in a variety of Tokamak Fusion Test Reactor tokamak discharges. The pellet clouds are viewed from

Garnier, Darren T.

259

Status of ORNL/ENEA-Frascati Collaboration on IGNITOR High-Speed Pellet Injector*  

E-Print Network [OSTI]

Status of ORNL/ENEA-Frascati Collaboration on IGNITOR High-Speed Pellet Injector* S. K. Combs, C. R June 15, 2011 #12;2! Background ­ ORNL History with High-Speed Pellet Injection ·Two-stage light gas development ·Accelerated plastic projectiles (4 and 6 mm) up to 5 km/s (single pellets) ·QUICKGUN Algorithm

260

Slug pellet spreading: the double-disc performances available with a single disc spreader  

E-Print Network [OSTI]

1 Slug pellet spreading: the double-disc performances available with a single disc spreader D for slug pellets application. The principal aim of this paper is to show the chosen way to reach spreading pellets 1 Introduction In France, slugs are considered as a harmful destroyer for crops. Their activities

Paris-Sud XI, Université de

Note: This page contains sample records for the topic "fuel pellet fabrication" 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.


261

PELLET COUNT INDICES COMPARED TO MARKRECAPTURE ESTIMATES FOR EVALUATING SNOWSHOE HARE DENSITY  

E-Print Network [OSTI]

PELLET COUNT INDICES COMPARED TO MARK­RECAPTURE ESTIMATES FOR EVALUATING SNOWSHOE HARE DENSITY L in the contiguous United States. Efforts to evalu- ate hare densities using pellets have traditionally been based there was concordance between pellet-based predictions and mark­recapture density estimates of hares. We developed local

262

Chromate transport through columns packed with surfactant-modified zeolite/zero valent iron pellets  

E-Print Network [OSTI]

Chromate transport through columns packed with surfactant-modified zeolite/zero valent iron pellets Chromate transport through columns packed with zeolite/zero valent iron (Z/ZVI) pellets, either untreated originated from chromate sorption onto the HDTMA modified Z/ZVI pellets. Due to dual porosity, the presence

Li, Zhaohui

263

Wood Pellets for UBC Boilers Replacing Natural Gas Based on LCA  

E-Print Network [OSTI]

Wood Pellets for UBC Boilers Replacing Natural Gas Based on LCA Submitted to Dr. Bi By Bernard Chan Pellets for UBC Boilers Replacing Natural Gas" By Bernard Chan, Brian Chan, and Christopher Young Abstract This report studies the feasibility of replacing natural gas with wood pellets for UBC boilers. A gasification

264

Bonded polyimide fuel cell package  

DOE Patents [OSTI]

Described herein are processes for fabricating microfluidic fuel cell systems with embedded components in which micron-scale features are formed by bonding layers of DuPont Kapton.TM. polyimide laminate. A microfluidic fuel cell system fabricated using this process is also described.

Morse, Jeffrey D.; Jankowski, Alan; Graff, Robert T.; Bettencourt, Kerry

2010-06-08T23:59:59.000Z

265

RIS-M-2245 A LIGHT-GAS GUN FOR ACCELERATION OF PELLETS OF SOLID D2  

E-Print Network [OSTI]

RIS?-M-2245 A LIGHT-GAS GUN FOR ACCELERATION OF PELLETS OF SOLID D2 A. Nordskov, H. Skovgård, H designed and built to be used for in- jecting solid D2 pellets into a small tokamak for pellet-plasma interaction studies. The pellets are formed and accelerated at temperatures close to those of liquid helium

266

Polymorphous computing fabric  

DOE Patents [OSTI]

Fabric-based computing systems and methods are disclosed. A fabric-based computing system can include a polymorphous computing fabric that can be customized on a per application basis and a host processor in communication with said polymorphous computing fabric. The polymorphous computing fabric includes a cellular architecture that can be highly parameterized to enable a customized synthesis of fabric instances for a variety of enhanced application performances thereof. A global memory concept can also be included that provides the host processor random access to all variables and instructions associated with the polymorphous computing fabric.

Wolinski, Christophe Czeslaw (Los Alamos, NM); Gokhale, Maya B. (Los Alamos, NM); McCabe, Kevin Peter (Los Alamos, NM)

2011-01-18T23:59:59.000Z

267

Model of U3Si2 Fuel System using BISON Fuel Code  

SciTech Connect (OSTI)

This research considers the proposed advanced fuel system: U3Si2 combined with an advanced cladding. U3Si2 has a number of advantageous thermophysical properties, which motivate its use as an accident tolerant fuel. This preliminary model evaluates the behavior of U3Si2 using available thermophysical data to predict the cladding-fuel pellet temperature and stress using the fuel performance code: BISON. The preliminary results obtained from the U3Si2 fuel model describe the mechanism of Pellet-Clad Mechanical Interaction for this system while more extensive testing including creep testing of U3Si2 is planned for improved understanding of thermophysical properties for predicting fuel performance.

K. E. Metzger; T. W. Knight; R. L. Williamson

2014-04-01T23:59:59.000Z

268

On the possibility of using uranium-beryllium oxide fuel in a VVER reactor  

SciTech Connect (OSTI)

The possibility of using UO{sub 2}-BeO fuel in a VVER reactor is considered with allowance for the thermophysical properties of this fuel. Neutron characteristics of VVER fuel assemblies with UO{sub 2}-BeO fuel pellets are estimated.

Kovalishin, A. A.; Prosyolkov, V. N.; Sidorenko, V. D. [National Research Center Kurchatov Institute (Russian Federation); Stogov, Yu. V., E-mail: YVStogov@mephi.ru [National Research Nuclear University MEPhI (Russian Federation)

2014-12-15T23:59:59.000Z

269

Pellet fuelling of plasmas with ELM mitigation by resonant magnetic perturbations in MAST  

E-Print Network [OSTI]

Shallow fuelling pellets are injected from the high field side into plasmas in which ELMs have been mitigated using external magnetic perturbation coils. The data are compared with ideal assumptions in the ITER fuelling model, namely that mitigated ELMs are not affected by fuelling pellets. Firstly it is shown that during the pellet evaporation an ELM is triggered, during which the amount particle loss could be larger (factor ~1.5) than the particle loss during an ELM which was not induced by pellet. Secondly, a favourable example is shown in which post-pellet particle losses due to mitigated ELMs are similar to the non-pellet case, however unfavourable counter-examples also exist.

Valovic, M; Garzotti, L; Gurl, C; Kirk, A; Naylor, G; Patel, A; Scannell, R; Thornton, A J

2013-01-01T23:59:59.000Z

270

Energy Input and Quality of Pellets Made from Steam-Exploded Douglas Fir (Pseudotsuga menziesii)  

SciTech Connect (OSTI)

Ground softwood Douglas fir (Pseudotsuga menziesii) was treated with pressurized saturated steam at 200-220 C (1.6-2.4 MPa) for 5-10 min in a sealed container. The contents of the container were released to the atmosphere for a sudden decompression. The steam-exploded wood particles were dried to 10% moisture content and pelletized in a single-piston-cylinder system. The pellets were characterized for their mechanical strength, chemical composition, and moisture sorption. The steamtreated wood required 12-81% more energy to compact into pellets than the untreated wood. Pellets made from steam-treated wood had a breaking strength 1.4-3.3 times the strength of pellets made from untreated wood. Steam-treated pellets had a reduced equilibrium moisture content of 2-4% and a reduced expansion after pelletization. There was a slight increase in the high heating value from 18.94 to 20.09 MJ/kg for the treated samples. Steam-treated pellets exhibited a higher lengthwise rigidity compared to untreated pellets.

Sokhansanj, Shahabaddine [ORNL; Bi, X.T. [University of British Columbia, Vancouver; Lim, C. Jim [University of British Columbia, Vancouver; Melin, Staffan [University of British Columbia, Vancouver

2011-01-01T23:59:59.000Z

271

MJG:TTM, 3/01 Plasma Fueling Program FIRE Fueling and Pumping Design  

E-Print Network [OSTI]

DRIVE (3X) D-T LIQUIFIER SCREW EXTRUDER HEAT SHIELD BARREL GUARD VACUUM GUN BLOCK PELLET CUTTER FAST 80 K 20 K SINGLE- STAGE CRYO- COOLER 2-STAGE CRYO- COOLER D-T FEED VACUUM PROPELLANT GAS EXTRUDER/DIII-D injector ·Employing new cryocooler and continuous extruder technology #12;PWF:6/6/01 Review Plasma Fueling

272

Contextualizing urban mobile fabrics  

E-Print Network [OSTI]

This thesis is focus on the urban fabric issues. To be more specific, I will focus on the "Mobile Fabrics" within the larger Asian urban context. Instead of working with a specific geographical site; I will focus on the ...

Lin, Michael Chia-Liang

2007-01-01T23:59:59.000Z

273

Verktyg fr lnsamhetsberkningar vid brnslekonvertering av spetslastpannor frn olja till pellets; Tool for estimating the profitability of converting a peak-load oil-fired boiler to pellets.  

E-Print Network [OSTI]

?? This report summarizes the development of a calculation program estimating the profitability of converting a peak-load oil-fired boiler to pellets. To convert an oil-fired (more)

Sorby, Jonathan

2013-01-01T23:59:59.000Z

274

Advanced Ultrasonic Inspection Techniques for General Purpose Heat Source Fueled Clad Closure Welds  

SciTech Connect (OSTI)

A radioisotope thermoelectric generator is used to provide a power source for long-term deep space missions. This General Purpose Heat Source (GPHS) is fabricated using iridium clad vent sets to contain the plutonium oxide fuel pellets. Integrity of the closure weld is essential to ensure containment of the plutonium. The Oak Ridge Y-12 Plant took the lead role in developing the ultrasonic inspection for the closure weld and transferring the inspection to Los Alamos National Laboratory for use in fueled clad inspection for the Cassini mission. Initially only amplitude and time-of-flight data were recorded. However, a number of benign geometric conditions produced signals that were larger than the acceptance threshold. To identify these conditions, a B-scan inspection was developed that acquired full ultrasonic waveforms. Using a test protocol the B-scan inspection was able to identify benign conditions such as weld shield fusion and internal mismatch. Tangential radiography was used to confirm the ultrasonic results. All but two of 29 fueled clads for which ultrasonic B-scan data was evaluated appeared to have signals that could be attributed to benign geometric conditions. This report describes the ultrasonic inspection developed at Y-12 for the Cassini mission.

Moyer, M.W.

2001-01-11T23:59:59.000Z

275

Fuel cycles for the 80's  

SciTech Connect (OSTI)

Papers presented at the American Nuclear Society's topical meeting on the fuel cycle are summarized. Present progress and goals in the areas of fuel fabrication, fuel reprocessing, spent fuel storage, accountability, and safeguards are reported. Present governmental policies which affect the fuel cycle are also discussed. Individual presentations are processed for inclusion in the Energy Data Base.(DMC)

Not Available

1980-01-01T23:59:59.000Z

276

Reduction of iron-oxide-carbon composites: part III. Shrinkage of composite pellets during reduction  

SciTech Connect (OSTI)

This article involves the evaluation of the volume change of iron-oxide-carbon composite pellets and its implications on reduction kinetics under conditions prevalent in a rotary hearth furnace (RHF) that were simulated in the laboratory. The pellets, in general, were found to shrink considerably during the reduction due to the loss of carbon and oxygen from the system, sintering of the iron-oxide, and formation of a molten slag phase at localized regions inside the pellets due to the presence of binder and coal/wood-charcoal ash at the reduction temperatures. One of the shortcomings of the RHF ironmaking process has been the inability to use multiple layers of composite pellets because of the impediment in heat transport to the lower layers of a multilayer bed. However, pellet shrinkage was found to have a strong effect on the reduction kinetics by virtue of enhancing the external heat transport to the lower layers. The volume change of the different kinds of composite pellets was studied as a function of reduction temperature and time. The estimation of the change in the amount of external heat transport with varying pellet sizes for a particular layer of a multilayer bed was obtained by conducting heat-transfer tests using inert low-carbon steel spheres. It was found that if the pellets of the top layer of the bed shrink by 30 pct, the external heat transfer to the second layer increases by nearly 6 times.

Halder, S.; Fruehan, R.J. [Praxair Inc., Tonawanda, NY (United States). Praxair Technological Center

2008-12-15T23:59:59.000Z

277

And how to use owl pellets to do it. By the standards of paleontology, Rebecca  

E-Print Network [OSTI]

And how to use owl pellets to do it. By the standards of paleontology, Rebecca Terry, PhD'08 drop their bones on the cave floor or (in the case of owls) ex- pel them in the form of pellets

Collar, Juan I.

278

Fuel Source Isotopic Tailoring Impact on ITER Design, Operation and Safety  

E-Print Network [OSTI]

1 Fuel Source Isotopic Tailoring and Its Impact on ITER Design, Operation and Safety M. J. Gouge, W. The isotopic tailoring concept consists of utilizing a tritium-rich pellet source for core fueling and a deuterium- rich gas source for edge fueling. Because of the improved particle confinement associated

279

Soil and Water Science Department University of Florida Environmental impacts of lead pellets at shooting ranges and arsenical herbicides  

E-Print Network [OSTI]

Soil and Water Science Department University of Florida Environmental impacts of lead pellets 4/1999-3/2002 Objectives: · Evaluate the environmental impacts of lead pellets at shooting ranges

Ma, Lena

280

Standard test method for carbon (total) in uranium oxide powders and pellets by direct combustion-infrared detection method  

E-Print Network [OSTI]

Standard test method for carbon (total) in uranium oxide powders and pellets by direct combustion-infrared detection method

American Society for Testing and Materials. Philadelphia

2009-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "fuel pellet fabrication" 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

Plasma Fueling, Pumping, and Tritium Handling Considerations for FIRE  

SciTech Connect (OSTI)

Tritium pellet injection will be utilized on the Fusion Ignition Research Experiment (FIRE) for efficient tritium fueling and to optimize the density profile for high fusion power. Conventional pneumatic pellet injectors, coupled with a guidetube system to launch pellets into the plasma from the high, field side, low field side, and vertically, will be provided for fueling along with gas puffing for plasma edge density control. About 0.1 g of tritium must be injected during each 10-s pulse. The tritium and deuterium will be exhausted into the divertor. The double null divertor will have 16 cryogenic pumps located near the divertor chamber to provide the required high pumping speed of 200 torr-L/s.

Fisher, P.W.; Foster, C.A.; Gentile, C.A.; Gouge, M.J.; Nelson, B.E.

1999-11-13T23:59:59.000Z

282

R. E. Estell, E. L. Fredrickson, D. M. Anderson and M. D. Remmenga mixtures on alfalfa pellet intake by lambs  

E-Print Network [OSTI]

R. E. Estell, E. L. Fredrickson, D. M. Anderson and M. D. Remmenga mixtures on alfalfa pellet and sesquiterpene mixtures on alfalfa pellet intake by lambs1 R. E. Estell,*2 E. L. Fredrickson,* D. M. Anderson. Four experiments were conducted to determine the effects of terpenes on intake of alfalfa pellets

283

CHOPPING VERSUS GRINDING AND PELLETING OF HAY : EFFECT ON AVAILABILITY OF TRACE ELEMENTS (Cu, Zn and Mn)  

E-Print Network [OSTI]

CHOPPING VERSUS GRINDING AND PELLETING OF HAY : EFFECT ON AVAILABILITY OF TRACE ELEMENTS (Cu, Zn often receive ground diets that may or may not be pelleted. We intended to examine the effect of transit) chopped into pieces 3 cm long, or ground in a grinder equipped with a 0.6 mm sieve and pelleted in 6 mm

Boyer, Edmond

284

HIGH-FIELD-SIDE PELLET INJECTION TECHNOLOGY S. K. Combs, L. R. Baylor, C. R. Foust, M. J. Gouge,  

E-Print Network [OSTI]

HIGH-FIELD-SIDE PELLET INJECTION TECHNOLOGY S. K. Combs, L. R. Baylor, C. R. Foust, M. J. Gouge, T of pellets, composed of frozen hydrogen isotopes and multimillimeter in size, is com- monly used for core tubes have typically been used to trans- port/deliver pellets from the acceleration device to the out

285

Pulsed laser evaporation of boron/carbon pellets: Infrared spectra and quantum chemical structures and frequencies for BCp  

E-Print Network [OSTI]

Pulsed laser evaporation of boron/carbon pellets: Infrared spectra and quantum chemical structures March 1993) Pulsed laser evaporation of pellets pressed from boron and graphite powder gave a new 1 decreased with increasing B/C ratio in the pellet and with increasing laser power. Augmented coupled cluster

Martin, Jan M.L.

286

Fabricating solid carbon porous electrodes from powders  

DOE Patents [OSTI]

Fabrication of conductive solid porous carbon electrodes for use in batteries, double layer capacitors, fuel cells, capacitive dionization, and waste treatment. Electrodes fabricated from low surface area (<50 m.sup.2 /gm) graphite and cokes exhibit excellent reversible lithium intercalation characteristics, making them ideal for use as anodes in high voltage lithium insertion (lithium-ion) batteries. Electrodes having a higher surface area, fabricated from powdered carbon blacks, such as carbon aerogel powder, carbon aerogel microspheres, activated carbons, etc. yield high conductivity carbon compositives with excellent double layer capacity, and can be used in double layer capacitors, or for capacitive deionization and/or waste treatment of liquid streams. By adding metallic catalysts to be high surface area carbons, fuel cell electrodes can be produced.

Kaschmitter, James L. (Pleasanton, CA); Tran, Tri D. (Livermore, CA); Feikert, John H. (Livermore, CA); Mayer, Steven T. (San Leandro, CA)

1997-01-01T23:59:59.000Z

287

Fabricating solid carbon porous electrodes from powders  

DOE Patents [OSTI]

Fabrication is described for conductive solid porous carbon electrodes for use in batteries, double layer capacitors, fuel cells, capacitive deionization, and waste treatment. Electrodes fabricated from low surface area (<50 m{sup 2}/gm) graphite and cokes exhibit excellent reversible lithium intercalation characteristics, making them ideal for use as anodes in high voltage lithium insertion (lithium-ion) batteries. Electrodes having a higher surface area, fabricated from powdered carbon blacks, such as carbon aerogel powder, carbon aerogel microspheres, activated carbons, etc. yield high conductivity carbon composites with excellent double layer capacity, and can be used in double layer capacitors, or for capacitive deionization and/or waste treatment of liquid streams. By adding metallic catalysts to high surface area carbons, fuel cell electrodes can be produced. 1 fig.

Kaschmitter, J.L.; Tran, T.D.; Feikert, J.H.; Mayer, S.T.

1997-06-10T23:59:59.000Z

288

Novel carbon-ion fuel cells. Second quarter 1995 technical progress report, April 1995--June 1995  

SciTech Connect (OSTI)

Research continued on carbon-ion fuel cells. This period, the project is proceeding with the construction of an apparatus to create a solid electrolyte in the form of castings, or highly pressed and sintered pellets of CeC{sub 2} and LaC{sub 2} and to test the castings or pellets for the ionic conduction of carbon-ions across the electrolyte.

LaViers, H.

1995-06-30T23:59:59.000Z

289

Prototype Development of Remote Operated Hot Uniaxial Press (ROHUP) to Fabricate Advanced Tc-99 Bearing Ceramic Waste Forms - 13381  

SciTech Connect (OSTI)

The objective of this senior student project is to design and build a prototype construction of a machine that simultaneously provides the proper pressure and temperature parameters to sinter ceramic powders in-situ to create pellets of rather high densities of above 90% (theoretical). This ROHUP (Remote Operated Hot Uniaxial Press) device is designed specifically to fabricate advanced ceramic Tc-99 bearing waste forms and therefore radiological barriers have been included in the system. The HUP features electronic control and feedback systems to set and monitor pressure, load, and temperature parameters. This device operates wirelessly via portable computer using Bluetooth{sup R} technology. The HUP device is designed to fit in a standard atmosphere controlled glove box to further allow sintering under inert conditions (e.g. under Ar, He, N{sub 2}). This will further allow utilizing this HUP for other potential applications, including radioactive samples, novel ceramic waste forms, advanced oxide fuels, air-sensitive samples, metallic systems, advanced powder metallurgy, diffusion experiments and more. (authors)

Alaniz, Ariana J.; Delgado, Luc R.; Werbick, Brett M. [University of Nevada - Las Vegas, Howard R. Hughes College of Engineering, 4505 S. Maryland Parkway, Box 454009, Las Vegas, NV 89154-4009 (United States)] [University of Nevada - Las Vegas, Howard R. Hughes College of Engineering, 4505 S. Maryland Parkway, Box 454009, Las Vegas, NV 89154-4009 (United States); Hartmann, Thomas [University of Nevada - Las Vegas, Harry Reid Canter, 4505 S. Maryland Parkway, Box 454009, Las Vegas, NV 89154-4009 (United States)] [University of Nevada - Las Vegas, Harry Reid Canter, 4505 S. Maryland Parkway, Box 454009, Las Vegas, NV 89154-4009 (United States)

2013-07-01T23:59:59.000Z

290

An evaluation of alternate production methods for Pu-238 general purpose heat source pellets  

SciTech Connect (OSTI)

For the past half century, the National Aeronautics and Space Administration (NASA) has used Radioisotope Thermoelectric Generators (RTG) to power deep space satellites. Fabricating heat sources for RTGs, specifically General Purpose Heat Sources (GPHSs), has remained essentially unchanged since their development in the 1970s. Meanwhile, 30 years of technological advancements have been made in the applicable fields of chemistry, manufacturing and control systems. This paper evaluates alternative processes that could be used to produce Pu 238 fueled heat sources. Specifically, this paper discusses the production of the plutonium-oxide granules, which are the input stream to the ceramic pressing and sintering processes. Alternate chemical processes are compared to current methods to determine if alternative fabrication processes could reduce the hazards, especially the production of respirable fines, while producing an equivalent GPHS product.

Mark Borland; Steve Frank

2009-06-01T23:59:59.000Z

291

Emissions Resulting from the Full-Scale Cofiring of Pelletized Refuse-Derived Fuel and Coal  

E-Print Network [OSTI]

grab and fly ash) 8 (combustion MM5 chamber) 9 & 10 (flue gases) MM5 11 Continuous dRDF/coal blend Ultimate analysis Proximate analysis Heating value Bulk density 13 trace metals Organics (PCBs, polyaromatic hydrocarbons, dioxins, furans... Opacity Feedstock flow rate Steam flow rate, temperature, and pressure Ambient temperature Pollution control equipment temperature and pressure Gases (CO, CO 2 O 2 , NO SOx) x TABLE 4 EP Tozicity Test Analysis of Bottom Ash and Fly Ash...

Ohlsson, O. O.; Daugherty, K.; Venables, B.

292

Status of Transuranic Bearing Metallic Fuel Development  

SciTech Connect (OSTI)

This paper summarizes the status of the metallic fuel development under the Advanced Fuel Cycle Initiative (AFCI). The metallic fuel development program includes fuel fabrication, characterization, advanced cladding research, irradiation testing and post-irradiation examination (PIE). The focus of this paper is on the recent irradiation experiments conducted in the Advanced Test Reactor and some PIE results from these tests.

Steve Hayes; Bruce Hilton; Heather MacLean; Debbie Utterbeck; Jon Carmack; Kemal Pasamehmetoglu

2009-09-01T23:59:59.000Z

293

Liquid Metal Bond for Improved Heat Transfer in LWR Fuel Rods  

SciTech Connect (OSTI)

A liquid metal (LM) consisting of 1/3 weight fraction each of Pb, Sn, and Bi has been proposed as the bonding substance in the pellet-cladding gap in place of He. The LM bond eliminates the large AT over the pre-closure gap which is characteristic of helium-bonded fuel elements. Because the LM does not wet either UO2 or Zircaloy, simply loading fuel pellets into a cladding tube containing LM at atmospheric pressure leaves unfilled regions (voids) in the bond. The HEATING 7.3 heat transfer code indicates that these void spaces lead to local fuel hot spots.

Donald Olander

2005-08-24T23:59:59.000Z

294

Influence of the physical form of the feed on the performance of bacon pigs. 1. Comparison between dry meal, soup and pellets.  

E-Print Network [OSTI]

dry meal, soup and pellets. 2. Technical and economical influence P. QUEMERE J. CASTAING J, a soup (2.5-3 1 per kg diet), or as pellets (dry pellets in trials 2 and 3). During the growing period, pellets improved the daily mean gain in all trials compared to dry meal or soup : on an average the daily

Boyer, Edmond

295

of dehydrated pelleted hay transit through the digestive tract. Nevertheless, this increase in calcium urinary and faecal excretion may be responsible for the bone deformation observed in  

E-Print Network [OSTI]

of dehydrated pelleted hay transit through the digestive tract. Nevertheless, this increase dehydrated pelleted hay during a long time. In lambs fed dchydrated pelleted rye-grass hay, the daily urinary was not observ- ed in lambs fed dehydrated pelleted lucerne hay. Thus, the calcium content of the hay seems

Paris-Sud XI, Université de

296

Effect of FeO-content and potentials for quality improvements of iron ore pellets  

SciTech Connect (OSTI)

The FeO-content strongly influences the physical and metallurgical properties of iron ore pellets. A wide range of FeO-contents within the pellet deliveries to the Germany market is evaluated. Investigations include the effect of pellet size. The paper concludes potentials for quality improvement of iron ore pellets. Most of the German blast furnaces are operated with high injection rates either of oil or of coal resulting in a decrease of coke consumption down to a level of about 300 kg/t hot metal. As the retention time of the burden increases, blast furnace operators demand higher quality burden material, basically with respect to strength before and during reduction.

Kortmann, H.A.; Mertins, E.; Ritz, V.J. [Studiengesellschaft fuer Eisenerzaufbereitung, Liebenburg-Othfresen (Germany)

1995-12-01T23:59:59.000Z

297

Residential Bulk-Fed Wood-Pellet Central Boilers and Furnace Rebate Program  

Broader source: Energy.gov [DOE]

The New Hampshire Public Utilities Commission (PUC) is offering rebates of 30% of the installed cost of qualifying new residential bulk-fed, wood-pellet central heating boilers or furnaces. The...

298

Standard test methods for analysis of sintered gadolinium oxide-uranium dioxide pellets  

E-Print Network [OSTI]

1.1 These test methods cover procedures for the analysis of sintered gadolinium oxide-uranium dioxide pellets to determine compliance with specifications. 1.2 The analytical procedures appear in the following order: Section Carbon (Total) by Direct CombustionThermal Conductivity Method C1408 Test Method for Carbon (Total) in Uranium Oxide Powders and Pellets By Direct Combustion-Infrared Detection Method Chlorine and Fluorine by Pyrohydrolysis Ion-Selective Electrode Method C1502 Test Method for Determination of Total Chlorine and Fluorine in Uranium Dioxide and Gadolinium Oxide Gadolinia Content by Energy-Dispersive X-Ray Spectrometry C1456 Test Method for Determination of Uranium or Gadolinium, or Both, in Gadolinium Oxide-Uranium Oxide Pellets or by X-Ray Fluorescence (XRF) Hydrogen by Inert Gas Fusion C1457 Test Method for Determination of Total Hydrogen Content of Uranium Oxide Powders and Pellets by Carrier Gas Extraction Isotopic Uranium Composition by Multiple-Filament Surface-Ioni...

American Society for Testing and Materials. Philadelphia

2006-01-01T23:59:59.000Z

299

New polymorphous computing fabric.  

SciTech Connect (OSTI)

This paper introduces a new polymorphous computing Fabric well suited to DSP and Image Processing and describes its implementation on a Configurable System on a Chip (CSOC). The architecture is highly parameterized and enables customization of the synthesized Fabric to achieve high performance for a specific class of application. For this reason it can be considered to be a generic model for hardware accelerator synthesis from a high level specification. Another important innovation is the Fabric uses a global memory concept, which gives the host processor random access to all the variables and instructions on the Fabric. The Fabric supports different computing models including MIMD, SPMD and systolic flow and permits dynamic reconfiguration. We present a specific implementation of a bank of FIR filters on a Fabric composed of 52 cells on the Altera Excalibur ARM running at 33 MHz. The theoretical performance of this Fabric is 1.8 GMACh. For the FIR application we obtain 1.6 GMAC/s real performance. Some automatic tools have been developed like the tool to provide a host access utility and assembler.

Wolinski, C. (Christophe); Gokhale, M. (Maya); McCabe, K. P. (Kevin P.)

2002-01-01T23:59:59.000Z

300

Microsoft Word - ICP-10-010webpost.doc  

Broader source: Energy.gov (indexed) [DOE]

of 64 drums of unirradiated fabricated single rods consisting of U0 2 ThO 2 fuel pellets in zirconium rods and one drum with two short rods and miscellaneous bagged pellets....

Note: This page contains sample records for the topic "fuel pellet fabrication" 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.


301

Licensed fuel facility status report  

SciTech Connect (OSTI)

NRC is committed to the periodic publication of licensed fuel facilities inventory difference data, following agency review of the information and completion of any related NRC investigations. Information in this report includes inventory difference data for active fuel fabrication facilities possessing more than one effective kilogram of high enriched uranium, low enriched uranium, plutonium, or uranium-233.

Joy, D.; Brown, C.

1993-04-01T23:59:59.000Z

302

New composite separator pellet to increase power density and reduce size of thermal batteries.  

SciTech Connect (OSTI)

We show that it is possible to manufacture strong macroporous ceramic films that can be backfilled with electrolyte to form rigid separator pellets suitable for use in thermal batteries. Several new ceramic manufacturing processes are developed to produce sintered magnesium oxide foams with connected porosities of over 80% by volume and with sufficient strength to withstand the battery manufacturing steps. The effects of processing parameters are quantified, and methods to imbibe electrolyte into the ceramic scaffold demonstrated. Preliminary single cell battery testing show that some of our first generation pellets exhibit longer voltage life with comparable resistance at the critical early times to that exhibited by a traditional pressed pellets. Although more development work is needed to optimize the processes to create these rigid separator pellets, the results indicate the potential of such ceramic separator pellets to be equal, if not superior to, current pressed pellets. Furthermore, they could be a replacement for critical material that is no longer available, as well as improving battery separator strength, decreasing production costs, and leading to shorter battery stacks for long-life batteries.

Mondy, Lisa Ann; Roberts, Christine Cardinal; Grillet, Anne Mary; Soehnel, Melissa Marie; Barringer, David Alan; DiAntonio, Christopher Brian; Chavez, Thomas P.; Ingersoll, David T.; Hughes, Lindsey Gloe; Evans, Lindsey R.; Fitchett, Stephanie

2013-11-01T23:59:59.000Z

303

Effect of pelleting on the recalcitrance and bioconversion of dilute-acid pretreated corn stover  

SciTech Connect (OSTI)

Background: Knowledge regarding the performance of densified biomass in biochemical processes is limited. The effects of densification on biochemical conversion are explored here. Methods: Pelleted corn stover samples were generated from bales that were milled to 6.35 mm. Low-solids acid pretreatment and simultaneous saccharification and fermentation were performed to evaluate pretreatment efficacy and ethanol yields achieved for pelleted and ground stover (6.35 mm and 2 mm) samples. Both pelleted and 6.35-mm ground stover were evaluated using a ZipperClave reactor under high-solids, process-relevant conditions for multiple pretreatment severities (Ro), followed by enzymatic hydrolysis of the washed, pretreated solids. Results: Monomeric xylose yields were significantly higher for pellets (approximately 60%) than for ground formats (approximately 38%). Pellets achieved approximately 84% of theoretical ethanol yield (TEY); ground stover formats had similar profiles, reaching approximately 68% TEY. Pelleting corn stover was not detrimental to pretreatment efficacy for both low- and high-solids conditions, and even enhanced ethanol yields.

Allison E Ray; Amber Hoover; Gary Gresham

2012-07-01T23:59:59.000Z

304

Fuel loading of PeBR for a long operation life on the lunar surface  

SciTech Connect (OSTI)

The Pellet Bed Reactor (PeBR) power system could provide 99.3 kW e to a lunar outpost for 66 full power years and is designed for no single point failures. The core of this fast energy spectrum reactor consists of three sectors that are neutronically and thermally coupled, but hydraulically independent. Each sector has a separate Closed Brayton Cycle (CBC) loop for energy conversion and separate water heat-pipes radiator panels for heat rejection. He-Xe (40 g/mole) binary gas mixture serves as the reactor coolant and CBC working fluid. On the lunar surface, the emplaced PeBR below grade is loaded with spherical fuel pellets (1-cm in dia.). It is launched unfueled and the pellets are launched in separate subcritical canisters, one for each core sector. This paper numerically simulates the transient loading of a core sector with fuel pellets on the Moon. The simulation accounts for the dynamic interaction of the pellets during loading and calculates the axial and radial distributions of the volume porosity in the sector. The pellets pack randomly with a volume porosity of 0.39 - 0.41 throughout most of the sector, except near the walls the local porosity is higher. (authors)

Schriener, T. M. [Inst. for Space and Nuclear Power Studies, Univ. of New Mexico, Albuquerque, NM (United States); Chemical and Nuclear Engineering Dept., Univ. of New Mexico, Albuquerque, NM (United States); El-Genk, M. S. [Inst. for Space and Nuclear Power Studies, Univ. of New Mexico, Albuquerque, NM (United States); Chemical and Nuclear Engineering Dept., Univ. of New Mexico, Albuquerque, NM (United States); Mechanical Engineering Dept., Univ. of New Mexico, Albuquerque, NM (United States)

2012-07-01T23:59:59.000Z

305

Biologically inspired digital fabrication  

E-Print Network [OSTI]

Objects and systems in nature are models for the practice of sustainable design and fabrication. From trees to bones, natural systems are characterized by the constant interplay of creation, environmental response, and ...

Han, Sarah (Sarah J.)

2013-01-01T23:59:59.000Z

306

Assessment of Biomass Pelletization Options for Greensburg, Kansas |  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergy Cooperation |South42.2 (April 2012)Tie Ltd |Line, LLC:LLCOffshoreContinental United States

307

Fabricated torque shaft  

DOE Patents [OSTI]

A fabricated torque shaft is provided that features a bolt-together design to allow vane schedule revisions with minimal hardware cost. The bolt-together design further facilitates on-site vane schedule revisions with parts that are comparatively small. The fabricated torque shaft also accommodates stage schedules that are different one from another in non-linear inter-relationships as well as non-linear schedules for a particular stage of vanes.

Mashey, Thomas Charles (Anderson, SC)

2002-01-01T23:59:59.000Z

308

Nuclear Fabrication Consortium  

SciTech Connect (OSTI)

This report summarizes the activities undertaken by EWI while under contract from the Department of Energy (DOE) â?? Office of Nuclear Energy (NE) for the management and operation of the Nuclear Fabrication Consortium (NFC). The NFC was established by EWI to independently develop, evaluate, and deploy fabrication approaches and data that support the re-establishment of the U.S. nuclear industry: ensuring that the supply chain will be competitive on a global stage, enabling more cost-effective and reliable nuclear power in a carbon constrained environment. The NFC provided a forum for member original equipment manufactures (OEM), fabricators, manufacturers, and materials suppliers to effectively engage with each other and rebuild the capacity of this supply chain by : â?¢ Identifying and removing impediments to the implementation of new construction and fabrication techniques and approaches for nuclear equipment, including system components and nuclear plants. â?¢ Providing and facilitating detailed scientific-based studies on new approaches and technologies that will have positive impacts on the cost of building of nuclear plants. â?¢ Analyzing and disseminating information about future nuclear fabrication technologies and how they could impact the North American and the International Nuclear Marketplace. â?¢ Facilitating dialog and initiate alignment among fabricators, owners, trade associations, and government agencies. â?¢ Supporting industry in helping to create a larger qualified nuclear supplier network. â?¢ Acting as an unbiased technology resource to evaluate, develop, and demonstrate new manufacturing technologies. â?¢ Creating welder and inspector training programs to help enable the necessary workforce for the upcoming construction work. â?¢ Serving as a focal point for technology, policy, and politically interested parties to share ideas and concepts associated with fabrication across the nuclear industry. The report the objectives and summaries of the Nuclear Fabrication Consortium projects. Full technical reports for each of the projects have been submitted as well.

Levesque, Stephen

2013-04-05T23:59:59.000Z

309

22.351 Systems Analysis of the Nuclear Fuel Cycle, Spring 2003  

E-Print Network [OSTI]

In-depth technical and policy analysis of various options for the nuclear fuel cycle. Topics include uranium supply, enrichment fuel fabrication, in-core physics and fuel management of uranium, thorium and other fuel types, ...

Kazimi, Mujid S.

310

Fossil fuels -- future fuels  

SciTech Connect (OSTI)

Fossil fuels -- coal, oil, and natural gas -- built America`s historic economic strength. Today, coal supplies more than 55% of the electricity, oil more than 97% of the transportation needs, and natural gas 24% of the primary energy used in the US. Even taking into account increased use of renewable fuels and vastly improved powerplant efficiencies, 90% of national energy needs will still be met by fossil fuels in 2020. If advanced technologies that boost efficiency and environmental performance can be successfully developed and deployed, the US can continue to depend upon its rich resources of fossil fuels.

NONE

1998-03-01T23:59:59.000Z

311

Lithium pellet injection experiments on the Alcator C-Mod tokamak  

SciTech Connect (OSTI)

A pellet enhanced performance mode, showing significantly reduced core transport, is regularly obtained after the injection of deeply penetrating lithium pellets into Alcator C-Mod discharges. These transient modes, which typically persist about two energy confinement times, are characterized by a steep pressure gradient ({ell}{sub p} {le} a/5) in the inner third of the plasma, indicating the presence of an internal transport barrier. Inside this barrier, particle and energy diffusivities are greatly reduced, with ion thermal diffusivity dropping to near neoclassical values. Meanwhile, the global energy confinement time shows a 30% improvement over ITER89-P L-mode scaling. The addition of ICRF auxiliary heating shortly after the pellet injection leads to high fusion reactivity with neutron rates enhanced by an order of magnitude over L-mode discharges with similar input powers. A diagnostic system for measuring equilibrium current density profiles of tokamak plasmas, employing high speed lithium pellets, is also presented. Because ions are confined to move along field lines, imaging the Li{sup +} emission from the toroidally extended pellet ablation cloud gives the direction of the magnetic field. To convert from temporal to radial measurements, the 3-D trajectory of the pellet is determined using a stereoscopic tracking system. These measurements, along with external magnetic measurements, are used to solve the Grad-Shafranov equation for the magnetic equilibrium of the plasma. This diagnostic is used to determine the current density profile of PEP modes by injection of a second pellet during the period of good confinement. This measurement indicates that a region of reversed magnetic shear exists at the plasma core. This current density profile is consistent with TRANSP calculations for the bootstrap current created by the pressure gradient. MHD stability analysis indicates that these plasmas are near the n = {infinity} and the n = 1 marginal stability limits.

Garnier, D.T.

1996-06-01T23:59:59.000Z

312

PWR core design, neutronics evaluation and fuel cycle analysis for thorium-uranium breeding recycle  

SciTech Connect (OSTI)

This paper was focused on core design, neutronics evaluation and fuel cycle analysis for Thorium-Uranium Breeding Recycle in current PWRs, without any major change to the fuel lattice and the core internals, but substituting the UOX pellet with Thorium-based pellet. The fuel cycle analysis indicates that Thorium-Uranium Breeding Recycle is technically feasible in current PWRs. A 4-loop, 193-assembly PWR core utilizing 17 x 17 fuel assemblies (FAs) was taken as the model core. Two mixed cores were investigated respectively loaded with mixed reactor grade Plutonium-Thorium (PuThOX) FAs and mixed reactor grade {sup 233}U-Thorium (U{sub 3}ThOX) FAs on the basis of reference full Uranium oxide (UOX) equilibrium-cycle core. The UOX/PuThOX mixed core consists of 121 UOX FAs and 72 PuThOX FAs. The reactor grade {sup 233}U extracted from burnt PuThOX fuel was used to fabrication of U{sub 3}ThOX for starting Thorium-. Uranium breeding recycle. In UOX/U{sub 3}ThOX mixed core, the well designed U{sub 3}ThOX FAs with 1.94 w/o fissile uranium (mainly {sup 233}U) were located on the periphery of core as a blanket region. U{sub 3}ThOX FAs remained in-core for 6 cycles with the discharged burnup achieving 28 GWD/tHM. Compared with initially loading, the fissile material inventory in U{sub 3}ThOX fuel has increased by 7% via 1-year cooling after discharge. 157 UOX fuel assemblies were located in the inner of UOX/U{sub 3}ThOX mixed core refueling with 64 FAs at each cycle. The designed UOX/PuThOX and UOX/U{sub 3}ThOX mixed core satisfied related nuclear design criteria. The full core performance analyses have shown that mixed core with PuThOX loading has similar impacts as MOX on several neutronic characteristic parameters, such as reduced differential boron worth, higher critical boron concentration, more negative moderator temperature coefficient, reduced control rod worth, reduced shutdown margin, etc.; while mixed core with U{sub 3}ThOX loading on the periphery of core has no visible impacts on neutronic characteristics compared with reference full UOX core. The fuel cycle analysis has shown that {sup 233}U mono-recycling with U{sub 3}ThOX fuel could save 13% of natural uranium resource compared with UOX once through fuel cycle, slightly more than that of Plutonium single-recycling with MOX fuel. If {sup 233}U multi-recycling with U{sub 3}ThOX fuel is implemented, more natural uranium resource would be saved. (authors)

Bi, G.; Liu, C.; Si, S. [Shanghai Nuclear Engineering Research and Design Inst., No. 29, Hongcao Road, Shanghai, 200233 (China)

2012-07-01T23:59:59.000Z

313

M. ,PELLET. -CON'l'RIBUTION 13 et elle sera ralise en Allemagne cette anne. Le flacon normal, dans  

E-Print Network [OSTI]

M. ,PELLET. - CON'l'RIBUTION 13 et elle sera réalisée en Allemagne cette année. Le flacon normal. CONTRIBUTION A L'?TUDE DU LAIT ST?RILIS? par M. PELLET, Ingénieur agronome. La stérilisation du lait a été j- vations à la Laiterie municipale de Nantes . .Simultanément, M. Pellet donna-t dans le « Lait» (Septembre

Boyer, Edmond

314

3 TTT>T7(T^/f^ Ris-M-2744 3 Investigation of Pellet Acceleration  

E-Print Network [OSTI]

3 TTT>T7(T^/f^ Risø-M-2744 s 3 Investigation of Pellet Acceleration by an Arc Heated Gas Gun S Roskilde, Denmark October 1988 #12;Risø-M-2744 IBVB8TIQATI0M OF PELLET ACCELEBATIOB BT AH ABC HEATED GAS describes work on pellet acceleration by means of an arc heated gas gun. Preliminary results were de

315

Covering Walls With Fabrics.  

E-Print Network [OSTI]

the glue a dull surface to adhere to. Fill any gouges or nail holes with patching plaster and sand smooth after they have dried thoroughly. Minor ripples can be covered with spackling compound, a plaster-like substance that is spread thinly... during dry weather and in a well-ventilated room. Cut each panel 3 inches longer than the ceiling height. Match and cut sufficient fabric widths to cover completely one wall at a time. Start with Corner I nstall the first fabric panel so...

Anonymous,

1979-01-01T23:59:59.000Z

316

SNAP and AI Fuel Summary Report  

SciTech Connect (OSTI)

The SNAP and AI Fuel Summary Report provides a detailed overview of treatment and storage of these fuels from fabrication through current storage including design parameters and reactor history. Chemical and physical characteristics are described, and potential indicators of as-stored fuel conditions are emphasized.

Lords, R.E.

1994-08-01T23:59:59.000Z

317

Metal hydride fuel storage and method thereof  

DOE Patents [OSTI]

Disclosed herein is a metal hydride fuel storage cartridge having integrated resistive heaters that can be used in conjunction with fuel cells such as MEMS-based fuel cells. The cartridge is fabricated using micromachining methods and thin/thick film materials synthesis techniques.

Morse, Jeffrey D. (Martinez, CA); Jankowski, Alan F. (Livermore, CA); Yu, Conrad (Antioch, CA)

2006-10-17T23:59:59.000Z

318

Metal hydride fuel storage and method thereof  

DOE Patents [OSTI]

Disclosed herein is a metal hydride fuel storage cartridge having integrated resistive heaters that can be used in conjunction with fuel cells such as MEMS-based fuel cells. The cartridge is fabricated using micromachining methods and thin/thick film materials synthesis techniques.

Morse, Jeffrey D [Martinez, CA; Jankowski, Alan F [Livermore, CA; Yu, Conrad [Antioch, CA

2009-05-05T23:59:59.000Z

319

Dry Process Electrode Fabrication  

Broader source: Energy.gov [DOE]

2013 DOE Hydrogen and Fuel Cells Program and Vehicle Technologies Program Annual Merit Review and Peer Evaluation Meeting

320

Liquid fuel reformer development: Autothermal reforming of Diesel fuel  

SciTech Connect (OSTI)

Argonne National Laboratory is developing a process to convert hydrocarbon fuels to clean hydrogen feeds for a polymer electrolyte fuel cell. The process incorporates an autothermal reforming catalyst that can process hydrocarbon feeds at lower temperatures than existing commercial catalysts. The authors have tested the catalyst with three diesel-type fuels: hexadecane, certified low-sulfur grade 1 diesel, and a standard grade 2 diesel. Hexadecane yielded products containing 60% hydrogen on a dry, nitrogen-free basis at 850 C, while maximum hydrogen product yields for the two diesel fuels were near 50%. Residual products in all cases included CO, CO{sub 2}, ethane, and methane. Further studies with grade 1 diesel showed improved conversion as the water:fuel ratio was increased from 1 to 2 at 850 C. Soot formation was reduced when the oxygen:carbon ratio was maintained at 1 at 850 C. There were no significant changes in hydrogen yield as the space velocity and the oxygen:fuel ratio were varied. Tests with a microchannel monolithic catalyst yielded similar or improved hydrogen levels at higher space velocities than with extruded pellets in a packed bed.

Pereira, C.; Bae, J-M.; Ahmed, S.; Krumpelt, M.

2000-07-24T23:59:59.000Z

Note: This page contains sample records for the topic "fuel pellet fabrication" 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

Lithographic fabrication of nanoapertures  

DOE Patents [OSTI]

A new class of silicon-based lithographically defined nanoapertures and processes for their fabrication using conventional silicon microprocessing technology have been invented. The new ability to create and control such structures should significantly extend our ability to design and implement chemically selective devices and processes.

Fleming, James G. (Albuquerque, NM)

2003-01-01T23:59:59.000Z

322

Fluidic fuel feed system  

SciTech Connect (OSTI)

This report documents the development and testing of a fluidic fuel injector for a coal-water slurry fueled diesel engine. The objective of this program was to improve the operating life of coal-water slurry fuel controls and injector components by using fluidic technology. This project addressed the application of fluidic devices to solve the problems of efficient atomization of coal-water slurry fuel and of injector component wear. The investigation of injector nozzle orifice design emphasized reducing the pressure required for efficient atomization. The effort to minimize injector wear includes the novel design of components allowing the isolation of the coal-water slurry from close-fitting injector components. Three totally different injectors were designed, fabricated, bench tested and modified to arrive at a final design which was capable of being engine tested. 6 refs., 25 figs., 3 tabs.

Badgley, P.

1990-06-01T23:59:59.000Z

323

Updated NGNP Fuel Acquisition Strategy  

SciTech Connect (OSTI)

A Next Generation Nuclear Plant (NGNP) fuel acquisition strategy was first established in 2007. In that report, a detailed technical assessment of potential fuel vendors for the first core of NGNP was conducted by an independent group of international experts based on input from the three major reactor vendor teams. Part of the assessment included an evaluation of the credibility of each option, along with a cost and schedule to implement each strategy compared with the schedule and throughput needs of the NGNP project. While credible options were identified based on the conditions in place at the time, many changes in the assumptions underlying the strategy and in externalities that have occurred in the interim requiring that the options be re-evaluated. This document presents an update to that strategy based on current capabilities for fuel fabrication as well as fuel performance and qualification testing worldwide. In light of the recent Pebble Bed Modular Reactor (PBMR) project closure, the Advanced Gas Reactor (AGR) fuel development and qualification program needs to support both pebble and prismatic options under the NGNP project. A number of assumptions were established that formed a context for the evaluation. Of these, the most important are: Based on logistics associated with the on-going engineering design activities, vendor teams would start preliminary design in October 2012 and complete in May 2014. A decision on reactor type will be made following preliminary design, with the decision process assumed to be completed in January 2015. Thus, no fuel decision (pebble or prismatic) will be made in the near term. Activities necessary for both pebble and prismatic fuel qualification will be conducted in parallel until a fuel form selection is made. As such, process development, fuel fabrication, irradiation, and testing for pebble and prismatic options should not negatively influence each other during the period prior to a decision on reactor type. Additional funding will be made available beginning in fiscal year (FY) 2012 to support pebble bed fuel fabrication process development and fuel testing while maintaining the prismatic fuel schedule. Options for fuel fabrication for prismatic and pebble bed were evaluated based on the credibility of each option, along with a cost and schedule to implement each strategy. The sole prismatic option is Babcock and Wilcox (B&W) producing uranium oxycarbide (UCO) tristructural-isotropic (TRISO) fuel particles in compacts. This option finishes in the middle of 2022 . Options for the pebble bed are Nuclear Fuel Industries (NFI) in Japan producing uranium dioxide (UO2) TRISO fuel particles, and/or B&W producing UCO or UO2 TRISO fuel particles. All pebble options finish in mid to late 2022.

David Petti; Tim Abram; Richard Hobbins; Jim Kendall

2010-12-01T23:59:59.000Z

324

BPAonFabric_jk  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-Series to someone6 M. Babzien, I. Ben-Zvi, P. Study ofJ U LY 2 9 - AU G U S T 2 ,

325

BPAonFabric_jk  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-Series to someone6 M. Babzien, I. Ben-Zvi, P. Study ofJ U LY 2 9 - AU G U S T 2

326

Coprocessed nuclear fuels containing (U, Pu) values as oxides, carbides or carbonitrides  

DOE Patents [OSTI]

Method for direct coprocessing of nuclear fuels derived from a product stream of a fuels reprocessing facility containing uranium, plutonium, and fission product values comprising nitrate stabilization of said stream vacuum concentration to remove water and nitrates, neutralization to form an acid deficient feed solution for the internal gelation mode of sol-gel technology, green spherule formation, recovery and treatment for loading into a fuel element by vibra packed or pellet formation technologies.

Lloyd, Milton H. (Oak Ridge, TN)

1983-01-01T23:59:59.000Z

327

Coprocessed nuclear fuels containing (U, Pu) values as oxides, carbides or carbonitrides  

DOE Patents [OSTI]

Method for direct coprocessing of nuclear fuels derived from a product stream of fuels reprocessing facility containing uranium, plutonium, and fission product values comprising nitrate stabilization of said stream vacuum concentration to remove water and nitrates, neutralization to form an acid deficient feed solution for the internal gelation mode of sol-gel technology, green spherule formation, recovery and treatment for loading into a fuel element by vibra packed or pellet formation technologies.

Lloyd, M.H.

1981-01-09T23:59:59.000Z

328

Laboratory Directed Research and Development (LDRD) on Mono-uranium Nitride Fuel Development for SSTAR and Space Applications  

SciTech Connect (OSTI)

The US National Energy Policy of 2001 advocated the development of advanced fuel and fuel cycle technologies that are cleaner, more efficient, less waste-intensive, and more proliferation resistant. The need for advanced fuel development is emphasized in on-going DOE-supported programs, e.g., Global Nuclear Energy Initiative (GNEI), Advanced Fuel Cycle Initiative (AFCI), and GEN-IV Technology Development. The Directorates of Energy & Environment (E&E) and Chemistry & Material Sciences (C&MS) at Lawrence Livermore National Laboratory (LLNL) are interested in advanced fuel research and manufacturing using its multi-disciplinary capability and facilities to support a design concept of a small, secure, transportable, and autonomous reactor (SSTAR). The E&E and C&MS Directorates co-sponsored this Laboratory Directed Research & Development (LDRD) Project on Mono-Uranium Nitride Fuel Development for SSTAR and Space Applications. In fact, three out of the six GEN-IV reactor concepts consider using the nitride-based fuel, as shown in Table 1. SSTAR is a liquid-metal cooled, fast reactor. It uses nitride fuel in a sealed reactor vessel that could be shipped to the user and returned to the supplier having never been opened in its long operating lifetime. This sealed reactor concept envisions no fuel refueling nor on-site storage of spent fuel, and as a result, can greatly enhance proliferation resistance. However, the requirement for a sealed, long-life core imposes great challenges to research and development of the nitride fuel and its cladding. Cladding is an important interface between the fuel and coolant and a barrier to prevent fission gas release during normal and accidental conditions. In fabricating the nitride fuel rods and assemblies, the cladding material should be selected based on its the coolant-side corrosion properties, the chemical/physical interaction with the nitride fuel, as well as their thermal and neutronic properties. The US NASA space reactor, the SP-100 was designed to use mono-uranium nitride fuel. Although the SP-100 reactor was not commissioned, tens of thousand of nitride fuel pellets were manufactured and lots of them, cladded in Nb-1-Zr had been irradiated in fast test reactors (FFTF and EBR-II) with good irradiation results. The Russian Naval submarines also use nitride fuel with stainless steel cladding (HT-9) in Pb-Bi coolant. Although the operating experience of the Russian submarine is not readily available, such combination of fuel, cladding and coolant has been proposed for a commercial-size liquid-metal cooled fast reactor (BREST-300). Uranium mono-nitride fuel is studied in this LDRD Project due to its favorable properties such as its high actinide density and high thermal conductivity. The thermal conductivity of mono-nitride is 10 times higher than that of oxide (23 W/m-K for UN vs. 2.3 W/m-K for UO{sub 2} at 1000 K) and its melting temperature is much higher than that of metal fuel (2630 C for UN vs. 1132 C for U metal). It also has relatively high actinide density, (13.51 gU/cm{sup 3} in UN vs. 9.66 gU/cm{sup 3} in UO{sub 2}) which is essential for a compact reactor core design. The objective of this LDRD Project is to: (1) Establish a manufacturing capability for uranium-based ceramic nuclear fuel, (2) Develop a computational capability to analyze nuclear fuel performance, (3) Develop a modified UN-based fuel that can support a compact long-life reactor core, and (4) Collaborate with the Nuclear Engineering Department of UC Berkeley on nitride fuel reprocessing and disposal in a geologic repository.

Choi, J; Ebbinghaus, B; Meiers, T; Ahn, J

2006-02-09T23:59:59.000Z

329

Method of preparation of bonded polyimide fuel cell package  

DOE Patents [OSTI]

Described herein are processes for fabricating microfluidic fuel cell systems with embedded components in which micron-scale features are formed by bonding layers of DuPont Kapton.TM. polyimide laminate. A microfluidic fuel cell system fabricated using this process is also described.

Morse, Jeffrey D. (Martinez, CA); Jankowski, Alan (Livermore, CA); Graff, Robert T. (Modesto, CA); Bettencourt, Kerry (Dublin, CA)

2011-04-26T23:59:59.000Z

330

Impact of Pellet Injection on Extension of the Operational Region in LHD  

SciTech Connect (OSTI)

Pellet injection has been used as a primary fuelling scheme in the Large Helical Device. With pellet injection, the operational region of NBI plasmas has been extended to higher densities while maintaining a favourable dependence of energy connement on density, and several important values, such as plasma stored energy of 0.88 MJ, energy connement time of 0.3 s, of 2.4% at 1.3 T and density of 1:11020 m 3, have been achieved. These parameters cannot be attained by gas pung. Ablation and the subsequent behaviour of the plasma have been investigated. The measured pellet penetration depth estimated on the basis of the duration of the H emission is shallower than the depth predicted from the simple neutral gas shielding (NGS) model. It can be explained by the NGS model with inclusion of the eect of fast ions on the ablation. Just after ablation, the redistribution of the ablated pellet mass was observed on a short timescale (400 ms). The redistribution causes shallow deposition and low fuelling eciency.

Sakamoto, R. [National Institute for Fusion Science, Toki, Japan; Yamada, H. [National Institute for Fusion Science, Toki, Japan; Tanaka, K. [National Institute for Fusion Science, Toki, Japan; Narihara, K. [National Institute for Fusion Science, Toki, Japan; Morita, S. [National Institute for Fusion Science, Toki, Japan; Sakakibara, S. [National Institute for Fusion Science, Toki, Japan; Masuzaki, S. [National Institute for Fusion Science, Toki, Japan; Inagaki, S. [National Institute for Fusion Science, Toki, Japan; Baylor, Larry R [ORNL; Fisher, Paul W [ORNL; Combs, Stephen Kirk [ORNL; Gouge, Michael J [ORNL; Kato, S. [National Institute for Fusion Science, Toki, Japan; Komori, A. [National Institute for Fusion Science, Toki, Japan; Kaneko, O. [National Institute for Fusion Science, Toki, Japan; Ashikawa, N. [Graduate University for Advanced Studies, Japan; DeVries, P. [National Institute for Fusion Science, Toki, Japan; Emoto, M. [National Institute for Fusion Science, Toki, Japan; Funaba, H. [National Institute for Fusion Science, Toki, Japan; Goto, M. [National Institute for Fusion Science, Toki, Japan; Ida, K. [National Institute for Fusion Science, Toki, Japan; Idei, H. [National Institute for Fusion Science, Toki, Japan; Ikeda, K. [National Institute for Fusion Science, Toki, Japan; Isobe, M. [National Institute for Fusion Science, Toki, Japan; Kado, S. [National Institute for Fusion Science, Toki, Japan; Kawahata, K. [National Institute for Fusion Science, Toki, Japan; Khlopenkov, K. [National Institute for Fusion Science, Toki, Japan; Kubo, S. [National Institute for Fusion Science, Toki, Japan; Kumazawa, R. [National Institute for Fusion Science, Toki, Japan; Minami, T. [National Institute for Fusion Science, Toki, Japan; Miyazawa, J. [National Institute for Fusion Science, Toki, Japan; Morisaki, T. [National Institute for Fusion Science, Toki, Japan; Murakami, S. [National Institute for Fusion Science, Toki, Japan; Muto, S. [National Institute for Fusion Science, Toki, Japan; Mutoh, T. [National Institute for Fusion Science, Toki, Japan; Nagayama, Y. [National Institute for Fusion Science, Toki, Japan; Nakamura, Y. [National Institute for Fusion Science, Toki, Japan; Nakanishi, H. [National Institute for Fusion Science, Toki, Japan; Nishimura, K. [National Institute for Fusion Science, Toki, Japan; Noda, N. [National Institute for Fusion Science, Toki, Japan; Notake, T. [Nagoya University, Japan; Kobuchi, T. [Graduate University for Advanced Studies, Japan; Liang, Y. [Graduate University for Advanced Studies, Japan; Ohdachi, S. [National Institute for Fusion Science, Toki, Japan; Ohyabu, N. [National Institute for Fusion Science, Toki, Japan; Oka, Y. [National Institute for Fusion Science, Toki, Japan; Osakabe, M. [National Institute for Fusion Science, Toki, Japan; Ozaki, T. [National Institute for Fusion Science, Toki, Japan; Pavlichenko, R. O. [National Institute for Fusion Science, Toki, Japan; Peterson, B. J. [National Institute for Fusion Science, Toki, Japan; Sagara, A. [National Institute for Fusion Science, Toki, Japan; Saito, K. [Nagoya University, Japan; Sasao, M. [National Institute for Fusion Science, Toki, Japan; Sato, K. [National Institute for Fusion Science, Toki, Japan; Sato, M. [National Institute for Fusion Science, Toki, Japan; Seki, T. [National Institute for Fusion Science, Toki, Japan; Shimozuma, T. [National Institute for Fusion Science, Toki, Japan; Shoji, M. [National Institute for Fusion Science, Toki, Japan; Sudo, S. [National Institute for Fusion Science, Toki, Japan; Suzuki, H. [National Institute for Fusion Science, Toki, Japan; Takechi, M. [National Institute for Fusion Science, Toki, Japan; Takeiri, Y. [National Institute for Fusion Science, Toki, Japan; Tamura, N. [Graduate University for Advanced Studies, Japan; et al.

2001-01-01T23:59:59.000Z

331

Design and implementation of a control and data acquisition system for pellet injectors  

SciTech Connect (OSTI)

A stand-alone control and data acquisition system for pellet injectors has been designed and implemented to support pellet injector development at Oak Ridge Laboratory (ORNL) and to enable ORNL pellet injectors to be installed on various fusion experimental devices. The stand-alone system permits LOCAL operation of the injector from a nearby panel and REMOTE operation from the experiment control room. Major components of the system are (1) an Allen-Bradley PLC 2/30 programmable controller, (2) a VAX minicomputer, and (3) a CAMAC serial highway interface. The programmable logic controller (PLC) is used to perform all control functions of the injector. In LOCAL, the operator interface is provided by an intelligent panel system that has a keypad and pushbutton module programmed from the PLC. In REMOTE, the operator interfaces via a VAX-based color graphics display and uses a trackball and keyboard to issue commands. Communications between the remote and local controls and to the fusion experiment supervisory system are via the CAMAC highway. The VAX archives transient data from pellet shots and trend data acquired from the PLC. Details of the hardware and software design and the operation of the system are presented in this paper. 3 refs., 1 fig.

Baylor, L.R.; Burris, R.D.; Greenwood, D.E.; Stewart, K.A.

1985-01-01T23:59:59.000Z

332

genomic DNA was isolated from these centrifuged cell pellets and used for am-  

E-Print Network [OSTI]

genomic DNA was isolated from these centrifuged cell pellets and used for am- plification of either changes in ruminal bacterial popula- tions. J Wood1, KP Scott,1, G Avgutin2,J Wood1 KP Scott, G of this group from rumen- extracted DNA. Restriction enzyme cleav- age of the PCR product yields profiles

Paris-Sud XI, Université de

333

Pellet property requirements for future blast-furnace operations and other new ironmaking processes  

SciTech Connect (OSTI)

The requirements for the physical, chemical and metallurgical properties of pellets have continued to become more stringent as blast-furnace productivity and coke rate have been rapidly improved during the last decade. In addition, the age and deterioration of the North American coke batteries, the lack of capital to sufficiently rebuild them, and the threat of increasingly more stringent environmental controls for the coke batteries has forced North American ironmakers to begin implementing pulverized coal injection to minimize the coke requirements for the blast furnace and to seriously investigate developing other ironmaking processes that use coal instead of coke. Therefore, the next major step in North American ironmaking has included injecting pulverized coal (PC) at 200 kilograms per ton of hot metal (kg/ton) [400 pounds per net ton of hot metal (lb/NTHM)] or greater which will result in the coke rate decreasing to less than 300 kg/ton (600 lb/NTHM) or less. As a result, the pellets will spend more time in the furnace and will be required to support more total weight. Pellets can also be a major iron unit source for other cokeless ironmaking processes such as the COREX process or the AISI direct ironmaking process. This paper will explore the pellet property requirements for future blast-furnace operations and cokeless ironmaking processes.

Agrawal, A.K.; Oshnock, T.W. [U.S. Steel, Monroeville, PA (United States)

1995-12-01T23:59:59.000Z

334

Trials with a 100% pellet burden in blast furnace No. 6 at Hoogovens IJmuiden  

SciTech Connect (OSTI)

The burden consists of 50% high basicity sinter and 50% home made olivine pellets. Two coke oven plants produce the required coke, about 340 kg/t (680 lb/NT). The average pulverized coal injection rate is 150 kg/t (300 lb/NT). To anticipate the aging coke oven plant No. 2 the coal injection capacity will e increased by 50% in 1996, by the installation of a third coal grinding line. In the Netherlands environmental issues have a high impact on further developments. In particular the environmental regulations require a significant decrease of dust, SO{sub 2} and dioxins emitted by the sinter plant. The appropriate measures must be concluded in the second part of this decade. To avoid costly conventional solutions Hoogovens has been testing since April, 1994 the Emission Optimized Sintering (EOS). In case of failure of EOS, the situation of a (partially) closed sinter plant was tested. Purchased pellets replaced sinter, leading to a 100% pellet and an 80% pellet/20% sinter trial. The trials were executed in the first half of 1994 at blast furnace No. 6, equipped with a PW-bell less top. Results are described.

Schoone, E.; Toxopeus, H.; Vos, D. [Hoogovens IJmuiden (Netherlands). Ironmaking and Raw Materials Div.

1995-12-01T23:59:59.000Z

335

Standard specification for nuclear-grade aluminum oxide-boron carbide composite pellets  

E-Print Network [OSTI]

1.1 This specification applies to pellets composed of mixtures of aluminum oxide and boron carbide that may be ultimately used in a reactor core, for example, in neutron absorber rods. 1.2 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.

American Society for Testing and Materials. Philadelphia

2005-01-01T23:59:59.000Z

336

additives doped-uo2 pellets: Topics by E-print Network  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

additives doped-uo2 pellets First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Journal of Nuclear...

337

Nondestructive evaluation of Polymer Coating Structures on Pharmaceutical Pellets using Full Field Optical Coherence Tomography  

E-Print Network [OSTI]

Full field optical coherence tomography (FF-OCT) using a conventional LED light source and a CMOS camera has been developed for characterising coatings on small pellet samples. A set of en-face images covering an area of 700m x 700m were taken...

Li, C; Zeitler, J. A; Dong, Y; Shen, Y.-C

338

SIDA DemoEast programme in Estonia. Supply, delivery and installation of wood pellet burning equipment  

E-Print Network [OSTI]

kW. The second light oil fuelled boiler will be in reserve. The total delivery programme has and Kiltsi light oil fired boilers have been converted to wood pellets burning. The supplier oil fuelling) and 26NOVA (with the capacity 700 kW with light oil fuelling). The boilers are fuelled

339

Biomass Fuel Characterization : Testing and Evaluating the Combustion Characteristics of Selected Biomass Fuels : Final Report May 1, 1988-July, 1989.  

SciTech Connect (OSTI)

Results show that two very important measures of combustion efficiency (gas temperature and carbon dioxide based efficiency) varied by only 5.2 and 5.4 percent respectively. This indicates that all nine different wood fuel pellet types behave very similarly under the prescribed range of operating parameters. The overall mean efficiency for all tests was 82.1 percent and the overall mean temperature was 1420 1{degree}F. Particulate (fly ash) ad combustible (in fly ash) data should the greatest variability. There was evidence of a relationship between maximum values for both particulate and combustible and the percentages of ash and chlorine in the pellet fuel. The greater the percentage of ash and chlorine (salt), the greater was the fly ash problem, also, combustion efficiency was decreased by combustible losses (unburned hydrocarbons) in the fly ash. Carbon monoxide and Oxides of Nitrogen showed the next greatest variability, but neither had data values greater than 215.0 parts per million (215.0 ppm is a very small quantity, i.e. 1 ppm = .001 grams/liter = 6.2E-5 1bm/ft{sup 3}). Visual evidence indicates that pellets fuels produced from salt laden material are corrosive, produce the largest quantities of ash, and form the only slag or clinker formations of all nine fuels. The corrosion is directly attributable to salt content (or more specifically, chloride ions and compounds formed during combustion). 45 refs., 23 figs., 19 tabs.

Bushnell, Dwight J.; Haluzok, Charles; Dadkhah-Nikoo, Abbas

1990-04-01T23:59:59.000Z

340

MEMS-based fuel cells with integrated catalytic fuel processor and method thereof  

DOE Patents [OSTI]

Described herein is a means to incorporate catalytic materials into the fuel flow field structures of MEMS-based fuel cells, which enable catalytic reforming of a hydrocarbon based fuel, such as methane, methanol, or butane. Methods of fabrication are also disclosed.

Jankowski, Alan F. (Livermore, CA); Morse, Jeffrey D. (Martinez, CA); Upadhye, Ravindra S. (Pleasanton, CA); Havstad, Mark A. (Davis, CA)

2011-08-09T23:59:59.000Z

Note: This page contains sample records for the topic "fuel pellet fabrication" 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

3 Morphology of contact areas The SEM examinations of the YSZ pellets revealed that when an impure nickel wire was used,  

E-Print Network [OSTI]

3 Morphology of contact areas The SEM examinations of the YSZ pellets revealed that when an impure.1 Samples with impure nickel wires as electrodes The surface of the YSZ pellets may, after the experiments.1. A schematic drawing of a pellet surface after an experiment. A line profile through the contact area is shown

342

Estimation of Food Consumption fr om Pellets Cast by Captive Ural Owls ( Strix uralensis ) Aki Higuchi and Manabu T . Abe1  

E-Print Network [OSTI]

551 Estimation of Food Consumption fr om Pellets Cast by Captive Ural Owls ( Strix uralensis ) Aki of the Ural Owl ( Strix uralensis) based on pellet analysis. Though it is possible to identify pr ey items- tat and manage for this species. In this study, ingested food and cast pellet mass were quantified

343

New Pellet Injection Schemes on DIII-D* S. K. Combs, L. R. Baylor, C. R. Foust, and T. C. Jernigan  

E-Print Network [OSTI]

New Pellet Injection Schemes on DIII-D* S. K. Combs, L. R. Baylor, C. R. Foust, and T. C. Jernigan Energy Research Corp. Abstract--The pellet system on DIII-D has been modified for injection of deuterium pellets from two vertical ports and two inner wall locations on the magnetic high-field side (HFS

344

VIII. FUELING W. A. HOULBERG (ORNL)  

E-Print Network [OSTI]

properties, but also give the addi- tional benefits of increased fusion production and ignition margin in BPX assessments, we present the latest information on pellet ablation and penetration and then give example-l. This dictates a minimum pellet frequency for pellets of a given size: 1 Hz for pellets of effective spherical

345

22.251 / 22.351 Systems Analysis of the Nuclear Fuel Cycle, Fall 2005  

E-Print Network [OSTI]

This course provides an in-depth technical and policy analysis of various options for the nuclear fuel cycle. Topics include uranium supply, enrichment fuel fabrication, in-core physics and fuel management of uranium, ...

Kazimi, Mujid S.

346

Incorporation of Integral Fuel Burnable Absorbers Boron and Gadolinium into Zirconium-Alloy Fuel Clad Material  

SciTech Connect (OSTI)

Long-lived fuels require the use of higher enrichments of 235U or other fissile materials. Such high levels of fissile material lead to excessive fuel activity at the beginning of life. To counteract this excessive activity, integral fuel burnable absorbers (IFBA) are added to some rods in the fuel assembly. The two commonly used IFBA elements are gadolinium, which is added as gadolinium-oxide to the UO2 powder, and boron, which is applied as a zirconium-diboride coating on the UO2 pellets using plasma spraying or chemical vapor deposition techniques. The incorporation of IFBA into the fuel has to be performed in a nuclear-regulated facility that is physically separated from the main plant. These operations tend to be very costly because of their small volume and can add from 20 to 30% to the manufacturing cost of the fuel. Other manufacturing issues that impact cost and performance are maintaining the correct levels of dosing, the reduction in fuel melting point due to gadolinium-oxide additions, and parasitic neutron absorption at fuel's end-of-life. The goal of the proposed research is to develop an alternative approach that involves incorporation of boron or gadolinium into the outer surface of the fuel cladding material rather than as an additive to the fuel pellets. This paradigm shift will allow for the introduction of the IFBA in a non-nuclear regulated environment and will obviate the necessity of additional handling and processing of the fuel pellets. This could represent significant cost savings and potentially lead to greater reproducibility and control of the burnable fuel in the early stages of the reactor operation. The surface alloying is being performed using the IBEST (Ion Beam Surface Treatment) process developed at Sandia National Laboratories. IBEST involves the delivery of energetic ion beam pulses onto the surface of a material, near-surface melting, and rapid solidification. The non-equilibrium nature of such processing allows for surface alloying well in excess of the thermodynamically dictated solubility limits, an effect that is particularly relevant to this research due to the negligible solubility of boron and gadolinium in zirconium. University of Wisconsin is performing the near surface materials characterization and analysis, aiding Sandia in process optimization, and promoting educational activities. Westinghouse is performing process manufacturability and scale-up analysis and is performing autoclave testing of the surface treated samples. The duration of this NERI project is 2 years, from 9/2002 to 9/2004.

Sridharan, K.; Renk, T.J.; Lahoda, E.J.; Corradini, M.L

2004-12-14T23:59:59.000Z

347

Decision-maker's guide to wood fuel for small industrial energy users. Final report. [Includes glossary  

SciTech Connect (OSTI)

The technology and economics of various wood energy systems available to the small industrial and commercial energy user are considered. This book is designed to help a plant manager, engineer, or others in a decision-making role to become more familiar with wood fuel systems and make informed decisions about switching to wood as a fuel. The following subjects are discussed: wood combustion, pelletized wood, fuel storage, fuel handling and preparation, combustion equipment, retrofitting fossil-fueled boilers, cogeneration, pollution abatement, and economic considerations of wood fuel use. (MHR)

Levi, M. P.; O'Grady, M. J.

1980-02-01T23:59:59.000Z

348

Fabrication development for the Advanced Neutron Source Reactor  

SciTech Connect (OSTI)

This report presents the fuel fabrication development for the Advanced Neutron Source (ANS) reactor. The fuel element is similar to that successfully fabricated and used in the High Flux Isotope Reactor (HFIR) for many years, but there are two significant differences that require some development. The fuel compound is U{sub 3}Si{sub 2} rather than U{sub 3}O{sub 8}, and the fuel is graded in the axial as well as the radial direction. Both of these changes can be accomplished with a straightforward extension of the HFIR technology. The ANS also requires some improvements in inspection technology and somewhat more stringent acceptance criteria. Early indications were that the fuel fabrication and inspection technology would produce a reactor core meeting the requirements of the ANS for the low volume fraction loadings needed for the highly enriched uranium design (up to 1.7 Mg U/m{sup 3}). Near the end of the development work, higher volume fractions were fabricated that would be required for a lower- enrichment uranium core. Again, results look encouraging for loadings up to {approx}3.5 Mg U/m{sup 3}; however, much less evaluation was done for the higher loadings.

Pace, B.W. [Babcock and Wilcox, Lynchburg, VA (United States); Copeland, G.L. [Oak Ridge National Lab., TN (United States)

1995-08-01T23:59:59.000Z

349

Carbon Nanotubes Based Nanoelectrode Arrays: Fabrication, Evaluation...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Arrays: Fabrication, Evaluation and Application in Voltammetric Analysis. Carbon Nanotubes Based Nanoelectrode Arrays: Fabrication, Evaluation and Application in Voltammetric...

350

Fuel pin  

DOE Patents [OSTI]

A fuel pin for a liquid metal nuclear reactor is provided. The fuel pin includes a generally cylindrical cladding member with metallic fuel material disposed therein. At least a portion of the fuel material extends radially outwardly to the inner diameter of the cladding member to promote efficient transfer of heat to the reactor coolant system. The fuel material defines at least one void space therein to facilitate swelling of the fuel material during fission.

Christiansen, D.W.; Karnesky, R.A.; Leggett, R.D.; Baker, R.B.

1987-11-24T23:59:59.000Z

351

Steady-sate and load-follow characteristics of various BWR fuel designs  

SciTech Connect (OSTI)

This paper describes the results of an irradiation study carried out in the Halden boiling water reactor (HBWR). The objective of this irradiation was to clarify the performance of various BWR fuel designs - helium prepressurization (0.3 MPa), pellet shape modification (annular and short-length annular) and barrier cladding (copper and zirconium) - under steady-state and load-follow operations.

Takei, K.; Kogai, T.; Matsumoto, T.; Umehara, H.; Uchida, M.

1986-01-01T23:59:59.000Z

352

Intraocular lens fabrication  

DOE Patents [OSTI]

This invention describes a method for fabricating an intraocular lens made rom clear Teflon.TM., Mylar.TM., or other thermoplastic material having a thickness of about 0.025 millimeters. These plastic materials are thermoformable and biocompatable with the human eye. The two shaped lenses are bonded together with a variety of procedures which may include thermosetting and solvent based adhesives, laser and impulse welding, and ultrasonic bonding. The fill tube, which is used to inject a refractive filling material is formed with the lens so as not to damage the lens shape. A hypodermic tube may be included inside the fill tube.

Salazar, Mike A. (Albuquerque, NM); Foreman, Larry R. (Los Alamos, NM)

1997-01-01T23:59:59.000Z

353

Intraocular lens fabrication  

DOE Patents [OSTI]

This invention describes a method for fabricating an intraocular lens made from clear Teflon{trademark}, Mylar{trademark}, or other thermoplastic material having a thickness of about 0.025 millimeters. These plastic materials are thermoformable and biocompatable with the human eye. The two shaped lenses are bonded together with a variety of procedures which may include thermosetting and solvent based adhesives, laser and impulse welding, and ultrasonic bonding. The fill tube, which is used to inject a refractive filling material is formed with the lens so as not to damage the lens shape. A hypodermic tube may be included inside the fill tube. 13 figs.

Salazar, M.A.; Foreman, L.R.

1997-07-08T23:59:59.000Z

354

Electrochemical fabrication of capacitors  

SciTech Connect (OSTI)

A film of nickel oxide is anodically deposited on a graphite sheet held in position on an electrochemical cell during application of a positive electrode voltage to the graphite sheet while exposed to an electrolytic nickel oxide solution within a volumetrically variable chamber of the cell. An angularly orientated x-ray beam is admitted into the cell for transmission through the deposited nickel oxide film in order to obtain structural information while the film is subject to electrochemical and in-situ x-ray spectroscopy from which optimum film thickness, may be determined by comparative analysis for capacitor fabrication purposes.

Mansour, A.N.; Melendres, C.A.

1999-12-14T23:59:59.000Z

355

Process for Fabrication of Efficient Solar Cells - Energy Innovation Portal  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 - SeptemberMicroneedles for4-16 FORPointsProcess for Fabrication of Efficient Solar

356

Fuel Summary Report: Shippingport Light Water Breeder Reactor - Rev. 2  

SciTech Connect (OSTI)

The Shippingport Light Water Breeder Reactor (LWBR) was developed by Bettis Atomic Power Laboratory to demonstrate the potential of a water-cooled, thorium oxide fuel cycle breeder reactor. The LWBR core operated from 1977-82 without major incident. The fuel and fuel components suffered minimal damage during operation, and the reactor testing was deemed successful. Extensive destructive and nondestructive postirradiation examinations confirmed that the fuel was in good condition with minimal amounts of cladding deformities and fuel pellet cracks. Fuel was placed in wet storage upon arrival at the Expended Core Facility, then dried and sent to the Idaho Nuclear Technology and Engineering Center for underground dry storage. It is likely that the fuel remains in good condition at its current underground dry storage location at the Idaho Nuclear Technology and Engineering Center. Reports show no indication of damage to the core associated with shipping, loading, or storage.

Olson, Gail Lynn; Mc Cardell, Richard Keith; Illum, Douglas Brent

2002-09-01T23:59:59.000Z

357

CFBC evaluation of fuels processed from Illinois coals. Final technical report, September 1, 1991--November 10, 1992  

SciTech Connect (OSTI)

The fuels studied in this project are (a) three flotation slurry fuels beneficiated from coal fines at various stages of the cleaning process and (b) coal-sorbent pellets made from the flotation concentrate of the same beneficiation process using corn starch as binder, (c) a run-of-mine Illinois No. 5 coal. Combustion data such as SO{sub 2}, NO{sub x} emissions, combustion efficiency and ash mineral matter analyses from the slurry and pellet fuels are compared with similar parameters from the reference coal burnt under similar conditions of bed temperature and fluidization velocity. The combustion tests performed in a 4 in. internal diameter CFBC showed that the combustion efficiency of the slurry fuels and the pellets were quite comparable with that of the standard coal in the range of 91--98%. Sulfur dioxide emissions in lbs per million Btu from the slurry fuels were low enough to satisfy EPA emissions requirements with Ca/S ratios of 1.5 or less. Oxides of nitrogen emissions were generally on the order of 0.3 lbs per million Btu from the slurry fuels under the conditions of the present tests, while that from the pellets were between 0.6 to 0.75 lbs per million Btu depending on bed temperature.

Rajan, S. [Southern Illinois Univ., Carbondale, IL (United States)

1992-12-31T23:59:59.000Z

358

Proceedings of the twelfth target fabrication specialists` meeting  

SciTech Connect (OSTI)

Research in fabrication for inertial confinement fusion (ICF) comprises at least three broad categories: targets for high energy density physics on existing drivers, ignition capsule fabrication, and cryogenic fuel layer formation. The latter two are being pursued primarily for the National Ignition Facility (NIF). Scientists from over 14 laboratories, universities, and businesses contributed over 100 papers on all aspects of ICF target fabrication. The NIF is well along in construction and photos of poured concrete and exposed steel added to the technical excitement. It was clear from the meeting that there has been significant progress toward the fabrication of an ignition target for NIF and that new techniques are resulting in higher quality targets for high energy density research.

NONE

1999-04-01T23:59:59.000Z

359

Irradiation Test of Advanced PWR Fuel in Fuel Test Loop at HANARO  

SciTech Connect (OSTI)

A new fuel test loop has been constructed in the research reactor HANARO at KAERI. The main objective of the FTL (Fuel Test Loop) is an irradiation test of a newly developed LWR fuel under PWR or Candu simulated conditions. The first test rod will be loaded within 2007 and its irradiation test will be continued until a rod average their of 62 MWd/kgU. A total of five test rods can be loaded into the IPS (In-Pile Section) and fuel centerline temperature, rod internal pressure and fuel stack elongation can be measured by an on-line real time system. A newly developed advanced PWR fuel which consists of a HANA{sup TM} alloy cladding and a large grain UO{sub 2} pellet was selected as the first test fuel in the FTL. The fuel cladding, the HANA{sup TM} alloy, is an Nb containing Zirconium alloy that has shown better corrosion and creep resistance properties than the current Zircaloy-4 cladding. A total of six types of HANA{sup TM} alloy were developed and two or three of these candidate alloys will be used as test rod cladding, which have shown a superior performance to the others. A large-grain UO{sub 2} pellet has a 14{approx}16 micron 2D diameter grain size for a reduction of a fission gas release at a high burnup. In this paper, characteristics of the FTL and IPS are introduced and the expected operation and irradiation conditions are summarized for the test periods. Also the preliminary fuel performance analysis results, such as the cladding oxide thickness, fission gas release and rod internal pressure, are evaluated from the test rod safety analysis aspects. (authors)

Yang, Yong Sik; Bang, Je Geon; Kim, Sun Ki; Song, Kun Woo [LWR Fuel Development Division, Korea Atomic Energy Research Institute, 1045, Daedeok-daero, Yuseong-gu, Daejeon, 305-353 (Korea, Republic of); Park, Su Ki [HANARO Utilization Technology Development Division, Korea Atomic Energy Research Institute, 1045, Daedeok-daero, Yuseong-gu, Daejeon, 305-353 (Korea, Republic of); Seo, Chul Gyo [HANARO Management Division, Korea Atomic Energy Research Institute, 1045, Daedeok-daero, Yuseong-gu, Daejeon, 305-353 (Korea, Republic of)

2007-07-01T23:59:59.000Z

360

Fuel Cells  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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Note: This page contains sample records for the topic "fuel pellet fabrication" 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

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

SciTech Connect (OSTI)

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

362

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

363

The Dissolution and Characterization of Aluminum Clad Oxide Fuel  

SciTech Connect (OSTI)

Laboratory dissolution studies of aluminum clad mixed oxide fuel rods have been conducted using two different F-Canyon decladding and dissolving flowsheets. During the first phase of the experimental program, materials from three different color coded fuel rods were dissolved in caustic and nitric acid solutions. The final phase of the laboratory program involved the dissolution and characterization of materials from three cracked pellet fuel rods using a selected caustic/ nitric acid flowsheet.Laboratory results obtained from the initial dissolution studies identified several inconsistencies and potential problem issues with the behavior of materials from the color coded fuel rods. Based on these findings and influenced by the difficulties introduced by using the RCRA listed mercury during processing, the flowsheet selected for dissolving these aluminum clad fuel rods in F-Canyon dissolvers was the two- step caustic decladding/ nitric acid dissolution flowsheet.The final phase of the experimental program involved testing materials from three cracked pellet fuel rods using the selected flowsheet. Again all aluminum fuel rod components dissolved during the decladding step. However, some uranium and plutonium bearing solids remained with the caustic decladding solution which could be sent to waste. The quantities of uranium and plutonium expected to remain with the caustic solutions are small.Fluoride ions will need to be present in the nitric acid dissolver solution to dissolve all solids. At 0.05 molar fluoride concentration, no plutonium bearing solids remained in the product solutions.

Gray, J.H.

1998-10-26T23:59:59.000Z

364

JOUENAL DE PHYSIQUE CoZZoque C7, suppZ6rnent au n07, Tome 40, J u i l l e t 2979, vage C7-743 IONIZATION OF ISOLATED DEUTERIUM PELLETS BY NEODYMIUM LASER RADIATION  

E-Print Network [OSTI]

IONIZATION OF ISOLATED DEUTERIUM PELLETS BY NEODYMIUM LASER RADIATION H. Baurnhacker, H. Brinkschulte, W

Paris-Sud XI, Université de

365

Lithium pellet production (LiPP): A device for the production of small spheres of lithium  

SciTech Connect (OSTI)

With lithium as a fusion material gaining popularity, a method for producing lithium pellets relatively quickly has been developed for NSTX. The Lithium Pellet Production device is based on an injector with a sub-millimeter diameter orifice and relies on a jet of liquid lithium breaking apart into small spheres via the Plateau-Rayleigh instability. A prototype device is presented in this paper and for a pressure difference of {Delta}P= 5 Torr, spheres with diameters between 0.91 < D < 1.37 mm have been produced with an average diameter of D= 1.14 mm, which agrees with the developed theory. Successive tests performed at Princeton Plasma Physics Laboratory with Wood's metal have confirmed the dependence of sphere diameter on pressure difference as predicted.

Fiflis, P.; Andrucyzk, D.; McGuire, M.; Curreli, D.; Ruzic, D. N. [Center for Plasma Material Interactions, Department of Nuclear, Plasma, and Radiological Engineering, University of Illinois at Urbana-Champaign, Urbana, Illinois 61801 (United States); Roquemore, A. L. [Princeton Plasma Physics Laboratory, Princeton, New Jersey 08540 (United States)

2013-06-15T23:59:59.000Z

366

Tracked pellets - a way to improve the efficiency of charmonium studies  

E-Print Network [OSTI]

We investigate the possibility of tracking individual hydrogen micro-spheres from an internal pellet target. Such a method aims to provide the primary vertex of a reaction to within about 100 micrometres, without utilizing any detector response. Apart from background considerations the knowledge of the reaction vertex may be essential for the reconstruction of many physics channels. This is in particular true for the study of the Psi(3770) decay into D-mesons planned at the PANDA detector at the future FAIR facility. Here, the reconstruction of displaced vertices is especially difficult since neutral particles are involved. Studies with a pellet target at The Svedberg Laboratory, Uppsala, show the technical feasibility of a tracking system utilizing fast CCD line-scan cameras. Simulations for the reaction p-bar p to Psi(3770) to D+ D- prove the large impact such a system would have on the data taking and reconstruction at PANDA.

Nordhage, O; Lith, J; Friden, C J; Wiedner, U

2006-01-01T23:59:59.000Z

367

Process and system for producing high-density pellets from a gaseous medium  

DOE Patents [OSTI]

A process and system for producing pellets of high density carbon dioxide or other gases utilize a chamber containing a plurality of cell-like freezing compartments within which ice is to be formed. A gas desired to be frozen into ice is introduced into the chamber while the internal pressure of the chamber is maintained at a level which is below the equilibrium triple pressure of the gas. The temperature of the freezing compartments is lowered to a temperature which is below the equilibrium vapor pressure temperature of the gas at the chamber pressure so that the gas condenses into ice within the compartments. The temperature of the freezing compartments is thereafter raised so that the ice is thereby released from and falls out of the compartments as pellets for collection.

Foster, Christopher A. (Clinton, TN)

1999-01-01T23:59:59.000Z

368

Cost and Schedule of the Mixed Oxide Fuel Fabrication Facility...  

Broader source: Energy.gov (indexed) [DOE]

at the Savannah River Site" BACKGROUND In September 2000, the United States and Russia signed a Plutonium Management and Disposition Agreement for the disposal of surplus...

369

Tritium assay of Li sub 2 O pellets in the LBM/LOTUS experiments  

SciTech Connect (OSTI)

One of the objectives of the Lithium Blanket Module (LBM) program is to test the ability of advanced neutronics codes to model the tritium breeding characteristics of a fusion blanket exposed to a toroidal fusion neutron source. The LBM consists of over 20,000 cylindrical lithium oxide pellets and numerous diagnostic pellets and wafers. The LBM has been irradiated at the Ecole Polytechnique Federale de Lausanne (EPFL) LOTUS facility with a Haefely sealed neutron generator that gives a point deuterium-tritium neutron source up to 5 {times} 10{sup 12} 14-MeV n/s. Both Princeton Plasma Physics Laboratory (PPL) and EPFL assayed the tritium bred at various positions in the LBM. EPFL employed a dissolution technique while PPL recovered the tritium by a thermal extraction method. EPFL uses 0.38-g, 75% TD, lithium oxide diagnostic wafers to evaluate the tritium bred in the LBM. PPPL employs a thermal extraction method to determine the tritium bred in lithium oxide samples. In the initial experiments, diagnostic pellets and wafers were placed at five locations in the LBM central removable test rod at distances of 3, 9, 21, 36, and 48 cm from the front face of the module. The two sets of data for the tritium bred in the LBM along its centerline as a function of distance from the front face of the module were compared with each other, and with the predictions of two-dimensional neutronics codes. 1 ref.

Quanci, J.; Azam, S.; Bertone, P.

1986-01-01T23:59:59.000Z

370

Effects of pelleting, dietary protein level and unidentified factors on feed cost and the performance of egg type layers  

E-Print Network [OSTI]

EFFECTS OF PELLETING, DIETARY PROTEIN LEVEL AND UNIDENTIFIED FACTORS ON FEED COST AND THE PERFORMANCE OF EGG TYPE LAYERS A Thesis by Hector Reruns]eewa Submitted to the Graduate School of the Agricultural and Mechanical College of Texas... in Partial Fulfillment of the requirements for the Degree of Master of Science August 1961 Ma)or Sub)ect - Poultry Science EPPECTS OP PELLETING, DIETARY PROTEIN LEVEL AND DNIDENTIPTED FACTORS ON PEED COST AND THE PERFORNANCE OP BIN' TTPE LAYERS A...

Karunajeewa, Hector

1961-01-01T23:59:59.000Z

371

Effect of process variables on the density and durability of the pellets made from high moisture corn stover  

SciTech Connect (OSTI)

A flat die pellet mill was used to understand the effect of high levels of feedstock moisture content in the range of 2838% (w.b.), with die rotational speeds of 4060 Hz, and preheating temperatures of 30110 C on the pelleting characteristics of 4.8 mm screen size ground corn stover using an 8 mm pellet die. The physical properties of the pelletised biomass studied are: (a) pellet moisture content, (b) unit, bulk and tapped density, and (c) durability. Pelletisation experiments were conducted based on central composite design. Analysis of variance (ANOVA) indicated that feedstock moisture content influenced all of the physical properties at P < 0.001. Pellet moisture content decreased with increase in preheating temperature to about 110 C and decreasing the feedstock moisture content to about 28% (w.b.). Response surface models developed for quality attributes with respect to process variables has adequately described the process with coefficient of determination (R2) values of >0.88. The other pellet quality attributes such as unit, bulk, tapped density, were maximised at feedstock moisture content of 3033% (w.b.), die speeds of >50 Hz and preheating temperature of >90 C. In case of durability a medium moisture content of 3334% (w.b.) and preheating temperatures of >70 C and higher die speeds >50 Hz resulted in high durable pellets. It can be concluded from the present study that feedstock moisture content, followed by preheating, and die rotational speed are the interacting process variables influencing pellet moisture content, unit, bulk and tapped density and durability.

Jaya Shankar Tumuluru

2014-03-01T23:59:59.000Z

372

Synthetic Fuel  

ScienceCinema (OSTI)

Two global energy priorities today are finding environmentally friendly alternatives to fossil fuels, and reducing greenhouse gass Two global energy priorities today are finding environmentally friendly alternatives to fossil fuels, and reducing greenhous

Idaho National Laboratory - Steve Herring, Jim O'Brien, Carl Stoots

2010-01-08T23:59:59.000Z

373

Fuel Economy  

Broader source: Energy.gov [DOE]

The Energy Department is investing in groundbreaking research that will make cars weigh less, drive further and consume less fuel.

374

Evaluation of Novel and Low-Cost Materials for Bipolar Plates in PEM Fuel Cells.  

E-Print Network [OSTI]

??Bipolar plate material and fabrication costs make up a significant fraction of the total cost in a polymer electrolyte membrane fuel cell stack. In an (more)

Desrosiers, Kevin Campbell

2002-01-01T23:59:59.000Z

375

Transportation Fuels  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas ConchasPassiveSubmittedStatusButler TinaContact-Information-TransmissionLaboratoryFuels

376

Fuel Cells  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-SeriesFlickr Flickr Editor's note:Computing | ArgonnechallengingFryFuel

377

PPPL3238 Preprint: February 1997, UC420 The Role of the Neutral Beam Fueling Profile in the Performance of the  

E-Print Network [OSTI]

of the heating beam fueling profile shape. Ion energy confinement and neutron production are relatively confinement and neutron production can be applied to all beam heated deuterium (D) discharges in TFTR [7], limiter High­mode (H­mode) plasmas [8], and Supershots enhanced by Lithium (Li) pellet

378

PPPL-3238 -Preprint: February 1997, UC-420 The Role of the Neutral Beam Fueling Profile in the Performance of the  

E-Print Network [OSTI]

of the heating beam fueling profile shape. Ion energy confinement and neutron production are relatively confinement and neutron production can be applied to all beam heated deuterium (D) discharges in TFTR [7], limiter High-mode (H-mode) plasmas [8], and Supershots enhanced by Lithium (Li) pellet

379

TPOP-II: Tritium Fueling at a Re P. W. Fisher and M. J. Gouge Oak Ridge National Labora  

E-Print Network [OSTI]

TPOP-II: Tritium Fueling at a Re Scale P. W. Fisher and M. J. Gouge Oak Ridge National Labora properties of extruded t repeating single-stage pneumatic pellet injector, called the Tritium-Proof-o Phase at the Los Alamos Nati Laboratory Tritium Systems Test Assembly (TSTA). About 38 g of tritium utilized

380

Woodfuel Usage Update 1 I Wood fuel use in Scotland 2012 I Hudson Consulting I November 2012  

E-Print Network [OSTI]

. Existing plant demand is forecast to grow in 2012, and together with projects currently in the building phase, total wood fuel demand is forecast to rise to 678k odt in 2012 and to 946k odt in 2013 80k odt of wood in 2011. There is a major increase in forecast demand for wood to be used as pellet

Note: This page contains sample records for the topic "fuel pellet fabrication" 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

Recovery of weapon plutonium as feed material for reactor fuel  

SciTech Connect (OSTI)

This report presents preliminary considerations for recovering and converting weapon plutonium from various US weapon forms into feed material for fabrication of reactor fuel elements. An ongoing DOE study addresses the disposition of excess weapon plutonium through its use as fuel for nuclear power reactors and subsequent disposal as spent fuel. The spent fuel would have characteristics similar to those of commercial power spent fuel and could be similarly disposed of in a geologic repository.

Armantrout, G.A.; Bronson, M.A.; Choi, Jor-Shan [and others

1994-03-16T23:59:59.000Z

382

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

SciTech Connect (OSTI)

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

383

Enforcement Letter, Parsons Technology Development & Fabrication...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

Technology Development & Fabrication Complex - April 13, 2010 Enforcement Letter, Parsons Technology Development & Fabrication Complex - April 13, 2010 April 13, 2010 Issued to...

384

A Validation Study of Pin Heat Transfer for MOX Fuel Based on the IFA-597 Experiments  

SciTech Connect (OSTI)

Abstract The IFA-597 (Integrated Fuel Assessment) experiments from the International Fuel Performance Experiments (IFPE) database were designed to study the thermal behavior of mixed oxide (MOX) fuel and the effects of an annulus on fission gas release in light-water-reactor fuel. An evaluation of nuclear fuel pin heat transfer in the FRAPCON-3.4 and Exnihilo codes for MOX fuel systems was performed, with a focus on the first 20 time steps ( 6 GWd/MT(iHM)) for explicit comparison between the codes. In addition, sensitivity studies were performed to evaluate the effect of the radial power shape and approximations to the geometry to account for the thermocouple hole, dish, and chamfer. The analysis demonstrated relative agreement for both solid (rod 1) and annular (rod 2) fuel in the experiment, demonstrating the accuracy of the codes and their underlying material models for MOX fuel, while also revealing a small energy loss artifact in how gap conductance is currently handled in Exnihilo for chamfered fuel pellets. The within-pellet power shape was shown to significantly impact the predicted centerline temperatures. This has provided an initial benchmarking of the pin heat transfer capability of Exnihilo for MOX fuel with respect to a well-validated nuclear fuel performance code.

Phillippe, Aaron M [ORNL; Clarno, Kevin T [ORNL; Banfield, James E [ORNL; Ott, Larry J [ORNL; Philip, Bobby [ORNL; Berrill, Mark A [ORNL; Sampath, Rahul S [ORNL; Allu, Srikanth [ORNL; Hamilton, Steven P [ORNL

2014-01-01T23:59:59.000Z

385

Biodiesel Fuel  

E-Print Network [OSTI]

publication 442-880 There are broad and increasing interests across the nation in using domestic, renewable bioenergy. Virginia farmers and transportation fleets use considerable amounts of diesel fuel in their operations. Biodiesel is an excellent alternative fuel for the diesel engines. Biodiesel can be produced from crops commonly grown in Virginia, such as soybean and canola, and has almost the same performance as petrodiesel. The purpose of this publication is to introduce the basics of biodiesel fuel and address some myths and answer some questions about biodiesel fuel before farmers and fleet owners use this type of fuel. ASTM standard for biodiesel (ASTM D6751) Biodiesel fuel, hereafter referred to as simply biodiesel,

unknown authors

386

MOX Lead Assembly Fabrication at the Savannah River Site  

SciTech Connect (OSTI)

The U. S. Department of Energy (DOE) announced its intent to prepare an Environmental Impact Statement (EIS) under the National Environmental Policy Act (NEPA) on the disposition of the nations weapon-usable surplus plutonium.This EIS is tiered from the Storage and Disposition of Weapons-Usable Fissile Material Programmatic Environmental Impact Statement issued in December 1996,and the associated Record of Decision issued on January, 1997. The EIS will examine reasonable alternatives and potential environmental impacts for the proposed siting, construction, and operation of three types of facilities for plutonium disposition. The three types of facilities are: a pit disassembly and conversion facility, a facility to immobilize surplus plutonium in a glass or ceramic form for disposition, and a facility to fabricate plutonium oxide into mixed oxide (MOX) fuel.As an integral part of the surplus plutonium program, Oak Ridge National Laboratory (ORNL) was tasked by the DOE Office of Fissile Material Disposition(MD) as the technical lead to organize and evaluate existing facilities in the DOE complex which may meet MD`s need for a domestic MOX fuel fabrication demonstration facility. The Lead Assembly (LA) facility is to produce 1 MT of usable test fuel per year for three years. The Savannah River Site (SRS) as the only operating plutonium processing site in the DOE complex, proposes two options to carry out the fabrication of MOX fuel lead test assemblies: an all Category I facility option and a combined Category I and non-Category I facilities option.

Geddes, R.L. [Westinghouse Savannah River Company, AIKEN, SC (United States); Spiker, D.L.; Poon, A.P.

1997-12-01T23:59:59.000Z

387

Fuel Cells  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsing ZirconiaPolicyFeasibilityFieldMinds"OfficeTourFrom3, 2015

388

Standard test method for determination of uranium or gadolinium (or both) in gadolinium oxide-uranium oxide pellets or by X-ray fluorescence (XRF)  

E-Print Network [OSTI]

Standard test method for determination of uranium or gadolinium (or both) in gadolinium oxide-uranium oxide pellets or by X-ray fluorescence (XRF)

American Society for Testing and Materials. Philadelphia

2008-01-01T23:59:59.000Z

389

Feasibility of Partial ZrO[subscript 2] Coatings on Outer Surface of Annular UO[subscript 2] Pellets to Control Gap Conductance  

E-Print Network [OSTI]

The viability of depositing a thin porous coating of zirconia on the outer surface of an annular UO[subscript 2] pellet

Feinroth, H.

390

Equipment specifications for an electrochemical fuel reprocessing plant  

SciTech Connect (OSTI)

Electrochemical reprocessing is a technique used to chemically separate and dissolve the components of spent nuclear fuel, in order to produce new metal fuel. There are several different variations to electrochemical reprocessing. These variations are accounted for by both the production of different types of spent nuclear fuel, as well as different states and organizations doing research in the field. For this electrochemical reprocessing plant, the spent fuel will be in the metallurgical form, a product of fast breeder reactors, which are used in many nuclear power plants. The equipment line for this process is divided into two main categories, the fuel refining equipment and the fuel fabrication equipment. The fuel refining equipment is responsible for separating out the plutonium and uranium together, while getting rid of the minor transuranic elements and fission products. The fuel fabrication equipment will then convert this plutonium and uranium mixture into readily usable metal fuel.

Hemphill, Kevin P [Los Alamos National Laboratory

2010-01-01T23:59:59.000Z

391

Assessment of reduction behavior of hematite iron ore pellets in coal fines for application in sponge ironmaking  

SciTech Connect (OSTI)

Studies on isothermal reduction kinetics (with F grade coal) in fired pellets of hematite iron ores, procured from four different mines of Orissa, were carried out in the temperature range of 850-1000C to provide information for the Indian sponge iron plants. The rate of reduction in all the fired iron ore pellets increased markedly with a rise of temperature up to 950C, and thereafter it decreased at 1000C. The rate was more intense in the first 30 minutes. All iron ores exhibited almost complete reduction in their pellets at temperatures of 900 and 950C in 2 hours' heating time duration, and the final product morphologies consisted of prominent cracks. The kinetic model equation 1-(1-a){sup 1/3}=kt was found to fit best to the experimental data, and the values of apparent activation energy were evaluated. Reductions of D. R. Pattnaik and M. G. Mohanty iron ore pellets were characterized by higher activation energies (183 and 150 kJ mol{sup -1}), indicating carbon gasification reaction to be the rate-controlling step. The results established lower values of activation energy (83 and 84 kJ mol{sup -1}) for the reduction of G. M. OMC Ltd. and Sakaruddin iron ore pellets, proposing their overall rates to be controlled by indirect reduction reactions.

Kumar, M.; Patel, S.K. [National Institute of Technology, Rourkela (India)

2009-07-01T23:59:59.000Z

392

Studies on the reduction kinetics of hematite iron ore pellets with noncoking coals for sponge iron plants  

SciTech Connect (OSTI)

In the present investigation, fired pellets were made by mixing hematite iron ore fines of -100, -16+18, and -8+10 mesh size in different ratios and studies on their reduction kinetics in Lakhanpur, Orient OC-2 and Belpahar coals were carried out at temperatures ranging from 850{sup o}C to 1000{sup o}C with a view toward promoting the massive utilization of fines in ironmaking. The rate of reduction in all the fired iron ore pellets increased markedly with an increase in temperature up to 1000{sup o}C, and it was more intense in the first 30min. The values of activation energy, calculated from integral and differential approaches, for the reduction of fired pellets (prepared from iron ore fines of -100 mesh size) in coals were found to be in the range 131-148 and 130-181 kJ mol{sup -1} (for =0.2 to 0.8), indicating the process is controlled by a carbon gasification reaction. The addition of selected larger size particles in the matrix of -100 mesh size fines up to the extent studied decreased the activation energy and slightly increased the reduction rates of resultant fired pellets. In comparison to coal, the reduction of fired pellets in char was characterized by significantly lower reduction rates and higher activation energy.

Kumar, M.; Mohapatra, P.; Patel, S.K. [National Institute of Technology, Rourkela (India). Dept. of Mechanical Engineering

2009-07-01T23:59:59.000Z

393

Design and Testing of Prototypic Elements Containing Monolithic Fuel  

SciTech Connect (OSTI)

The US fuel development team has performed numerous irradiation tests on small to medium sized specimens containing low enriched uranium fuel designs. The team is now focused on qualification and demonstration of the uranium-molybdenum Base Monolithic Design and has entered the next generation of testing with the design and irradiation of prototypic elements which contain this fuel. The designs of fuel elements containing monolithic fuel, such as AFIP-7 (which is currently under irradiation) and RERTR-FE (which is currently under fabrication), are appropriate progressions relative to the technology life cycle. The culmination of this testing program will occur with the design, fabrication, and irradiation of demonstration products to include the base fuel demonstration and design demonstration experiments. Future plans show that design, fabrication, and testing activities will apply the rigor needed for a demonstration campaign.

N.E. Woolstenhulme; M.K. Meyer; D.M. Wachs

2011-10-01T23:59:59.000Z

394

Fuel-cycle facilities: preliminary safety and environmental information document. Volume VII  

SciTech Connect (OSTI)

Information is presented concerning the mining and milling of uranium and thorium; uranium hexafluoride conversion; enrichment; fuel fabrication; reprocessing; storage options; waste disposal options; transportation; heavy-water-production facilities; and international fuel service centers.

Not Available

1980-01-01T23:59:59.000Z

395

Evaluation and validation of criticality codes for fuel dissolver calculations  

SciTech Connect (OSTI)

During the past ten years an OECD/NEA Criticality Working Group has examined the validity of criticality safety computational methods. International calculation tools which were shown to be valid in systems for which experimental data existed were demonstrated to be inadequate when extrapolated to fuel dissolver media. The spread of the results in the international calculation amounted to {plus minus} 12,000 pcm in the realistic fuel dissolver exercise n{degrees} 19 proposed by BNFL, and to {plus minus} 25,000 pcm in the benchmark n{degrees} 20 in which fissile material in solid form is surrounded by fissile material in solution. A theoretical study of the main physical parameters involved in fuel dissolution calculations was performed, i.e. range of moderation, variation of pellet size and the fuel double heterogeneity effect. The APOLLO/P{sub IC} method developed to treat latter effect, permits us to supply the actual reactivity variation with pellet dissolution and to propose international reference values. The disagreement among contributors' calculations was analyzed through a neutron balance breakdown, based on three-group microscopic reaction rates solicited from the participants. The results pointed out that fast and resonance nuclear data in criticality codes are not sufficiently reliable. Moreover the neutron balance analysis emphasized the inadequacy of the standard self-shielding formalism (NITAWL in the international SCALE package) to account for {sup 238}U resonance mutual self-shielding in the pellet-fissile liquor interaction. Improvements in the up-dated 1990 contributions, as do recent complementary reference calculations (MCNP, VIM, ultrafine slowing-down CGM calculation), confirm the need to use rigorous self-shielding methods in criticality design-oriented codes. 6 refs., 11 figs., 3 tabs.

Santamarina, A.; Smith, H.J. (CEA Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-lez-Durance (France)); Whitesides, G.E. (Oak Ridge National Lab., TN (United States))

1991-01-01T23:59:59.000Z

396

Tenth target fabrication specialists` meeting: Proceedings  

SciTech Connect (OSTI)

This tenth meeting of specialists in target fabrication for inertial confinement is unique in that it is the first meeting that was completely unclassified. As a result of the new classification, we were able to invite more foreign participation. In addition to participants from the US, UK, and Canada, representatives from France, Japan, and two Russian laboratories attended, about 115 in all. This booklet presents full papers and poster sessions. Indirect and direct drive laser implosions are considered. Typical topics include: polymer or aluminium or resorcinol/formaldehyde shells, laser technology, photon tunneling microscopy as a characterization tool, foams, coatings, hohlraums, and beryllium capsules. Hydrogen, deuterium, tritium, and beryllium are all considered as fuels.

Foreman, L.R.; Stark, J.C. [comp.

1995-11-01T23:59:59.000Z

397

Los Alamos National Laboratory summary plan to fabricate mixed oxide lead assemblies for the fissile material disposition program  

SciTech Connect (OSTI)

This report summarizes an approach for using existing Los Alamos National Laboratory (Laboratory) mixed oxide (MOX) fuel-fabrication and plutonium processing capabilities to expedite and assure progress in the MOX/Reactor Plutonium Disposition Program. Lead Assembly MOX fabrication is required to provide prototypic fuel for testing in support of fuel qualification and licensing requirements. It is also required to provide a bridge for the full utilization of the European fabrication experience. In part, this bridge helps establish, for the first time since the early 1980s, a US experience base for meeting the safety, licensing, safeguards, security, and materials control and accountability requirements of the Department of Energy and Nuclear Regulatory Commission. In addition, a link is needed between the current research and development program and the production of disposition mission fuel. This link would also help provide a knowledge base for US regulators. Early MOX fabrication and irradiation testing in commercial nuclear reactors would provide a positive demonstration to Russia (and to potential vendors, designers, fabricators, and utilities) that the US has serious intent to proceed with plutonium disposition. This report summarizes an approach to fabricating lead assembly MOX fuel using the existing MOX fuel-fabrication infrastructure at the Laboratory.

Buksa, J.J.; Eaton, S.L.; Trellue, H.R.; Chidester, K.; Bowidowicz, M.; Morley, R.A.; Barr, M.

1997-12-01T23:59:59.000Z

398

Structure and yarn sensor for fabric  

DOE Patents [OSTI]

A structure and yarn sensor for fabric directly determines pick density in a fabric thereby allowing fabric length and velocity to be calculated from a count of the picks made by the sensor over known time intervals. The structure and yarn sensor is also capable of detecting full length woven defects and fabric. As a result, an inexpensive on-line pick (or course) density measurement can be performed which allows a loom or knitting machine to be adjusted by either manual or automatic means to maintain closer fiber density tolerances. Such a sensor apparatus dramatically reduces fabric production costs and significantly improves fabric consistency and quality for woven or knitted fabric.

Mee, David K. (Knoxville, TN); Allgood, Glenn O. (Powell, TN); Mooney, Larry R. (Knoxville, TN); Duncan, Michael G. (Clinton, TN); Turner, John C. (Clinton, TN); Treece, Dale A. (Knoxville, TN)

1998-01-01T23:59:59.000Z

399

Production and blast-furnace smelting of boron-alloyed iron-ore pellets  

SciTech Connect (OSTI)

Industrial test data are presented regarding the production (at Sokolovsk-Sarbaisk mining and enrichment enterprise) and blast-furnace smelting (at Magnitogorsk metallurgical works) of boron-alloyed iron-ore pellets (500000 t). It is shown that, thanks to the presence of boron, the compressive strength of the roasted pellets is increased by 18.5%, while the strength in reduction is doubled; the limestone consumption is reduced by 11%, the bentonite consumption is halved, and the dust content of the gases in the last section of the roasting machines is reduced by 20%. In blast-furnace smelting, the yield of low-sulfur (<0.02%) hot metal is increased from 65-70 to 85.1% and the furnace productivity from 2.17-2.20 to 2.27 t/(m{sup 3} day); coke consumption is reduced by 3-8 kg/t of hot metal. The plasticity and stamping properties of 08IO auto-industry steel are improved by microadditions of boron.

A.A. Akberdin; A.S. Kim [Abishev Chemicometallurgical Institute, Abishev (Kazakhstan)

2008-08-15T23:59:59.000Z

400

Simulating Pelletization Strategies to Reduce the Biomass Supply Risk at Americas Biorefineries  

SciTech Connect (OSTI)

Demand for cellulosic ethanol and other advanced biofuels has been on the rise, due in part to federal targets enacted in 2005 and extended in 2007. The industry faces major challenges in meeting these worthwhile and ambitious targets. The challenges are especially severe in the logistics of timely feedstock delivery to biorefineries. Logistical difficulties arise from seasonal production that forces the biomass to be stored in uncontrolled field-side environments. In this storage format physical difficulties arise; transportation is hindered by the low bulk density of baled biomass and the unprotected material can decay leading to unpredictable losses. Additionally, uncertain yields and contractual difficulties can exacerbate these challenges making biorefineries a high-risk venture. Investors risk could limit business entry and prevent America from reaching the targets. This paper explores pelletizer strategies to convert the lignocellulosic biomass into a denser form more suitable for storage. The densification of biomass would reduce supply risks, and the new system would outperform conventional biorefinery supply systems. Pelletizer strategies exhibit somewhat higher costs, but the reduction in risk is well worth the extra cost if America is to grow the advanced biofuels industry in a sustainable manner.

Jacob J. Jacobson; Shane Carnohan; Andrew Ford; Allyson Beall

2014-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "fuel pellet fabrication" 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.


401

ME 4171 Environmentally Conscious Design & Manufacturing (Bras) Assignment Aircraft Fuel Tank Production Pollution Prevention  

E-Print Network [OSTI]

ME 4171 ­ Environmentally Conscious Design & Manufacturing (Bras) Assignment ­ Aircraft Fuel Tank Production Pollution Prevention A local company manufactures a wide variety of fabric fuel tanks for use mainly in the aircraft industry. The main reasons for using fabric in the construction of these tanks

402

Fully Ceramic Microencapsulated Fuel Development for LWR Applications  

SciTech Connect (OSTI)

The concept, fabrication, and key feasibility issues of a new fuel form based on the microencapsulated (TRISO-type) fuel which has been specifically engineered for LWR application and compacted within a SiC matrix will be presented. This fuel, the so-called fully ceramic microencapsulated fuel is currently undergoing development as an accident tolerant fuel for potential UO2 replacement in commercial LWRs. While the ability of this fuel to facilitate normal LWR cycle performance is an ongoing effort within the program, this will not be a focus of this paper. Rather, key feasibility and performance aspects of the fuel will be presented including the ability to fabricate a LWR-specific TRISO, the need for and route to a high thermal conductivity and fully dense matrix that contains neutron poisons, and the performance of that matrix under irradiation and the interaction of the fuel with commercial zircaloy clad.

Snead, Lance Lewis [ORNL; Besmann, Theodore M [ORNL; Terrani, Kurt A [ORNL; Voit, Stewart L [ORNL

2012-01-01T23:59:59.000Z

403

lOS :II. PELLET. -COXTHIBDTIOX GAUCHER, de l'action mcanique de l'estom~c et de la dure du sjour  

E-Print Network [OSTI]

lOS :II. PELLET. - COXTHIBDTIOX GAUCHER, de l'action mécanique de l'estom~c et de la durée du animaux. CONTRIBUTION' A L'?TUDE DU LAIT ST?RILIS? par :M. PELLET, Ingénieur agronome. (8uite) IV

Boyer, Edmond

404

Reduction of Edge Localized Mode Intensity on DIII-D by On-demand triggering with High Frequency Pellet Injection and Implications for ITER  

SciTech Connect (OSTI)

The injection of small deuterium pellets at high repetition rates up to 12 the natural edge localized mode (ELM) frequency has been used to trigger high-frequency ELMs in otherwise low natural ELM frequency H-mode deuterium discharges in the DIII-D tokamak [J. L. Luxon and L. G. Davis, Fusion Technol. 8, 441 (1985)]. The resulting pellet-triggered ELMs result in up to 12 lower energy and particle fluxes to the divertor than the natural ELMs. The plasma global energy confinement and density are not strongly affected by the pellet perturbations. The plasma core impurity density is strongly reduced with the application of the pellets. These experiments were performed with pellets injected from the low field side pellet in plasmas designed to match the ITER baseline configuration in shape and normalized operation with input heating power just above the H-mode power threshold. Nonlinear MHD simulations of the injected pellets show that destabilization of ballooning modes by a local pressure perturbation is responsible for the pellet ELM triggering. This strongly reduced ELM intensity shows promise for exploitation in ITER to control ELM size while maintaining high plasma purity and performance.

Baylor, Larry R [ORNL; Commaux, Nicolas JC [ORNL; Jernigan, T. C. [Oak Ridge National Laboratory (ORNL); Meitner, Steven J [ORNL; Combs, Stephen Kirk [ORNL; Isler, Ralph C [ORNL; Unterberg, Ezekial A [ORNL; Brooks, N. H. [General Atomics, San Diego; Evans, T.E. [General Atomics, San Diego; Leonard, A. W. [General Atomics; Osborne, T. H. [General Atomics; Parks, P. B. [General Atomics; Snyder, P. B. [General Atomics; Strait, E. J. [General Atomics; Fenstermacher, M. E. [Lawrence Livermore National Laboratory (LLNL); Lasnier, C. J. [Lawrence Livermore National Laboratory (LLNL); Moyer, R.A. [University of California, San Diego; Loarte, A. [ITER Organization, Cadarache, France; Huijsmans, G.T.A. [ITER Organization, Saint Paul Lez Durance, France; Futantani, S. [ITER Organization, Saint Paul Lez Durance, France

2013-01-01T23:59:59.000Z

405

Reduction of edge localized mode intensity on DIII-D by on-demand triggering with high frequency pellet injection and implications for ITER  

SciTech Connect (OSTI)

The injection of small deuterium pellets at high repetition rates up to 12 the natural edge localized mode (ELM) frequency has been used to trigger high-frequency ELMs in otherwise low natural ELM frequency H-mode deuterium discharges in the DIII-D tokamak [J. L. Luxon and L. G. Davis, Fusion Technol. 8, 441 (1985)]. The resulting pellet-triggered ELMs result in up to 12 lower energy and particle fluxes to the divertor than the natural ELMs. The plasma global energy confinement and density are not strongly affected by the pellet perturbations. The plasma core impurity density is strongly reduced with the application of the pellets. These experiments were performed with pellets injected from the low field side pellet in plasmas designed to match the ITER baseline configuration in shape and normalized ? operation with input heating power just above the H-mode power threshold. Nonlinear MHD simulations of the injected pellets show that destabilization of ballooning modes by a local pressure perturbation is responsible for the pellet ELM triggering. This strongly reduced ELM intensity shows promise for exploitation in ITER to control ELM size while maintaining high plasma purity and performance.

Baylor, L. R.; Commaux, N.; Jernigan, T. C.; Meitner, S. J.; Combs, S. K.; Isler, R. C.; Unterberg, E. A. [Oak Ridge National Laboratory, PO Box 2008, Oak Ridge, Tennessee 37830-6169 (United States)] [Oak Ridge National Laboratory, PO Box 2008, Oak Ridge, Tennessee 37830-6169 (United States); Brooks, N. H.; Evans, T. E.; Leonard, A. W.; Osborne, T. H.; Parks, P. B.; Snyder, P. B.; Strait, E. J. [General Atomics, PO Box 85608, San Diego, California 92186-5608 (United States)] [General Atomics, PO Box 85608, San Diego, California 92186-5608 (United States); Fenstermacher, M. E.; Lasnier, C. J. [Lawrence Livermore National Laboratory, 700 East Ave, Livermore, California 94550 (United States)] [Lawrence Livermore National Laboratory, 700 East Ave, Livermore, California 94550 (United States); Moyer, R. A. [University of California San Diego, 9500 Gilman Dr., La Jolla, California 92093-0417 (United States)] [University of California San Diego, 9500 Gilman Dr., La Jolla, California 92093-0417 (United States); Loarte, A.; Huijsmans, G. T. A.; Futatani, S. [ITER Organization, Route de Vinon sur Verdon, 13115 St. Paul Lez Durance (France)] [ITER Organization, Route de Vinon sur Verdon, 13115 St. Paul Lez Durance (France)

2013-08-15T23:59:59.000Z

406

Electrochemical/Pyrometallurgical Waste Stream Processing and Waste Form Fabrication  

SciTech Connect (OSTI)

This report summarizes treatment and waste form options being evaluated for waste streams resulting from the electrochemical/pyrometallurgical (pyro ) processing of used oxide nuclear fuel. The technologies that are described are South Korean (Republic of Korea ROK) and United States of America (US) centric in the approach to treating pyroprocessing wastes and are based on the decade long collaborations between US and ROK researchers. Some of the general and advanced technologies described in this report will be demonstrated during the Integrated Recycle Test (IRT) to be conducted as a part of the Joint Fuel Cycle Study (JFCS) collaboration between US Department of Energy (DOE) and ROK national laboratories. The JFCS means to specifically address and evaluated the technological, economic, and safe guard issues associated with the treatment of used nuclear fuel by pyroprocessing. The IRT will involve the processing of commercial, used oxide fuel to recover uranium and transuranics. The recovered transuranics will then be fabricated into metallic fuel and irradiated to transmutate, or burn the transuranic elements to shorter lived radionuclides. In addition, the various process streams will be evaluated and tested for fission product removal, electrolytic salt recycle, minimization of actinide loss to waste streams and waste form fabrication and characterization. This report specifically addresses the production and testing of those waste forms to demonstrate their compatibility with treatment options and suitability for disposal.

Steven Frank; Hwan Seo Park; Yung Zun Cho; William Ebert; Brian Riley

2014-12-01T23:59:59.000Z

407

RERTR Fuel Developmemt and Qualification Plan  

SciTech Connect (OSTI)

In late 2003 it became evident that U-Mo aluminum fuels under development exhibited significant fuel performance problems under the irradiation conditions required for conversion of most high-powered research reactors. Solutions to the fuel performance issue have been proposed and show promise in early testing. Based on these results, a Reduced Enrichment Research and Test Reactor (RERTR) program strategy has been mapped to allow generic fuel qualification to occur prior to the end of FY10 and reactor conversion to occur prior to the end of FY14. This strategy utilizes a diversity of technologies, test conditions, and test types. Scoping studies using miniature fuel plates will be completed in the time frame of 2006-2008. Irradiation of larger specimens will occur in the Advanced Test Reactor (ATR) in the United States, the Belgian Reactor-2 (BR2) reactor in Belgium, and in the OSIRIS reactor in France in 2006-2009. These scoping irradiation tests provide a large amount of data on the performance of advanced fuel types under irradiation and allow the down selection of technology for larger scale testing during the final stages of fuel qualification. In conjunction with irradiation testing, fabrication processes must be developed and made available to commercial fabricators. The commercial fabrication infrastructure must also be upgraded to ensure a reliable low enriched uranium (LEU) fuel supply. Final qualification of fuels will occur in two phases. Phase I will obtain generic approval for use of dispersion fuels with density less than 8.5 g-U/cm3. In order to obtain this approval, a larger scale demonstration of fuel performance and fabrication technology will be necessary. Several Materials Test Reactor (MTR) plate-type fuel assemblies will be irradiated in both the High Flux Reactor (HFR) and the ATR (other options include the BR2 and Russian Research Reactor, Dmitrovgrad, Russia [MIR] reactors) in 2008-2009. Following postirradiation examination, a report detailing very-high density fuel behavior will be submitted to the U.S. Nuclear Regulatory Commission (NRC). Assuming acceptable fuel behavior, it is anticipated that NRC will issue a Safety Evaluation Report granting generic approval of the developed fuels based on the qualification report. It is anticipated that Phase I of fuel qualification will be completed prior to the end of FY10. Phase II of the fuel qualification requires development of fuels with density greater than 8.5 g-U/cm3. This fuel is required to convert the remaining few reactors that have been identified for conversion. The second phase of the fuel qualification effort includes both dispersion fuels with fuel particle volume loading on the order of 65 percent, and monolithic fuels. Phase II presents a larger set of technical unknowns and schedule uncertainties than phase I. The final step in the fuel qualification process involves insertion of lead test elements into the converting reactors. Each reactor that plans to convert using the developed high-density fuels will develop a reactor specific conversion plan based upon the reactor safety basis and operating requirements. For some reactors (FRM-II, High-Flux Isotope Reactor [HFIR], and RHF) conversion will be a one-step process. In addition to the U.S. fuel development effort, a Russian fuel development strategy has been developed. Contracts with Russian Federation institutes in support of fuel development for Russian are in place.

Dan Wachs

2007-01-01T23:59:59.000Z

408

Advanced Fuel Cycle Cost Basis  

SciTech Connect (OSTI)

This report, commissioned by the U.S. Department of Energy (DOE), provides a comprehensive set of cost data supporting a cost analysis for the relative economic comparison of options for use in the Advanced Fuel Cycle Initiative (AFCI) Program. The report describes the AFCI cost basis development process, reference information on AFCI cost modules, a procedure for estimating fuel cycle costs, economic evaluation guidelines, and a discussion on the integration of cost data into economic computer models. This report contains reference cost data for 25 cost modules23 fuel cycle cost modules and 2 reactor modules. The cost modules were developed in the areas of natural uranium mining and milling, conversion, enrichment, depleted uranium disposition, fuel fabrication, interim spent fuel storage, reprocessing, waste conditioning, spent nuclear fuel (SNF) packaging, long-term monitored retrievable storage, near surface disposal of low-level waste (LLW), geologic repository and other disposal concepts, and transportation processes for nuclear fuel, LLW, SNF, transuranic, and high-level waste.

D. E. Shropshire; K. A. Williams; W. B. Boore; J. D. Smith; B. W. Dixon; M. Dunzik-Gougar; R. D. Adams; D. Gombert; E. Schneider

2008-03-01T23:59:59.000Z

409

Advanced Fuel Cycle Cost Basis  

SciTech Connect (OSTI)

This report, commissioned by the U.S. Department of Energy (DOE), provides a comprehensive set of cost data supporting a cost analysis for the relative economic comparison of options for use in the Advanced Fuel Cycle Initiative (AFCI) Program. The report describes the AFCI cost basis development process, reference information on AFCI cost modules, a procedure for estimating fuel cycle costs, economic evaluation guidelines, and a discussion on the integration of cost data into economic computer models. This report contains reference cost data for 26 cost modules24 fuel cycle cost modules and 2 reactor modules. The cost modules were developed in the areas of natural uranium mining and milling, conversion, enrichment, depleted uranium disposition, fuel fabrication, interim spent fuel storage, reprocessing, waste conditioning, spent nuclear fuel (SNF) packaging, long-term monitored retrievable storage, near surface disposal of low-level waste (LLW), geologic repository and other disposal concepts, and transportation processes for nuclear fuel, LLW, SNF, and high-level waste.

D. E. Shropshire; K. A. Williams; W. B. Boore; J. D. Smith; B. W. Dixon; M. Dunzik-Gougar; R. D. Adams; D. Gombert

2007-04-01T23:59:59.000Z

410

The mechanics of pressed-pellet separators in molten salt batteries.  

SciTech Connect (OSTI)

We present a phenomenological constitutive model that describes the macroscopic behavior of pressed-pellet materials used in molten salt batteries. Such materials include separators, cathodes, and anodes. The purpose of this model is to describe the inelastic deformation associated with the melting of a key constituent, the electrolyte. At room temperature, all constituents of these materials are solid and do not transport cations so that the battery is inert. As the battery is heated, the electrolyte, a constituent typically present in the separator and cathode, melts and conducts charge by flowing through the solid skeletons of the anode, cathode, and separator. The electrochemical circuit is closed in this hot state of the battery. The focus of this report is on the thermal-mechanical behavior of the separator, which typically exhibits the most deformation of the three pellets during the process of activating a molten salt battery. Separator materials are composed of a compressed mixture of a powdered electrolyte, an inert binder phase, and void space. When the electrolyte melts, macroscopically one observes both a change in volume and shape of the separator that depends on the applied boundary conditions during the melt transition. Although porous flow plays a critical role in the battery mechanics and electrochemistry, the focus of this report is on separator behavior under flow-free conditions in which the total mass of electrolyte is static within the pellet. Specific poromechanics effects such as capillary pressure, pressure-saturation, and electrolyte transport between layers are not considered. Instead, a phenomenological model is presented to describe all such behaviors including the melting transition of the electrolyte, loss of void space, and isochoric plasticity associated with the binder phase rearrangement. The model is appropriate for use finite element analysis under finite deformation and finite temperature change conditions. The model reasonably describes the stress dependent volume and shape change associated with dead load compression and spring-type boundary conditions; the latter is relevant in molten salt batteries. Future work will transition the model towards describing the solid skeleton of the separator in the traditional poromechanics context.

Long, Kevin Nicholas; Roberts, Christine Cardinal; Roberts, Scott Alan; Grillet, Anne

2014-06-01T23:59:59.000Z

411

Possible effects of UO/sub 2/ oxidation on light water reactor spent fuel performance in long-term geologic disposal  

SciTech Connect (OSTI)

Disposal of spent nuclear fuel in a conventionally mined geologic formation is the nearest-term option for permanently isolating radionuclides from the biosphere. Because irradiated uranium dioxide (UO/sub 2/) fuel pellets retain 95 to 99% of the radionuclides generated during normal light water reactor operation, they may represent a significant barrier to radionuclide release. This document presents a technical assessment of published literature representing the current level of understanding of spent fuel characteristics and conditions that may degrade pellet integrity during a geologic disposal sequence. A significant deterioration mechanism is spent UO/sub 2/ oxidation with possible consequences identified as fission gas release, rod diameter increases, cladding breach extension, and release of solid fuel particles containing radionuclides. Areas requiring further study to support development of a comprehensive spent fuel performance prediction model are highlighted. A program and preliminary schedule to obtain the information needed to develop model correlations are also presented.

Almassy, M.Y.; Woodley, R.E.

1982-08-01T23:59:59.000Z

412

Fabrication of metallic glass structures  

DOE Patents [OSTI]

Amorphous metal powders or ribbons are fabricated into solid shapes of appreciable thickness by the application of compaction energy. The temperature regime wherein the amorphous metal deforms by viscous flow is measured. The metal powders or ribbons are compacted within the temperature regime.

Cline, C.F.

1983-10-20T23:59:59.000Z

413

Unconventional fuel: Tire derived fuel  

SciTech Connect (OSTI)

Material recovery of scrap tires for their fuel value has moved from a pioneering concept in the early 1980`s to a proven and continuous use in the United States` pulp and paper, utility, industrial, and cement industry. Pulp and paper`s use of tire derived fuel (TDF) is currently consuming tires at the rate of 35 million passenger tire equivalents (PTEs) per year. Twenty mills are known to be burning TDF on a continuous basis. The utility industry is currently consuming tires at the rate of 48 million PTEs per year. Thirteen utilities are known to be burning TDF on a continuous basis. The cement industry is currently consuming tires at the rate of 28 million PTEs per year. Twenty two cement plants are known to be burning TDF on a continuous basis. Other industrial boilers are currently consuming tires at the rate of 6.5 million PTEs per year. Four industrial boilers are known to be burning TDF on a continuous basis. In total, 59 facilities are currently burning over 117 million PTEs per year. Although 93% of these facilities were not engineered to burn TDF, it has become clear that TDF has found acceptance as a supplemental fuel when blending with conventional fuels in existing combustion devices designed for normal operating conditions. The issues of TDF as a supplemental fuel and its proper specifications are critical to the successful development of this fuel alternative. This paper will focus primarily on TDF`s use in a boiler type unit.

Hope, M.W. [Waste Recovery, Inc., Portland, OR (United States)

1995-09-01T23:59:59.000Z

414

Development of alkaline fuel cells.  

SciTech Connect (OSTI)

This project focuses on the development and demonstration of anion exchange membrane (AEM) fuel cells for portable power applications. Novel polymeric anion exchange membranes and ionomers with high chemical stabilities were prepared characterized by researchers at Sandia National Laboratories. Durable, non-precious metal catalysts were prepared by Dr. Plamen Atanassov's research group at the University of New Mexico by utilizing an aerosol-based process to prepare templated nano-structures. Dr. Andy Herring's group at the Colorado School of Mines combined all of these materials to fabricate and test membrane electrode assemblies for single cell testing in a methanol-fueled alkaline system. The highest power density achieved in this study was 54 mW/cm2 which was 90% of the project target and the highest reported power density for a direct methanol alkaline fuel cell.

Hibbs, Michael R.; Jenkins, Janelle E.; Alam, Todd Michael; Janarthanan, Rajeswari [Colorado School of Mines, Golden, CO; Horan, James L. [Colorado School of Mines, Golden, CO; Caire, Benjamin R. [Colorado School of Mines, Golden, CO; Ziegler, Zachary C. [Colorado School of Mines, Golden, CO; Herring, Andrew M. [Colorado School of Mines, Golden, CO; Yang, Yuan [Colorado School of Mines, Golden, CO; Zuo, Xiaobing [Argonne National Laboratory, Argonne, IL; Robson, Michael H. [University of New Mexico, Albuquerque, NM; Artyushkova, Kateryna [University of New Mexico, Albuquerque, NM; Patterson, Wendy [University of New Mexico, Albuquerque, NM; Atanassov, Plamen Borissov [University of New Mexico, Albuquerque, NM

2013-09-01T23:59:59.000Z

415

Yeast Genomic DNA Preparation from Spheroplasts 1. Resuspend with 50 mM Tris, 25 mM EDTA (pH 8) in 10X the spheroplast pellet volume.  

E-Print Network [OSTI]

) in 10X the spheroplast pellet volume. 2. Immediately add 1/10 volume of 10% SDS. Mix. 3. Incubate 30 up pellets. Wash for at least 5 minutes at 25°C. 11. Centrifuge 10 minutes in SS-34 rotor at 10,000 rpm at 4°C. Discard supernatant. 12. Drain and dry pellets on bench. Dissolve each pellet completely

Aris, John P.

416

BWR Fuel Assembly BWR Fuel Assembly PWR Fuel Assembly  

National Nuclear Security Administration (NNSA)

BWR Fuel Assembly BWR Fuel Assembly PWR Fuel Assembly PWR Fuel Assembly The PWR 17x17 assembly is approximately 160 inches long (13.3 feet), 8 inches across, and weighs 1,500 lbs....

417

Imminent: Irradiation Testing of (Th,Pu)O{sub 2} Fuel - 13560  

SciTech Connect (OSTI)

Commercial-prototype thorium-plutonium oxide (Th-MOX) fuel pellets have been loaded into the material test reactor in Halden, Norway. The fuel is being operated at full power - with instrumentation - in simulated LWR / PHWR conditions and its behaviour is measured 'on-line' as it operates to high burn-up. This is a vital test on the commercialization pathway for this robust new thoria-based fuel. The performance data that is collected will support a fuel modeling effort to support its safety qualification. Several different samples of Th-MOX fuel will be tested, thereby collecting information on ceramic behaviours and their microstructure dependency. The fuel-cycle reasoning underpinning the test campaign is that commercial Th- MOX fuels are an achievable intermediate / near-term SNF management strategy that integrates well with a fast reactor future. (authors)

Kelly, Julian F. [Thor Energy AS, Sommerrogaten 13-15, Oslo 0255 (Norway)] [Thor Energy AS, Sommerrogaten 13-15, Oslo 0255 (Norway); Franceschini, Fausto [Westinghouse Electric Company LLC, 1000 Cranberry Woods Drive, Cranberry Township, PA 16066 (United States)] [Westinghouse Electric Company LLC, 1000 Cranberry Woods Drive, Cranberry Township, PA 16066 (United States)

2013-07-01T23:59:59.000Z

418

Property:Building/SPPurchasedEngyForPeriodMwhYrPellets | Open Energy  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 No revision hasInformationInyo County, California |SPElectrtyUsePercRefrigerationInformation

419

Property:Building/SPPurchasedEngyNrmlYrMwhYrPellets | Open Energy  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 No revision hasInformationInyo County, CaliforniaInformationInformationInformation

420

Fossil Fuels  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Fossil Fuels A B C D E F G H I J K L M N O P Q R S T U V W X Y Z Abu-Khamsin, Sidqi - Department of Petroleum Engineering, King Fahd University of Petroleum and Minerals...

Note: This page contains sample records for the topic "fuel pellet fabrication" 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.


421

Digital fabrication in the architectural design process  

E-Print Network [OSTI]

Digital fabrication is affecting the architectural design process due to the increasingly important role it has in the fabrication of architectural models. Many design professionals, professors, and students have experienced ...

Seely, Jennifer C. K., 1975-

2004-01-01T23:59:59.000Z

422

4.212 Design Fabrication, Spring 2003  

E-Print Network [OSTI]

Design Fabrication is an introductory course in the field of advanced computing, prototyping and building fabrication. The class is focused on the relationship between design, various forms of computer modeling both explicit ...

Sass, Lawrence

423

Connections for solid oxide fuel cells  

DOE Patents [OSTI]

A connection for fuel cell assemblies is disclosed. The connection includes compliant members connected to individual fuel cells and a rigid member connected to the compliant members. Adjacent bundles or modules of fuel cells are connected together by mechanically joining their rigid members. The compliant/rigid connection permits construction of generator fuel cell stacks from basic modular groups of cells of any desired size. The connections can be made prior to installation of the fuel cells in a generator, thereby eliminating the need for in-situ completion of the connections. In addition to allowing pre-fabrication, the compliant/rigid connections also simplify removal and replacement of sections of a generator fuel cell stack.

Collie, Jeffrey C. (Pittsburgh, PA)

1999-01-01T23:59:59.000Z

424

Fabrication of boron sputter targets  

DOE Patents [OSTI]

A process for fabricating high density boron sputtering targets with sufficient mechanical strength to function reliably at typical magnetron sputtering power densities and at normal process parameters. The process involves the fabrication of a high density boron monolithe by hot isostatically compacting high purity (99.9%) boron powder, machining the boron monolithe into the final dimensions, and brazing the finished boron piece to a matching boron carbide (B.sub.4 C) piece, by placing aluminum foil there between and applying pressure and heat in a vacuum. An alternative is the application of aluminum metallization to the back of the boron monolithe by vacuum deposition. Also, a titanium based vacuum braze alloy can be used in place of the aluminum foil.

Makowiecki, Daniel M. (Livermore, CA); McKernan, Mark A. (Livermore, CA)

1995-01-01T23:59:59.000Z

425

Fuel cell-fuel cell hybrid system  

DOE Patents [OSTI]

A device for converting chemical energy to electricity is provided, the device comprising a high temperature fuel cell with the ability for partially oxidizing and completely reforming fuel, and a low temperature fuel cell juxtaposed to said high temperature fuel cell so as to utilize remaining reformed fuel from the high temperature fuel cell. Also provided is a method for producing electricity comprising directing fuel to a first fuel cell, completely oxidizing a first portion of the fuel and partially oxidizing a second portion of the fuel, directing the second fuel portion to a second fuel cell, allowing the first fuel cell to utilize the first portion of the fuel to produce electricity; and allowing the second fuel cell to utilize the second portion of the fuel to produce electricity.

Geisbrecht, Rodney A.; Williams, Mark C.

2003-09-23T23:59:59.000Z

426

FUEL CELL TECHNOLOGIES PROGRAM Hydrogen and Fuel  

E-Print Network [OSTI]

collectors. In a Polymer Electrolyte Membrane (PEM) fuel cell, which is widely regarded as the most promisingFUEL CELL TECHNOLOGIES PROGRAM Hydrogen and Fuel Cell Technologies Program: Fuel Cells Fuel Cells -- is the key to making it happen. Stationary fuel cells can be used for backup power, power for remote loca

427

Structure and yarn sensor for fabric  

DOE Patents [OSTI]

A structure and yarn sensor for fabric directly determines pick density in a fabric thereby allowing fabric length and velocity to be calculated from a count of the picks made by the sensor over known time intervals. The structure and yarn sensor is also capable of detecting full length woven defects and fabric. As a result, an inexpensive on-line pick (or course) density measurement can be performed which allows a loom or knitting machine to be adjusted by either manual or automatic means to maintain closer fiber density tolerances. Such a sensor apparatus dramatically reduces fabric production costs and significantly improves fabric consistency and quality for woven or knitted fabric. 13 figs.

Mee, D.K.; Allgood, G.O.; Mooney, L.R.; Duncan, M.G.; Turner, J.C.; Treece, D.A.

1998-10-20T23:59:59.000Z

428

Advanced Fuels Campaign FY 2010 Accomplishments Report  

SciTech Connect (OSTI)

The Fuel Cycle Research and Development (FCRD) Advanced Fuels Campaign (AFC) Accomplishment Report documents the high-level research and development results achieved in fiscal year 2010. The AFC program has been given responsibility to develop advanced fuel technologies for the Department of Energy (DOE) using a science-based approach focusing on developing a microstructural understanding of nuclear fuels and materials. The science-based approach combines theory, experiments, and multi-scale modeling and simulation aimed at a fundamental understanding of the fuel fabrication processes and fuel and clad performance under irradiation. The scope of the AFC includes evaluation and development of multiple fuel forms to support the three fuel cycle options described in the Sustainable Fuel Cycle Implementation Plan4: Once-Through Cycle, Modified-Open Cycle, and Continuous Recycle. The word fuel is used generically to include fuels, targets, and their associated cladding materials. This document includes a brief overview of the management and integration activities; but is primarily focused on the technical accomplishments for FY-10. Each technical section provides a high level overview of the activity, results, technical points of contact, and applicable references.

Lori Braase

2010-12-01T23:59:59.000Z

429

Comparison of measured and calculated LWR fuel behavior during a hypothetical reactivity initiated accident  

SciTech Connect (OSTI)

Comparisons of measured and calculated LWR fuel rod responses during a reactivity initiated accident test are presented. The results indicate that the computer code, FRAP-T5, adequately calculates the fuel rod behavior up to the time at which the gap closes and provides a good thermal solution up to the time of gross fuel and cladding relocation. Three areas have been identified for further model development: (a) development of a fuel swelling model for near molten fuel temperatures; (b) incorporation of a deformable fuel pellet model that is applicable for the closed gap, high strain rate regime; and (c) expansion of the failure stress data base to include heat-up rates of up to 5000 K/s.

Fukuda, S.K.; MacDonald, P.E.; Garner, R.W.

1980-01-01T23:59:59.000Z

430

U-Mo Foil/Cladding Interactions in Friction Stir Welded Monolithic RERTR Fuel Plates  

SciTech Connect (OSTI)

Interaction between U-Mo fuel and Al has proven to dramatically impact the overall irradiation performance of RERTR dispersion fuels. It is of interest to better understand how similar interactions may affect the performance of monolithic fuel plates, where a uranium alloy fuel is sandwiched between aluminum alloy cladding. The monolithic fuel plate removes the fuel matrix entirely, which reduces the total surface area of the fuel that is available to react with the aluminum and moves the interface between the fuel and cladding to a colder region of the fuel plate. One of the major fabrication techniques for producing monolithic fuel plates is friction stir welding. This paper will discuss the interactions that can occur between the U-Mo foil and 6061 Al cladding when applying this fabrication technique. It has been determined that the time at high temperatures should be limited as much as is possible during fabrication or any post-fabrication treatment to reduce as much as possible the interactions between the foil and cladding. Without careful control of the fabrication process, significant interaction between the U-Mo foil and Al alloy cladding can result. The reaction layers produced from such interactions can exhibit notably different morphologies vis--vis those typically observed for dispersion fuels.

D.D. Keiser; J.F. Jue; C.R. Clark

2006-10-01T23:59:59.000Z

431

Developing a High Thermal Conductivity Fuel with Silicon Carbide Additives  

SciTech Connect (OSTI)

The objective of this research is to increase the thermal conductivity of uranium oxide (UO{sub 2}) without significantly impacting its neutronic properties. The concept is to incorporate another high thermal conductivity material, silicon carbide (SiC), in the form of whiskers or from nanoparticles of SiC and a SiC polymeric precursor into UO{sub 2}. This is expected to form a percolation pathway lattice for conductive heat transfer out of the fuel pellet. The thermal conductivity of SiC would control the overall fuel pellet thermal conductivity. The challenge is to show the effectiveness of a low temperature sintering process, because of a UO{sub 2}-SiC reaction at 1,377C, a temperature far below the normal sintering temperature. Researchers will study three strategies to overcome the processing difficulties associated with pore clogging and the chemical reaction of SiC and UO{sub 2} at temperatures above 1,300C:

Ronald baney; James Tulenko

2012-11-20T23:59:59.000Z

432

Reference Alloy Waste Form Fabrication and Initiation of Reducing Atmosphere and Reductive Additives Study on Alloy Waste Form Fabrication  

SciTech Connect (OSTI)

This report describes the fabrication of two reference alloy waste forms, RAW-1(Re) and RAW-(Tc) using an optimized loading and heating method. The composition of the alloy materials was based on a generalized formulation to process various proposed feed streams resulting from the processing of used fuel. Waste elements are introduced into molten steel during alloy fabrication and, upon solidification, become incorporated into durable iron-based intermetallic phases of the alloy waste form. The first alloy ingot contained surrogate (non-radioactive), transition-metal fission products with rhenium acting as a surrogate for technetium. The second alloy ingot contained the same components as the first ingot, but included radioactive Tc-99 instead of rhenium. Understanding technetium behavior in the waste form is of particular importance due the longevity of Tc-99 and its mobility in the biosphere in the oxide form. RAW-1(Re) and RAW-1(Tc) are currently being used as test specimens in the comprehensive testing program investigating the corrosion and radionuclide release mechanisms of the representative alloy waste form. Also described in this report is the experimental plan to study the effects of reducing atmospheres and reducing additives to the alloy material during fabrication in an attempt to maximize the oxide content of waste streams that can be accommodated in the alloy waste form. Activities described in the experimental plan will be performed in FY12. The first aspect of the experimental plan is to study oxide formation on the alloy by introducing O2 impurities in the melt cover gas or from added oxide impurities in the feed materials. Reducing atmospheres will then be introduced to the melt cover gas in an attempt to minimize oxide formation during alloy fabrication. The second phase of the experimental plan is to investigate melting parameters associated with alloy fabrication to allow the separation of slag and alloy components of the melt.

S.M. Frank; T.P. O'Holleran; P.A. Hahn

2011-09-01T23:59:59.000Z

433

Polymer micromold and fabrication process  

DOE Patents [OSTI]

A mold assembly is disclosed with micro-sized features in which the hollow portion thereof is fabricated from a sacrificial mandrel which is surface treated and then coated to form an outer shell. The sacrificial mandrel is then selectively etched away leaving the outer shell as the final product. The sacrificial mandrel is fabricated by a precision lathe, for example, so that when removed by etching the inner or hollow area has diameters as small as 10`s of micros ({micro}m). Varying the inside diameter contours of the mold can be accomplished with specified ramping slopes formed on the outer surface of the sacrificial mandrel, with the inside or hollow section being, for example, 275 {micro}m in length up to 150 {micro}m in diameter within a 6 mm outside diameter (o.d.) mold assembly. The mold assembly itself can serve as a micronozzle or microneedle, and plastic parts, such as microballoons for angioplasty, polymer microparts, and microactuators, etc., may be formed within the mold assembly. 6 figs.

Lee, A.P.; Northrup, M.A.; Ahre, P.E.; Dupuy, P.C.

1997-08-19T23:59:59.000Z

434

Methodology for determining criteria for storing spent fuel in air  

SciTech Connect (OSTI)

Dry storage in an air atmosphere is a method being considered for spent light water reactor (LWR) fuel as an alternative to storage in an inert gas environment. However, methods to predict fuel integrity based on oxidation behavior of the fuel first must be evaluated. The linear cumulative damage method has been proposed as a technique for defining storage criteria. Analysis of limited nonconstant temperature data on nonirradiated fuel samples indicates that this approach yields conservative results for a strictly decreasing-temperature history. On the other hand, the description of damage accumulation in terms of remaining life concepts provides a more general framework for making predictions of failure. Accordingly, a methodology for adapting remaining life concepts to UO/sub 2/ oxidation has been developed at Pacific Northwest Laboratory. Both the linear cumulative damage and the remaining life methods were used to predict oxidation results for spent fuel in which the temperature was decreased with time to simulate the temperature history in a dry storage cask. The numerical input to the methods was based on oxidation data generated with nonirradiated UO/sub 2/ pellets. The calculated maximum allowable storage temperatures are strongly dependent on the temperature-time profile and emphasize the conservatism inherent in the linear cumulative damage model. Additional nonconstant temperature data for spent fuel are needed to both validate the proposed methods and to predict temperatures applicable to actual spent fuel storage.

Reid, C.R.; Gilbert, E.R.

1986-11-01T23:59:59.000Z

435

Performance and Fabrication Status of TREAT LEU Conversion Conceptual Design Concepts  

SciTech Connect (OSTI)

Resumption of transient testing at the TREAT facility was approved in February 2014 to meet U.S. Department of Energy (DOE) objectives. The National Nuclear Security Administrations Global Threat Reduction Initiative Convert Program is evaluating conversion of TREAT from its existing highly enriched uranium (HEU) core to a new core containing low enriched uranium (LEU). This paper describes briefly the initial pre-conceptual designs screening decisions with more detailed discussions on current feasibility, qualification and fabrication approaches. Feasible fabrication will be shown for a LEU fuel element assembly that can meet TREAT design, performance, and safety requirements. The statement of feasibility recognizes that further development, analysis, and testing must be completed to refine the conceptual design. Engineering challenges such as cladding oxidation, high temperature material properties, and fuel block fabrication along with neutronics performance, will be highlighted. Preliminary engineering and supply chain evaluation provided confidence that the conceptual designs can be achieved.

IJ van Rooyen; SR Morrell; AE Wright; E. P Luther; K Jamison; AL Crawford; HT III Hartman

2014-10-01T23:59:59.000Z

436

CASL-U-2015-0035-000 High Fidelity Modeling of Pellet-Clad Interaction  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation Proposed New Substation Sites Proposed Route Segments (notCAMDL2 Milestone1EPRI6-0002-0005-000

437

Plasma Fueling, Pumping, and Tritium Handling Considerations for FIRE P.W. Fisher', M. J.Gouge', C. A. Foster',B. E. Nelson', C. A. Gentile' andthe FIRE StudyTeam  

E-Print Network [OSTI]

Plasma Fueling, Pumping, and Tritium Handling Considerations for FIRE P.W. Fisher', M. J.Gouge', C,P.O.Box 2009,OakRidge,TN 3783l-8071 *PrincetonPlasmaPhysicsLaboratory, P.O.Box 451,Princeton,NJ 08543 Abstract-Tritium pellet injection will be utilized on the Fusion Ignition Research Experiment (FIRE) for efficient tritium

438

Coal-fueled diesel technology development: Nozzle development for coal-fueled diesel engines  

SciTech Connect (OSTI)

Direct injection of a micronized coal water mixture fuel into the combustion chambers of a diesel engine requires atomizing an abrasive slurry fuel with accurately sized orifices. Five injector orifice materials were evaluated: diamond compacts, chemical vapor deposited diamond tubes, thermally stabilized diamond, tungsten carbide with cobalt binder, and tungsten carbide with nickel binder with brazed and mechanically mounted orifice inserts. Nozzle bodies were fabricated of Armco 17-4 precipitation hardening stainless steel and Stellite 6B in order to withstand cyclic injection pressures and elevated temperatures. Based on a total of approximately 200 cylinder hours of engine operation with coal water mixture fuel diamond compacts were chosen for the orifice material.

Johnson, R.N.; Lee, M.; White, R.A.

1994-01-01T23:59:59.000Z

439

AFCI Transmutation Fuel Processes and By-Products Planning: Interim Report  

SciTech Connect (OSTI)

The goals of the Advanced Fuel Cycle Initiative (AFCI) Program are to reduce high-level waste volume, reduce long-lived and radiotoxic elements, and reclaim valuable energy content of spent nuclear fuel. The AFCI chartered the Fuel Development Working Group (FDWG) to develop advanced fuels in support of the AFCI goals. The FDWG organized a phased strategy of fuel development that is designed to match the needs of the AFCI program: Phase 1 - High-burnup fuels for light-water reactors (LWRs) and tri-isotopic (TRISO) fuel for gas-cooled reactors Phase 2 Mixed oxide fuels with minor actinides for LWRs, Am transmutation targets for LWRs, inert matrix fuels for LWRs, and TRISO fuel containing Pu and other transuranium for gas-cooled reactors Phase 3 Fertile free or low-fertile metal, ceramic, ceramic dispersed in a metal matrix (CERMET), and ceramics dispersed in a ceramic matrix (CERCER) that would be used primarily in fast reactors. Development of advanced fuels requires the fabrication, assembly, and irradiation of prototypic fuel under bounding reactor conditions. At specialized national laboratory facilities small quantities of actinides are being fabricated into such fuel for irradiation tests. Fabrication of demonstration quantities of selected fuels for qualification testing is needed but not currently feasible, because existing manual glovebox fabrication approaches result in significant radiation exposures when larger quantities of actinides are involved. The earliest demonstration test fuels needed in the AFCI program are expected to be variants of commercial mixed oxide fuel for use in an LWR as lead test assemblies. Manufacture of such test assemblies will require isolated fabrication lines at a facility not currently available in the U.S. Such facilities are now being planned as part of an Advanced Fuel Cycle Facility (AFCF). Adequate planning for and specification of actinide fuel fabrication facilities capable of producing transmutation fuels dictates the need for detailed process flows, mass balances, batch size data, and radiological dose estimates. Full definition of the materials that will need to be handled in the facility as feed material inputs, in-process fuel, scrap recycle, scrap requiring recovery, and by-product wastes is required. The feed material for demonstrating transmutation fuel fabrication will need to come from the separations of actinides from spent nuclear fuel processed in the same AFCF.

Eric L. Shaber

2005-09-01T23:59:59.000Z

440

Fuel Processing Valri Lightner  

E-Print Network [OSTI]

of Hydrogen · Fuel Processors for PEM Fuel Cells Nuvera Fuel Cells, Inc. GE Catalytica ANL PNNL University-Board Fuel Processing Barriers $35/kW Fuel Processor $10/kW Fuel Cell Power Systems $45/kW by 2010 BARRIERS · Fuel processor start-up/ transient operation · Durability · Cost · Emissions and environmental issues

Note: This page contains sample records for the topic "fuel pellet fabrication" 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.


441

Fabrication and characterization of conducting polymer microwires  

E-Print Network [OSTI]

Flexible microwires fabricated from conducting polymers have a wide range of potential applications, including smart textiles that incorporate sensing, actuation, and data processing. The development of garments that ...

Saez, Miguel Angel

2009-01-01T23:59:59.000Z

442

Fuel reforming for fuel cell application.  

E-Print Network [OSTI]

??Fossil fuels, such as natural gas, petroleum, and coal are currently the primary source of energy that drives the world economy. However, fossil fuel is (more)

Hung, Tak Cheong

2006-01-01T23:59:59.000Z

443

Sulfonated Polysulfone/POSS Nanofiber Composite Membranes for PEM Fuel Cells  

E-Print Network [OSTI]

Sulfonated Polysulfone/POSS Nanofiber Composite Membranes for PEM Fuel Cells Jonghyun Choi. Historically, most of the research work on Nafion replacements for proton exchange membrane PEM fuel cells has in H2/air fuel cells that operate at low humidity. The membranes were fabricated from electrospun

Mather, Patrick T.

444

Methods for making a porous nuclear fuel element  

DOE Patents [OSTI]

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; Williams, Brian E; Benander, Robert E

2014-12-30T23:59:59.000Z

445

Alternative Fuel Vehicle Resources  

Broader source: Energy.gov [DOE]

Alternative fuel vehicles use fuel types other than petroleum and include such fuels as electricity, ethanol, biodiesel, natural gas, hydrogen, and propane. Compared to petroleum, these...

446

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

Alternative Fuel Grants and Rebates The Arkansas Alternative Fuels Development Program (Program) provides grants to alternative fuel producers, feedstock processors, and...

447

Alternative Fuel Implementation Toolkit  

E-Print Network [OSTI]

? Alternative Fuels, the Smart Choice: Alternative fuels ­ biodiesel, electricity, ethanol (E85), natural gas...........................................................................................................................................................................6 Trends and Fleet Examples: Alternative Fuel Decision Table

448

Saving Fuel, Reducing Emissions  

E-Print Network [OSTI]

would in turn lower PHEV fuel costs and make them morestretches from fossil-fuel- powered conventional vehiclesbraking, as do Saving Fuel, Reducing Emissions Making Plug-

Kammen, Daniel M.; Arons, Samuel M.; Lemoine, Derek M.; Hummel, Holmes

2009-01-01T23:59:59.000Z

449

Low Carbon Fuel Standards  

E-Print Network [OSTI]

in 1990. These many alternative-fuel initiatives failed tolow-cost, low-carbon alternative fuels would thrive. Theto introduce low-carbon alternative fuels. Former Federal

Sperling, Dan; Yeh, Sonia

2009-01-01T23:59:59.000Z

450

Hydrogen Fuel Cell Vehicles  

E-Print Network [OSTI]

Research Institute 1990 Fuel Cell Status," Proceedings ofMiller, "Introduction: Fuel-Cell-Powered Vehicle DevelopmentPrograms," presented at Fuel Cells for Transportation,

Delucchi, Mark

1992-01-01T23:59:59.000Z

451

CONTAINER MATERIALS, FABRICATION AND ROBUSTNESS  

SciTech Connect (OSTI)

The multi-barrier 3013 container used to package plutonium-bearing materials is robust and thereby highly resistant to identified degradation modes that might cause failure. The only viable degradation mechanisms identified by a panel of technical experts were pressurization within and corrosion of the containers. Evaluations of the container materials and the fabrication processes and resulting residual stresses suggest that the multi-layered containers will mitigate the potential for degradation of the outer container and prevent the release of the container contents to the environment. Additionally, the ongoing surveillance programs and laboratory studies should detect any incipient degradation of containers in the 3013 storage inventory before an outer container is compromised.

Dunn, K.; Louthan, M.; Rawls, G.; Sindelar, R.; Zapp, P.; Mcclard, J.

2009-11-10T23:59:59.000Z

452

Patterned Fabric Know - How (Plaids, Stripes, Checks, and Figured Designs).  

E-Print Network [OSTI]

DC \\1\\245.7 '13 Fbiterned Fabric mow-Kbw Contents Design Principles and Patterned Fabrics Pattern Selection Fabric Construction Selecting and Preparing Fabric Kinds of Plaids and Stripes Pri nts Other Patterned Fabrics Combining..., Stripes, Checks and Figured Designs) Extension Clothing Specialists The Texas A&M University System Patterned fabrics provide an interesting di mension to anyone's wardrobe. In a garment or as an accent, patterned fabrics are colorful and ex citing...

Anoymous,

1984-01-01T23:59:59.000Z

453

Reactivity Initiated Accident Test Series Test RIA 1-1 (radial average fuel enthalpy of 285 cal/g) fuel behavior report  

SciTech Connect (OSTI)

Analyses, interpretations, and discussions of results from the Reactivity Initiated Accident (RIA) Test Series, Test RIA 1-1, conducted in the Power Burst Facility reactor are presented. Four light water reactor (LWR) type test fuel rods, two previously irradiated and two previously unirradiated, were subjected to a single power transient resulting in an estimated axial peak, radial average fuel enthalpy of 285 cal/g (335 and 315 cal/g peak fuel enthalpy near the pellet surface of the previously irradiated and unirradiated test rods, respectively). The total radial average energy deposition for the test was 365 cal/g UO2. All four test rods failed as a result of the RIA power burst. Test fuel rod behavior was assessed from instrumentation response data and post-test metallurgical observations.

Seiffert, S.L.; Martinson, Z.R.; Fukuda, S.K.

1980-09-01T23:59:59.000Z

454

Coal based fuels, fuel systems and alternative fuels  

SciTech Connect (OSTI)

The introduction of coal based fuel systems such as coal/air and coal water mixtures was an attempt to minimize the use of heavy fuel oils in large scale power generation processes. This need was based on forecasts of fuel reserves and future pricing of fuel oils, therefore economic considerations predominated over environmental benefits, if any, which could result from widespread use of these fuels. Coal continued as the major fuel used in the power generation industry and combustion systems were developed to minimize gaseous emissions, such as NOx. Increasing availability of natural gas led to consideration of its use in combination with coal in fuel systems involving combined cycle or topping cycle operations. Dual fuel coal natural gas operations also offered the possibility of improved performance in comparison to 100% coal based fuel systems. Economic considerations have more recently looked at emulsification of heavy residual liquid fuels for consumption in power generation boiler and Orimulsion has emerged as a prime example of this alternative fuel technology. The paper will discuss some aspects of the burner technology related to the application of these various coal based fuels, fuel systems and alternative fuels in the power generation industry.

Allen, J.W.; Beal, P.R.

1998-07-01T23:59:59.000Z

455

Coal based fuels, fuel systems and alternative fuels  

SciTech Connect (OSTI)

The introduction of coal based fuel systems such as coal/air and coal water mixtures was an attempt to minimise the use of heavy fuel oils in large scale power generation processes. This need was based on forecasts of fuel reserves and future pricing of fuel oils, therefore economic considerations predominated over environmental benefits, if any, which could result from widespread use of these fuels. Coal continued as the major fuel used in the power generation industry and combustion systems were developed to minimise gaseous emissions, such as NO{sub x}. Increasing availability of natural gas led to consideration of its use in combination with coal in fuel systems involving combined cycle or topping cycle operations. Dual fuel coal natural gas operations also offered the possibility of improved performance in comparison to 100% coal based fuel systems. Economic considerations have more recently looked at emulsification of heavy residual liquid fuels for consumption in power generation boiler and Orimulsion has emerged as a prime example of this alternative fuel technology. The next sections of the paper will discuss some aspects of the burner technology related to the application of these various coal based fuels, fuel systems and alternative fuels in the power generation industry.

Allen, J.W.; Beal, P.R. [ABB Combustion Services Limited, Derby (United Kingdom)

1998-04-01T23:59:59.000Z

456

Nanotube Fabrication byNanotube Fabrication by Anodic Aluminum Oxide,Anodic Aluminum Oxide,  

E-Print Network [OSTI]

Nanotube Fabrication byNanotube Fabrication by Anodic Aluminum Oxide,Anodic Aluminum Oxide, Self-regulating phenomena in materials science: Self-assembly of nanopores during anodic oxidation of aluminum (AAO) Self combined anodic aluminum oxide (AAO) nanostructures with atomic layer deposition (ALD) to fabricate

Rubloff, Gary W.

457

A neutronic feasibility study of the AP1000 design loaded with fully ceramic micro-encapsulated fuel  

SciTech Connect (OSTI)

A neutronic feasibility study is performed to evaluate the utilization of fully ceramic microencapsulated (FCM) fuel in the AP1000 reactor design. The widely used Monte Carlo code MCNP is employed to perform the full core analysis at the beginning of cycle (BOC). Both the original AP1000 design and the modified design with the replacement of uranium dioxide fuel pellets with FCM fuel compacts are modeled and simulated for comparison. To retain the original excess reactivity, ranges of fuel particle packing fraction and fuel enrichment in the FCM fuel design are first determined. Within the determined ranges, the reactor control mechanism employed by the original design is directly used in the modified design and the utilization feasibility is evaluated. The worth of control of each type of fuel burnable absorber (discrete/integral fuel burnable absorbers and soluble boron in primary coolant) is calculated for each design and significant differences between the two designs are observed. Those differences are interpreted by the fundamental difference of the fuel form used in each design. Due to the usage of silicon carbide as the matrix material and the fuel particles fuel form in FCM fuel design, neutron slowing down capability is increased in the new design, leading to a much higher thermal spectrum than the original design. This results in different reactivity and fission power density distributions in each design. We conclude that a direct replacement of fuel pellets by the FCM fuel in the AP1000 cannot retain the original optimum reactor core performance. Necessary modifications of the core design should be done and the original control mechanism needs to be re-designed. (authors)

Liang, C.; Ji, W. [Department of Mechanical, Aerospace, and Nuclear Engineering Rensselaer, Polytechnic Institute, 110 8th Street, Troy, NY 12180 (United States)

2013-07-01T23:59:59.000Z

458

Oxidation Protection of Uranium Nitride Fuel using Liquid Phase Sintering  

SciTech Connect (OSTI)

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

459

Polymer microcantilevers fabricated via multiphoton absorption polymerization  

E-Print Network [OSTI]

Polymer microcantilevers fabricated via multiphoton absorption polymerization Z. Bayindir, Y. Sun February 2005 We have used multiphoton absorption polymerization to fabricate a series of microscale.1063/1.1863414 Multiphoton absorption polymerization MAP 1­4 offers the unparalleled ability to create arbitrarily complex 3D

Teich, Malvin C.

460

Apparatus and method for fabricating a microbattery  

DOE Patents [OSTI]

An apparatus and method for fabricating a microbattery that uses silicon as the structural component, packaging component, and semiconductor to reduce the weight, size, and cost of thin film battery technology is described. When combined with advanced semiconductor packaging techniques, such a silicon-based microbattery enables the fabrication of autonomous, highly functional, integrated microsystems having broad applicability.

Shul, Randy J. (Albuquerque, NM); Kravitz, Stanley H. (Albuquerque, NM); Christenson, Todd R. (Albuquerque, NM); Zipperian, Thomas E. (Edgewood, NM); Ingersoll, David (Albuquerque, NM)

2002-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "fuel pellet fabrication" 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.


461

The design of a microfabricated air electrode for liquid electrolyte fuel cells  

E-Print Network [OSTI]

In this dissertation, the microfabricated electrode (MFE) concept was applied to the design of an air electrode for liquid electrolyte fuel cells. The catalyst layer of the electrode is envisioned to be fabricated by using ...

Pierre, Fritz, 1977-

2007-01-01T23:59:59.000Z

462

Effect of Hydrogen Inlets on Planar μPEM Fuel Cell Stacks.  

E-Print Network [OSTI]

??Planar μPEM Fuel Cell Stacks are designed and fabricated in-house through a deep UV lithography technique, with SU 8 photoresist used as the microstructure mold (more)

Yeh, Jian-liang

2010-01-01T23:59:59.000Z

463

Fuel-disruption experiments under high-ramp-rate heating conditions. [LMFBR  

SciTech Connect (OSTI)

This topical report presents the preliminary results and analysis of the High Ramp Rate fuel-disruption experiment series. These experiments were performed in the Annular Core Research Reactor at Sandia National Laboratories to investigate the timing and mode of fuel disruption during the prompt-burst phase of a loss-of-flow accident. High-speed cinematography was used to observe the timing and mode of the fuel disruption in a stack of five fuel pellets. Of the four experiments discussed, one used fresh mixed-oxide fuel, and three used irradiated mixed-oxide fuel. Analysis of the experiments indicates that in all cases, the observed disruption occurred well before fuel-vapor pressure was high enough to cause the disruption. The disruption appeared as a rapid spray-like expansion and occurred near the onset of fuel melting in the irradiated-fuel experiments and near the time of complete fuel melting in the fresh-fuel experiment. This early occurrence of fuel disruption is significant because it can potentially lower the work-energy release resulting from a prompt-burst disassembly accident.

Wright, S.A.; Worledge, D.H.; Cano, G.L.; Mast, P.K.; Briscoe, F.

1983-10-01T23:59:59.000Z

464

DIESEL FUEL TANK FOUNDATIONS  

SciTech Connect (OSTI)

The purpose of this analysis is to design structural foundations for the Diesel Fuel Tank and Fuel Pumps.

M. Gomez

1995-01-18T23:59:59.000Z

465

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE: Alternative Fuels Data Center HomeNewEmissions Test Requirementand Fuel-EfficientAlternative Fuel

466

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE: Alternative Fuels Data Center HomeNewEmissionsPropane BoardAlternative Fuel Vehicle (AFV)Fuel

467

Alternative Fuel Vehicle  

Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE: Alternative Fuels Data Center Home Page onAlternative Fuel Vehicle & Fueling Infrastructure

468

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE: Alternative Fuels Data Center Home Page onAlternative Fuel Vehicle & FuelingDo alternative

469

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE: Alternative Fuels Data Center Home Page onAlternative Fuel Vehicle & FuelingDo

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