Sample records for fuel pellet fabrication

  1. Fabrication of high exposure nuclear fuel pellets

    DOE Patents [OSTI]

    Frederickson, James R. (Richland, WA)

    1987-01-01T23:59:59.000Z

    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.

  2. Recent advances in pelletized fuels

    SciTech Connect (OSTI)

    Buggey, T.J.

    1999-07-01T23:59:59.000Z

    As US utilities are deregulated and begin to compete, they are more willing to consider alternate fuels if available at lower prices. This in combination with new methods of pelletizing coal fines and the availability of tax credits, has encouraged reclaiming fine-sized coal from impoundments. Approximately thirty (30) plants are, or will soon be, recovering and cleaning pond fines which are then extruded into fuel pellets. The fines are typically removed by dredging and pumped to a processing facility as a slurry. In addition, a cost-effective process has been developed for manufacturing a composite pellet fuel (E-Fuel) from coal, biomass, and waste.

  3. Modeling of Selected Ceramic Processing Parameters Employed in the Fabrication of 238PuO2 Fuel Pellets

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Brockman, R. A. [Univ. of Dayton, OH (United States); Kramer, Daniel P. [Univ. of Dayton, OH (United States); Barklay, Chadwick D. [Univ. of Dayton, OH (United States); Cairns-Gallimore, Dirk [U.S. Department of Energy, Germantown, MD (United States); Brown, J. L. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Huling, J. C. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); van Pelt, C. E. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2011-01-01T23:59:59.000Z

    Recent deep space missions utilize the thermal output of the radioisotope plutonium-238 as the fuel in the thermal to electrical power system. Since the application of plutonium in its elemental state has several disadvantages, the fuel employed in these deep space power systems is typically in the oxide form such as plutonium-238 dioxide (238PuO2). As an oxide, the processing of the plutonium dioxide into fuel pellets is performed via ''classical'' ceramic processing unit operations such as sieving of the powder, pressing, sintering, etc. Modeling of these unit operations can be beneficial in the understanding and control of processing parameters with the goal of further enhancing the desired characteristics of the 238PuO2 fuel pellets. A finite element model has been used to help identify the time-temperature-stress profile within a pellet during a furnace operation taking into account that 238PuO2 itself has a significant thermal output. Results of the modeling efforts will be discussed.

  4. Modeling of Selected Ceramic Processing Parameters Employed in the Fabrication of 238PuO2 Fuel Pellets

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Brockman, R. A.; Kramer, Daniel P.; Barklay, Chadwick D.; Cairns-Gallimore, Dirk; Brown, J. L.; Huling, J. C.; van Pelt, C. E.

    2011-01-01T23:59:59.000Z

    Recent deep space missions utilize the thermal output of the radioisotope plutonium-238 as the fuel in the thermal to electrical power system. Since the application of plutonium in its elemental state has several disadvantages, the fuel employed in these deep space power systems is typically in the oxide form such as plutonium-238 dioxide (238PuO2). As an oxide, the processing of the plutonium dioxide into fuel pellets is performed via ''classical'' ceramic processing unit operations such as sieving of the powder, pressing, sintering, etc. Modeling of these unit operations can be beneficial in the understanding and control of processing parameters withmore »the goal of further enhancing the desired characteristics of the 238PuO2 fuel pellets. A finite element model has been used to help identify the time-temperature-stress profile within a pellet during a furnace operation taking into account that 238PuO2 itself has a significant thermal output. Results of the modeling efforts will be discussed.« less

  5. 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 ÂĄ Hydrogen properties ÂĄ Ice/pellet formation techniques ÂĄ Acceleration

  6. Manufacturing Fuel Pellets from Biomass Introduction

    E-Print Network [OSTI]

    Boyer, Elizabeth W.

    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

  7. 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...

  8. Development of Pellet Technologies for Plasma Fueling

    SciTech Connect (OSTI)

    Kapralov, V.G. [State Polytechnical University (Russian Federation); Kuteev, B.V. [NFI RRC 'Kurchatov institute' (Russian Federation); Baranov, G.A. [D.V. Efremov Scientific Research Institute of Electrophysical Apparatus (Russian Federation)] (and others)

    2005-01-15T23:59:59.000Z

    This contribution presents recent results of pellet technologies development for plasma fuelling in magnetic confinement machines with open or closed magnetic configuration. The current status of ITV7 pellet injector for GOL3 multimirror linear machine, PGS2.2 pellet guide system of ITV4 in-situ pellet injector for TUMAN- 3M tokamak and ITV5 centrifuge pellet injector for Globus-M spherical tokamak is reported. New results on modeling of tangential pellet injection into TUMAN-3M tokamak are discussed as well.

  9. Pellet Fueling and Control of Burning Plasmas in ITER

    SciTech Connect (OSTI)

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

    2007-01-01T23:59:59.000Z

    Pellet injection from the inner wall is planned for use on ITER as the primary core fueling system since gas fueling is expected to be highly inefficient in burning plasmas. Tests of the inner wall guide tube have shown that 5mm pellets with up to 300 m/s speeds can survive intact and provide the necessary core fueling rate. Modeling and extrapolation of the inner wall pellet injection experiments from today's smaller tokamaks leads to the prediction that this method will provide efficient core fueling beyond the pedestal region. Using pellets for triggering of frequent small edge localized modes is an attractive additional benefit that the pellet injection system can provide. A description of the ITER pellet injection system capabilities for fueling and ELM triggering are presented and performance expectations and fusion power control aspects are discussed.

  10. Fabrication of thorium bearing carbide fuels

    DOE Patents [OSTI]

    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

    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.

  11. Fueling efficiency of pellet injection on DIII-D

    SciTech Connect (OSTI)

    Baylor, L.R.; Jernigan, T.C.; Maingi, R. [Oak Ridge National Lab., TN (United States); Lasnier, C.J. [Lawrence Livermore National Lab., CA (United States); Ali Mahdavi, M. [General Atomics, San Diego, CA (United States)

    1998-05-01T23:59:59.000Z

    Pellet injection has been used on the DIII-D tokamak to study density limits and particle transport in H-mode and inner wall limited L-mode plasmas. These experiments have provided a variety of conditions in which to examine the fueling efficiency of pellets injected into DIII-D plasmas. The fueling efficiency defined as the total increase in number of plasma electrons divided by the number of pellet fuel atoms, is determined by measurements of density profiles before and just after pellet injection. The authors have found that there is a decrease in the pellet fueling efficiency with increased neutral beam injection power. The pellet penetration depth also decreases with increased neutral beam injection power so that, in general, fueling efficiency increases with penetration depth. The fueling efficiency is generally 25% lower in ELMing H-mode discharges than in L-mode due to an expulsion of particles with a pellet triggered ELM. A comparison with fueling efficiency data from other tokamaks shows similar behavior.

  12. Recent advances in fueling magnetically confined plasmas with pellets

    SciTech Connect (OSTI)

    Baylor, L.R.; Combs, S.K.; Fisher, P.W.; Gouge, M.J.; Jernigan, T.C.

    2000-07-01T23:59:59.000Z

    Pellet injection has been used for many years in a number of magnetic confinement fusion experiments to provide plasma fueling and density profile control. A pellet fueling system for a reactor-sized device will need to supply hydrogenic fuel as deeply into the plasma as possible to replace the deuterium-tritium ions consumed and to provide a density gradient for plasma particle (especially helium ash) flow to the edge. Development of injection systems that can provide deep fueling with sufficient throughput to provide these features remains a high priority in the fusion technology program. Several tokamak devices, including DIII-D, ASDEX-Upgrade, and JET, have recently employed pellet injection from the high magnetic field side (inner wall). Injection from the high field side (HFS) yields improved fuel penetration and fueling efficiency over the usual simpler method of low-field-side injection from the outside midplane. There is a resulting improvement in fueling efficiency and fuel deposition. The improvement is believed to be due to a {del}B drift and curvature-induced drift of the pellet ablatant in the major radius direction. Curved guide tubes must be employed to inject from the inner wall in all current devices requiring slow to moderate pellet speeds to obtain intact pellets. Alternative injection schemes that take advantage of the HFS injection while allowing for high-speed pellet injection are possible using a vertical injection geometry. The technology to produce cryogenic pellets of hydrogenic isotopes has matured to the level of reliable pellet injection devices that produce and accelerate intact pellets at high repetition rates. New technology enhancements to pneumatic guns have been developed for the production of slower-speed pellets that can survive the curved guide tubes required for HFS injection. Centrifugal accelerators have also been operated at the low velocities required for HFS fueling. The understanding of pellet mechanical properties gained from impact studies has allowed for curved guide-tube designs that allow pellets to survive intact at moderate speeds.

  13. Deposition of fuel pellets injected into tokamak plasmas

    SciTech Connect (OSTI)

    Baylor, L.R.; Jernigan, T.C. [Oak Ridge National Lab., TN (United States); Hsieh, C. [General Atomics, San Diego, CA (United States)

    1998-06-01T23:59:59.000Z

    Pellet injection has been used on tokamak devices in a number of experiments to provide plasma fueling and density profile control. The mass deposition of these fuel pellets defined as the change in density profile caused by the pellet, has been found to show an outward displacement of the ablated material from that expected by mapping the theoretical ablation rate onto the flux surfaces. This suggests that fast transport of the pellet ablatant occurs during the flow along field lines that may be driven by {del}B drift effects. A comparison of the deposition of pellets from different machines shows similar behavior. Initial results from alternative injection locations designed to take advantage of the outward ablatant drift is presented.

  14. 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...

  15. advanced 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...

  16. abb-2901 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...

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

    DOE Patents [OSTI]

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

    1982-08-19T23:59:59.000Z

    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.

  18. Studies on Pellet Fueling of ITER-Like Plasmas

    SciTech Connect (OSTI)

    Kamelander, Gerald [Austrian Research Center Seibersdorf (Austria); Weimann, Geert [Austrian Research Center Seibersdorf (Austria); Garzotti, Luca [Consorzio RFX, Corso Stati Uniti 4 (Italy); Litaudon, Xavier [DSM, CEA Cadarache (France); Moreau, Didier [DSM, CEA Cadarache (France); Pegourie, Bernard [DSM, CEA Cadarache (France)

    2004-06-15T23:59:59.000Z

    The paper reports on simulation of pellet-fueled plasmas in a fusion reactor. The simulations have been performed by means of the ASTRA transport code. We have studied physical modeling of pellet injection as well as the numerical conditions to resolve pellet injection correctly. As a first step the essential mechanisms for density control have been studied based on simplified assumptions with a generic source of additional heating. The experience gained has been used to simulate advanced scenarios including internal transport barriers. It has been confirmed that it is possible to drive the plasma of a next-generation tokamak into a high-Q regime and to maintain it in a steady-state regime. Nevertheless, the pellet injection parameters required are rather demanding and imply a significant technological improvement of pellet injectors. Those investigations represent an improvement of simulations done earlier with a control of the central density at constant profile.

  19. Pellet Fueling Technology Development for Efficient Fueling of Burning Plasmas in ITER

    SciTech Connect (OSTI)

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

    2007-01-01T23:59:59.000Z

    Pellet injection from the inner wall is planned for use on ITER as the primary core fueling system since gas fueling is expected to be highly inefficient in burning plasmas. Tests of the inner wall guide tube have shown that 5mm pellets with up to 300 m/s speeds can survive intact and provide the necessary core fueling rate. Modeling and extrapolation of the inner wall pellet injection experiments from today's smaller tokamaks leads to the prediction that this method will provide efficient core fueling beyond the pedestal region. Using pellets for triggering of frequent small edge localized modes is an attractive additional benefit that the pellet injection system can provide. A description of the ITER pellet injection system capabilities for fueling and ELM triggering are presented and performance expectations are discussed.

  20. 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

  1. Pellet fueling technology development leading to efficient fueling of ITER burning plasmas

    SciTech Connect (OSTI)

    Baylor, L.R.; Combs, S.K.; Jernigan, T.C.; Houlberg, W.A.; Owen, L.W.; Rasmussen, D.A.; Maruyama, S.; Parks, P.B. [Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831-6169 (United States)

    2005-05-15T23:59:59.000Z

    Pellet injection is the primary fueling technique planned for core fueling of ITER [ITER Technical Basis 2002 ITER EDA Documentation Series (Vienna: IAEA)] burning plasmas. Efficient core plasma fueling with deuterium and tritium D-T is a requirement for achieving high fusion gain and it cannot be achieved with gas fueling. 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. Modeling of the fueling deposition from inner wall pellet injection using the Parks ExB drift model indicates that pellets have the capability to fuel well inside the separatrix. Gas fueling calculations show very poor neutral penetration due to the high density and wide scrape off layer. Isotopically mixed D-T pellets can provide efficient tritium fueling that will minimize tritium wall loading when compared to gas puffing. Currently the performance of the ITER inner wall guide tube design is under test with initial results indicating that pellet speeds in excess of 300 m/s will lead to fragmented pellets. The ITER pellet injection technology requirements and remaining development issues are discussed along with a plan to reach the design goal for employment on ITER.

  2. 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 onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand JumpConceptual Model,DOEHazel Crest,EnergySerranopolis Jump to: navigation, search Name:Energetix

  3. Apparatus and method for classifying fuel pellets for nuclear reactor

    DOE Patents [OSTI]

    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

    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.

  4. Fueling efficiency of pellet injection on DIIID* L.R. Baylora

    E-Print Network [OSTI]

    Fueling efficiency of pellet injection on DIII­D* L.R. Baylora , T.C. Jernigana , C.J. Lasnierb , R of conditions in which to examine the fueling efficiency of pellets injected into DIII- D plasmas. The fueling efficiency defined as the total increase in number of plasma electrons divided by the number of pellet fuel

  5. 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 (

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

    SciTech Connect (OSTI)

    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

    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.

  7. Neutronic fuel element fabrication

    DOE Patents [OSTI]

    Korton, George (Cincinnati, OH)

    2004-02-24T23:59:59.000Z

    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.

  8. Pellet Fueling, ELM pacing, and Disruption Mitigation Technology Development for ITER

    SciTech Connect (OSTI)

    Baylor, Larry R [ORNL; Combs, Stephen Kirk [ORNL; Foust, Charles R [ORNL; Jernigan, Thomas C [ORNL; Meitner, S. J. [Oak Ridge National Laboratory (ORNL); Parks, P. B. [General Atomics; Caughman, John B [ORNL; Maruyama, S. [ITER International Team, Garching, Germany; Qualls, A L [ORNL; Rasmussen, David A [ORNL; ThomasJr., C. E. [Third Dimension Technologies, LLC, Knoxville, TN

    2009-01-01T23:59:59.000Z

    Plasma fueling with pellet injection, pacing of edge localized modes (ELMs) by small frequent pellets, and disruption mitigation with gas jets or injected pellets are some of the most important technological capabilities needed for successful operation of ITER. Tools are being developed at Oak Ridge National Laboratory that can be employed on ITER to provide the necessary core pellet fueling and the mitigation of ELMs and disruptions. Here we present progress on the development of the technology to provide reliable high throughput inner wall pellet fueling, pellet ELM pacing with high frequency small pellets, and disruption mitigation with gas jets and pellets. Examples of how these tools can be employed on ITER are discussed.

  9. Fabrication Characteristics of Large Grain DUPIC Fuel Using SIMFUEL

    SciTech Connect (OSTI)

    Park, Geun IL; Lee, Jung Won; Lee, Jae Won; Yang, Myung Seung; Song, Kee Chan [Korea Atomic Energy Research Institute, 150-1 Duckjin-Dong, 1045 Daedeokdaero, Yuseong, Daejeon Korea, 305-353 (Korea, Republic of)

    2007-07-01T23:59:59.000Z

    Fabrication characteristics to improve the density and grain size of DUPIC fuel with relation to its fuel performance were experimentally evaluated using SIMFUEL as a surrogate for an actual spent PWR fuel due to the high radioactivity of a spent fuel. Hence, SIMFUELs with a burn-up of 35,000 MWd/tU and 60,000 MWd/tU were used to investigate the influence of fission products contents as an impurity on the fuel powder properties and on the density and grain size of a simulated DUPIC pellet. In order to improve the densification and grain growth of the simulated DUPIC fuel, the effect of the addition of sintering aids was investigated. The specific surface area of the OREOX powders was increased with an increase of the impurities by the dissolved oxides in UO{sub 2} among the impurity groups. The specific surface area of the powders milled after the OXREOX treatment was slightly higher than the UO{sub 2} powder used for a nuclear power plant, thus resulting in sintered pellets with a higher than 95% T.D. (theoretical density). The grain size of the sintered pellets was significantly decreased with increasing amount of the metallic and oxide precipitates. However, on adding the sintering aids such as TiO{sub 2} and Nb{sub 2}O{sub 5}, the grain size of the sintering aids-doped pellets was greatly improved by up to around 3 times that of the raw pellets and their sintered density was also increased by up to 2%. (authors)

  10. Improved Fueling and Transport Barrier Formation with Pellet Injection from Different Locations on DIII-D

    SciTech Connect (OSTI)

    Baylor, Larry R [ORNL; Jernigan, Thomas C [ORNL; Gohil, P. [General Atomics; Schmidt, G. L. Schmidt [Princeton Plasma Physics Laboratory (PPPL); Burrell, K. H. [General Atomics; Combs, Stephen Kirk [ORNL; Ernst, D. R. [Princeton Plasma Physics Laboratory (PPPL); Greenfield, C. M. [General Atomics; Groebner, R. J. [General Atomics; Houlberg, Wayne A [ORNL; Hsieh, C. [General Atomics; Murakami, Masanori [ORNL; Parks, P. B. [General Atomics; Porkolab, M. [Massachusetts Institute of Technology (MIT); Sessions, W. D. [Tennessee Technological University; Staebler, G. M. [General Atomics; Synakowski, E. J. [Princeton Plasma Physics Laboratory (PPPL)

    2001-05-01T23:59:59.000Z

    Pellet injection has been employed on DIII-D from different injection locations to optimize the mass deposition for density profile control and internal transport barrier formation. Transport barriers have been formed deep in the plasma core with central mass deposition from high field side (HFS) injected pellets and in the edge with pellets that trigger L-mode to H-mode transitions. Pellets injected from all locations can trigger the H-mode transition, which depends on the edge density gradient created and not on the radial extent of the pellet deposition. Pellets injected from inside the magnetic axis from the inner wall or vertical port lead to stronger central mass deposition than pellets injected from the low field side (LFS) and thus yield deeper more efficient fueling.

  11. Integrated Recycling Test Fuel Fabrication

    SciTech Connect (OSTI)

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

    2013-03-01T23:59:59.000Z

    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.

  12. A Comparison of Fueling with Deuterium Pellet Injection from Different Locations on the DIII-D Tokamak

    SciTech Connect (OSTI)

    Baylor, L.R.; Combs, S.K.; Gohil, P.; Houlberg, W.A.; Hsieh, C.; Jernigan, T.C.; Parks, P.B.

    1999-06-14T23:59:59.000Z

    Initial pellet injection experiments on DIII-D with high field side (HFS) injection have demonstrated that deeper pellet fuel deposition is possible even with HFS injected pellets that are significantly slower than pellets injected from the low field side (LFS) (outer midplane) location. A radial displacement of the pellet mass shortly after or during the ablation process is consistent with the observed mass deposition profiles measured shortly after injection. Vertical injection inside the magnetic axis shows some improvement in fueling efficiency over LFS injection and may provide an optimal injection location for fueling with high speed pellets.

  13. advanced-feature 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...

  14. Update On Monolithic Fuel Fabrication Development

    SciTech Connect (OSTI)

    C. R Clark; J. M. Wight; G. C. Knighton; G. A. Moore; J. F. Jue

    2005-11-01T23:59:59.000Z

    Efforts to develop a viable monolithic research reactor fuel plate have continued at Idaho National Laboratory. These efforts have concentrated on both fabrication process refinement and scale-up to produce full sized fuel plates. Advancements have been made in the production of U-Mo foil including full sized foils. Progress has also been made in the friction stir welding and transient liquid phase bonding fabrication processes resulting in better bonding, more stable processes and the ability to fabricate larger fuel plates.

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

    E-Print Network [OSTI]

    Lebrun-Grandié, Damien Thomas

    2014-03-05T23:59:59.000Z

    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...

  16. Ignition and fueling scenario calculations for neutral-beam-heated Tokamak reactors based on pellet injection

    SciTech Connect (OSTI)

    Lengyel, L.L.

    1986-11-01T23:59:59.000Z

    Results of ignition and continuous fueling scenario calculations are presented that were obtained in the framework of an assessment performed for the Next European Torus based on International Tokamak Reactors (INTOR) parameters. The results obtained with pellet injection are compared with results corresponding to gas puffing. Pellet injection transports fresh fuel to the reaction zone on a time scale that is much shorter than the diffusion time characterizing the gas puffing method, thus making the method flexible and readily adaptable to different situations. In the case of ignition by pellet injection, it may become possible to have deep neutral beam penetration and maintain favorable heat deposition profiles up to the moment of density ramp-up, thus substantially relaxing beam output requirements. The importance of a proper match between beam characteristics and pellet parameters is shown. In the case of continuous fueling of an already ignited discharge, the alpha power production notably increases if repetitive pellet injection, instead of gas puffing, is applied. The advantages of pellet injection are substantial, even at moderate pellet velocities.

  17. Fuel Fabrication Capability Research and Development Plan

    SciTech Connect (OSTI)

    Senor, David J.; Burkes, Douglas

    2013-06-28T23:59:59.000Z

    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.

  18. Fuel Fabrication for Surrogate Sphere-Pac Rodlet

    SciTech Connect (OSTI)

    Del Cul, G.D.

    2005-07-19T23:59:59.000Z

    Sphere-pac fuel consists of a blend of spheres of two or three different size fractions contained in a fuel rod. The smear density of the sphere-pac fuel column can be adjusted to the values obtained for light-water reactor (LWR) pellets (91-95%) by using three size fractions, and to values typical of the fast-reactor oxide fuel column ({approx}85%) by using two size fractions. For optimum binary packing, the diameters of the two sphere fractions must differ by at least a factor of 7 (ref. 3). Blending of spheres with smaller-diameter ratios results in difficult blending, nonuniform loading, and lower packing fractions. A mixture of about 70 vol% coarse spheres and 30 vol% fine spheres is needed to obtain high packing fractions. The limiting smear density for binary packing is 86%, with about 82% achieved in practice. Ternary packing provides greater smear densities, with theoretical values ranging from 93 to 95%. Sphere-pac technology was developed in the 1960-1990 period for thermal and fast spectrum reactors of nearly all types (U-Th and U-Pu fuel cycles, oxide and carbide fuels), but development of this technology was most strongly motivated by the need for remote fabrication in the thorium fuel cycle. The application to LWR fuels as part of the DOE Fuel Performance Improvement Program did not result in commercial deployment for a number of reasons, but the relatively low production cost of existing UO{sub 2} pellet fuel is probably the most important factor. In the case of transmutation fuels, however, sphere-pac technology has the potential to be a lower-cost alternative while also offering great flexibility in tailoring the fuel elements to match the exact requirements of any particular reactor core at any given time in the cycle. In fact, the blend of spheres can be adjusted to offer a different composition for each fuel pin or group of pins in a given fuel element. Moreover, it can even provide a vertical gradient of composition in a single fuel pin. For minor-actinide-bearing fuels, the sphere-pac form is likely to accept the large helium release from {sup 241}Am transmutation with less difficulty than pellet forms and is especially well suited to remote fabrication as a dustless fuel form that requires a minimum number of mechanical operations. The sphere-pac (and vi-pac) fuel forms are being explored for use as a plutonium-burning fuel by the European Community, the Russian Federation, and Japan. Sphere-pac technology supports flexibility in the design and fabrication of fuels. For example, the blend composition can be any combination of fissile, fertile, transmutation, and inert components. Since the blend of spheres can be used to fill any geometric form, nonconventional fuel geometries (e.g., annular fuels rods, or annular pellets with the central region filled with spheres) are readily fabricated using sphere-pac loading methods. A project, sponsored by the U.S. Department of Energy Advanced Fuel Cycle Initiative (AFCI), has been initiated at Oak Ridge National Laboratory (ORNL) with the objective of conducting the research and development necessary to evaluate sphere-pac fuel for transmutation in thermal and fast-spectrum reactors. This AFCI work is unique in that it targets minor actinide transmutation and explores the use of a resin-loading technology for the fabrication of the remote-handled minor actinide fraction. While there are extensive data on sphere-pac fuel performance for both thermal-spectrum and fast-spectrum reactors, there are few data with respect to their use as a transmutation fuel. The sphere-pac fuels developed will be tested as part of the AFCI LWR-2 irradiations. This report provides a review of development efforts related to the fabrication of a sphere-pac rodlet containing surrogate fuel materials. The eventual goal of this activity is to develop a robust process that can be used to fabricate fuels or targets containing americium. The report also provides a review of the materials, methods, and techniques to be used in the fabrication of the surrogate fuel rodlet that will also b

  19. UPDATE ON MONOLITHIC FUEL FABRICATION METHODS

    SciTech Connect (OSTI)

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

    2006-10-01T23:59:59.000Z

    Efforts to develop a viable monolithic research reactor fuel plate have continued at Idaho National Laboratory. These efforts have concentrated on both fabrication process refinement and scale-up to produce full sized fuel plates. Progress at INL has led to fabrication of hot isostatic pressed uranium-molybdenum bearing monolithic fuel plates. These miniplates are part of the RERTR-8 miniplate irradiation test. Further progress has also been made on friction stir weld processing which has been used to fabricate full size fuel plates which will be irradiated in the ATR and OSIRIS reactors.

  20. Production of a pellet fuel from Illinois coal fines. Technical report, September 1--November 30, 1994

    SciTech Connect (OSTI)

    Rapp, D.; Lytle, J.; Berger, R.

    1994-12-31T23:59:59.000Z

    The primary goal of this research is to produce a pellet fuel from low-sulfur Illinois coal fines which could burn with emissions of less than 1.8 lbs SO{sub 2}/10{sup 6} Btu in stoker-fired boilers. The significance of 1.8 lbs SO{sub 2}/10{sup 6} Btu is that in the Chicago (9 counties) and St. Louis (2 counties) metropolitan areas, industrial users of coal currently must comply with this level of emissions. Stokers are an attractive market for pellets because pellets are well-suited for this application and because western coal is not a competitor in the stoker market. Compliance stoker fuels come from locations such as Kentucky and West Virginia and the price for fuels from these locations is high relative to the current price of Illinois coal. This market offers the most attractive near-term economic environment for commercialization of pelletization technology. For this effort, the authors will be investigating the use of fines from two Illinois mines which currently mine relatively low-sulfur reserves and that discard their fines fraction (minus 100 mesh). The research will involve investigation of multiple unit operations including column flotation, filtration and pellet production. The end result of the effort will allow for an evaluation of the commercial viability of the approach. This quarter pellet production work commenced and planning for collection and processing of a preparation plant fines fraction is underway.

  1. Radial Power Profile of MOX and LEU Fuel Pellet Versus Burnup

    SciTech Connect (OSTI)

    Chang, Gray S.; Pedersen, Robert C. [INEEL - Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID 83415 (United States)

    2002-07-01T23:59:59.000Z

    One of challenge to burn the WG-Pu in Mixed Oxide (MOX) fuel in light water reactors (LWR) is to demonstrate that the differences between WG-MOX, RG-MOX, and LWR LEU fuel are minimal, and therefore, the commercial MOX and LEU fuel experience base is applicable. The MCWO-calculated Radial Power Profile of LEU, Weapons Grade-MOX and Reactor Grade-MOX fuel pellets at various burnups are similar toward the end of life (50 GWd/t). Therefore, the LEU fuel performance evaluation code - FRAPCON-3 with modifications, such as, the detailed fission power profiles versus burnup, can be used in the MOX fuel pellet performance analysis. MCWO also calculated the {sup 240}Pu/Pu ratio in WG-MOX versus burnup, which reaches an average of 31.25% at discharged burnup of 50 GWd/t. It meets the spent fuel standard for WG-Pu disposition in LWR. (authors)

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

    E-Print Network [OSTI]

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

    Full-scale cofiring tests of binder-enhanced pellets of densified, refuse-derived fuel (dRDF) and high-sulfur coal were conducted during June and July of 1987 in Boiler #5 at Argonne National Laboratory. These tests were conducted with industry...

  3. CHEMICAL ASPECTS OF PELLET-CLADDING INTERACTION IN LIGHT WATER REACTOR FUEL ELEMENTS

    E-Print Network [OSTI]

    Olander, D.R.

    2010-01-01T23:59:59.000Z

    Tubing in Relation to the Pellet-Cladding Interaction010155 CHEMICAL ASPECTS OF PELLET-CLADDING INTERACTION INthe mechanical as­ pects of pellet-cladding interaction(PCI)

  4. Determination of Gd concentration profile in UO2-Gd2O3 fuel pellets

    E-Print Network [OSTI]

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

    2014-02-28T23:59:59.000Z

    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.

  5. Determination of Gd concentration profile in UO2-Gd2O3 fuel pellets

    E-Print Network [OSTI]

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

    2014-01-01T23:59:59.000Z

    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.

  6. Method for producing sintered ceramic, layered, circular fuel pellets

    DOE Patents [OSTI]

    Harlow, John L. (East Berne, NY)

    1983-01-01T23:59:59.000Z

    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.

  7. Processing and Properties of Bulk Y?Ba?Cu?O Superconductors Fabricated by Top Seeded Melt Growth from Precursor Pellets Containing a Graded CeO2 Composition

    E-Print Network [OSTI]

    Zhai, Wei; Shi, Yunhua; Durrell, John H.; Dennis, Anthony R.; Zhang, Zhiwei; Cardwell, David A.

    2015-01-08T23:59:59.000Z

    be effective in improving the applied magnetic properties of these technologically important materials. Single grain, bulk YBCO superconductors fabricated from precursor pellets containing a graded CeO2 composition have been prepared corresponding to a...

  8. Fuel Fabrication Capability Research and Development Plan

    SciTech Connect (OSTI)

    Senor, David J.; Burkes, Douglas

    2014-04-17T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

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

    2013-03-01T23:59:59.000Z

    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.

  10. Automated catalyst processing for cloud electrode fabrication for fuel cells

    DOE Patents [OSTI]

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

    1980-01-01T23:59:59.000Z

    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.

  11. Actual Scale MOX Powder Mixing Test for MOX Fuel Fabrication Plant in Japan

    SciTech Connect (OSTI)

    Osaka, Shuichi; Kurita, Ichiro; Deguchi, Morimoto [Japan Nuclear Fuel Ltd., 4-108, Aza okitsuke, oaza obuchi rokkasyo-mura, kamikita-gun, Aomori 039-3212 (Japan); Ito, Masanori [Japan Atomic Energy Agency, 4-33 Muramatu, Tokai-mura, Ibaraki 319-1194 (Japan); Goto, Masakazu [Nuclear Fuel Industries, Ltd., 14-10, Mita 3-chome, Minato-ku, Tokyo 108-0073 (Japan)

    2007-07-01T23:59:59.000Z

    Japan Nuclear Fuel Ltd. (hereafter, JNFL) promotes a program of constructing a MOX fuel fabrication plant (hereafter, J-MOX) to fabricate MOX fuels to be loaded in domestic light water reactors. Since Japanese fiscal year (hereafter, JFY) 1999, JNFL, to establish the technology for a smooth start-up and the stable operation of J-MOX, has executed an evaluation test for technology to be adopted at J-MOX. JNFL, based on a consideration that J-MOX fuel fabrication comes commercial scale production, decided an introduction of MIMAS technology into J-MOX main process, from powder mixing through pellet sintering, well recognized as mostly important to achieve good quality product of MOX fuel, since it achieves good results in both fuel production and actual reactor irradiation in Europe, but there is one difference that JNFL is going to use Japanese typical plutonium and uranium mixed oxide powder converted with the micro-wave heating direct de-nitration technology (hereafter, MH-MOX) but normal PuO{sub 2} of European MOX fuel fabricators. Therefore, in order to evaluate the suitability of the MH-MOX powder for the MIMAS process, JNFL manufactured small scale test equipment, and implemented a powder mixing evaluation test up until JFY 2003. As a result, the suitability of the MH-MOX powder for the MIMAS process was positively evaluated and confirmed It was followed by a five-years test named an 'actual test' from JFY 2003 to JFY 2007, which aims at demonstrating good operation and maintenance of process equipment as well as obtaining good quality of MOX fuel pellets. (authors)

  12. Update on US High Density Fuel Fabrication Development

    SciTech Connect (OSTI)

    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

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

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

    SciTech Connect (OSTI)

    Jason Hales; Various

    2014-06-01T23:59:59.000Z

    The US DOE’s 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.

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

    SciTech Connect (OSTI)

    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

    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

  15. 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

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

    SciTech Connect (OSTI)

    Folk, Richard L.; Govett, Robert L.

    1992-07-01T23:59:59.000Z

    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.

  17. 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

  18. Tritium pellet injector TPI-1

    SciTech Connect (OSTI)

    Viniar, I.V.; Kuteev, B.V.; Koblents, P.Yu. [Technical Univ., Saint-Petersburg (Russian Federation); Saksagansky, G.L.; Skripunov, V.N. [Efremov Inst., Saint-Petersburg (Russian Federation)

    1995-12-31T23:59:59.000Z

    The current concept of fueling large fusion devices is based on gas puffing and pellet injection. The pellet injector produces, accelerates and transports into a plasmas the pellets composed of hydrogen isotopes. Here, tasks and design of a tritium repeating pellet injector developed in Russia are presented. The injector uses improved in-situ and extrusion technologies for pellet formation.

  19. Pellet and Molecular Beam Injection Fueling on the HL-1M Tokamak

    SciTech Connect (OSTI)

    Xiao Zhenggui; Li Bo; Li Li; Liu Dequan; Yao Lianghua; Dong Jiafu; Guo Gancheng; Deng Zhongchao; Zheng Yinjia; Hong Wenyu; Yan Longwen; Liu Yi; Liu Yong; Wang, Enyao [Southwestern Institute of Physics (China)

    2003-01-15T23:59:59.000Z

    The Eight-shot Pellet Injector (EPI) and Molecular Beam Injector (MBI) as new plasma fueling methods have been developed and installed on the HL-1M tokamak for fueling experiments. The main structures and characteristics of the fueling device and the typical fueling experimental results with EPI and the MBI are reported. In these experiments, typical responses of plasma in discharges with PI and MBI are the peaked density profile Q{sub n} n{sub e}(0)/<(n{sub e})> of >1.65 for MBI and of 2 for PI. The improvement of confinement time E is usually better than 10 to 30% of Gas Puffing (GP) discharge in the same operation condition. In addition, the penetration depth and deposition region of fueling particles, the variance of soft X-ray sawteeth, the rotation and flow of plasma in edge region as well as the photographing of ablation clouds with PI and MBI are compared and presented in this paper.

  20. Fabrication of Small Diesel Fuel Injector Orifices

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

    Micro-Orifice Fabrication - Nickel Vapor Deposition - Laser Micro-Drilling NVD - Weber Laser - Sparkle Publications & PatentsInventions Publications - Fenske, G.,...

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

    SciTech Connect (OSTI)

    McDonald, R.

    2009-12-01T23:59:59.000Z

    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

  2. Advanced Safeguards Approaches for New TRU Fuel Fabrication Facilities

    SciTech Connect (OSTI)

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

    2007-12-15T23:59:59.000Z

    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.

  3. MONOLITHIC FUEL FABRICATION PROCESS DEVELOPMENT AT THE IDAHO NATIONAL LABORATORY

    SciTech Connect (OSTI)

    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

    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.

  4. ag fuel fabrication: Topics by E-print Network

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

    current design a plate ... Ie, Tze Yung Andrew, 1978- 2004-01-01 6 Fabrication of carbon-aerogel electrodes for use in phosphoric acid fuel cells MIT - DSpace Summary: An...

  5. Coated U(Mo) Fuel: As-Fabricated Microstructures

    SciTech Connect (OSTI)

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

    2014-04-01T23:59:59.000Z

    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 µm 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 500°C. 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 500°C 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 500°C.

  6. MONOLITHIC FUEL FABRICATION PROCESS DEVELOPMENT AT THE IDAHO NATIONAL LABORATORY_

    SciTech Connect (OSTI)

    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

    Full-size/prototypic U10Mo monolithic fuel-foils and aluminum clad fuel plates are being developed at the Idaho National Laboratory’s (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).

  7. Fabrication and Characterization of Fully Ceramic Microencapsulated Fuels

    SciTech Connect (OSTI)

    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

    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.

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

    SciTech Connect (OSTI)

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

    2011-11-14T23:59:59.000Z

    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.

  9. Greenfield Alternative Study LEU-Mo Fuel Fabrication Facility

    SciTech Connect (OSTI)

    Washington Division of URS

    2008-07-01T23:59:59.000Z

    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.

  10. Pellet injection technology

    SciTech Connect (OSTI)

    Combs, S.K. (Oak Ridge National Laboratory, P.O. Box 2009, Oak Ridge, Tennessee 37831-8071 (United States))

    1993-07-01T23:59:59.000Z

    During the last 10 to 15 years, significant progress has been made worldwide in the area of pellet injection technology. This specialized field of research originated as a possible solution to the problem of depositing atoms of fuel deep within magnetically confined, hot plasmas for refueling of fusion power reactors. Using pellet injection systems, frozen macroscopic (millimeter-size) pellets composed of the isotopes of hydrogen are formed, accelerated, and transported to the plasma for fueling. The process and benefits of plasma fueling by this approach have been demonstrated conclusively on a number of toroidal magnetic confinement configurations; consequently, pellet injection is the leading technology for deep fueling of magnetically confined plasmas for controlled thermonuclear fusion research. Hydrogen pellet injection devices operate at very low temperatures ([congruent]10 K) at which solid hydrogen ice can be formed and sustained. Most injectors use conventional pneumatic (light gas gun) or centrifuge (mechanical) acceleration concepts to inject hydrogen or deuterium pellets at speeds of [congruent]1--2 km/s. Pellet injectors that can operate at quasi-steady state (pellet delivery rates of 1--40 Hz) have been developed for long-pulse fueling. The design and operation of injectors with the heaviest hydrogen isotope, tritium, offer some special problems because of tritium's radioactivity. To address these problems, a proof-of-principle experiment was carried out in which tritium pellets were formed and accelerated to speeds of 1.4 km/s. Tritium pellet injection is scheduled on major fusion research devices within the next few years. Several advanced accelerator concepts are under development to increase the pellet velocity. One of these is the two-stage light gas gun, for which speeds of slightly over 4 km/s have already been reported in laboratory experiments with deuterium ice.

  11. Decommissioning of a mixed oxide fuel fabrication plant at Winfrith Technolgy Centre

    SciTech Connect (OSTI)

    Pengelly, M.G.A. [AEA Technology, Dorchester (United Kingdom)

    1994-01-01T23:59:59.000Z

    The Alpha Materials Laboratory (Building A52) at Winfrith contained a mixed oxide fuel fabrication plant which had a capability of producing 10 te/yr of pelleted/compacted fuel and was in operation from 1962 until 1980, when the requirement for this type of fuel in the UK diminished, and the plant became surplus to requirements. A program to develop decommissioning techniques for plutonium plants was started in 1983, addressing the following aspects of alpha plant decommissioning: (1) Re-usable containment systems, (2) Strippable coating technology, (3) Mobile air filtration plant, (4) Size reduction primarily using cold cutting, (5) techniques, (6) Waste packing, and (7) Alpha plant decommissioning methodology. The technology developed has been used to safely and efficiently decommission radioactive plant and equipment including Pu contaminated glove boxes. (63 glove boxes to date) The technology has been widely adopted in the United Kingdom and elsewhere. This paper outlines the general strategies adopted and techniques used for glove box decommissioning in building A52.

  12. Method to fabricate high performance tubular solid oxide fuel cells

    DOE Patents [OSTI]

    Chen, Fanglin; Yang, Chenghao; Jin, Chao

    2013-06-18T23:59:59.000Z

    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.

  13. Fabrication of small-orifice fuel injectors for diesel engines.

    SciTech Connect (OSTI)

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

    2005-04-08T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Hai Huang; Ben Spencer; Jason Hales

    2014-10-01T23:59:59.000Z

    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.

  15. Pellet inspection apparatus

    DOE Patents [OSTI]

    Wilks, Robert S. (Plum Borough, PA); Taleff, Alexander (Churchill Borough, PA); Sturges, Jr., Robert H. (Plum Borough, PA)

    1982-01-01T23:59:59.000Z

    Apparatus for inspecting nuclear fuel pellets in a sealed container for diameter, flaws, length and weight. The apparatus includes, in an array, a pellet pick-up station, four pellet inspection stations and a pellet sorting station. The pellets are delivered one at a time to the pick-up station by a vibrating bowl through a vibrating linear conveyor. Grippers each associated with a successive pair of the stations are reciprocable together to pick up a pellet at the upstream station of each pair and to deposit the pellet at the corresponding downstream station. The gripper jaws are opened selectively depending on the state of the pellets at the stations and the particular cycle in which the apparatus is operating. Inspection for diameter, flaws and length is effected in each case by a laser beam projected on the pellets by a precise optical system while each pellet is rotated by rollers. Each laser and its optical system are mounted in a container which is free standing on a precise surface and is provided with locating buttons which engage locating holes in the surface so that each laser and its optical system is precisely set. The roller stands are likewise free standing and are similarly precisely positioned. The diameter optical system projects a thin beam of light which scans across the top of each pellet and is projected on a diode array. The fl GOVERNMENT CONTRACT CLAUSE The invention herein described was made in the course of or under a contract or subcontract thereunder with the Department of Energy bearing No. EY-67-14-C-2170.

  16. Fuel cell collector plate and method of fabrication

    DOE Patents [OSTI]

    Braun, James C. (Juno Beach, FL); Zabriskie, Jr., John E. (Port St. Lucie, FL); Neutzler, Jay K. (Palm Beach Gardens, FL); Fuchs, Michel (Boynton Beach, FL); Gustafson, Robert C. (Palm Beach Gardens, FL)

    2001-01-01T23:59:59.000Z

    An improved molding composition is provided for compression molding or injection molding a current collector plate for a polymer electrolyte membrane fuel cell. The molding composition is comprised of a polymer resin combined with a low surface area, highly-conductive carbon and/or graphite powder filler. The low viscosity of the thermoplastic resin combined with the reduced filler particle surface area provide a moldable composition which can be fabricated into a current collector plate having improved current collecting capacity vis-a-vis comparable fluoropolymer molding compositions.

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

    SciTech Connect (OSTI)

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

    2010-03-01T23:59:59.000Z

    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.

  18. Pelletizing lignite

    DOE Patents [OSTI]

    Goksel, Mehmet A. (Houghton, MI)

    1983-11-01T23:59:59.000Z

    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.

  19. 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

  20. Fabrication of solid oxide fuel cell by electrochemical vapor deposition

    DOE Patents [OSTI]

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

    1989-01-01T23:59:59.000Z

    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.

  1. Fabrication of solid oxide fuel cell by electrochemical vapor deposition

    DOE Patents [OSTI]

    Riley, B.; Szreders, B.E.

    1988-04-26T23:59:59.000Z

    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.

  2. A compact flexible pellet injector for the TJ-II stellarator

    SciTech Connect (OSTI)

    McCarthy, K. J.; Carmona, J. M. [Laboratory Nacional de Fusion, CIEMAT, Av. Complutense 22, 28040 Madrid (Spain); Combs, S. K.; Baylor, L. R.; Caughman, J. B. O.; Fehling, D. T.; Foust, C. R.; McGill, J. M.; Rasmussen, D. A. [Oak Ridge National Laboratory, P.O. Box 2009, Oak Ridge, Tennessee 37831-8071 (United States)

    2008-10-15T23:59:59.000Z

    A compact pellet injector is being built for the TJ-II stellarator. It is an upgraded version of the 'pellet injector in a suitcase' developed at Oak Ridge National Laboratory and installed on the Madison Symmetric Torus where it continues to be used in many plasma experiments. The design aim is to provide maximum flexibility at minimal cost, while allowing for future upgrades. It is a four-barrel system equipped with a cryogenic refrigerator for in situ hydrogen pellet formation, a combined mechanical punch/propellant valve system, pellet diagnostics, and an injection line, destined for use as an active diagnostic and for fueling. In order to fulfill both objectives it will be sufficiently flexible to permit pellets, with diameters from 0.4 to 1 mm, to be fabricated and accelerated to velocities from 150 to {approx}1000 m s{sup -1}.

  3. A compact Flexible Pellet Injector for the TJ-II Stellarator

    SciTech Connect (OSTI)

    McCarthy, K. J. [Harvard-Smithsonian Center for Astrophysics; Combs, Stephen Kirk [ORNL; Baylor, Larry R [ORNL; Caughman, John B [ORNL; Fehling, Dan T [ORNL; Foust, Charles R [ORNL; McGill, James M [ORNL; Carmona, J. M. [Laboratory Nacional de Fusion, CIEMAT; Rasmussen, David A [ORNL

    2008-01-01T23:59:59.000Z

    A compact pellet injector is being built for the TJ-II stellarator. It is an upgraded version of the pellet injector in a suitcase developed at Oak Ridge National Laboratory and installed on the Madison Symmetric Torus where it continues to be used in many plasma experiments. The design aim is to provide maximum flexibility at minimal cost, while allowing for future upgrades. It is a four-barrel system equipped with a cryogenic refrigerator for in situ hydrogen pellet formation, a combined mechanical punch/propellant valve system, pellet diagnostics, and an injection line, destined for use as an active diagnostic and for fueling. In order to fulfill both objectives it will be sufficiently flexible to permit pellets, with diameters from 0.4 to 1 mm, to be fabricated and accelerated to velocities from 150 to 1000 m s 1.

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

    SciTech Connect (OSTI)

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

    2005-12-05T23:59:59.000Z

    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

  5. Pellet injector development at ORNL

    SciTech Connect (OSTI)

    Combs, S.K.; Milora, S.L.; Baylor, L.R. [and others

    1996-10-01T23:59:59.000Z

    Oak Ridge National Laboratory (ORNL) has been developing pellet injection systems for plasma fueling experiments on magnetic fusion confinement devices for about 20 years. Recently, the development has focused on meeting the complex fueling needs of the International Thermonuclear Experimental Reactor (ITER) and future reactors. The proposed ITER fueling system will use a combination of deuterium- tritium (D-T) gas puffing and pellet injection to achieve and maintain ignited plasmas. The pellet injection system will have to provide D-T fueling for much longer pulse lengths (up to {approx}1000 s) than present day applications (typically limited to less than several seconds). In this paper, we describe the ongoing pellet injector development activities at ORNL, including the following three in direct support of ITER: (1) an improved pellet feed system for the centrifuge injector, (2) a steady-state extruder feed system, and (3) tritium extruder technology. In addition to the major activities, a repeating two-stage light gas gun for high-speed pellet injection ({approx}2.5 km/s) has been developed in a collaboration with ENEA Frascati; also, the production of impurity pellets (Ne, Ar, and Kr) has been demonstrated using the DIII-D and Tokamak Fusion Test Reactor pneumatic pellet injection system.

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

    E-Print Network [OSTI]

    Hall, Kwame (Kwame J.)

    2009-01-01T23:59:59.000Z

    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 ...

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

    E-Print Network [OSTI]

    Victoria, University of

    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

  8. Development of a Tritium Extruder for ITER Pellet Injection

    SciTech Connect (OSTI)

    M.J. Gouge; P.W. Fisher

    1998-09-01T23:59:59.000Z

    As part of the International Thermonuclear Experimental Reactor (ITER) plasma fueling development program, Oak Ridge National Laboratory (ORNL) has fabricated a pellet injection system to test the mechanical and thermal properties of extruded tritium. Hydrogenic pellets will be used in ITER to sustain the fusion power in the plasma core and may be crucial in reducing first-wall tritium inventories by a process of "isotopic fueling" in which tritium-rich pellets fuel the burning plasma core and deuterium gas fuels the edge. This repeating single-stage pneumatic pellet injector, called the Tritium-Proof-of-Principle Phase II (TPOP-II) Pellet Injector, has a piston-driven mechanical extruder and is designed to extrude and accelerate hydrogenic pellets sized for the ITER device. The TPOP-II program has the following development goals: evaluate the feasibility of extruding tritium and deuterium-tritium (D-T) mixtures for use in future pellet injection systems; determine the mechanical and thermal properties of tritium and D-T extrusions; integrate, test, and evaluate the extruder in a repeating, single-stage light gas gun that is sized for the ITER application (pellet diameter -7 to 8 mm); evaluate options for recycling propellant and extruder exhaust gas; and evaluate operability and reliability of ITER prototypical fueling systems in an environment of significant tritium inventory that requires secondary and room containment systems. In tests with deuterium feed at ORNL, up to 13 pellets per extrusion have been extruded at rates up to 1 Hz and accelerated to speeds of 1.0 to 1.1 km/s, using hydrogen propellant gas at a supply pressure of 65 bar. Initially, deuterium pellets 7.5 mm in diameter and 11 mm in length were produced-the largest cryogenic pellets produced by the fusion program to date. These pellets represent about a 10% density perturbation to ITER. Subsequently, the extruder nozzle was modified to produce pellets that are almost 7.5-mm right circular cylinders. Tritium and D-T pellets have been produced in experiments at the Los Alamos National Laboratory Tritium Systems Test Assembly. About 38 g of tritium have been utilized in the experiment. The tritium was received in eight batches, six from product containers and two from the Isotope Separation System. Two types of runs were made: those in which the material was only extruded and those in which pellets were produced and fired with deuterium propellant. A total of 36 TZ runs and 28 D-T runs have been made. A total of 36 pure tritium runs and 28 D-T mixture runs were made. Extrusion experiments indicate that both T2 and D-T will require higher extrusion forces than D2 by about a factor of two.

  9. Production of zinc pellets

    DOE Patents [OSTI]

    Cooper, John F. (Oakland, CA)

    1996-01-01T23:59:59.000Z

    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.

  10. Production of zinc pellets

    DOE Patents [OSTI]

    Cooper, J.F.

    1996-11-26T23:59:59.000Z

    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.

  11. Ash pelletization

    SciTech Connect (OSTI)

    Woodall, M.

    1994-12-31T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

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

    2007-06-01T23:59:59.000Z

    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.

  13. 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 DataDepartment of Energy Your Density Isn't YourTransport in RepresentativeDepartment of Energy

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

    SciTech Connect (OSTI)

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

    1999-12-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Schock, Alfred

    1995-08-01T23:59:59.000Z

    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.

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

    E-Print Network [OSTI]

    Tharp, Ronald S

    2005-01-01T23:59:59.000Z

    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 ...

  17. Thermo-mechanical modeling of a micro-fabricated solid oxide fuel cell

    E-Print Network [OSTI]

    Ie, Tze Yung Andrew, 1978-

    2004-01-01T23:59:59.000Z

    A micro-fabricated solid oxide fuel cell is currently being designed by the Micro-chemical Power Team(funded under the Multidisciplinary University Research Initiative(MURI) Research Program). In the current design a plate ...

  18. 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...

  19. 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 DataDepartment of Energy Your Density Isn't YourTransport in RepresentativeDepartment of Energy 1.DepartmentofDEPARTMENT2EnergySmall

  20. 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC) Environmental Assessments (EA) /EmailMolecularGE,OzoneContacts& TARGET

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

    SciTech Connect (OSTI)

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

    2014-03-10T23:59:59.000Z

    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 2800°C in vacuum and about 750°C 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 UO2–CNT composites without affecting the neutronic property of UO2 significantly. The concept of this goal is to utilize a rapid sintering method (5–15 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.

  2. Evaluation of LANL Capabilities for Fabrication of TREAT Conversion Fuel

    SciTech Connect (OSTI)

    Luther, Erik Paul [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Leckie, Rafael M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Dombrowski, David E. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2014-03-06T23:59:59.000Z

    This report estimates costs and schedule associated with scale up and fabrication of a low-enriched uranium (LEU) core for the Transient Reactor Test Facility (TREAT) reactor. This study considers facilities available at Los Alamos National Laboratory, facility upgrades, equipment, installation and staffing costs. Not included are costs associated with raw materials and off-site shipping. These estimates are considered a rough of magnitude. At this time, no specifications for the LEU core have been made and the final schedule needed by the national program. The estimate range (+/-100%) reflects this large uncertainty and is subject to change as the project scope becomes more defined.

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

    SciTech Connect (OSTI)

    Not Available

    1980-08-01T23:59:59.000Z

    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.

  4. 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

  5. atr fuel fabrication: Topics by E-print Network

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

    on hydrogen rich mixtures best Hydrogen rich leads to highest power density in fuel cell Cost of SOFC is high, lower cost SOFC system is potentially highest power density...

  6. Design, fabrication, and characterization of a micro fuel processor

    E-Print Network [OSTI]

    Blackwell, Brandon S. (Brandon Shaw)

    2008-01-01T23:59:59.000Z

    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 ...

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

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

    project review conducted by NNSA 1 Mixed oxide fuel is produced by mixing plutonium with depleted uranium. concluded that the MOX Facility had a very low probability of being...

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

    SciTech Connect (OSTI)

    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

    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.

  9. Safety issues in fabricating mixed oxide fuel using surplus weapons plutonium

    SciTech Connect (OSTI)

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

    1998-07-01T23:59:59.000Z

    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.

  10. Trans-Atlantic Fuel Fabrication Security of Supply Program

    SciTech Connect (OSTI)

    Bobo Perez, Emilio I. [ENUSA Industrias Avanzadas, S.A., Santiago Rusinol 12, 28040 Madrid (Spain); Novo Sanjurjo, Manuel [CC.NN. Almaraz-Trillo, AIE, Avenida de Manoteras, 46 bis, Edificio Delta Norte, 3 planta 5a, 28050 - Madrid (Spain); Ferguson, Scott [Wolf Creek Nuclear Operating Corporation, Wolf Creek Generating Station, Post Office Box 411, Burlington, KS 66839 (United States); Feagin, Bob; Dwight, James [Westinghouse Electric Company LLC, P.O. Drawer R, Columbia, South Carolina 29250 (United States); Gonzalez Villegas, Roberto [ENUSA Industrias Avanzadas, S.A., Santiago Rusinol 12, 28040 Madrid (Spain)

    2007-07-01T23:59:59.000Z

    The present paper describes one of the latest initiatives put in place by the nuclear industry to secure the supply of nuclear fuel for LWR. The project presented here is focused on the manufacturing phase of the supply chain and is the result of a cooperation between US and Spanish entities - nuclear power plant as well as fuel manufacturers - with the added value of the participation of other facilities located in Europe. The main objectives, challenges and characteristics of the program are discussed as well as the expected results. (authors)

  11. Method of fabricating a monolithic solid oxide fuel cell

    DOE Patents [OSTI]

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

    1994-03-01T23:59:59.000Z

    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.

  12. Method of fabricating a monolithic solid oxide fuel cell

    DOE Patents [OSTI]

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

    1994-01-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Karen L. Shropshire

    2008-04-01T23:59:59.000Z

    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 fuel’s 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 tool’s 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 study’s results also provide support and validation for other nuclear fuel development studies and conclusions. Recommendations are offered for further research.

  14. Standard specification for sintered gadolinium oxide-uranium dioxide pellets

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2008-01-01T23:59:59.000Z

    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...

  15. Conductivity fuel cell collector plate and method of fabrication

    DOE Patents [OSTI]

    Braun, James C. (Juno Beach, FL)

    2002-01-01T23:59:59.000Z

    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.

  16. Fabrication of fuel cell electrodes and other catalytic structures

    DOE Patents [OSTI]

    Smith, J.L.

    1987-02-11T23:59:59.000Z

    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.

  17. Current generation by phased injection of pellets

    SciTech Connect (OSTI)

    Fisch, N.J.

    1983-08-01T23:59:59.000Z

    By phasing the injection of frozen pellets into a tokamak plasma, it is possible to generate current. The current occurs when the electron flux to individual members of an array of pellets is asymmetric with respect to the magnetic field. The utility of this method for tokamak reactors, however, is unclear; the current, even though free in a pellet-fueled reactor, may not be large enough to be worth the trouble. Uncertainty as to the utility of this method is, in part, due to uncertainty as to proper modeling of the one-pellet problem.

  18. 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 DataDepartment of Energy Your Density Isn't YourTransport inEnergy0.pdfTechnologies Program

  19. Literature on fabrication of tungsten for application in pyrochemical processing of spent nuclear fuels

    SciTech Connect (OSTI)

    Edstrom, C.M.; Phillips, A.G.; Johnson, L.D.; Corle, R.R.

    1980-10-11T23:59:59.000Z

    The pyrochemical processing of nuclear fuels requires crucibles, stirrers, and transfer tubing that will withstand the temperature and the chemical attack from molten salts and metals used in the process. This report summarizes the literature that pertains to fabrication (joining, chemical vapor deposition, plasma spraying, forming, and spinning) is the main theme. This report also summarizes a sampling of literature on molbdenum and the work previously performed at Argonne National Laboratory on other container materials used for pyrochemical processing of spent nuclear fuels.

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

    E-Print Network [OSTI]

    Zhao, Tianshou

    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

  1. 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

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

    SciTech Connect (OSTI)

    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

    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)

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

    SciTech Connect (OSTI)

    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

    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.

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

    SciTech Connect (OSTI)

    S. T. Khericha

    2007-04-01T23:59:59.000Z

    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.

  5. Comment on Li pellet Conditioning in TFTR

    SciTech Connect (OSTI)

    R.V. Budny

    2011-05-23T23:59:59.000Z

    Li pellet conditioning in TFTR results in a reduction of the edge electron density which allows increased neutral beam penetration, central heating, and fueling. Consequently the temperature profiles became more peaked with higher central Ti, Te, and neutron emission rates.

  6. 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

  7. Development of repetitive railgun pellet accelerator and steady-state pellet supply system

    SciTech Connect (OSTI)

    Oda, Y.; Onozuka, M.; Azuma, K. [Mitsubishi Heavy Industries, Ltd., Kobe (Japan); Kasai, S.; Hasegawa, K. [Japan Atomic Energy Research Inst., Naka (Japan)

    1995-12-31T23:59:59.000Z

    A railgun system for repetitive high-speed pellet acceleration and steady-state pellet supply system has been developed and investigated. Using a 2m-long railgun system, the hydrogen pellet was accelerated to 2.6km/sec by the supplied energy of 1.7kJ. It is expected that the hydrogen pellet can be accelerated to 3km/sec using the present pneumatic pellet accelerator and a 2m-long augment railgun. Screw-driven hydrogen-isotope filament extruding system has been fabricated and will be tested to examine its applicability to the steady-state extrusion of the solid hydrogen-isotope filament.

  8. Actinide partitioning-transmutation program final report. IV. Miscellaneous aspects. [Transport; fuel fabrication; decay; policy; economics

    SciTech Connect (OSTI)

    Alexander, C.W.; Croff, A.G.

    1980-09-01T23:59:59.000Z

    This report discusses seven aspects of actinide partitioning-transmutation (P-T) which are important in any complete evaluation of this waste treatment option but which do not fall within other major topical areas concerning P-T. The so-called miscellaneous aspects considered are (1) the conceptual design of a shipping cask for highly neutron-active fresh and spent P-T fuels, (2) the possible impacts of P-T on mixed-oxide fuel fabrication, (3) alternatives for handling the existing and to-be-produced spent fuel and/or wastes until implementation of P-T, (4) the decay and dose characteristics of P-T and standard reactor fuels, (5) the implications of P-T on currently existing nuclear policy in the United States, (6) the summary costs of P-T, and (7) methods for comparing the risks, costs, and benefits of P-T.

  9. 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

  10. Buffer Pellets for High-Yield, Top-Seeded Melt Growth of Large Grain Y?Ba?Cu?O Superconductors

    E-Print Network [OSTI]

    Kumar, Namburi Devendra; Shi, Yunhua; Zhai, Wei; Dennis, Anthony R.; Durrell, John H.; Cardwell, David A.

    2015-01-19T23:59:59.000Z

    , which was determined by optimizing targeted critical parameters of the buffer pellet, including the choice of the buffer pellet composition and its aspect ratio, for the reliable fabrication of large, single grains of (RE)BCO. Potential candidates...

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

    SciTech Connect (OSTI)

    Schock, Alfred

    1994-06-01T23:59:59.000Z

    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.

  12. Cryogenic pellet production developments for long-pulse plasma operation

    SciTech Connect (OSTI)

    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

    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.

  13. Pellet injector research and development at ORNL

    SciTech Connect (OSTI)

    Combs, S.K.; Argo, B.E.; Baylor, L.R.; Cole, M.J.; Dyer, G.R.; Fehling, D.T.; Fisher, P.W.; Foster, C.A.; Foust, C.R.; Gouge, M.J.; Jernigan, T.C.; Langley, R.A.; Milora, S.L.; Qualls, A.L.; Schechter, E.; Sparks, D.O.; Tsai, C.C.; Wilgen, J.B.; Whealton, J.W.

    1993-06-01T23:59:59.000Z

    A variety of pellet injector designs have been developed at ORNL including single-shot guns that inject one pellet, multiple-shot guns that inject four and eight pellets, machine gun-types (single- and multiple-barrel) that can inject up to >100 pellets, and centrifugal accelerators (mechanical devices that are inherently capable of high repetition rates and long-pulse operation). With these devices, macroscopic pellets (1--6 mm in diameter) composed of hydrogen isotopes are typically accelerated to speeds of {approximately}1.0 to 2.0 km/s for injection into plasmas of experimental fusion devices. In the past few years, steady progress has been made at ORNL in the development and application of pellet injectors for fueling present-day and future fusion devices. In this paper, we briefly describe some research and development activities at ORNL, including: (1) two recent applications and a new one on large experimental fusion devices, (2) high-velocity pellet injector development, and (3) tritium injector research.

  14. Reciprocating pellet press

    DOE Patents [OSTI]

    Jones, Charles W. (Seminole, FL)

    1981-04-07T23:59:59.000Z

    A machine for pressing loose powder into pellets using a series of reciprocating motions has an interchangeable punch and die as its only accurately machines parts. The machine reciprocates horizontally between powder receiving and pressing positions. It reciprocates vertically to press, strip and release a pellet.

  15. Penetration Studies for Deuterium Pellets in Wendelstein 7-AS

    SciTech Connect (OSTI)

    Baldzuhn, Juergen [Max Planck Institut fuer Plasmaphysik (Germany); Baylor, Larry Robert [Oak Ridge National Laboratory (United States); Lyon, James F. [Oak Ridge National Laboratory (United States)

    2004-09-15T23:59:59.000Z

    Deep particle fueling into a fusion-relevant plasma can be performed by the injection of cryogenic hydrogen or deuterium pellets. However, the penetration depth and fueling efficiency can be greatly limited when enhanced pellet ablation by fast particles occurs. Only a limited database exists for the penetration depth of ice pellets into stellarators. The penetration depth is measured during pellet injection into purely electron cyclotron resonance heated plasmas on the Wendelstein 7-AS (W7-AS) stellarator. These data are compared with the International Pellet Ablation Database (IPADBASE). Good agreement is found, if the neutral gas shielding model is applied for the scaling law of the penetration depth. The experimental data from W7-AS are used as a basis for planning a new pellet injection system for the Wendelstein 7-X stellarator, which is now under construction.

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

    SciTech Connect (OSTI)

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

    1997-11-01T23:59:59.000Z

    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.

  17. Pellet driven disruptions in tokamaks

    SciTech Connect (OSTI)

    Strauss, H. R. [Courant Institute of Mathematical Sciences, New York University, New York, New York 10012 (United States)] [Courant Institute of Mathematical Sciences, New York University, New York, New York 10012 (United States); Park, W. [Princeton Plasma Physics Laboratory, Princeton, New Jersey 08543 (United States)] [Princeton Plasma Physics Laboratory, Princeton, New Jersey 08543 (United States)

    2000-01-01T23:59:59.000Z

    Pellet injection can trigger ballooning like instability in tokamaks, driven by the large pressure perturbation of the pellet cloud. The instability is easier to excite when pellets are injected on the low magnetic field side of the tokamak, which is the usual case. This is because the pellet pressure perturbation tends to add to the background pressure drive. When pellets are injected on the high field side, the instability is harder to excite, because the pellet pressure perturbation opposes the background pressure drive. Nonlinearly, the instability causes fragmentation of the pellet cloud, and can give anomalous pellet penetration. This effect might explain recent experimental observations. (c) 2000 American Institute of Physics.

  18. Lignite pellets and methods of agglomerating or pelletizing

    DOE Patents [OSTI]

    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

    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.

  19. 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)

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

    2002-06-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Toevs, J.W.

    1997-12-31T23:59:59.000Z

    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.

  1. 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)

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

    1981-10-01T23:59:59.000Z

    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.

  2. 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)

    Not Available

    1989-08-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Not Available

    1989-08-01T23:59:59.000Z

    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.

  4. 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)

    Not Available

    1989-08-01T23:59:59.000Z

    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.

  5. 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)

    Shott, Gregory [NSTec

    2014-08-31T23:59:59.000Z

    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.

  6. Standard specification for nuclear-grade aluminum oxide pellets

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2008-01-01T23:59:59.000Z

    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.

  7. Radation shielding pellets

    DOE Patents [OSTI]

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

    1988-01-01T23:59:59.000Z

    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.

  8. Mobile Biomass Pelletizing System

    SciTech Connect (OSTI)

    Thomas Mason

    2009-04-16T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

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

    1986-02-21T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

    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

    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.

  11. New Pellet Injection Schemes on DIII-D

    SciTech Connect (OSTI)

    Anderson, P.M.; Baylor, L.R.; Combs, S.K.; Foust, C.R.; Jernigan, T.C.; Robinson, J.I.

    1999-11-13T23:59:59.000Z

    The pellet fueling 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) of the tokamak. The HFS pellet injection technique was first employed on ASDEX-Upgrade with significant improvements reported in both pellet penetration and fueling efficiency. The new pellet injection schemes on DIII-D required the installation of new guide tubes. These lines are {approx_equal}12.5 m in total length and are made up of complex bends and turns (''roller coaster'' like) to route pellets from the injector to the plasma, including sections inside the torus. The pellet speed at which intact pellets can survive through the curved guide tubes is limited ({approx_equal}200-300 m/s for HFS injection schemes). Thus, one of the three gas guns on the injector was modified to provide pellets in a lower speed regime than the original guns (normal speed range {approx_equal}500 to 1000 m/s). The guide tube installations and gun modifications are described along with the injector operating parameters, and the latest test results are highlighted.

  12. Entry/exit control at fuel fabrication facilities using or possessing formula quantities of strategic special nuclear material

    SciTech Connect (OSTI)

    Dwyer, P.A.

    1988-12-01T23:59:59.000Z

    This document presents information on entry/exit control at fuel fabrication facilities using or possessing formula quantities of strategic special nuclear material. It describes NRC requirements and methods for conducting personnel, package, and vehicle searches at these facilities. Testing methods for determining the detection capability of firearms, explosives, and metal detectors are provided.

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

    SciTech Connect (OSTI)

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

    2003-02-26T23:59:59.000Z

    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.

  14. Numerical Study on Behavior of Hydrogen Ice Pellet in Drift Tube

    SciTech Connect (OSTI)

    Yokomine, Takehiko [Interdisciplinary Graduate School of Engineering Sciences, Kyushu University (Japan); Yonemoto, Yukihiro [Hitachi Industries Co. Ltd. (Japan); Ebara, Shinji [Interdisciplinary Graduate School of Engineering Sciences, Kyushu University (Japan); Shimizu, Akihiko [Interdisciplinary Graduate School of Engineering Sciences, Kyushu University (Japan)

    2005-04-15T23:59:59.000Z

    Pellet injection with a bent drift tube is considered as one of the flexible methods to have a variety of fueling locations and injection angles in fusion plasma. Since both pellet mass and velocity greatly affect the plasma properties, mass loss and velocity attenuation of the pellet in the drift tube should be evaluated properly. We focused on the impact of the pellet on the tube wall and numerically estimated the mass loss and the velocity attenuation.

  15. Twin-Screw Extruder and Pellet Accelerator Integration Developments for ITER

    SciTech Connect (OSTI)

    Meitner, Steven J [ORNL; Baylor, Larry R [ORNL; Combs, Stephen Kirk [ORNL; Fehling, Dan T [ORNL; Foust, Charles R [ORNL; McGill, James M [ORNL; Rasmussen, David A [ORNL; Maruyama, So [ITER Organization, Cadarache, France

    2011-01-01T23:59:59.000Z

    The ITER pellet injection system consisting of a twinscrew frozen hydrogen isotope extruder, coupled to a combination solenoid actuated pellet cutter and pneumatic pellet accelerator, is under development at the Oak Ridge National Laboratory. A prototype extruder has been built to produce a continuous solid deuterium extrusion and will be integrated with a secondary section, where pellets are cut, chambered, and launched with a single-stage pneumatic accelerator into the plasma through a guide tube. This integrated pellet injection system is designed to provide 5 mm fueling pellets, injected at a rate up to 10 Hz, or 3 mm edge localized mode (ELM) triggering pellets, injected at higher rates up to 20 Hz. The pellet cutter, chamber mechanism, and the solenoid operated pneumatic valve for the accelerator are optimized to provide pellet velocities between 200-300 m/s to ensure high pellet survivability while traversing the inner wall fueling guide tubes, and outer wall ELMpacing guide tubes. This paper outlines the current twin-screwextruder design, pellet accelerator design, and the integrationrequired for both fueling and ELM pacing pellets.

  16. US-Russian collaboration for enhancing nuclear materials protection, control, and accounting at the Elektrostal uranium fuel-fabrication plant

    SciTech Connect (OSTI)

    Smith, H. [Los Alamos National Lab., NM (United States); Allentuck, J. [Brookhaven National Lab., Upton, NY (United States); Barham, M. [Oak Ridge National Lab., TN (United States); Bishop, M. [Sandia National Labs., Albuquerque, NM (United States); Wentz, D. [Lawrence Livermore National Lab., CA (United States); Steele, B.; Bricker, K. [Pacific Northwest National Lab., Richland, WA (United States); Cherry, R. [USDOE, Washington, DC (United States); Snegosky, T. [Dept. of Defense, Washington, DC (United States). Defense Nuclear Agency

    1996-09-01T23:59:59.000Z

    In September 1993, an implementing agreement was signed that authorized collaborative projects to enhance Russian national materials control and accounting, physical protection, and regulatory activities, with US assistance funded by the Nunn-Lugar Act. At the first US-Russian technical working group meeting in Moscow in February 1994, it was decided to identify a model facility where materials protection, control, and accounting (MPC and A) and regulatory projects could be carried out using proven technologies and approaches. The low-enriched uranium (LEU or RBMK and VVER) fuel-fabrication process at Elektrostal was selected, and collaborative work began in June 1994. Based on many factors, including initial successes at Elektrostal, the Russians expanded the cooperation by proposing five additional sites for MPC and A development: the Elektrostal medium-enriched uranium (MEU or BN) fuel-fabrication process and additional facilities at Podolsk, Dmitrovgrad, Obninsk, and Mayak. Since that time, multilaboratory teams have been formed to develop and implement MPC and A upgrades at the additional sites, and much new work is underway. This paper summarizes the current status of MPC and A enhancement projects in the LEU fuel-fabrication process and discusses the status of work that addresses similar enhancements in the MEU (BN) fuel processes at Elektrostal, under the recently expanded US-Russian MPC and A cooperation.

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

    SciTech Connect (OSTI)

    Lloyd, R.

    1980-10-01T23:59:59.000Z

    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.

  18. I Investigation of Pellet Acceleration

    E-Print Network [OSTI]

    I Investigation of Pellet Acceleration by an Arc heated Gas Gun An Interim Report INVESTIGATION OP PELLET ACCELERATION BY AN ARC HEATED GAS GUN* An Interim Report on the Investigations carried, and K.-V. Weisberg Abstract. Deep penetration of pellets into the JET plasma may prove to be a useful

  19. MICROBIAL POPULATIONS FECAL PELLETS AND

    E-Print Network [OSTI]

    Luther, Douglas S.

    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

  20. 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

  1. Evaluation of UF{sub 6}-to-UO{sub 2} conversion capability at commercial nuclear fuel fabrication facilities.

    SciTech Connect (OSTI)

    Ranek, N. L.; Monette, F. A.

    2001-06-08T23:59:59.000Z

    This report examines the capabilities of existing commercial nuclear fuel fabrication facilities to convert depleted uranium hexafluoride (UF{sub 6}) to uranium oxide (UO{sub 2}). The U.S. Department of Energy (DOE) needs this information to determine whether using such capacity to convert DOE's inventory of depleted UF{sub 6} to a more stable form is a reasonable alternative that should be considered in the site-specific environmental impact statement for construction and operation of depleted UF{sub 6} conversion facilities. Publicly available information sources were consulted to ascertain the information summarized in this report. For domestic facilities, the information summarized includes currently operating capacity to convert depleted UF{sub 6} to UO{sub 2}; transportation distances from depleted UF{sub 6} storage locations near Oak Ridge, Tennessee, Portsmouth, Ohio, and Paducah, Kentucky, to the facilities; and regulatory requirements applicable to nuclear fuel fabrication and transportation of depleted UF{sub 6}. The report concludes that the total currently operating capability of U.S. commercial nuclear fuel fabricators to convert UF{sub 6} to UO{sub 2} is approximately 5,200 metric tons of UF{sub 6} per annum (tUF{sub 6}/a). This total includes 666 tUF{sub 6}/a scheduled for shutdown by the end of 2001. However, only about 300 tUF{sub 6}/a of this capacity could be confirmed as being possibly available to DOE. The report also provides some limited descriptions of the capabilities of foreign fuel fabrication plants to convert UF{sub 6} to uranium oxide forms.

  2. Dongara Pellet Plant | 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 onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directedAnnual SiteofEvaluating A Potential MicrohydroDistrict of Columbia:DominionDongara Pellet Plant Jump

  3. 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 onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere I Geothermal Pwer PlantMunhall,Missouri:EnergyOssian,Parle Biscuits PvtPawPearland,Peekskill,Pellet Zone Ltd

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

    SciTech Connect (OSTI)

    Douglas W. Marshall

    2014-10-01T23:59:59.000Z

    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.

  5. Experimental study of curved guide tubes for pellet injection

    SciTech Connect (OSTI)

    Combs, S.K.; Baylor, L.R.; Foust, C.R.; Gouge, M.J.; Jernigan, T.C.; Milora, S.L.

    1997-12-01T23:59:59.000Z

    The use of curved guide tubes for transporting frozen hydrogen pellets offers great flexibility for pellet injection into plasma devices. While this technique has been previously employed, an increased interest in its applicability has been generated with the recent ASDEX Upgrade experimental data for magnetic high-field side (HFS) pellet injection. In these innovative experiments, the pellet penetration appeared to be significantly deeper than for the standard magnetic low-field side injection scheme, along with corresponding greater fueling efficiencies. Thus, some of the major experimental fusion devices are planning experiments with HFS pellet injection. Because of the complex geometries of experimental fusion devices, installations with multiple curved guide tube sections will be required for HFS pellet injection. To more thoroughly understand and document the capability of curved guide tubes, an experimental study is under way at the Oak Ridge National Laboratory (ORNL). In particular, configurations and pellet parameters applicable for the DIII-D tokamak and the International Thermonuclear Experimental Reactor (ITER) were simulated in laboratory experiments. Initial test results with nominal 2.7- and 10-mm-diam deuterium pellets are presented and discussed.

  6. Pellet Dropper Devices for ELM Control on DIII-D

    SciTech Connect (OSTI)

    Combs, Stephen Kirk [ORNL; Baylor, Larry R [ORNL; Foust, Charles R [ORNL; McGill, James M [ORNL; Caughman, John B [ORNL; Fehling, Dan T [ORNL; Hansink, M. J. [General Atomics, San Diego; Jernigan, Thomas C [ORNL; Rasmussen, David A [ORNL

    2007-01-01T23:59:59.000Z

    On several experimental tokamaks, pellet injection has been found to trigger edge localized modes (ELMs) in H-mode plasmas. This can provide a technique for ELM amelioration by reducing the ELM size with small high-frequency pellets. The key for success appears to be small pellets that penetrate just beyond the separatix, enough to trigger an ELM, but not enough to strongly fuel the plasma. To provide a source of small pellets, a pellet dropper device has been developed at the Oak Ridge National Laboratory and installed on the DIII-D tokamak. The pellet dropper consists of a batch extruder with an exit nozzle to provide a filament of solid deuterium (nominal 1-mm diameter), from which pellets are punched/dropped at rates of up to ?50 Hz and at speeds of <10 m/s. The pellets are propelled directly downward and through a vertical injection port on DIII-D. In this paper, the design and the initial test results are presented, and the installation on DIII-D is described.

  7. Pellet imaging techniques on ASDEX

    SciTech Connect (OSTI)

    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

    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.

  8. Nuclear fuel element

    DOE Patents [OSTI]

    Zocher, Roy W. (Los Alamos, NM)

    1991-01-01T23:59:59.000Z

    A nuclear fuel element and a method of manufacturing the element. The fuel element is comprised of a metal primary container and a fuel pellet which is located inside it and which is often fragmented. The primary container is subjected to elevated pressure and temperature to deform the container such that the container conforms to the fuel pellet, that is, such that the container is in substantial contact with the surface of the pellet. This conformance eliminates clearances which permit rubbing together of fuel pellet fragments and rubbing of fuel pellet fragments against the container, thus reducing the amount of dust inside the fuel container and the amount of dust which may escape in the event of container breach. Also, as a result of the inventive method, fuel pellet fragments tend to adhere to one another to form a coherent non-fragmented mass; this reduces the tendency of a fragment to pierce the container in the event of impact.

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

    SciTech Connect (OSTI)

    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

    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)

  10. Overview of Recent Developments in Pellet Injection for ITER

    SciTech Connect (OSTI)

    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

    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.

  11. Fabrication, inspection, and test plan for the Advanced Test Reactor (ATR) Mixed-Oxide (MOX) fuel irradiation project

    SciTech Connect (OSTI)

    Wachs, G.W.

    1997-11-01T23:59:59.000Z

    The Department of Energy (DOE) Fissile Materials Disposition Materials Disposition Program (FMDP) has announced that reactor irradiation of MOX fuel is one of the preferred alternatives for disposal of surplus weapons-usable plutonium (Pu). MOX fuel has been utilized domestically in test reactors and on an experimental basis in a number of Commercial Light Water Reactors (CLWRs). Most of this experience has been with Pu derived from spent low enriched uranium (LEU) fuel, known as reactor grade (RG) Pu. The MOX fuel test will be irradiated in the ATR to provide preliminary data to demonstrate that the unique properties of surplus weapons-derived or weapons-grade (WG) plutonium (Pu) do not compromise the applicability of this MOX experience base. In addition, the test will contribute experience with irradiation of gallium-containing fuel to the data base required for resolution of generic CLWR fuel design issues (ORNL/MD/LTR-76). This Fabrication, Inspection, and Test Plan (FITP) is a level 2 document as defined in the FMDP LWR MOX Fuel Irradiation Test Project Plan (ORNL/MD/LTR-78).

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

    SciTech Connect (OSTI)

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

    2009-04-30T23:59:59.000Z

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

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

    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 DataDepartment of Energy Your Density Isn't YourTransport(FactDepartment of EnergyIndustry15Among States in theWAPA1

  14. 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 DataDepartment of Energy Your Density Isn't YourTransport in RepresentativeDepartment of Energy 1.DepartmentofDEPARTMENT2Energy

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

    SciTech Connect (OSTI)

    G. A. Moore; M. C. Marshall

    2010-01-01T23:59:59.000Z

    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-µm-thick zirconium barrier layer on each face of the ~0.3-mm-thick U10Mo fuel foil.

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

    SciTech Connect (OSTI)

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

    2009-05-18T23:59:59.000Z

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

  17. Technique for controlling shrinkage distortion in cold-pressed annular pellets

    DOE Patents [OSTI]

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

    1982-06-28T23:59:59.000Z

    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.

  18. Microwave drying of ferric oxide pellets

    SciTech Connect (OSTI)

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

    1997-12-31T23:59:59.000Z

    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.

  19. Standard specification for sintered (Uranium-Plutonium) dioxide pellets

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2001-01-01T23:59:59.000Z

    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...

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

    SciTech Connect (OSTI)

    Myott, C.F.

    1994-01-24T23:59:59.000Z

    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.

  1. /sup 238/Pu fuel-form processes. Quarterly report, October-December 1981

    SciTech Connect (OSTI)

    Not Available

    1982-05-01T23:59:59.000Z

    Progress in the Savannah River /sup 238/Pu Fuel Form Program is summarized. Work during this period concentrated on the extensive cracking of the /sup 238/PuO/sub 2/ fuel form prior to encapsulation in the iridium containment shell for heat sources. This cracking results in increased recycle cost and decreased production efficiency. To better understand this cracking, Savannah River Laboratory (SRL) has made an extensive review of the development of /sup 238/PuO/sub 2/ fuel forms from small-scale Multi-hundred Watt (MHW) pellets through the current GPHS full-scale pellet production. Historically, /sup 238/PuO/sub 2/ fuel has almost always been uncracked after hot pressing in a graphite die, but has emerged cracked and fragile from the final heat-treatment furnace. The cracking tendency depends on the microstructure of the fuel form and on the hot pressing conditions used to fabricate it. In general, a microstructure of large intershard porosity is more desirable because it allows internal gas to escape more readily and it can absorb more reoxidation strain. Studies of the GPHS microstructure showed that the internal structures of typical GPHS Pellets fabricated at LANL and in the PEF differed significantly. The LANL pellets had severe density gradients and were extensively cracked.

  2. Development of advanced mixed oxide fuels for plutonium management

    SciTech Connect (OSTI)

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

    1997-06-01T23:59:59.000Z

    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.

  3. QUALITY OF WOOD PELLETS PRODUCED IN BRITISH COLUMBIA FOR EXPORT

    SciTech Connect (OSTI)

    Tumuluru, J.S. [Idaho National Laboratory (INL); Sokhansanj, Shahabaddine [ORNL; Lim, C. Jim [University of British Columbia, Vancouver; Bi, X.T. [University of British Columbia, Vancouver; Lau, A.K. [University of British Columbia, Vancouver; Melin, Staffan [University of British Columbia, Vancouver; Oveisi, E. [University of British Columbia, Vancouver; Sowlati, T. [University of British Columbia, Vancouver

    2010-11-01T23:59:59.000Z

    Wood pellet production and its use for heat and power production are increasing worldwide. The quality of export pellets has to consistently meet certain specifications as stipulated by the larger buyers, such as power utilities or as specified by the standards used for the non-industrial bag market. No specific data is available regarding the quality of export pellets to Europe. To develop a set of baseline data, wood pellets were sampled at an export terminal in Vancouver, British Columbia, Canada. The sampling period was 18 months in 2007-2008 when pellets were transferred from storage bins to the ocean vessels. The sampling frequency was once every 1.5 to 2 months for a total of 9 loading/shipping events. The physical properties of the wood pellets measured were moisture content in the range of 3.5% to 6.5%, bulk density from 728 to 808 kg/m3, durability from 97% to 99%, fines content from 0.03% to 0.87%, calorific value as is from 17 to almost 18 MJ/kg, and ash content from 0.26% to 0.93%.The diameter and length were in the range of 6.4 to 6.5 mm and 14.0 to 19.0 mm, respectively. All of these values met the published non-industrial European grades (CEN) and the grades specified by the Pellet Fuel Institute for the United States for the bag market. The measured values for wood pellet properties were consistent except the ash content values decreased over the test period.

  4. Quality of Wood Pellets Produced in British Columbia for Export

    SciTech Connect (OSTI)

    J. S. Tumuluru; S. Sokhansanj; C. J. Lim; T. Bi; A. Lau; S. Melin; T. Sowlati; E. Oveisi

    2010-11-01T23:59:59.000Z

    Wood pellet production and its use for heat and power production are increasing worldwide. The quality of export pellets has to consistently meet certain specifications as stipulated by the larger buyers, such as power utilities or as specified by the standards used for the non-industrial bag market. No specific data is available regarding the quality of export pellets to Europe. To develop a set of baseline data, wood pellets were sampled at an export terminal in Vancouver, British Columbia, Canada. The sampling period was 18 months in 2007-2008 when pellets were transferred from storage bins to the ocean vessels. The sampling frequency was once every 1.5 to 2 months for a total of 9 loading/shipping events. The physical properties of the wood pellets measured were moisture content in the range of 3.5% to 6.5%, bulk density from 728 to 808 kg/m3, durability from 97% to 99%, fines content from 0.03% to 0.87%, calorific value as is from 17 to almost 18 MJ/kg, and ash content from 0.26% to 0.93%.The diameter and length were in the range of 6.4 to 6.5 mm and 14.0 to 19.0 mm, respectively. All of these values met the published non-industrial European grades (CEN) and the grades specified by the Pellet Fuel Institute for the United States for the bag market. The measured values for wood pellet properties were consistent except the ash content values decreased over the test period.

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

    SciTech Connect (OSTI)

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

    2011-02-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    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

    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.

  7. Method of fabricating a monolithic core for a solid oxide fuel cell

    DOE Patents [OSTI]

    Zwick, Stanley A. (Woodridge, IL); Ackerman, John P. (Downers Grove, IL)

    1985-01-01T23:59:59.000Z

    A method is disclosed for forming a core for use in a solid oxide fuel cell that electrochemically combines fuel and oxidant for generating galvanic output. The core has an array of electrolyte and interconnect walls that are substantially devoid of any composite inert materials for support consisting instead only of the active anode, cathode, electrolyte and interconnect materials. Each electrolyte wall consists of cathode and anode materials sandwiching electrolyte material therebetween, and each interconnect wall consists of the cathode and anode materials sandwiching interconnect material therebetween. The electrolyte and interconnect walls define a plurality of substantially parallel core passageways alternately having respectively the inside faces thereof with only the anode material or with only the cathode material exposed. In the wall structure, the electrolyte and interconnect materials are only 0.002-0.01 cm thick; and the cathode and anode materials are only 0.002-0.05 cm thick. The method consists of building up the electrolyte and interconnect walls by depositing each material on individually and endwise of the wall itself, where each material deposit is sequentially applied for one cycle; and where the depositing cycle is repeated many times until the material buildup is sufficient to formulate the core. The core is heat cured to become dimensionally and structurally stable.

  8. Method of Fabrication of High Power Density Solid Oxide Fuel Cells

    DOE Patents [OSTI]

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

    2008-09-09T23:59:59.000Z

    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.

  9. Comment on Li pellet conditioning in tokamak fusion test reactor

    SciTech Connect (OSTI)

    Budny, R. V. [Princeton Plasma Physics Laboratory, Princeton, New Jersey 08543 (United States)

    2011-09-15T23:59:59.000Z

    Li pellet conditioning in TFTR results in a reduction of the edge electron density which allows increased neutral beam penetration, central heating, and fueling. Consequently, the temperature profiles became more peaked with higher central T{sub i}, T{sub e}, toroidal rotation, and neutron emission rates.

  10. 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...

  11. Initial deuterium pellet experiments on FTU

    SciTech Connect (OSTI)

    Snipes, J.A.

    1993-01-01T23:59:59.000Z

    Initial experiments have been performed with the Single Pellet INjector (SPIN) on FTU. SPIN is a two-stage cryogenic deuterium pellet injector capable of injection,a pellets with velocities up to 2.5 km/s. The nominal pellet mass for these experiments was approximately 1 [times] 10[sup 20] atoms. These initial pellet experiments concentrated on studying pellet penetration under a variety of plasma conditions to compare with code predictions and to examine toroidal particle transport. The principal diagnostics used were two fast ([approximately]1 [mu]sec) photomultiplier tubes at nearly opposite toroidal locations with H[sub [alpha

  12. Carbonation as a binding mechanism for coal/calcium hydroxide pellets. Technical report, December 1, 1992--February 28, 1993

    SciTech Connect (OSTI)

    Rapp, D.; Lytle, J.; Hackley, K.; Dagamac, M. [Illinois State Geological Survey, Champaign, IL (United States); Berger, R. [Illinois Univ., Urbana, IL (United States); Schanche, G. [Army Construction Engineering Research Lab., Champaign, IL (United States)

    1993-05-01T23:59:59.000Z

    Pelletization of fine coal with calcium hydroxide, a sulfur capturing sorbent, represents a method to produce a fuel which will burn in compliance with the recently passed Clean Air Act Amendments (CAAA`s). To harden the pellets, the reaction of carbon dioxide with calcium hydroxide, referred to as carbonation, is being studied. Carbonation forms a bonding matrix of calcium carbonate. This is a two-year research program. This report covers the second quarter of the second year. Research is indicating that 5 to 10 wt% calcium hydroxide pellets can be produced via a roller-and-die pellet mill and air cured to achieve sufficient quality for handling and transportation. This quarter, 1/2 inch-diameter pellets containing 10% calcium hydroxide were demonstrated to gradually react with atmospheric carbon dioxide (3 days) while air drying to achieve compressive strengths equivalent to those attained for fully dried pellets which had been carbonated for one-hour with 100% commercial grade carbon dioxide. It was also demonstrated that an organic, adhesive binder, corn starch, can be very effective at producing strong pellets but drying is required before appreciable pellet strength is attained. For pellets containing 2 wt% corn starch, it was determined that less than 50% of the ultimate strength was achieved as the pellets were dried from 20 wt% to 5 wt% moisture. Strength improved considerably as the pellet moisture content was reduced below 5 wt%.

  13. Method for making spherical binderless pellets

    DOE Patents [OSTI]

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

    1983-01-01T23:59:59.000Z

    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.

  14. New ORNL Pellet Injection System and Installation/Initial Operations on MST

    SciTech Connect (OSTI)

    Combs, S.K. [Oak Ridge National Laboratory (United States); Baylor, L.R. [Oak Ridge National Laboratory (United States); Fehling, D.T. [Oak Ridge National Laboratory (United States); Fisher, P.W. [Oak Ridge National Laboratory (United States); Foust, C.R. [Oak Ridge National Laboratory (United States); Rasmussen, D.A. [Oak Ridge National Laboratory (United States); Wilgen, J.B. [Oak Ridge National Laboratory (United States); Chapman, B.E. [University of Wisconsin-Madison (United States); Oliva, S.P. [University of Wisconsin-Madison (United States); Prager, S.C. [University of Wisconsin-Madison (United States); Sarff, J.S. [University of Wisconsin-Madison (United States); Wyman, M.D. [University of Wisconsin-Madison (United States); Brower, D.L. [University of California-Los Angeles (United States); Ding, W.X. [University of California-Los Angeles (United States); Terry, S.D. [University of California-Los Angeles (United States); Deng, B.H. [University of California-Los Angeles (United States)

    2003-09-15T23:59:59.000Z

    A compact pellet injection system that was recently developed at the Oak Ridge National Laboratory has been installed on the Madison Symmetric Torus (MST) at University of Wisconsin and used in initial plasma fueling experiments. The system, referred to as a ''pellet injector in a suitcase,'' is a pipe gun device with a four-barrel capability (presently equipped with two 1.0-mm-bore barrels), and it uses a cryogenic refrigerator for in-situ hydrogen pellet formation (typically, D{sub 2} pellets). This new, portable, stand-alone pellet injection system was developed to provide a flexible means of plasma fueling on a wide variety of magnetic confinement devices, with relatively low costs for installation and operation. The injector has already been used to produce useful results with pellets on MST plasmas, including significant and rapid increases (almost 100%) in the line average density, and effectively depositing fuel in the plasma core (central densities of [approximately equal to] 1.4 x 10{sup 19} m{sup -3}). In this paper, the injection system, its performance, and reliability will be described, and results from some initial MST pellet experiments will be highlighted.

  15. Co-combustion of pellets from Soma lignite and waste dusts of furniture works

    SciTech Connect (OSTI)

    Deveci, N.D.; Yilgin, M.; Pehlivan, D. [Firat University, Elazig (Turkey). Faculty of Engineering

    2008-07-01T23:59:59.000Z

    In this work, volatiles and char combustion behaviors of the fuel pellets prepared from a low quality lignite and the dusts of furniture works and their various blends were investigated in an experimental fixed bed combustion system through which air flowed by natural convection. Combustion data obtained for varied bed temperatures, mass of pellets, and blend compositions has showed that ignition times of the pellets decreased and volatiles combustion rates tended to increase with the burning temperature. It was concluded that some synergy had existed between lignite and lower ratios of furniture work dusts, which was indicated by a prompt effect on the volatiles combustion rates. Char combustion rates of blend pellets have depended predominantly on the amount of lignite in the blend. The amounts of combustion residues of the pellets were considerably higher than those calculated from individual ash contents of the raw materials and related to lignite ratio in the blends.

  16. Technique for measuring D{sub 2} pellet mass loss through a curved guide tube using two microwave cavity detectors

    SciTech Connect (OSTI)

    Combs, S. K.; Caughman, J. B. O.; Wilgen, J. B. [Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831-8071 (United States)

    2006-07-15T23:59:59.000Z

    Two microwave cavity mass detectors have been used to measure the mass loss of deuterium (D{sub 2}) pellets transported through a curved guide tube. The test tube was a mock-up of the pellet injection guide tube for the proposed ITER experiment, which will be used to transport pellets, including deuterium-tritium (D-T), from the pellet acceleration device to the inner wall (or magnetic high-field side) of the large tokamak for pellet injection and core fueling of plasmas. An accurate estimate of the mass loss is particularly important for D-T injection, because the inventory of the radioactive isotope (T) for ITER is limited and accountability and recycling will be crucial issues. In the laboratory, frozen cylindrical D{sub 2} pellets of nominal 5.3-mm diameter were shot through the stainless steel test tube ({approx_equal}10 m in length and 10-mm inside diameter), with each end equipped with a microwave cavity. As the pellet passes through each tuned microwave cavity, the peak output signal from the electronics is directly proportional to the pellet mass. An absolute calibration of the cavities, which can be problematic, is not needed for the nondestructive technique described here. Instead, a cross calibration of the two cavities with pellets of varying masses provides the relationship to determine mass loss more precisely than any other technique previously reported. In addition, the individual output signals from the cavities can be used to identify intact pellets (a single signal peak) or broken pellets (multiple signal peaks). For the pellet speed range tested in this study (100-500 m/s), the mass loss for intact pellets was directly dependent on the pellet speed, with {approx_equal}10% mass loss at 300 m/s. The microwave cavities and the associated electronics, as well as some basic theory, are described; calibration and experimental data are presented and discussed.

  17. New extruder-based deuterium feed system for centrifuge pellet injection

    SciTech Connect (OSTI)

    Combs, S.K.; Foust, C.R. [Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831-8071 (United States)] [Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831-8071 (United States)

    1997-12-01T23:59:59.000Z

    The pellet injection systems for the next-generation fusion devices (such as the International Thermonuclear Experimental Reactor) and future fusion reactors will have to provide deuterium-tritium fueling for much longer pulse lengths (up to {approx}1000s) than present applications (typically limited to less than several seconds). Thus, a prototype pellet feed system for centrifuge pellet injection has been developed and used in long-pulse ({gt}100s) tests at the Oak Ridge National Laboratory (ORNL). The new apparatus has two key components: (1) a cryogenic deuterium extruder and (2) an electromagnetic pellet punch mechanism. For maximum testing flexibility, the prototype is equipped with several other active components that allow remote adjustments, including precise positioning of the punch and the capability to index through eight different pellet lengths. The new feed system was designed to mate with an existing centrifuge accelerator facility at ORNL, and experiments in the facility were carried out to document the performance and reliability of the new feed system. With 2.3-mm-diam deuterium pellets and a catenary-shaped accelerator ({approx}1.2mdiam), the prototype feed system was found to be capable of placing up to {approx}90{percent} of the punched pellets in the proper time/space window for pickup and acceleration by the high-speed rotating ({approx}50Hz) arbor. For these operating parameters, the pellet nominal speed was {approx}430m/s, and maximum pellet feed rates of 10 pellets/s and greater were tested. In this article the equipment is briefly described, and the experimental test results are summarized. Also, issues affecting overall pellet delivery efficiency are discussed. {copyright} {ital 1997 American Institute of Physics.}

  18. Wood and Pellet Heating Basics | Department of Energy

    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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33Frequently20,000 Russian Nuclear Warheads|ofEvents »SSL BasicsKawtarSue CangeWendeWood and Pellet

  19. Lightning arrestor connector lead magnesium niobate qualification pellet test procedures.

    SciTech Connect (OSTI)

    Tuohig, W. (Honeywell FM& T, Kansas City, MO); Mahoney, Patrick A.; Tuttle, Bruce Andrew; Wheeler, Jill Susanne

    2009-02-01T23:59:59.000Z

    Enhanced knowledge preservation for DOE DP technical component activities has recently received much attention. As part of this recent knowledge preservation effort, improved documentation of the sample preparation and electrical testing procedures for lead magnesium niobate--lead titanate (PMN/PT) qualification pellets was completed. The qualification pellets are fabricated from the same parent powders used to produce PMN/PT lightning arrestor connector (LAC) granules at HWF&T. In our report, the procedures for fired pellet surface preparation, electrode deposition, electrical testing and data recording are described. The dielectric measurements described in our report are an information only test. Technical reasons for selecting the electrode material, electrode size and geometry are presented. The electrical testing is based on measuring the dielectric constant and dissipation factor of the pellet during cooling from 280 C to 220 C. The most important data are the temperature for which the peak dielectric constant occurs (Curie Point temperature) and the peak dielectric constant magnitude. We determined that the peak dielectric constant for our procedure would be that measured at 1 kHz at the Curie Point. Both the peak dielectric constant and the Curie point parameters provide semi-quantitative information concerning the chemical and microstructural homogeneity of the parent material used for the production of PMN/PT granules for LACs. Finally, we have proposed flag limits for the dielectric data for the pellets. Specifically, if the temperature of the peak dielectric constant falls outside the range of 250 C {+-} 30 C we propose that a flag limit be imposed that will initiate communication between production agency and design agency personnel. If the peak dielectric constant measured falls outside the range 25,000 {+-} 10,000 we also propose that a flag limit be imposed.

  20. A New Four-Barrel Pellet Injection System for the TJ-II Stellarator

    SciTech Connect (OSTI)

    Combs, Stephen Kirk [ORNL] [ORNL; Foust, Charles R [ORNL] [ORNL; McGill, James M [ORNL] [ORNL; Baylor, Larry R [ORNL] [ORNL; Caughman, John B [ORNL] [ORNL; Fehling, Dan T [ORNL] [ORNL; Harris, Jeffrey H [ORNL] [ORNL; Meitner, Steven J [ORNL] [ORNL; Rasmussen, David A [ORNL] [ORNL; McCarthy, K. J. [EURATOM-CIEMAT, Madrid, Spain] [EURATOM-CIEMAT, Madrid, Spain; Chamorro, M. [Laboratory Nacional de Fusion, Madrid, Spain] [Laboratory Nacional de Fusion, Madrid, Spain; Garcia, R. [Laboratory Nacional de Fusion, Madrid, Spain] [Laboratory Nacional de Fusion, Madrid, Spain; Hildago, C. [Laboratory Nacional de Fusion, Madrid, Spain] [Laboratory Nacional de Fusion, Madrid, Spain; Medrano, M. [Laboratory Nacional de Fusion, Madrid, Spain] [Laboratory Nacional de Fusion, Madrid, Spain; Unamuno, R. [Laboratory Nacional de Fusion, Madrid, Spain] [Laboratory Nacional de Fusion, Madrid, Spain

    2011-01-01T23:59:59.000Z

    A new pellet injection system for the TJ-II stellarator has been developed/constructed as part of a collaboration between the Oak Ridge National Laboratory (ORNL) and the Centro de Investigaciones Energ ticas, Medioambientales y Tecnol gicas (CIEMAT). ORNL is providing most of the injector hardware and instrumentation, the pellet diagnostics, and the pellet transport tubes; CIEMAT is responsible for the injector stand/interface to the stellarator, cryogenic refrigerator, vacuum pumps/ballast volumes, gas manifolds, remote operations, plasma diagnostics, and data acquisition. The pellet injector design is an upgraded version of that used for the ORNL injector installed on the Madison Symmetric Torus (MST). It is a four-barrel system equipped with a cryogenic refrigerator for in situ hydrogen pellet formation and a combined mechanical punch/propellant valve system for pellet acceleration (speeds ~100 to 1000 m/s). On TJ-II, it will be used as an active diagnostic and for fueling. To accommodate the plasma experiments planned for TJ-II, pellet sizes significantly smaller than those typically used for the MST application are required. The system will initially be equipped with four different pellet sizes, with the gun barrel bores ranging between ~0.5 to 1.0 mm. The new system is almost complete and is described briefly here, highlighting the new features added since the original MST injector was constructed. Also, the future installation on TJ-II is reviewed.

  1. Experimental Study of Pellet Delivery to the ITER Inner Wall through a Curved Guide Tube at Steady-State Pressure

    SciTech Connect (OSTI)

    Combs, Stephen Kirk [ORNL; Baylor, Larry R [ORNL; Caughman, John B [ORNL; Fehling, Dan T [ORNL; Foust, Charles R [ORNL; Maruyama, S. [ITER International Team, Garching, Germany; McGill, James M [ORNL; Rasmussen, David A [ORNL

    2006-01-01T23:59:59.000Z

    Injection of solid hydrogen pellets from the magnetic high-field side will be the primary technique for depositing fuel particles into the core of International Thermonuclear Experimental Reactor (ITER) burning plasmas. This injection scheme will require the use of a curved guide tube to route the pellets from the acceleration device, under the divertor, and to the inside wall launch location. In an initial series of pellet tests in support of ITER, single 5.3-mm-diam cylindrical D2 pellets were shot through a mock-up of the planned ITER curved guide tube. Those data showed that the pellet speed had to be limited to ?300 m/s for reliable delivery of intact pellets. Also, microwave cavity mass detectors located upstream and downstream of the test tube indicated that ?10% of the pellet mass was lost in the guide tube at 300 m/s. The tube base pressure for that test series was ?10-4 torr. However, for steady-state pellet fueling on ITER, the guide tube will operate at an elevated pressure due to the pellet erosion in the tube. Assuming the present design values for ITER pellet fueling rates/vacuum pumping and a 10% pellet mass loss during flight in the tube, calculations suggest a steadystate operating pressure in the range of 10-20 torr. Thus, experiments to ascertain the pellet integrity and mass loss under these conditions have been carried out. Also, some limited test data were collected at a tube pressure of ?100 torr. No significant detrimental effects have been observed at the higher tube pressures. The new test results are presented and compared to the baseline data previously reported.

  2. Magnetohydrodynamic effects on pellet injection in tokamaks

    SciTech Connect (OSTI)

    Strauss, H.R. [Courant Institute of Mathematical Sciences, New York University, 251 Mercer Street, New York, New York 10012 (United States)] [Courant Institute of Mathematical Sciences, New York University, 251 Mercer Street, New York, New York 10012 (United States); Park, W. [Princeton Plasma Physics Laboratory, Princeton, New Jersey 08543 (United States)] [Princeton Plasma Physics Laboratory, Princeton, New Jersey 08543 (United States)

    1998-07-01T23:59:59.000Z

    The location at which pellets are injected into a plasma can have a significant effect on what fraction of the pellet mass remains in the plasma for refueling purposes. Magnetohydrodynamic (MHD) simulations presented here, confirm the results of pellet injection experiments: toroidal curvature makes it favorable to inject pellets from the inboard side or from the top or bottom, rather than from the outboard side. Sufficiently large pellets injected at the inboard edge can reach the plasma center, and in the process drive magnetic reconnection to produce negative central shear. Injection at the top (or bottom) of the tokamak causes relatively little displacement of the pellet. A scaling law is obtained for pellet displacement which agrees well with the simulations. The MHD simulations were carried out with a new unstructured mesh finite element version of the MH3D full MHD code. {copyright} {ital 1998 American Institute of Physics.}

  3. Light water reactor mixed-oxide fuel irradiation experiment

    SciTech Connect (OSTI)

    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

    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.

  4. Small-bore (1. 8-mm), high-firing-rate (10-Hz) version of a repeating pneumatic hydrogen pellet injector

    SciTech Connect (OSTI)

    Combs, S.K.; Foust, C.R.; Milora, S.L. (Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831 (United States))

    1995-03-01T23:59:59.000Z

    Repeating pneumatic pellet injectors developed at the Oak Ridge National Laboratory (ORNL) were used for plasma fueling experiments on the Tokamak Fusion Test Reactor (TFTR) and the Joint European Torus (JET). For plasma fueling on the DIII--D tokamak, a small-bore (1.8-mm) injector has been developed and tested in the laboratory at pellet rates of up to 10 Hz and speeds of [le]1 km/s (for pulse lengths of up to 15 s). This performance represents the smallest pellet size and highest repetition rate demonstrated with an ORNL repeating pneumatic pellet injector. The design has been incorporated in the three-barrel injector that was previously used on JET; the injection system, equipped with nominal pellet sizes of 1.8-, 2.7-, and 4.0-mm diameter, has been installed on DIII--D and will be used in future plasma fueling experiments.

  5. U.S. Pellet Industry Analysis

    SciTech Connect (OSTI)

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

    2011-06-01T23:59:59.000Z

    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.

  6. Economic Implications of Pelleting Cotton Gin Trash as an Alternative Energy Source.

    E-Print Network [OSTI]

    Moore, Donald S.; Lacewell, Ronald D.; Parnell, Calvin

    1982-01-01T23:59:59.000Z

    , to produce pelletized gin trash at Lubbock. The wide range in costs results from alternative levels of payment to gins and different heat losses resulting from storage. Thus, pelletized gin trash is not currently competitive with natural gas or coal..., and the total heat content that might be converted from gin trash for commercial use. 2. To describe the production processes involved in converting gin trash to pellets for use as a source of fuel and to estimate the total costs of each of the production...

  7. Carbonation as a binding mechanism for coal/calcium hydroxide pellets

    SciTech Connect (OSTI)

    Rapp, D.M.

    1991-01-01T23:59:59.000Z

    Current coal mining and processing procedures produce a significant quanity of fine coal that is difficult to handle and transport. The objective of this work is to determine if these fines can be economically pelletized with calcium hydroxide, a sulfur capturing sorbent, to produce a clean-burning fuel for fluidized-bed combustors or stoker boilers. To harden these pellets, carbonation, which is the reaction of calcium hydroxide with carbon dioxide to produce a cementitious matrix of calcium carbonate, is being investigated. Previous research indicated that carbonation significantly improved compressive strength, impact and attrition resistance and weatherproofed'' pellets formed with sufficient calcium hydroxide (5 to 10% for minus 28 mesh coal fines).

  8. Speed limit of frozen pellets (H{sub 2}, D{sub 2}, and Ne) through single-loop and multiloop tubes and implications for fusion plasma research

    SciTech Connect (OSTI)

    Combs, S. K.; Griffith, A. E.; Foust, C. R.

    2001-01-01T23:59:59.000Z

    Frozen pellets (H{sub 2}, D{sub 2}, and Ne at 8 K) of nominal 2.7 mm diam were shot through a coiled tube (single loop of {approx}0.6 m diam and 8.5 mm bore), and the speed limit for survival was recorded for each pellet type. Intact H{sub 2} pellets were observed at speeds approaching 500 m/s; but neon pellets could not survive much more than 100 m/s. The speed limit for D{sub 2} pellets fell in the middle at {approx}300 m/s. Some D{sub 2} pellets were also shot through a 30 m coiled tube consisting of 11 loops (average loop diameter of {approx}0.8 m), and a speed limit of {approx}100 m/s was observed. Injection of frozen H{sub 2} or D{sub 2} pellets is commonly used for core fueling of magnetically confined plasmas, and frozen neon pellets are sometimes used for impurity transport studies in similar experiments. The results from these tests add to a pellet database for injection lines with single- and complex multiple-curved guide tubes. All of the information to date suggests that frozen pellets can be delivered reliably from a pellet source to any accessible plasma location on a fusion device via ''roller-coaster'' tubes as long as the pellet speed is maintained below a threshold limit.

  9. Fabrication and characterization of anode-supported single chamber solid oxide fuel cell based on La0.6Sr0.4Co0.2Fe0.8O3--

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    -CGO cathode 1. Introduction Single-chamber solid oxide fuel cells (SC-SOFCs) have received many attentionsFabrication and characterization of anode-supported single chamber solid oxide fuel cell based-supported solid oxide fuel cells consisting of nickel-gadolinium doped ceria (NiO-CGO, 60:40 wt%) anode

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

    E-Print Network [OSTI]

    Naramore, Michael J

    2010-08-03T23:59:59.000Z

    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 it’s performance is limited by its low thermal conductivity. The fuel concept considered here is a...

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

    E-Print Network [OSTI]

    Naramore, Michael J

    2010-08-03T23:59:59.000Z

    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 it’s performance is limited by its low thermal conductivity. The fuel concept considered here is a...

  12. 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

  13. 25 years of pelletizing at CVRD

    SciTech Connect (OSTI)

    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

    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.

  14. Impurity pellet injection experiments at TFTR

    SciTech Connect (OSTI)

    Marmar, E.S.

    1992-01-01T23:59:59.000Z

    Impurity (Li and C) pellet injection experiments on TFTR have produced a number of new and significant results. (1) We observe reproducible improvements of TFTR supershots after wall-conditioning by Li pellet injection ( lithiumization'). (2) We have made accurate measurements of the pitch angle profiles of the internal magnetic field using two novel techniques. The first measures the internal field pitch from the polarization angles of Li[sup +] line emission from the pellet ablation cloud, while the second measures the pitch angle profiles by observing the tilt of the cigar-shaped Li[sup +] emission region of the ablation cloud. (3) Extensive measurements of impurity pellet penetration into plasmas with central temperatures ranging from [approximately]0.3 to [approximately]7 keV have been made and compared with available theoretical models. Other aspects of pellet cloud physics have been investigated. (4) Using pellets as a well defined perturbation has allowed study of transport phenomena. In the case of small pellet perturbations, the characteristics of the background plasmas are probed, while with large pellets, pellet induced effects are clearly observed. These main results are discussed in more detail in this paper.

  15. AFIP-6 Fabrication Summary Report

    SciTech Connect (OSTI)

    Glenn A. Moore; M. Craig Marshall

    2011-09-01T23:59:59.000Z

    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.

  16. AFIP-2 Fabrication Summary Report

    SciTech Connect (OSTI)

    Glenn Moore

    2010-02-01T23:59:59.000Z

    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.

  17. AFIP-4 Fabrication Summary Report

    SciTech Connect (OSTI)

    Glenn A. Moore

    2010-02-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

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

    2012-09-01T23:59:59.000Z

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

  19. Carbonation as a binding mechanism for coal/calcium hydroxide pellets. Technical report, December 1, 1991--February 29, 1992

    SciTech Connect (OSTI)

    Rapp, D.M. Ehrlinger, H.P.; Hackley, K.C.; Lytle, J.M.; Moran, D.L. [Illinois State Geological Survey, Champaign, IL (United States); Berger, R.L. [Univ. Illinois, Champaign, IL (United States). Dept. of Civil Engineering; Schanche, G. [Army Construction Engineering Research Lab., Champaign, IL (United States); Chow, Poo [Univ. Illinois, Champaign, IL (United States). Dept. of Forestry; Strickland, R. [Tennessee Valley Authority, Muscle Shoals, AL (United States)

    1992-09-01T23:59:59.000Z

    In this project supported by the CRSC, the Tennessee Valley Authority (TVA) and the Engineering Research Laboratory (CERL), ISGS is investigating the pelletization of fine coal with calcium hydroxide, a sulfur capturing sorbent. The objective is to produce a readily-transportable fuel which will burn in compliance with the recently passed Clean Air Act Amendments. To improve the economics of pelletization, carbonation, or, the reaction of carbon dioxide with calcium hydroxide to produce a binding matrix of calcium carbonate, is being investigated as a method of hardening pelletized coal fines. Previous results indicate that carbonation significantly improves pellet quality including serving to weatherproof the pellets. During this quarter, work was conducted on several topics. Calcium oxide was investigated as a potentially lower cost binder than calcium hydroxide and was determined to be of comparable effectiveness on a molar basis indicating some potential for an overall cost savings. The effect of pellet size on pellet quality was also investigated. Results indicate that 1/4 and 1/2-inch diameter pellets have similar compressive strengths when compared on the basis of pounds per square inch crushing pressure. Also a low cost starch was tested as an alternative binder. Although cheaper per pound than a starch binder previously tested, it was not less expensive when evaluated on the basis of pellet quality attained.

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

    SciTech Connect (OSTI)

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

    1998-08-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

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

    1980-03-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

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

    1998-08-01T23:59:59.000Z

    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.

  3. Twin-Screw Extruder Development for the ITER Pellet Injection System

    SciTech Connect (OSTI)

    Meitner, Steven J [ORNL; Baylor, Larry R [ORNL; Combs, Stephen Kirk [ORNL; Fehling, Dan T [ORNL; McGill, James M [ORNL; Rasmussen, David A [ORNL; Leachman, J. W. [University of Wisconsin, Madison

    2009-01-01T23:59:59.000Z

    The ITER pellet injection system is comprised of devices to form and accelerate pellets, and will be connected to inner wall guide tubes for fueling, and outer wall guide tubes for ELM pacing. An extruder will provide a stream of solid hydrogen isotopes to a secondary section, where pellets are cut and accelerated with a gas gun into the plasma. The ITER pellet injection system is required to provide a plasma fueling rate of 120 Pa-m3/s (900 mbar-L/s) and durations of up to 3000 s. The fueling pellets will be injected at a rate up to 10 Hz and pellets used to trigger ELMs will be injected at higher rates up to 20 Hz. A twin-screw extruder for the ITER pellet injection system is under development at the Oak Ridge National Laboratory. A one-fifth ITER scale prototype has been built and has demonstrated the production of a continuous solid deuterium extrusion. The 27 mm diameter, intermeshed, counter-rotating extruder screws are rotated at a rate up to ?5 rpm. Deuterium gas is pre-cooled and liquefied and solidified in separate extruder barrels. The precooler consists of a deuterium gas filled copper coil suspended in a separate stainless steel vessel containing liquid nitrogen. The liquefier is comprised of a copper barrel connected to a Cryomech AL330 cryocooler, which has a machined helical groove surrounded by a copper jacket, through which the pre-cooled deuterium condenses. The lower extruder barrel is connected to a Cryomech GB-37 cryocooler to solidify the deuterium (at ?15 K) before it is forced through the extruder die. The die forms the extrusion to a 3 mm x 4 mm rectangular cross section. Design improvements have been made to improve the pre-cooler and liquefier heat exchangers, to limit the loss of extrusion through gaps in the screws. This paper will describe the design improvements for the next iteration of the extruder prototype.

  4. Cryogenic pellet launcher adapted for controlling of tokamak plasma edge instabilities

    SciTech Connect (OSTI)

    Lang, P. T.; Cierpka, P.; Harhausen, J.; Neuhauser, J.; Wittmann, C.; Gal, K.; Kalvin, S.; Kocsis, G.; Sarkoezi, J.; Szepesi, T.; Dorner, C.; Kauke, G. [Max-Planck-Institut fuer Plasmaphysik, EURATOM Association, Boltzmannstrasse 2, 85748 Garching (Germany); KFKI-RMKI, EURATOM Association, P.O. Box 49, H-1525 Budapest-114 (Hungary); Fachhochschule Regensburg, Fachbereich Maschinenbau, Galgenbergstrasse 30, 93053 Regensburg (Germany)

    2007-02-15T23:59:59.000Z

    One of the main challenges posed recently on pellet launcher systems in fusion-oriented plasma physics is the control of the plasma edge region. Strong energy bursts ejected from the plasma due to edge localized modes (ELMs) can form a severe threat for in-vessel components but can be mitigated by sufficiently frequent triggering of the underlying instabilities using hydrogen isotope pellet injection. However, pellet injection systems developed mainly for the task of ELM control, keeping the unwanted pellet fueling minimized, are still missing. Here, we report on a novel system developed under the premise of its suitability for control and mitigation of plasma edge instabilities. The system is based on the blower gun principle and is capable of combining high repetition rates up to 143 Hz with low pellet velocities. Thus, the flexibility of the accessible injection geometry can be maximized and the pellet size kept low. As a result the new system allows for an enhancement in the tokamak operation as well as for more sophisticated experiments investigating the underlying physics of the plasma edge instabilities. This article reports on the design of the new system, its main operational characteristics as determined in extensive test bed runs, and also its first test at the tokamak experiment ASDEX Upgrade.

  5. High Performance Fuel Desing for Next Generation Pressurized Water Reactors

    SciTech Connect (OSTI)

    Mujid S. Kazimi; Pavel Hejzlar

    2006-01-31T23:59:59.000Z

    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.

  6. 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...

  7. An economical and market analysis of Canadian wood pellets.

    SciTech Connect (OSTI)

    Peng, J. [University of British Columbia, Vancouver

    2010-08-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Not Available

    1994-05-01T23:59:59.000Z

    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.

  9. Fuel

    SciTech Connect (OSTI)

    NONE

    1999-10-01T23:59:59.000Z

    Two subjects are covered in this section. They are: (1) Health effects of possible contamination at Paducah Gaseous Diffusion Plant to be studied; and (2) DOE agrees on test of MOX fuel in Canada.

  10. Carbonation as a binding mechanism for coal/calcium hydroxide pellets. Technical report, September 1, 1991--November 30, 1991

    SciTech Connect (OSTI)

    Rapp, D.M.

    1991-12-31T23:59:59.000Z

    Current coal mining and processing procedures produce a significant quanity of fine coal that is difficult to handle and transport. The objective of this work is to determine if these fines can be economically pelletized with calcium hydroxide, a sulfur capturing sorbent, to produce a clean-burning fuel for fluidized-bed combustors or stoker boilers. To harden these pellets, carbonation, which is the reaction of calcium hydroxide with carbon dioxide to produce a cementitious matrix of calcium carbonate, is being investigated. Previous research indicated that carbonation significantly improved compressive strength, impact and attrition resistance and ``weatherproofed`` pellets formed with sufficient calcium hydroxide (5 to 10% for minus 28 mesh coal fines).

  11. Eco 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 onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directedAnnual SiteofEvaluating A Potential MicrohydroDistrictInformationEau ClaireEcoEco Kinetics

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

    E-Print Network [OSTI]

    Mieloszyk, Alexander James

    2012-01-01T23:59:59.000Z

    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 ...

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

    E-Print Network [OSTI]

    by light fuel oil. The annual light oil consumption is approx. 50 tons and the maximum heat demand capacity 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

  14. Binder enhanced refuse derived fuel

    DOE Patents [OSTI]

    Daugherty, Kenneth E. (Lewisville, TX); Venables, Barney J. (Denton, TX); Ohlsson, Oscar O. (Naperville, IL)

    1996-01-01T23:59:59.000Z

    A refuse derived fuel (RDF) pellet having about 11% or more particulate calcium hydroxide which is utilized in a combustionable mixture. The pellets are used in a particulate fuel bring a mixture of 10% or more, on a heat equivalent basis, of the RDF pellet which contains calcium hydroxide as a binder, with 50% or more, on a heat equivalent basis, of a sulphur containing coal. Combustion of the mixture is effective to produce an effluent gas from the combustion zone having a reduced SO.sub.2 and polycyclic aromatic hydrocarbon content of effluent gas from similar combustion materials not containing the calcium hydroxide.

  15. The enhanced ASDEX Upgrade pellet centrifuge launcher

    SciTech Connect (OSTI)

    Plöckl, 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

    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.

  16. Lithium Pellet Injector Development for NSTX

    SciTech Connect (OSTI)

    G. Gettelfinger; J. Dong; R. Gernhardt; H. Kugel; P. Sichta; J. Timberlake

    2003-12-04T23:59:59.000Z

    A pellet injector suitable for the injection of lithium and other low-Z pellets of varying mass into plasmas at precise velocities from 5 to 500 m/s is being developed for use on NSTX (National Spherical Torus Experiment). The ability to inject low-Z impurities will significantly expand NSTX experimental capability for a broad range of diagnostic and operational applications. The architecture employs a pellet-carrying cartridge propelled through a guide tube by deuterium gas. Abrupt deceleration of the cartridge at the end of the guide tube results in the pellet continuing along its intended path, thereby giving controlled reproducible velocities for a variety of pellets materials and a reduced gas load to the torus. The planned injector assembly has four hundred guide tubes contained in a rotating magazine with eight tubes provided for injection into plasmas. A PC-based control system is being developed as well and will be described elsewhere in these Proceedings. The development path and mechanical performance of the injector will be described.

  17. Rough order of magnitude cost estimate for immobilization of 18.2 MT of plutonium sharing existing facilities at Hanford with MOX fuel fabrication facility: alternative 4B/011

    SciTech Connect (OSTI)

    DiSabatino, A., LLNL

    1998-06-01T23:59:59.000Z

    The purpose of this Cost Estimate Report is to identify preliminary capital and operating costs for a facility to immobilize 18.2 metric tons (nominal) of plutonium as a ceramic in an existing facility at Hanford, the Fuels and Materials Examination Facility (FMEF). The MOX Fuel Fabrication Facility (MFFF), which is being costed in a separate report, will also be located in the FMEF in this co-location option.

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

    E-Print Network [OSTI]

    furnish of 150k odt/yr in 2012. 9. Including wood going for the production of pellets, usage of wood in progress 3.3. Wood fuel usage by fuel category 3.4. Pellet plants 3.5. Greenhouse gas emissions 4 to 1.073 million odt in 2014. 8. Four wood pellet manufacturing plants in Scotland used in total some

  19. International Trade of Wood Pellets (Brochure)

    SciTech Connect (OSTI)

    Not Available

    2013-05-01T23:59:59.000Z

    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.

  20. Torrefaction of Pelletized Oil Palm Empty Fruit Bunches

    E-Print Network [OSTI]

    Nyakuma, Bemgba Bevan; Johari, Anwar; Abdullah, Tuan Amran Tuan; Oladokun, Olagoke

    2015-01-01T23:59:59.000Z

    The torrefaction of oil palm Empty Fruit Bunch (EFB) briquettes was examined in this study. The results indicate that temperature significantly influenced the mass yield, energy yield and heating value of oil palm empty fruit bunch (OPEFB) briquettes during torrefaction. The solid uniform compact nature of EFB briquettes ensured a slow rate of pyrolysis or devolatization which enhanced torrefaction. The mass yield decreased from 79.70 % to 43.03 %, energy yield from 89.44 % to 64.27 % during torrefaction from 250 {\\deg}C to 300 {\\deg}C. The heating value (HHV) of OPEFB briquettes improved significantly from 17.57 MJ/kg to 26.24 MJ/kg after torrefaction at 300 {\\deg}C for 1 hour. Fundamentally, the study has highlighted the effects of pelletization and torrefaction on solid fuel properties of oil palm EFB briquettes and its potential as a solid fuel for future thermal applications.

  1. Volume Ignition via Time-like Detonation in Pellet Fusion

    E-Print Network [OSTI]

    Csernai, L P

    2015-01-01T23:59:59.000Z

    Relativistic fluid dynamics and the theory of relativistic detonation fronts are used to estimate the space-time dynamics of the burning of the D-T fuel in Laser driven pellet fusion experiments. The initial "High foot" heating of the fuel makes the compressed target transparent to radiation, and then a rapid ignition pulse can penetrate and heat up the whole target to supercritical temperatures in a short time, so that most of the interior of the target ignites almost simultaneously and instabilities will have no time to develop. In these relativistic, radiation dominated processes both the interior, time-like burning front and the surrounding space-like part of the front will be stable against Rayleigh-Taylor instabilities. To achieve this rapid, volume ignition the pulse heating up the target to supercritical temperature should provide the required energy in less than ~ 10 ps.

  2. 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...

  3. Cryogenic neutron moderator on mesitylene pellets for IBR-2 reactor

    E-Print Network [OSTI]

    Titov, Anatoly

    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

  4. RUMEN DIGESTION PARAMETERS IN LAMBS FED WITH PELLETED DIET

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    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

  5. Updated 2-13-06 Grass Pelleting The Process

    E-Print Network [OSTI]

    Pawlowski, Wojtek

    Updated 2-13-06 Grass Pelleting ­ The Process Bioenergy Information Sheet #7 Department of Crop is to describe the steps involved in pelleting biofuels. Worldwide Perspective Grass biomass is a bulky material. Densification into briquettes, cubes or pellets, however, gives the feedstock more uniform density and physical

  6. 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

  7. Pellet Driven Disruptions in Tokamaks H.R. Strauss

    E-Print Network [OSTI]

    Strauss, Hank

    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

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

    E-Print Network [OSTI]

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

    2010-01-01T23:59:59.000Z

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

  9. 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 onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand Jump to: navigation,Pillar GroupInformation SPPurchasedEngyNrmlYrMwhYrPellets Jump to: navigation,

  10. Novel Accident-Tolerant Fuel Meat and Cladding

    SciTech Connect (OSTI)

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

    2013-09-01T23:59:59.000Z

    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.

  11. Cotton-pellet, Inflammation Correspondence to author:

    E-Print Network [OSTI]

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

    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

  12. Fuel injection

    SciTech Connect (OSTI)

    Iiyoshi, A.; Vogoshi, S.

    1983-12-01T23:59:59.000Z

    The Plasma Physics Laboratory and the Dept. of Electrical Engineering report on three types of pellet injectors which have different applications: injection of a pellet into a magnetic bottle for magnetic confinement; injection of a pellet into a vacuum chamber for an inertial confinement experiment; and injection of a pellet into a magnetic bottle where the pellet is ionized by high-power laser irradiation for target plasma production. The requirements of pellet injectors are summarized in a table. Theoretical studies on pellet ablation in hot plasma and ablated particle diffusion are underway.

  13. Simulations of plasma behavior during pellet injection in ITER

    SciTech Connect (OSTI)

    Klaywittaphat, P., E-mail: thawatchai@siit.tu.ac.th; Onjun, T. [Thammasat University, School of Manufacturing Systems and Mechanical Engineering, Sirindhorn International Institute of Technology (Thailand)

    2012-06-15T23:59:59.000Z

    Plasma behavior during pellet injection in ITER is investigated using a 1.5D BALDUR integrated predictive modeling code. In these simulations, the pellet ablation is described using the neutral gas shielding (NGS) model developed by Parks and Turnbull [Phys. Fluids 21, 1735 (1978)]. The NGS pellet ablation model that includes the {nabla}B drift effect is coupled with a plasma core transport model, which is a combination of an MMM95 anomalous transport model and an NCLASS neoclassical transport model. The combination of core transport models, together with pellet model, is used to simulate the time evolution of plasma current, ion and electron temperatures, and density profiles for ITER standard type-I ELMy H-mode discharges during the pellet injection. It is found that the injection of pellet can result in either enhancement or degradation of plasma performance. The {nabla}B drift effect on the pellet deposition is very strong in ITER. The plasma density with high field side pellets, which favorable with the {nabla}B drift effect, is much higher and pellet can penetrate much deeper than that with low field side pellets.

  14. Tests of Tritium Pellet Injector TPI-1 Under Closed Cycle Mode

    SciTech Connect (OSTI)

    Vedeneev, A.I. [Russian Federal Nuclear Center-All-Russia Scientific Institute of Experimental Physics (Russian Federation); Abramov, I.A. [Russian Federal Nuclear Center-All-Russia Scientific Institute of Experimental Physics (Russian Federation); Lebedev, S.E. [Russian Federal Nuclear Center-All-Russia Scientific Institute of Experimental Physics (Russian Federation); Kazakovsky, N.T. [Russian Federal Nuclear Center-All-Russia Scientific Institute of Experimental Physics (Russian Federation); Pimanikhin, S.A. [Russian Federal Nuclear Center-All-Russia Scientific Institute of Experimental Physics (Russian Federation); Saksagansky, G.L. [Efremov Institute (Russian Federation); Sten'gach, A.V. [Russian Federal Nuclear Center-All-Russia Scientific Institute of Experimental Physics (Russian Federation); Shirnin, P.V. [Russian Federal Nuclear Center-All-Russia Scientific Institute of Experimental Physics (Russian Federation); Viniar, I.V

    2005-07-15T23:59:59.000Z

    First experimental results of a tritium pellet injector steady-state operation is presented. The tritium injector TPI-1 was developed at the PELIN Laboratory and put in operation in Russian Federal Nuclear Center. It is a part of an experimental closed circuit for simulation of ITER fuel cycle. Results of several continuous extrusions of solid rod made of various hydrogen isotopes are presented. Transverse dimensions of an extruded ice rod with rectangular cross-section were {approx} 3 x 4.mm. The greatest extrusion velocity came to 15 mm/s for hydrogen and 9 mm/s for D-T mixture; tritium content in fuel mixture did not exceed 11%; pellet velocity ran up to 500 m/s at repetitive mode. An optimal mode of D-T ice extrusion was determined.

  15. JET multi-pellet injection experiments

    SciTech Connect (OSTI)

    Kupschus, P.; Bartlett, D.V.; Behringer, K.; Campbell, D.J.; Cheetham, A.; Cordey, J.G.; Corti, S.; Gadeberg, M.; Gondhalekar, A.; Gottardi, N.A.; Jarvis, O.N.; Morgan, P.; O'Rourke, J.; Sadler, G.; Snipes, J.; Stubberfield, D.; Taroni, A.; Tubbing, B.; Von Hellermann, M. (JET Joint Undertaking, Abingdon (UK)); Baylor, L.R.; Houlberg, W.A.; Jernigan, T.C.; Milora, S.L. (Oak Ridge National Lab., TN (USA)); Galvao, R.

    1988-01-01T23:59:59.000Z

    The multiple injection of deuterium pellets into JET plasmas under various scenarios for limiter and X-point discharges with currents up to 5 MA with pure ohmic, neutral beam and RF heating has been undertaken in a collaborative effort between JET and an USDOE team under the umbrella of the EURATOM-USDOE (US Department of Energy) Fusion Agreement on Pellet Injection using an ORNL built 3-barrel, repetitive multi-pellet launcher. The best plasma performance with pellet injection and additional heating so far has been obtained by injecting early into 3 MA, 3.1 T pulses while centrally depositing the pellet mass, with N{sub eo} initially well in excess of 10{sup 20} m{sup {minus}3}. Subsequent central heating of this dense and clean core by ion cyclotron resonance heating (ICRH) with H and {sup 3}He minorities in the 10 MW range yields T{sub eo} up to 12 keV and T{sub io} up to more than 10 keV, while n{sub eo} is decreasing (within up to 1.5s) decaying to 0.6 {times} 10{sup 20} m{sup {minus}3}, suggesting an enhanced central energy confinement in limiter discharges with only modestly improved global L-mode confinement. In this plasma core electron pressures of more than 1 bar with gradients in the order of 4 bar*m{sup {minus}1} have been reached with the total pressure approaching ballooning stability limits. The resulting total neutron rate from D-D reactions of up to 4.5*10{sup 15} s{sup {minus}1} so far increases strongly with RF power and can exceed that of similar non-enhanced shots by factors of 3 to 5. n{sub D}(O)*T{sub i}(O)*{tau}{sub E}(a) products in the range of 1 to 2*10{sup 20} m{sup {minus}3} keVs are obtained but combined power with neutral beams (up to 28 MW total), generally degrades the performance though leading to higher neutron rates of up to 7*10{sup 15} s{sup {minus}1}. 10 refs., 8 figs.

  16. 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...

  17. Operating experience with 100% pellet burden on Amanda blast furnace

    SciTech Connect (OSTI)

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

    1993-01-01T23:59:59.000Z

    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.

  18. Microstability analysis of pellet fuelled discharges in MAST

    E-Print Network [OSTI]

    Garzotti, L; Roach, C M; Valovic, M; Dickinson, D; Naylor, G; Romanelli, M; Scannell, R; Szepesi, G

    2014-01-01T23:59:59.000Z

    Reactor grade plasmas are likely to be fuelled by pellet injection. This technique transiently perturbs the profiles, driving the density profile hollow and flattening the edge temperature profile. After the pellet perturbation, the density and temperature profiles relax towards their quasi-steady-state shape. Microinstabilities influence plasma confinement and will play a role in determining the evolution of the profiles in pellet fuelled plasmas. In this paper we present the microstability analysis of pellet fuelled H-mode MAST plasmas. Taking advantage of the unique capabilities of the MAST Thomson scattering system and the possibility of synchronizing the eight lasers with the pellet injection, we were able to measure the evolution of the post-pellet electron density and temperature profiles with high temporal and spatial resolution. These profiles, together with ion temperature profiles measured using a charge exchange diagnostic, were used to produce equilibria suitable for microstability analysis of th...

  19. Study of fueling requirements for the Engineering Test Reactor

    SciTech Connect (OSTI)

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

    1987-10-16T23:59:59.000Z

    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.

  20. Durable zinc ferrite sorbent pellets for hot coal gas desulfurization

    DOE Patents [OSTI]

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

    1988-01-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Haase, S.

    2009-11-01T23:59:59.000Z

    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.

  2. Impurity pellet injection experiments at TFTR. Final performance report

    SciTech Connect (OSTI)

    Marmar, E.S.

    1992-12-01T23:59:59.000Z

    Impurity (Li and C) pellet injection experiments on TFTR have produced a number of new and significant results. (1) We observe reproducible improvements of TFTR supershots after wall-conditioning by Li pellet injection (`lithiumization`). (2) We have made accurate measurements of the pitch angle profiles of the internal magnetic field using two novel techniques. The first measures the internal field pitch from the polarization angles of Li{sup +} line emission from the pellet ablation cloud, while the second measures the pitch angle profiles by observing the tilt of the cigar-shaped Li{sup +} emission region of the ablation cloud. (3) Extensive measurements of impurity pellet penetration into plasmas with central temperatures ranging from {approximately}0.3 to {approximately}7 keV have been made and compared with available theoretical models. Other aspects of pellet cloud physics have been investigated. (4) Using pellets as a well defined perturbation has allowed study of transport phenomena. In the case of small pellet perturbations, the characteristics of the background plasmas are probed, while with large pellets, pellet induced effects are clearly observed. These main results are discussed in more detail in this paper.

  3. 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...

  4. DESIGN/COST STUDY OF AN INDUCTION LINAC FOR HEAVY IONS FOR PELLET-FUSION

    E-Print Network [OSTI]

    Faltens, A.

    2010-01-01T23:59:59.000Z

    LINAC FOR HEAVY IONS FOR PELLET-FUSION* Andris Faltens. EgonContract The physics of the pellet implosion sets strin-deposition in the pellet > 20 MJ/g. Thus, considerable

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

    E-Print Network [OSTI]

    Wagner, Diane

    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

  6. 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...

  7. Pellet-Plasma Interaction Studies at ASDEX Upgrade

    SciTech Connect (OSTI)

    Kocsis, G.; Belonohy, E.; Gal, K.; Kalvin, S.; Veres, G. [KFKI-RMKI, EURATOM Association, P.O.Box 49, H-1525 Budapest-114 (Hungary); Lang, P. T.; Schneider, W. [MPI fuer Plasmaphysik, EURATOM Association, Boltzmannstr. 2, 85748 Garching (Germany)

    2006-01-15T23:59:59.000Z

    Pellet-plasma interaction is investigated both experimentally at ASDEX Upgrade tokamak and theoretically based on the obtained experimental data. For ELM triggering pellets were injected from the high field side at the ASDEX Upgrade tokamak into type-I ELMy H-mode plasma with a frequency much smaller than the natural ELM frequency. Every pellet triggered an ELM. In order to gain information about the triggering mechanism the delay between the time the pellet crossing the separatrix and the ELM onset was investigated by injecting pellets with two different velocities (240m/s, 600m/s). It was found that the delay time is in the order of 100{mu}s and is shorter at higher pellet velocity. Pellets trigger ELMs when only a minor part the mass is ablated in the plasma: about 2 {center_dot} 1018 (vp 240m/s) and 8 {center_dot} 1017 (vp = 600m/s) particles are deposited along the pellet path until the ELM onset is detected.

  8. Fabrication technology for ODS Alloy MA957

    SciTech Connect (OSTI)

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

    2000-03-16T23:59:59.000Z

    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.

  9. 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...

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

    SciTech Connect (OSTI)

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

    1998-08-01T23:59:59.000Z

    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.

  11. ITER Ion Cyclotron Heating and Fueling Systems

    SciTech Connect (OSTI)

    Rasmussen, D.A. [Oak Ridge National Laboratory (United States); Baylor, L.R. [Oak Ridge National Laboratory (United States); Combs, S.K. [Oak Ridge National Laboratory (United States); Fredd, E. [Princeton Plasma Physics Laboratory (United States); Goulding, R.H. [Oak Ridge National Laboratory (United States); Hosea, J. [Princeton Plasma Physics Laboratory (United States); Swain, D.W. [Oak Ridge National Laboratory (United States)

    2005-04-15T23:59:59.000Z

    The ITER burning plasma and advanced operating regimes require robust and reliable heating and current drive and fueling systems. The ITER design documents describe the requirements and reference designs for the ion cyclotron and pellet fueling systems. Development and testing programs are required to optimize, validate and qualify these systems for installation on ITER.The ITER ion cyclotron system offers significant technology challenges. The antenna must operate in a nuclear environment and withstand heat loads and disruption forces beyond present-day designs. It must operate for long pulse lengths and be highly reliable, delivering power to a plasma load with properties that will change throughout the discharge. The ITER ion cyclotron system consists of one eight-strap antenna, eight rf sources (20 MW, 35-65 MHz), associated high-voltage DC power supplies, transmission lines and matching and decoupling components.The ITER fueling system consists of a gas injection system and multiple pellet injectors for edge fueling and deep core fueling. Pellet injection will be the primary ITER fuel delivery system. The fueling requirements will require significant extensions in pellet injector pulse length ({approx}3000 s), throughput (400 torr-L/s,) and reliability. The proposed design is based on a centrifuge accelerator fed by a continuous screw extruder. Inner wall pellet injection with the use of curved guide tubes will be utilized for deep fueling.

  12. 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)

    Timothy A. Hyde

    2012-06-01T23:59:59.000Z

    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.

  13. Pellet injection in the RFP (Reversed Field Pinch)

    SciTech Connect (OSTI)

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

    1988-01-01T23:59:59.000Z

    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.

  14. Consolidated waste forms: glass marbles and ceramic pellets

    SciTech Connect (OSTI)

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

    1982-05-01T23:59:59.000Z

    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.

  15. Fast imaging of intact and shattered cryogenic neon pellets

    SciTech Connect (OSTI)

    Wang, Zhehui, E-mail: zwang@lanl.gov [Los Alamos National Laboratory, Los Alamos, New Mexico 87545 (United States); Combs, S. K.; Baylor, L. R.; Foust, C. R.; Lyttle, M. S.; Meitner, S. J.; Rasmussen, D. A. [Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831 (United States)

    2014-11-15T23:59:59.000Z

    Compact condensed-matter injection technologies are increasingly used in magnetic fusion. One recent application is in disruption mitigation. An imaging system with less-than-100-µm- and sub-µs-resolution is described and used to characterize intact and shattered cryogenic neon pellets. Shattered pellets contain fine particles ranging from tens of µm to about 7 mm. Time-of-flight analyses indicate that pellets could slow down if hitting the wall of the guide tube. Fast high-resolution imaging systems are thus useful to neon and other condensed-matter injector development.

  16. Fabrication, Inspection, and Test Plan for the Advanced Test Reactor (ATR) High-Power Mixed-Oxide (MOX) Fuel Irradiation Project

    SciTech Connect (OSTI)

    Wachs, G. W.

    1998-09-01T23:59:59.000Z

    The Department of Energy (DOE) Fissile Disposition Program (FMDP) has announced that reactor irradiation of Mixed-Oxide (MOX) fuel is one of the preferred alternatives for disposal of surplus weapons-usable plutonium (Pu). MOX fuel has been utilized domestically in test reactors and on an experimental basis in a number of Commercial Light Water Reactors (CLWRs). Most of this experience has been with Pu derived from spent low enriched uranium (LEU) fuel, known as reactor grade (RG) Pu. The High-Power MOX fuel test will be irradiated in the Advanced Test Reactor (ATR) to provide preliminary data to demonstrate that the unique properties of surplus weapons-derived or weapons-grade (WG) plutonium (Pu) do not compromise the applicability of this MOX experience base. The purpose of the high-power experiment, in conjunction with the currently ongoing average-power experiment at the ATR, is to contribute new information concerning the response of WG plutonium under more severe irradiation conditions typical of the peak power locations in commercial reactors. In addition, the high-power test will contribute experience with irradiation of gallium-containing fuel to the database required for resolution of generic CLWR fuel design issues. The distinction between "high-power" and "average-power" relates to the position within the nominal CLWR core. The high-power test project is subject to a number of requirements, as discussed in the Fissile Materials Disposition Program Light Water Reactor Mixed Oxide Fuel Irradiation High-Power Test Project Plan (ORNL/MD/LTR-125).

  17. Persistent Density Perturbations at Rational q Surfaces Following Pellet Injection in the Joint European Torus

    E-Print Network [OSTI]

    Persistent Density Perturbations at Rational q Surfaces Following Pellet Injection in the Joint European Torus

  18. Integrated simulation of ELM Triggered by Pellet Through Energy Absorption and Transport Enhancement

    E-Print Network [OSTI]

    Integrated simulation of ELM Triggered by Pellet Through Energy Absorption and Transport Enhancement

  19. Integrated Simulation of ELM Triggered by Pellet through Energy Absorption and Transport Enhancement

    E-Print Network [OSTI]

    Integrated Simulation of ELM Triggered by Pellet through Energy Absorption and Transport Enhancement

  20. PPPL3173 Preprint: May 1996, UC420, 426 Design and Operation of the Pellet Charge Exchange

    E-Print Network [OSTI]

    PPPL­3173 ­ Preprint: May 1996, UC­420, 426 Design and Operation of the Pellet Charge Exchange­Z impurity pellet injection. When injected into a high temperature plasma, an impurity pellet (e.g. Lithium with the pellet. This ablation cloud provides a dense target with which the alpha particles produced in D­T fusion

  1. The measurement of ultrasound backscattering from cell pellet biophantoms and tumors ex vivo

    E-Print Network [OSTI]

    Illinois at Urbana-Champaign, University of

    The measurement of ultrasound backscattering from cell pellet biophantoms and tumors ex vivo Aiguo from the tumors is 100% volume fraction cell pellets of the same cell lines. Cell pellets and ex vivo and backscatter coefficient (BSC) are estimated. BSC compari- sons are made between cell pellets and tumors

  2. 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

  3. 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

  4. 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

  5. European Pellet Centre | 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 onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directedAnnual SiteofEvaluating A PotentialJumpGerman Aerospace Center (DLR)European Fuel Cell GmbHEuropean

  6. 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...

  7. Lithium pellet injection into high pressure magnetically confined plasmas

    E-Print Network [OSTI]

    Böse, Brock (Brock Darrel)

    2010-01-01T23:59:59.000Z

    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 ...

  8. 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.

  9. Low-Z Shell Pellet Experiments on DIII-D

    SciTech Connect (OSTI)

    Hollmann, E. M.; Yu, J. H. [University of California-San Diego, La Jolla, CA, 92093-0417 (United States); James, A. N.; Parks, P. B.; Evans, T. E.; Humphreys, D. A.; Jackson, G. L.; La Haye, R. J.; Strait, E. J.; West, W. P.; Wu, W. [General Atomics, PO Box 85608, San Diego, CA 92186-5608 (United States); Jernigan, T. C. [Oak Ridge National Laboratory, PO Box 2008, Oak Ridge, TN 37831 (United States)

    2009-09-10T23:59:59.000Z

    Small (o.d. = 1.8 mm, t = 0.37 mm) polystyrene shells filled with either pressurized argon gas or boron powder have been fired into DIII-D plasmas for disruption mitigation experiments. The pellet shells were observed to burn up at rhoapprox =0.5, roughly consistent with ablation rate calculations. Pellet slowing from 350 m/s down to 100 m/s was observed, which is not well-understood at present. Negligible plasma current contraction or MHD onset were seen as a result of the shell burn-up in the plasma edge, consistent with calculations. The pellet payloads were observed to ionize rapidly in the pellet vicinity (<1 cm radius) and rapid (<15 ms) mixing through the plasma core was observed.

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

    SciTech Connect (OSTI)

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

    1998-08-01T23:59:59.000Z

    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.

  11. Metal Matrix Microencapsulated (M3) fuel neutronics performance in PWRs

    SciTech Connect (OSTI)

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

    2012-01-01T23:59:59.000Z

    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.

  12. 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...

  13. 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 onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directed off Energy.gov. Are you sure you wantJoin us for|IdahotheWhat is the FOIA ? What

  14. Duffield Wood 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 onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directedAnnual SiteofEvaluating A Potential MicrohydroDistrict ofDongjin Semichem CoDowOhio:

  15. 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 onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand Jump to:Ezfeedflag JumpID-fTriWildcatAntrim County,Delhi (NCT), India Sector: SolarAppling County

  16. 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 onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand Jump to:Ezfeedflag JumpID-fTriWildcatAntrim County,Delhi (NCT),Arborview Capital Jump to:

  17. Brazilian Pellet Participation | 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 onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directedAnnual Siteof EnergyInnovation in CarbonofBiotinsBoston CollegeBraziland EEREEPAFinance,Brazilian

  18. 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]

    Fletcher, Thomas H.

    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

  19. LMFBR fuel assembly design for HCDA fuel dispersal

    DOE Patents [OSTI]

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

    1984-01-01T23:59:59.000Z

    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.

  20. Biomass gasification for liquid fuel production

    SciTech Connect (OSTI)

    Najser, Jan, E-mail: jan.najser@vsb.cz, E-mail: vaclav.peer@vsb.cz; Peer, Václav, 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

    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.

  1. Valve for fuel pin loading system

    DOE Patents [OSTI]

    Christiansen, David W. (Kennewick, WA)

    1985-01-01T23:59:59.000Z

    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.

  2. Valve for fuel pin loading system

    DOE Patents [OSTI]

    Christiansen, D.W.

    1984-01-01T23:59:59.000Z

    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.

  3. Potential Impact of Interfacial Bonding Efficiency on High-Burnup Spent Nuclear Fuel Vibration Integrity during Normal Transportation

    SciTech Connect (OSTI)

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

    2014-01-01T23:59:59.000Z

    Finite element analysis (FEA) was used to investigate the impacts of interfacial bonding efficiency at pellet pellet and pellet clad interfaces on spent nuclear fuel (SNF) vibration integrity. The FEA simulation results were also validated and benchmarked with reverse 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 on SNF vibration integrity include the moment carrying capacity distribution between pellets and clad and the impact of cohesion 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. The above-noted phenomenon was calibrated and validated by reverse bending fatigue testing using a surrogate rod system.

  4. Repeating pneumatic pipe-gun for plasma fueling

    SciTech Connect (OSTI)

    Viniar, I. [State Technical University, Saint Petersburg 195251 (Russia)] [State Technical University, Saint Petersburg 195251 (Russia); Sudo, S. [National Institute for Fusion Science, Nagoya 464-01 (Japan)] [National Institute for Fusion Science, Nagoya 464-01 (Japan)

    1997-03-01T23:59:59.000Z

    A pellet injector of the repeating pneumatic pipe-gun type has been designed for plasma fueling applications. Its use reduces the time for pellet formation by an {ital in situ} technique from 2 to 3 min to 2{endash}10 s. The basic idea of the proposed approach to pellet formation is to melt prefrozen solid fuel and to admit it through a porous unit into a barrel for refreezing. The injector provides for a continuous injection of an unlimited number of pellets. Over 250 hydrogen and deuterium pellets of 3 mm diameter and 3{endash}10 mm in length were accelerated to 1.2 km/s at a rate of 1 pellet per 10{endash}34 s by manually controlled injector operation. An automatically controlled multishot pellet injector ({gt}10 barrels) is capable of providing a continuous and reliable fueling of large fusion devices such as the large helical device and the International Thermonuclear Experimental Reactor (ITER). {copyright} {ital 1997 American Institute of Physics.}

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

    E-Print Network [OSTI]

    Matthews, Adrian

    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

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

    E-Print Network [OSTI]

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

    2012-12-15T23:59:59.000Z

    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%.

  7. Massive Pellet and Rupture Disk Testing for Disruption Mitigation Applications

    SciTech Connect (OSTI)

    Combs, Stephen Kirk [ORNL] [ORNL; Meitner, Steven J [ORNL] [ORNL; Baylor, Larry R [ORNL] [ORNL; Caughman, John B [ORNL] [ORNL; Commaux, Nicolas JC [ORNL] [ORNL; Fehling, Dan T [ORNL] [ORNL; Foust, Charles R [ORNL] [ORNL; Jernigan, Thomas C [ORNL] [ORNL; McGill, James M [ORNL] [ORNL; Parks, P. B. [General Atomics] [General Atomics; Rasmussen, David A [ORNL] [ORNL

    2009-01-01T23:59:59.000Z

    Injection of massive quantities of noble gases or D2 has proven to be effective at mitigating some of the deleterious effects of disruptions in tokamaks. Two alternative methods that might offer some advantages over the present technique for massive gas injection are shattering massive pellets and employing close-coupled rupture disks. Laboratory testing has been carried out to evaluate their feasibility. For the study of massive pellets, a pipe gun pellet injector cooled with a cryogenic refrigerator was fitted with a relatively large barrel (16.5 mm bore), and D2 and Ne pellets were made and were accelerated to speeds of ~600 and 300 m/s, respectively. Based on the successful proof-of-principle testing with the injector and a special double-impact target to shatter pellets, a similar system has been prepared and installed on DIII-D and should be ready for experiments later this year. To study the applicability of rupture disks for disruption mitigation, a simple test apparatus was assembled in the lab. Commercially available rupture disks of 1 in. nominal diameter were tested at conditions relevant for the application on tokamaks, including tests with Ar and He gases and rupture pressures of ~54 bar. Some technical and practical issues of implementing this technique on a tokamak are discussed.

  8. Coaxial pellets for metallic impurity injection on the large helical device

    SciTech Connect (OSTI)

    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

    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.

  9. Microwave measurement of the mass of frozen hydrogen pellets

    DOE Patents [OSTI]

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

    1990-01-01T23:59:59.000Z

    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.

  10. Organic binders for iron ore pelletization and steelmaking

    SciTech Connect (OSTI)

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

    1995-12-01T23:59:59.000Z

    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.

  11. Wall conditioning experiments on TFTR using impurity pellet injection

    SciTech Connect (OSTI)

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

    1993-11-01T23:59:59.000Z

    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.

  12. Vacuum Predictions and Measurements for an Internal Pellet Target

    E-Print Network [OSTI]

    Lehmann, I; Friden, C J; Norman, G; Ekström, 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

    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.

  13. Vacuum Predictions and Measurements for an Internal Pellet Target

    E-Print Network [OSTI]

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

    2007-01-04T23:59:59.000Z

    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.

  14. Control System for the NSTX Lithium Pellet Injector

    SciTech Connect (OSTI)

    P. Sichta; J. Dong; R. Gernhardt; G. Gettelfinger; H. Kugel

    2003-10-27T23:59:59.000Z

    The Lithium Pellet Injector (LPI) is being developed for the National Spherical Torus Experiment (NSTX). The LPI will inject ''pellets'' of various composition into the plasma in order to study wall conditioning, edge impurity transport, liquid limiter simulations, and other areas of research. The control system for the NSTX LPI has incorporated widely used advanced technologies, such as LabVIEW and PCI bus I/O boards, to create a low-cost control system which is fully integrated into the NSTX computing environment. This paper will present the hardware and software design of the computer control system for the LPI.

  15. Shattered Pellet Disruption Mitigation Technology Development for ITER

    SciTech Connect (OSTI)

    Baylor, Larry R [ORNL; Combs, Stephen Kirk [ORNL; Jernigan, T. C. [Oak Ridge National Laboratory (ORNL); Meitner, Steven J [ORNL; Edgemon, Timothy D [ORNL; Parks, P. B. [General Atomics; Commaux, Nicolas JC [ORNL; Maruyama, S. [ITER International Team, Garching, Germany; Caughman, John B [ORNL; Rasmussen, David A [ORNL

    2010-01-01T23:59:59.000Z

    The mitigation of first wall thermal and mechanical loads and damage from runaway electrons during disruptions are critical for successful long term operation of ITER. Disruption mitigation tools based on shattered pellet injection are being developed at Oak Ridge National Laboratory that can be employed on ITER to provide the necessary mitigation of thermal and mechanical loads from disruptions as well as provide collisional damping to inhibit the formation of runaway electrons . Here we present progress on the development of the technology to provide reliable disruption mitigation with large shattered cryogenic pellets. An example of how this concept can be employed on ITER is discussed.

  16. Effect of Parallel Flows and Toroidicity on Cross-Field Transport of Pellet Ablation Matter in Tokakmak Plasmas

    SciTech Connect (OSTI)

    Parks, P. B. [General Atomics; Baylor, Larry R [ORNL

    2005-01-01T23:59:59.000Z

    The first complete set of time-dependent equations describing the cross-field drift of ionized pellet ablation matter in tokamak plasma caused by polarization in the nonuniform magnetic field has been developed and solved numerically. Important new features impacting the drift dynamics have been identified, including the effect of pressure profile variations in the tokamak plasma, curvature drive by near-sonic field-aligned (parallel) flows, and the rotational transform of the magnetic field lines, and are considered from the viewpoint of the parallel vorticity equation. These new features are necessary to obtain favorable quantitative agreement between theory and experimental fuel deposition profiles for both inner and outer wall launched pellet injection cases on the DIII-D tokamak.

  17. The evolution of pellet size and shape during spheronisation of an extruded microcrystalline cellulose paste

    E-Print Network [OSTI]

    Lau, C. L. S.; Yu, Q.; Lister, V. Y.; Rough, S. L.; Wilson, D. I.; Zhang, M.

    2014-01-17T23:59:59.000Z

    The process by which cylindrical rods of soft solid paste extrudate are converted into round pellets on a spheroniser (Marumeriser™) plate was studied by interrupting spheronisation tests and measuring the size and shape of the pellets. Batches...

  18. Comparing SNePS with Topbraid/Pellet SNeRG Technical Note 42

    E-Print Network [OSTI]

    Shapiro, Stuart C.

    Comparing SNePS with Topbraid/Pellet SNeRG Technical Note 42 Michael Kandefer and Stuart C. Shapiro Editing Tool (Top Quadrant Inc. 2007) using the Pellet OWL DL Reasoner (Clark & Parsia, LLC 2007

  19. EFFECT OF GRINDING AND PELLETING OF HAY ON COPPER METABOLISM IN SHEEP.

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    EFFECT OF GRINDING AND PELLETING OF HAY ON COPPER METABOLISM IN SHEEP. STUDIES WITH RADIOACTIVE was undertaken. The sheep were then given the same lucern hay ground and pelleted (containing 12 mg Cu/kg D

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

    DOE Patents [OSTI]

    Siriwardane, Ranjani V. (Morgantown, WV)

    1997-01-01T23:59:59.000Z

    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.

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

    DOE Patents [OSTI]

    Siriwardane, R.V.

    1997-12-30T23:59:59.000Z

    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.

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

    E-Print Network [OSTI]

    Mitchison, Tim

    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

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

    DOE Patents [OSTI]

    Siriwardane, R.V.

    1999-02-02T23:59:59.000Z

    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.

  4. 2D-Modelling of pellet injection in the poloidal plane: results of numerical tests

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    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

  5. Durable regenerable sorbent pellets for removal of hydrogen sulfide coal gas

    DOE Patents [OSTI]

    Siriwardane, Ranjani V. (Morgantown, WV)

    1999-01-01T23:59:59.000Z

    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.

  6. Fuel-performance-improvement program. Semiannual progress report, October 1980-March 1981. [Sphere-pac and annular-coated-pressurized

    SciTech Connect (OSTI)

    Crouthamel, C E; Freshley, M D

    1981-04-01T23:59:59.000Z

    Progress on the Fuel Performance Improvement Program's fuel test and demonstration irradiations is reported for the period of October 1980-March 1981. The purpose of the program is to test and demonstrate improved light water reactor fuel concepts that are more resistant to failure from pellet-cladding interaction during power increases than standard pellet fuel. This would also offer extended burnup potential and, hence, improved uranium utilization.

  7. A MULTIDIMENSIONAL AND MULTIPHYSICS APPROACH TO NUCLEAR FUEL BEHAVIOR SIMULATION

    SciTech Connect (OSTI)

    R. L. Williamson; J. D. Hales; S. R. Novascone; M. R. Tonks; D. R. Gaston; C. J. Permann; D. Andrs; R. C. Martineau

    2012-04-01T23:59:59.000Z

    Important aspects of fuel rod behavior, for example pellet-clad mechanical interaction (PCMI), fuel fracture, oxide formation, non-axisymmetric cooling, and response to fuel manufacturing defects, are inherently multidimensional in addition to being complicated multiphysics problems. Many current modeling tools are strictly 2D axisymmetric or even 1.5D. This paper outlines the capabilities of a new fuel modeling tool able to analyze either 2D axisymmetric or fully 3D models. These capabilities include temperature-dependent thermal conductivity of fuel; swelling and densification; fuel creep; pellet fracture; fission gas release; cladding creep; irradiation growth; and gap mechanics (contact and gap heat transfer). The need for multiphysics, multidimensional modeling is then demonstrated through a discussion of results for a set of example problems. The first, a 10-pellet rodlet, demonstrates the viability of the solution method employed. This example highlights the effect of our smeared cracking model and also shows the multidimensional nature of discrete fuel pellet modeling. The second example relies on our the multidimensional, multiphysics approach to analyze a missing pellet surface problem. As a final example, we show a lower-length-scale simulation coupled to a continuum-scale simulation.

  8. Standard specification for nuclear-Grade boron carbide pellets

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2007-01-01T23:59:59.000Z

    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.

  9. Method for producing pellets for use in a cryoblasting process

    DOE Patents [OSTI]

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

    1997-01-01T23:59:59.000Z

    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.

  10. Standard Specification for Nuclear Grade Zirconium Oxide Pellets

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2009-01-01T23:59:59.000Z

    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.

  11. 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...

  12. Assessment of Biomass Pelletization Options for Greensburg, Kansas

    SciTech Connect (OSTI)

    Haase, S.

    2010-05-01T23:59:59.000Z

    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.

  13. Multiscale Modeling and Solution Multiplicity in Catalytic Pellet Reactors Kedar Kulkarni,

    E-Print Network [OSTI]

    Linninger, Andreas A.

    Multiscale Modeling and Solution Multiplicity in Catalytic Pellet Reactors Kedar Kulkarni, Jeonghwa phenomena in catalytic pellet reactors are often difficult to analyze because of coupling between heat at the macroscopic level as well as the catalyst pellets at the microscopic level. The resulting approach yields

  14. BPO Inputs to ITER Design Review on Pellet Pacing, RMP and RWM Coils,

    E-Print Network [OSTI]

    BPO Inputs to ITER Design Review on Pellet Pacing, RMP and RWM Coils, and Disruption Mitigation Collaboration Essential Ingredient Contributions to Pellet Pacing USBPO: L. Baylor and P. Parks EU: P. Lang, A the acceptable energy loss from ELMs. Reducing the energy loss to pellet pacing is challenging. DIII

  15. Estimating snowshoe hare population density from pellet plots: a further evaluation

    E-Print Network [OSTI]

    Krebs, Charles J.

    Estimating snowshoe hare population density from pellet plots: a further evaluation Charles J fecal pellets of snowshoe hares (Lepus americanus) once a year in 10 areas in the southwestern Yukon from 1987 to 1996. Pellets in eighty 0.155-m2 quadrats were counted and cleared each June on all areas

  16. PPPL3298, Preprint: May 1998, UC426 Operation of the TFTR Pellet Charge Exchange Diagnostic

    E-Print Network [OSTI]

    PPPL­3298, Preprint: May 1998, UC­426 Operation of the TFTR Pellet Charge Exchange Diagnostic, USA Abstract The Pellet Charge Exchange technique on TFTR has been used primarily to obtain active) in conjunction with impurity pellet injection (Li and B) with the scintillator­ photomultiplier detector system

  17. PPPL-3298, Preprint: May 1998, UC-426 Operation of the TFTR Pellet Charge Exchange Diagnostic

    E-Print Network [OSTI]

    PPPL-3298, Preprint: May 1998, UC-426 Operation of the TFTR Pellet Charge Exchange Diagnostic Abstract The Pellet Charge Exchange technique on TFTR has been used primarily to obtain active charge with impurity pellet injection (Li and B) with the scintillator- photomultiplier detector system operated

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

    E-Print Network [OSTI]

    Mills, L. Scott

    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

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

    E-Print Network [OSTI]

    Budny, Robert

    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

  20. 4June2013 Page 1 of 8 Sodium Hydroxide (Pellets) SOP Standard Operating Procedures

    E-Print Network [OSTI]

    Cohen, Ronald C.

    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

  1. 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

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

    E-Print Network [OSTI]

    Cotty, Peter J.

    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

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

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    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

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

    E-Print Network [OSTI]

    Roy, Sumantra Dutta

    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

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

    E-Print Network [OSTI]

    Vlad, Gregorio

    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

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

    E-Print Network [OSTI]

    Richner, Heinz

    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

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

    E-Print Network [OSTI]

    Alvarez, Nadir

    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

  8. 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

  9. Lithium Pellet Injection Experiments on the Alcator C-Mod Tokamak

    E-Print Network [OSTI]

    Garnier, Darren T.

    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

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

    E-Print Network [OSTI]

    Strauss, Hank

    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

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

    E-Print Network [OSTI]

    Vincent, Warwick F.

    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

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

    E-Print Network [OSTI]

    Illinois at Urbana-Champaign, University of

    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

  13. 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

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

    E-Print Network [OSTI]

    Vlad, Gregorio

    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

  15. 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

  16. 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

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

    E-Print Network [OSTI]

    Garnier, Darren T.

    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

  18. 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

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

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    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

  20. 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

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

    E-Print Network [OSTI]

    Li, Zhaohui

    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

  2. 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

  3. Volume measurement of cryogenic deuterium pellets by Bayesian analysis of single shadowgraphy images

    SciTech Connect (OSTI)

    Szepesi, T.; Kalvin, S.; Kocsis, G. [KFKI Research Institute for Particle and Nuclear Physics, EURATOM Association, P.O. Box 49, H-1525 Budapest-114 (Hungary); Lang, P. T.; Wittmann, C. [Max-Planck-Institut fuer Plasmaphysik, EURATOM Association, Boltzmannstr. 2, 85748 Garching (Germany)

    2008-03-15T23:59:59.000Z

    In situ commissioning of the Blower-gun injector for launching cryogenic deuterium pellets at ASDEX Upgrade tokamak was performed. This injector is designed for high repetitive launch of small pellets for edge localised modes pacing experiments. During the investigation the final injection geometry was simulated with pellets passing to the torus through a 5.5 m long guiding tube. For investigation of pellet quality at launch and after tube passage laser flash camera shadowgraphy diagnostic units before and after the tube were installed. As indicator of pellet quality we adopted the pellet mass represented by the volume of the main remaining pellet fragment. Since only two-dimensional (2D) shadow images were obtained, a reconstruction of the full three-dimensional pellet body had to be performed. For this the image was first converted into a 1-bit version prescribing an exact 2D contour. From this contour the expected value of the volume was calculated by Bayesian analysis taking into account the likely cylindrical shape of the pellet. Under appropriate injection conditions sound pellets with more than half of their nominal mass are detected after acceleration; the passage causes in average an additional loss of about 40% to the launched mass. Analyzing pellets arriving at tube exit allowed for deriving the injector's optimized operational conditions. For these more than 90% of the pellets were arriving with sound quality when operating in the frequency range 5-50 Hz.

  4. Bonded polyimide fuel cell package

    DOE Patents [OSTI]

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

    2010-06-08T23:59:59.000Z

    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.

  5. In-Home Performance of Exempt Pellet Stoves in Medford, Oregon.

    SciTech Connect (OSTI)

    Barnett, Stockton G.; Fields, Paula G.

    1991-07-05T23:59:59.000Z

    Pellet stoves that are considered exempt'' operate at an air-to-fuel ratio in excess of 35:1. They therefore qualify for exemption from the emissions certification process. A primary goal of this project was to determine how a sample of such stoves, operated in homes, would perform compared to their certified cousins,'' which were evaluated the previous year. In-home performance data documenting emissions from exempt stoves and net delivered efficiencies was particularly desired. This project evaluated six pellet stoves representing three major brands in Medford, Oregon. There were three Breckwell model P24FS, one Horizon Eclipse, one Horizon Destiny, and one Earth Stove TP40. The stoves were monitored for four week-long intervals in January and February 1991, for a total of 24 tests. Evaluations were conducted for particulate, CO (carbon monoxide) and PAH (polycyclic aromatic hydrocarbon) emissions and net efficiency. Monitoring was conducted using the AWES (automated woodstove emissions sampler) sampling system. A new data logger, developed for this project, was used to control the AWES and record real time data. 22 refs., 17 figs., 6 tabs.

  6. Covering Walls With Fabrics.

    E-Print Network [OSTI]

    Anonymous,

    1979-01-01T23:59:59.000Z

    TDOC . Z TA24S.7 8873 NO.1227 WALLS with ;FABRICS Texas Agricultural Extension Service . The Texas A&M University System Daniel C. Pfannstiel, Director, College Station, Texas Covering Walls with Fabrics* When tastefully applied, fabrics... it is applied, fabric-covered walls improve the sound-absorbing acoustical properties of a room. Also, fabrics can be used for covering walls of either textured gypsum board or wood paneling. Home decorating magazines are good sources for ideas about fabric...

  7. Pellet fuelling with edge-localised modes controlled by external magnetic perturbations in MAST

    E-Print Network [OSTI]

    Valovic, M; Gurl, C; Kirk, A; Dunai, D; Field, A R; Lupelli, I; Naylor, G; Thornton, A

    2014-01-01T23:59:59.000Z

    The fuelling of plasmas by shallow frozen pellets with simultaneous mitigation of edge localised modes (ELM) by external magnetic perturbation is demonstrated on the MAST tokamak. Post-pellet particle loss is dominated by ELMs and inter-ELM gas fuelling. It is shown that the size of post-pellet ELMs can be controlled by external magnetic perturbations. Post-pellet ELMs remove particles from the large part of pellet deposition zone including the area with positive density gradient. The mechanism explaining this peculiarity of particle loss is suggested.

  8. Performance testing and Bayesian Reliability Analysis of small diameter, high power electric heaters for the simulation of nuclear fuel rod temperatures 

    E-Print Network [OSTI]

    O'Kelly, David Sean

    2000-01-01T23:59:59.000Z

    ), indirect electric heaters to simulate the centerline temperatures of operating nuclear fuel in a pressurized water reactor. The heater was inserted into annular surrogate fuel pellets containing depleted uranium, cerium oxide and trace quantities (10 ppm...

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

    E-Print Network [OSTI]

    RISĂ?-M-2245 A LIGHT-GAS GUN FOR ACCELERATION OF PELLETS OF SOLID D2 A. Nordskov, H. SkovgĂĄrd, 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

  10. Model of U3Si2 Fuel System using BISON Fuel Code

    SciTech Connect (OSTI)

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

    2014-04-01T23:59:59.000Z

    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.

  11. Polymorphous computing fabric

    DOE Patents [OSTI]

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

    2011-01-18T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    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

    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.

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

    E-Print Network [OSTI]

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

    2013-01-01T23:59:59.000Z

    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.

  14. Analysis of D pellet injection experiments in the W7-AS Stellarator

    SciTech Connect (OSTI)

    Lyon, J.F.; Baylor, L.R. [Oak Ridge National Lab., TN (United States). Fusion Energy Div.; Baldzuhn, J.; Fiedler, S.; Hirsch, M.; Kuehner, G.; Weller, A. [EURATOM Association, Garching (Germany). Max-Planck-Inst. fuer Plasmaphysik

    1997-07-01T23:59:59.000Z

    A centrifugal injector was used to inject deuterium pellets (with 3--5 x 10{sup 19} atoms) at approx. equal 600 m/s into current-less, nearly shear-less plasmas in the Wendelstein 7-AS (W7-AS) stellarator. The D pellet was injected horizontally at a location where the non-circular and non-axisymmetric plasma cross section is nearly triangular. Visible-light TV pictures usually showed the pellet as a single ablating mass in the plasma, although the pellet occasionally broke in two or splintered into a cloud of small particles. The density evolution following pellet injection and the effect of pellet injection on energy confinement and fluctuations are discussed.

  15. Contextualizing urban mobile fabrics

    E-Print Network [OSTI]

    Lin, Michael Chia-Liang

    2007-01-01T23:59:59.000Z

    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 ...

  16. Development of a precise size-controllable pellet injector for the detailed studies of ablation phenamena and mechanism

    E-Print Network [OSTI]

    Ichizono, K; Nourgostar, S; Sato, K N; Group, Triam Exp.

    2004-01-01T23:59:59.000Z

    From the viewpoint of performance of nuclear fusion plasmas, pellet injection experiments have been actively carried out in many toroidal devices in the sense of controlling density profile, obtaining high density or improved confinement, and diagnostic purposes. In order to have a common measure of pellet ablation, the regression study has been performed as an international cooperation activity, obtaining "IPAD" (International Pellet Ablation Database) >. However, these are an empirical scaling, and the mechanism of pellet ablation still remains to be studied. According to the code calculations based on a typical pellet ablation model (e. g., so-called the neutral gas shielding model), it is understood that the penetration depth into plasma is always quite sensitive to the pellet size. If the pellet size is too large, the pellet passes through the plasma, and if it is too small, it is trapped at the plasma surface. Also, an effective or suitable range of the pellet size for a certain plasma is generally very...

  17. Impacts of pellets injected from the low-field side on plasma in ITER

    SciTech Connect (OSTI)

    Wisitsorasak, A. [Mahidol University, Faculty of Science (Thailand); Onjun, T. [Thammasat University, School of Manufacturing Systems and Mechanical Engineering, Sirindhorn International Institute of Technology (Thailand)

    2011-01-15T23:59:59.000Z

    Impacts of pellets injected from the low-field side (LFS) on plasma in ITER are investigated using the 1.5D BALDUR integrated predictive modeling code. In these simulations, the pellet ablation is described using the neutral gas shielding (NGS) model. The pellet ablation model is coupled with the plasma core transport model, which is a combination of the MMM95 anomalous transport model and NCLASS neoclassical transport model. The boundary conditions are assumed to be at the top of the pedestal, in which the pedestal parameters are predicted using a pedestal model based on the theoretical-based pedestal width scaling (either magnetic and flow shear stabilization width scaling, or flow shear stabilization width scaling, or normalized poloidal pressure width scaling) and the infinite-n ballooning mode pressure gradient limit. These pedestal models depend sensitively on the density at the top of the pedestal, which can be strongly influenced by the injection of pellets. The combination of the MMM95 and NCLASS models, together with the pedestal and NGS models, is used to simulate the time evolution of the plasma current, ion and electron temperatures, and density profiles for ITER standard type-I ELMy H-mode discharges during the injection of LFS pellets. It is found that the injection of pellets results in a complicated plasma scenario, especially in the outer region of the plasma and the plasma conditions at the boundary in which the pellet has an impact on increasing the plasma edge density, but reducing the plasma edge temperature. The LFS pellet has a stronger impact on the edge as compared to the center. For fusion performance, the pellet can result in either enhancement or degradation, depending sensitively on the pellet parameters; such as the pellet size, pellet velocity, and pellet frequency. For example, when a series of deuterium pellets with a size of 0.5 cm, velocity of 1 km/s, and frequency of 2 Hz are injected into the ITER plasma from the LFS, the plasma performance, evaluated in terms of Q{sub fusion}, can increase to 72% of that before the use of pellets. It is also found that the injection of pellets results in an increase in the ion and electron densities, but does not enhance the central plasma density. On the other hand, it results in the formation of another peak of the plasma density in the outer region near the plasma edge. The formation of the density peak results in the reduction of plasma transports near the edge by decreasing the contributions of ion-temperature-gradient and trapped electron modes, as well as kinetic ballooning modes.

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

    SciTech Connect (OSTI)

    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

    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.

  19. Long-term survival and maturation of spinally grafted human fetal and embryonic stem cellderived neural precursors in implantable tacrolimus pellet- immunosuppressed ALS SOD1-G93A model rat

    E-Print Network [OSTI]

    Goldberg, Danielle S.

    2012-01-01T23:59:59.000Z

    after Tacrolimus releasable pellet implantation. Rats werein implantable tacrolimus pellet-immunosuppressed ALS SOD1-releasing Tacrolimus pellets……………………………. 12 3.2 Tolerability

  20. Fuel cycles for the 80's

    SciTech Connect (OSTI)

    Not Available

    1980-01-01T23:59:59.000Z

    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)

  1. Verification of the BISON fuel performance code

    SciTech Connect (OSTI)

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

    2014-09-01T23:59:59.000Z

    BISON is a modern finite element-based nuclear fuel performance code that has been under development at Idaho National Labo- ratory (USA) since 2009. The code is applicable to both steady and transient fuel behavior and is used to analyze 1D spherical, 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 and other well known fuel performance codes. Results from several assessment cases are reported, with emphasis on fuel centerline temperatures at various stages of fuel life, fission gas release, and clad deformation during pellet clad mechanical interaction (PCMI). BISON comparisons to fuel centerline temperature measurements are very good at beginning of life and reasonable at high burnup. Although limited to date, fission gas release comparisons are very good. Comparisons of rod diameter following significant power ramping are also good and demonstrate BISON’s unique ability to model discrete pellet behavior and accurately predict clad ridging from PCMI.

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

    SciTech Connect (OSTI)

    Moyer, M.W.

    2001-01-11T23:59:59.000Z

    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.

  3. 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

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

    E-Print Network [OSTI]

    Collar, Juan I.

    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

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

    SciTech Connect (OSTI)

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

    2008-12-15T23:59:59.000Z

    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.

  6. Plasma Fueling, Pumping, and Tritium Handling Considerations for FIRE

    SciTech Connect (OSTI)

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

    1999-11-13T23:59:59.000Z

    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.

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

    E-Print Network [OSTI]

    Ma, Lena

    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

  8. Fabricating solid carbon porous electrodes from powders

    DOE Patents [OSTI]

    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

    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.

  9. Fabricating solid carbon porous electrodes from powders

    DOE Patents [OSTI]

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

    1997-06-10T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    LaViers, H.

    1995-06-30T23:59:59.000Z

    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.

  11. First results about hydrogen loading by means of pulsed electrolysis of Y$_{1}$Ba$_{2}$Cu$_{3}$O$_{7}$ pellets

    E-Print Network [OSTI]

    Celani, F; Di Gioacchino, D; Spallone, A; Tripodi, P; Pace, S; Polichetti, M; Marini, P

    1994-01-01T23:59:59.000Z

    First results about hydrogen loading by means of pulsed electrolysis of Y$_{1}$Ba$_{2}$Cu$_{3}$O$_{7}$ pellets

  12. Standard test method for determination of total hydrogen content of uranium oxide powders and pellets by carrier gas extraction

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2000-01-01T23:59:59.000Z

    Standard test method for determination of total hydrogen content of uranium oxide powders and pellets by carrier gas extraction

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

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2009-01-01T23:59:59.000Z

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

  14. IFR fuel cycle

    SciTech Connect (OSTI)

    Battles, J.E.; Miller, W.E. (Argonne National Lab., IL (United States)); Lineberry, M.J.; Phipps, R.D. (Argonne National Lab., Idaho Falls, ID (United States))

    1992-01-01T23:59:59.000Z

    The next major milestone of the IFR program is engineering-scale demonstration of the pyroprocess fuel cycle. The EBR-II Fuel Cycle Facility has just entered a startup phase, which includes completion of facility modifications and installation and cold checkout of process equipment. This paper reviews the development of the electrorefining pyroprocess, the design and construction of the facility for the hot demonstration, the design and fabrication of the equipment, and the schedule and initial plan for its operation.

  15. IFR fuel cycle

    SciTech Connect (OSTI)

    Battles, J.E.; Miller, W.E. [Argonne National Lab., IL (United States); Lineberry, M.J.; Phipps, R.D. [Argonne National Lab., Idaho Falls, ID (United States)

    1992-04-01T23:59:59.000Z

    The next major milestone of the IFR program is engineering-scale demonstration of the pyroprocess fuel cycle. The EBR-II Fuel Cycle Facility has just entered a startup phase, which includes completion of facility modifications and installation and cold checkout of process equipment. This paper reviews the development of the electrorefining pyroprocess, the design and construction of the facility for the hot demonstration, the design and fabrication of the equipment, and the schedule and initial plan for its operation.

  16. Energy Systems Fabrication Laboratory (Fact Sheet)

    SciTech Connect (OSTI)

    Not Available

    2011-10-01T23:59:59.000Z

    This fact sheet describes the purpose, lab specifications, applications scenarios, and information on how to partner with NREL's Energy Systems Fabrication Laboratory at the Energy Systems Integration Facility. The Energy Systems Fabrication Laboratory at NREL's Energy Systems Integration Facility (ESIF) manufactures components for fuel cells and electrochemical cells using a variety of manufacturing techniques. Fabricated components include catalysts, thin-film and gas diffusion electrodes, and membrane electrode assemblies (MEAs). The laboratory supports NREL's fuel cell and electrochemical cell related research. The main focus of the laboratory is to provide support for fuel cell research that is performed in adjacent laboratories. The laboratory enables NREL to manufacture fuel cells in-house using, for example, experimental catalyst developed at NREL. It further enables the creation of MEAs containing artificial defects required for the systematic study of performance and lifetime effects and the evaluation of in-house and externally developed quality control diagnostics for high volume production of fuel cell. Experiments performed in the laboratory focus mainly on the development of alternative fuel cell manufacturing methods.

  17. Requirements for GNEP Transmutation Fuels

    SciTech Connect (OSTI)

    D. C. Crawford; M. K. Meyer; S. L. Hayes

    2007-03-01T23:59:59.000Z

    The purpose of this document is to provide a baseline set of requirements to guide fuel fabrication development and irradiation testing performed as part of the AFCRD Transmutation Fuel Development Program. This document can be considered a supplement to the GNEP TRU Fuel Development and Qualification Plan, and will be revised as necessary to maintain a documented set of fuel testing objectives and requirements consistent with programmatic decisions and advances in technical knowledge.

  18. Controls of Magnetic Islands by Pellet Injection in Tokamaks

    SciTech Connect (OSTI)

    Shaing, K. C. [University of Wisconsin; Houlberg, Wayne A [ORNL; Peng, Yueng Kay Martin [ORNL

    2007-01-01T23:59:59.000Z

    The appearance of magnetic islands in tokamaks degrades plasma confinement. It is therefore important to control or eliminate the growth of the islands to improve the performance of a tokamak. A theory is developed to control magnetic islands using the localized pressure gradient driven bootstrap current by injecting pellets at the O-point of the island to create a peaked plasma pressure profile inside the island. This localized bootstrap current replenishes the missing equilibrium bootstrap current density that causes the island to grow in the first place. It is shown that the effect of the localized bootstrap current tends to reduce or eliminate the original drive for the growth of the island in the island evolution equation. The theory is also valid for the localized bootstrap current created by localized heating, but with much less effectiveness. A possibility of eliminating the island by controlling the equilibrium profiles is also discussed.

  19. Control of magnetic islands by pellet injection in tokamaks

    SciTech Connect (OSTI)

    Shaing, K. C. [University of Wisconsin; Rome, James A [ORNL; Peng, Yueng Kay Martin [ORNL

    2007-01-01T23:59:59.000Z

    The appearance of magnetic islands in tokamaks degrades plasma confinement. It is therefore important to control or eliminate the growth of the islands to improve the performance of a tokamak. A theory is developed to control magnetic islands using the localized pressure gradient driven bootstrap current by injecting pellets at the O-point of the island to create a peaked plasma pressure profile inside the island. This localized bootstrap current replenishes the missing equilibrium bootstrap current density that causes the island to grow in the first place. It is shown that the effect of the localized bootstrap current tends to reduce or eliminate the original drive for the growth of the island in the island evolution equation. The theory is also valid for the localized bootstrap current created by localized heating, but with much less effectiveness. A possibility of eliminating the island by controlling the equilibrium profiles is also discussed. (c) 2007 American Institute of Physics.

  20. Control of magnetic islands by pellet injection in tokamaks

    SciTech Connect (OSTI)

    Shaing, K. C.; Houlberg, W. A.; Peng, M. [Engineering Physics Department, University of Wisconsin, Madison, Wisconsin 53706 (United States); Fusion Energy Division, Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831 (United States)

    2007-07-15T23:59:59.000Z

    The appearance of magnetic islands in tokamaks degrades plasma confinement. It is therefore important to control or eliminate the growth of the islands to improve the performance of a tokamak. A theory is developed to control magnetic islands using the localized pressure gradient driven bootstrap current by injecting pellets at the O-point of the island to create a peaked plasma pressure profile inside the island. This localized bootstrap current replenishes the missing equilibrium bootstrap current density that causes the island to grow in the first place. It is shown that the effect of the localized bootstrap current tends to reduce or eliminate the original drive for the growth of the island in the island evolution equation. The theory is also valid for the localized bootstrap current created by localized heating, but with much less effectiveness. A possibility of eliminating the island by controlling the equilibrium profiles is also discussed.

  1. Development of a precise size-controllable pellet injector for the detailed studies of ablation phenomena and mechanism

    E-Print Network [OSTI]

    Boyer, Edmond

    Development of a precise size-controllable pellet injector for the detailed studies of ablation, pellet injection experiments have been actively carried out in many toroidal devices in the sense. In order to have a common measure of pellet ablation, the regression study has been performed

  2. 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

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

    E-Print Network [OSTI]

    Boyer, Edmond

    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

  4. 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

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

    E-Print Network [OSTI]

    Martin, Jan M.L.

    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

  6. Design and performance of a punch mechanism based pellet injector for alternative injection in the large helical device

    SciTech Connect (OSTI)

    Mishra, J. S. [Graduate University for Advanced Studies, SOKENDAI Toki, 509-5292 (Japan); Sakamoto, R.; Motojima, G.; Matsuyama, A.; Yamada, H. [National Institute for Fusion Science, Toki, 509-5292 (Japan)

    2011-02-15T23:59:59.000Z

    A low speed single barrel pellet injector, using a mechanical punch device has been developed for alternative injection in the large helical device. A pellet is injected by the combined operation of a mechanical punch and a pneumatic propellant system. The pellet shape is cylindrical, 3 mm in diameter and 3 mm in length. Using this technique the speed of the pellet can be controlled flexibly in the range of 100-450 m/s, and a higher speed can be feasible for a higher gas pressure. The injector is equipped with a guide tube selector to direct the pellet to different injection locations. Pellets are exposed to several curved parts with the curvature radii R{sub c}= 0.8 and 0.3 m when they are transferred in guided tubes to the respective injection locations. Pellet speed variation with pressure at different pellet formation temperatures has been observed. Pellet intactness tests through these guide tubes show a variation in the intact speed limit over a range of pellet formation temperatures from 6.5 to 9.8 K. Pellet speed reduction of less than 6% has been observed after the pellet moves through the curved guide tubes.

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

    SciTech Connect (OSTI)

    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

    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)

  8. Strength Loss in MA-MOX Green Pellets from Radiation Damage to Binders

    SciTech Connect (OSTI)

    Paul A. Lessing; W.R. Cannon; Gerald W. Egeland; Larry D. Zuck; James K. Jewell; Douglas W. Akers; Gary S. Groenewold

    2013-06-01T23:59:59.000Z

    The fracture strength of green Minor Actinides (MA)-MOX pellets containing 75 wt.% DUO2, 20 wt. % PuO2, 3 wt. % AmO2 and 2 wt. % NpO2 was studied as a function of storage time, after mixing in the binder and before sintering, to test the effect of radiation damage on binders. Fracture strength degraded continuously over the 10 days of the study for all three binders studied: PEG binder (Carbowax 8000), microcrystalline wax (Mobilcer X) and Styrene-acrylic copolymer (Duramax B1022) but the fracture strength of Duramax B1022 degraded the least. For instance, for several hours after mixing Carbowax 8000 with MA MOX, the fracture strength of a pellet was reasonably high and pellets were easily handled without breaking but the pellets were too weak to handle after 10 days. Strength measured using diametral compression test showed strength degradation was more rapid in pellets containing 1.0 wt. % Carbowax PEG 8000 compared to those containing only 0.2 wt. %, suggesting that irradiation not only left the binder less effective but also reduced the pellet strength. In contrast the strength of pellets containing Duramax B1022 degraded very little over the 10 day period. It was suggested that the styrene portion of the Duramax B1022 copolymer provided the radiation resistance.

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

    SciTech Connect (OSTI)

    Mark Borland; Steve Frank

    2009-06-01T23:59:59.000Z

    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.

  10. Spent Nuclear Fuel project, project management plan

    SciTech Connect (OSTI)

    Fuquay, B.J.

    1995-10-25T23:59:59.000Z

    The Hanford Spent Nuclear Fuel Project has been established to safely store spent nuclear fuel at the Hanford Site. This Project Management Plan sets forth the management basis for the Spent Nuclear Fuel Project. The plan applies to all fabrication and construction projects, operation of the Spent Nuclear Fuel Project facilities, and necessary engineering and management functions within the scope of the project

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

    E-Print Network [OSTI]

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

    1988-01-01T23:59:59.000Z

    and baghouse to remove S02 and particulates from the flue gases. A schematic of the steam-generating equipment and air pollution control devices is shown in Fig. 1. During the ANL/NTSU test burns, Boiler IS was the only boiler being used. The other four... Precipitation Inc., contains 105 cyclones and has part iculate removal efficiencies of 80% and 90% for gas flo[1 rates of 50,000 and 25,000 standard ft 3 /min respectively. After the flue gases exit the multiclone collector, they enter the spray dryer...

  12. Drop Test Results for the Combustion Engineering Model No. ABB-2901 Fuel Pellet Package

    SciTech Connect (OSTI)

    Hafner, R S; Mok, G C; Hagler, L G

    2004-04-23T23:59:59.000Z

    The U.S. Nuclear Regulatory Commission (USNRC) contracted with the Packaging Review Group (PRG) at Lawrence Livermore National Laboratory (LLNL) to conduct a single, 30-ft shallow-angle drop test on the Combustion Engineering ABB-2901 drum-type shipping package. The purpose of the test was to determine if bolted-ring drum closures could fail during shallow-angle drops. The PRG at LLNL planned the test, and Defense Technologies Engineering Division (DTED) personnel from LLNL's Site-300 Test Group executed the plan. The test was conducted in November 2001 using the drop-tower facility at LLNL's Site 300. Two representatives from Westinghouse Electric Company in Columbia, South Carolina (WEC-SC); two USNRC staff members; and three PRG members from LLNL witnessed the preliminary test runs and the final test. The single test clearly demonstrated the vulnerability of the bolted-ring drum closure to shallow-angle drops-the test package's drum closure was easily and totally separated from the drum package. The results of the preliminary test runs and the 30-ft shallow-angle drop test offer valuable qualitative understandings of the shallow-angle impact.

  13. Fabrication options for depleted uranium components in shielded containers

    SciTech Connect (OSTI)

    Derrington, S.B.; Thompson, J.E.; Coates, C.W.

    1994-01-27T23:59:59.000Z

    Depleted uranium (DU) is an attractive material for the gamma-shielding components in containers designed for the storage, transport, and disposal of high-level radioactive wastes or spent nuclear fuel. The size and weight of these components present fabrication challenges. A broad range of technical expertise, capabilities, and facilities for uranium manufacturing and technology development exist at the Department of Energy laboratories and production facilities and within commercial industry. Several cast and wrought processes are available to fabricate the DU components. Integration of the DU fabrication capabilities and physical limitations for handling the DU components into the early design phase will ensure a fabricable product.

  14. Pellet injection into H-mode ITER plasma with the presence of internal transport barriers

    SciTech Connect (OSTI)

    Leekhaphan, P. [Thammasat University, School of Bio-Chemical Engineering and Technology, Sirindhorn International Institute of Technology (Thailand); Onjun, T. [Thammasat University, School of Manufacturing Systems and Mechanical Engineering, Sirindhorn International Institute of Technology (Thailand)

    2011-04-15T23:59:59.000Z

    The impacts of pellet injection into ITER type-1 ELMy H-mode plasma with the presence of internal transport barriers (ITBs) are investigated using self-consistent core-edge simulations of 1.5D BALDUR integrated predictive modeling code. In these simulations, the plasma core transport is predicted using a combination of a semi-empirical Mixed B/gB anomalous transport model, which can self-consistently predict the formation of ITBs, and the NCLASS neoclassical model. For simplicity, it is assumed that toroidal velocity for {omega}{sub E Multiplication-Sign B} calculation is proportional to local ion temperature. In addition, the boundary conditions are predicted using the pedestal temperature model based on magnetic and flow shear stabilization width scaling; while the density of each plasma species, including both hydrogenic and impurity species, at the boundary are assumed to be a large fraction of its line averaged density. For the pellet's behaviors in the hot plasma, the Neutral Gas Shielding (NGS) model by Milora-Foster is used. It was found that the injection of pellet could result in further improvement of fusion performance from that of the formation of ITB. However, the impact of pellet injection is quite complicated. It is also found that the pellets cannot penetrate into a deep core of the plasma. The injection of the pellet results in a formation of density peak in the region close to the plasma edge. The injection of pellet can result in an improved nuclear fusion performance depending on the properties of pellet (i.e., increase up to 5% with a speed of 1 km/s and radius of 2 mm). A sensitivity analysis is carried out to determine the impact of pellet parameters, which are: the pellet radius, the pellet velocity, and the frequency of injection. The increase in the pellet radius and frequency were found to greatly improve the performance and effectiveness of fuelling. However, changing the velocity is observed to exert small impact.

  15. Short-interval multi-laser Thomson scattering measurements of hydrogen pellet ablation in LHD

    SciTech Connect (OSTI)

    Yasuhara, R., E-mail: yasuhara@nifs.ac.jp; Sakamoto, R.; Yamada, I.; Motojima, G.; Hayashi, H. [National Institute for Fusion Science, 322–6 Oroshi-cho, Toki 509–5292 (Japan)

    2014-11-15T23:59:59.000Z

    Thomson scattering forms an important aspect of measuring the electron density and temperature profiles of plasmas. In this study, we demonstrate Thomson scattering measurements obtained over a short interval (<1 ms) by using an event triggering system with a multi-laser configuration. We attempt to use our system to obtain the electron temperature and density profiles before and immediately after pellet injection into the large helical device. The obtained profiles exhibit dramatic changes after pellet injection as per our shot-by-shot measurements. We believe that this measurement technique will contribute towards a better understanding of the physics of the pellet deposition.

  16. Liquid Metal Bond for Improved Heat Transfer in LWR Fuel Rods

    SciTech Connect (OSTI)

    Donald Olander

    2005-08-24T23:59:59.000Z

    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.

  17. Demonstration of ELM pacing by Pellet Injection on DIII-D and Extrapolation to ITER

    SciTech Connect (OSTI)

    Baylor, Larry R [ORNL; Commaux, Nicolas JC [ORNL; Jernigan, Thomas C [ORNL; Parks, P. B. [General Atomics; Evans, T.E. [General Atomics, San Diego; Osborne, T. H. [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; Yu, J.H. [University of California, San Diego

    2010-01-01T23:59:59.000Z

    Demonstration of ELM pacing by pellet injection on DIII-D and extrapolation to ITER<#_ftn1>* L.R. Baylor1, N. Commaux1, T.C. Jernigan1, P.B. Parks2, T.E. Evans2, T.H. Osborne2, E.J. Strait2, M.E. Fenstermacher3, C.J. Lasnier3, R.A. Moyer4, J.H. Yu4 1Oak Ridge National Laboratory, Oak Ridge, TN, USA 2General Atomics, San Diego, CA, USA 3 Lawrence Livermore National Laboratory, Livermore, CA, USA 4University of California San Diego, La Jolla, CA, USA Deuterium pellet injection has been used in experiments on the DIII-D tokamak to investigate the possibility of triggering small rapid edge localized modes (ELMs) in reactor relevant plasma regimes. ELMs have been observed to be triggered from small 1.8 mm pellets injected from all available locations and under all H-mode operating scenarios in DIII-D. Experimental details have shown that the ELMs are triggered before the pellets reach the top of the H-mode pedestal, implying that very small shallow penetrating pellets are sufficient to trigger ELMs. Fast camera images of the pellet entering the plasma from the low field side show a single plasma filament becoming visible near the pellet cloud and striking the outer vessel wall within 200 ms. Additional ejected filaments are then observed to subsequently reach the wall. The plasma stored energy loss from the pellet triggered ELMs is a function of the elapsed time after a previous ELM. Pellet ELM pacing has been proposed as a method to prevent large ELMs that can damage the ITER plasma facing components [1]. A demonstration of pacing of ELMs on DIII-D was made by injecting slow 14 Hz pellets on the low field side in an ITER shape plasma with low natural ELM frequency and a normalized b of 1.8. The non-pellet discharge natural ELM frequency was ~5 Hz with ELM energy losses up to 85 kJ (>10% of total stored energy) while the case with pellets was able to demonstrate >20 Hz ELMs with an average ELM energy loss less than 22 kJ (<3% of the total). The resulting ELM frequency was larger than the pellet frequency indicating both a direct ELM trigger by each pellet and an indirect effect on the overall pedestal stability to ELMs from the multiple pellets. No increase in density or significant decrease in energy confinement with the pellets was observed. The implications of these results for possible pellet ELM pacing on ITER will be discussed. [1] P.T. Lang et al., Nucl. Fusion 44 (2004) 665.

  18. Licensed fuel facility status report

    SciTech Connect (OSTI)

    Joy, D.; Brown, C.

    1993-04-01T23:59:59.000Z

    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.

  19. New polymorphous computing fabric.

    SciTech Connect (OSTI)

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

    2002-01-01T23:59:59.000Z

    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.

  20. 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....

  1. 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]

    Boyer, Edmond

    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

  2. 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]

    Paris-Sud XI, Université de

    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

  3. Assessment of Biomass Pelletization Options for Greensburg, Kansas |

    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 DataDepartment of Energy Your Density Isn't Your Destiny: The FutureComments from Tarasa U.S.LLC |AquionMr.August 4, 2011Assessment

  4. 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...

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

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2006-01-01T23:59:59.000Z

    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...

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

    SciTech Connect (OSTI)

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

    1995-12-01T23:59:59.000Z

    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.

  7. Observation and analysis of pellet material del B drift on MAST

    SciTech Connect (OSTI)

    Garzotti, L. [EURATOM, Culham Sci Ctr, Abingdon, Oxon England; Baylor, Larry R [ORNL; Kochi, F. [Austrian Academy of Sciences, Vienna, Austria; Pegourie, B. [CEA Cadarache, St. Paul lex Durance, France; Valovic, M [EURATOM, Culham Sci Ctr, Abingdon, Oxon England; Axon, K. B. [EURATOM, Culham Sci Ctr, Abingdon, Oxon England; Dowling, J. [EURATOM, Culham Sci Ctr, Abingdon, Oxon England; Guri, C. [EURATOM, Culham Sci Ctr, Abingdon, Oxon England; Maddison, G. P. [EURATOM, Culham Sci Ctr, Abingdon, Oxon England; Nehme, H. [CEA Cadarache, St. Paul lex Durance, France; O'Gorman, T. [EURATOM, Culham Sci Ctr, Abingdon, Oxon England; Patel, A. [EURATOM, Culham Sci Ctr, Abingdon, Oxon England; Price, M. [EURATOM, Culham Sci Ctr, Abingdon, Oxon England; Scannell, R. [EURATOM, Culham Sci Ctr, Abingdon, Oxon England; Walsh, M. [EURATOM, Culham Sci Ctr, Abingdon, Oxon England

    2010-01-01T23:59:59.000Z

    Pellet material deposited in a tokamak plasma experiences a drift towards the low field side of the torus induced by the magnetic field gradient. Plasma fuelling in ITER relies on the beneficial effect of this drift to increase the pellet deposition depth and fuelling efficiency. It is therefore important to analyse this phenomenon in present machines to improve the understanding of the del B induced drift and the accuracy of the predictions for ITER. This paper presents a detailed analysis of pellet material drift in MAST pellet injection experiments based on the unique diagnostic capabilities available on this machine and compares the observations with predictions of state-of-the-art ablation and deposition codes.

  8. 3D Adaptive Mesh Refinement Simulations of Pellet Injection in Tokamaks

    SciTech Connect (OSTI)

    R. Samtaney; S.C. Jardin; P. Colella; D.F. Martin

    2003-10-20T23:59:59.000Z

    We present results of Adaptive Mesh Refinement (AMR) simulations of the pellet injection process, a proven method of refueling tokamaks. AMR is a computationally efficient way to provide the resolution required to simulate realistic pellet sizes relative to device dimensions. The mathematical model comprises of single-fluid MHD equations with source terms in the continuity equation along with a pellet ablation rate model. The numerical method developed is an explicit unsplit upwinding treatment of the 8-wave formulation, coupled with a MAC projection method to enforce the solenoidal property of the magnetic field. The Chombo framework is used for AMR. The role of the E x B drift in mass redistribution during inside and outside pellet injections is emphasized.

  9. Coprolites and fecal pellets in a late carboniferous coal swamp: morphologic and paleoecologic analysis 

    E-Print Network [OSTI]

    Cutlip, Paul G

    1997-01-01T23:59:59.000Z

    Permineralized peats provide an excellent opportunity to study the ecology of the coal swamps of the Upper Carboniferous. In this study, I examine the coprolites and fecal pellet accumulations in pertnineralized peats from ...

  10. Coprolites and fecal pellets in a late carboniferous coal swamp: morphologic and paleoecologic analysis

    E-Print Network [OSTI]

    Cutlip, Paul G

    1997-01-01T23:59:59.000Z

    Permineralized peats provide an excellent opportunity to study the ecology of the coal swamps of the Upper Carboniferous. In this study, I examine the coprolites and fecal pellet accumulations in pertnineralized peats from the Williamson No. 3 mine...

  11. Fossil fuels -- future fuels

    SciTech Connect (OSTI)

    NONE

    1998-03-01T23:59:59.000Z

    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.

  12. 22.351 Systems Analysis of the Nuclear Fuel Cycle, Spring 2003

    E-Print Network [OSTI]

    Kazimi, Mujid S.

    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, ...

  13. Experimental Verification of a Cracked Fuel Mechanical Model

    SciTech Connect (OSTI)

    Williford, R. E.

    1982-12-01T23:59:59.000Z

    This report describes the results of a series of laboratory experiments conducted to independently verify a model that describes the nonlinear mechanical behavior of cracked fuel in pelletized UO{sub 2}/Zircaloy nuclear fuel rods under normal operating conditions. After a brief description of the analytical model, each experiment is discussed in detail. Experiments were conducted to verify the general behavior and numerical values for the three primary independent modelling parameters (effective crack roughness, effective gap roughness, and total crack length), and to verify the model predictions that the effective Young's moduli for cracked fuel systems were substantially less than those for solid UO{sub 2} pellets. In general, the model parameters and predictions were confirmed, and new insight was gained concerning the complexities of cracked fuel mechanics.

  14. Biologically inspired digital fabrication

    E-Print Network [OSTI]

    Han, Sarah (Sarah J.)

    2013-01-01T23:59:59.000Z

    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 ...

  15. Response of South Texas Plains mixed-brush communities to pelleted picloram

    E-Print Network [OSTI]

    Kitchen, Lynn Maurice

    1977-01-01T23:59:59.000Z

    RESPONSE OF SOUTH TEXAS PLAINS MIXED-BRUSH COMMUNITIES TO PELLETED PICLORAM A Thesis by LYNN MAURICE KITCHEN Submitted to the Graduate College of Texas A&M University in partial fulfillment of the requirement for the degree of MASTER... OF SCIENCE December 1977 Major Subject: Range Science RESPONSE OF SOUTH TEXAS PLAINS MIXED-BRUSH COMMUNITIES TO PELLETED PICLORAM A Thesis LYNN MAURICE KITCHEN Approved as to style and content by: (Ch an o ommittee) (Head of Department) (Member...

  16. The kinetics of microbial decomposition in a fecal pellet-seawater system

    E-Print Network [OSTI]

    Kaplan, Warren Allan

    1970-01-01T23:59:59.000Z

    THE KINETICS OF MICROBIAL DECOMPOSITION IN A FECAL PELLET ? SEAWATER SYSTEM A Thesis WARREN ALLAN KAPLAE Submitted to the Graduate College of Texas A&K University in partial fulfillment of the requirement for the degree of MASTER OF SCIENCE... August 1970 Major Subject: Biological Oceanography THE KINETICS OF MICROBIAL DECOMPOSITION IN A FECAL PELLET ? SEAWATER SYSTEM A Thesis by WARREN ALLAN KAPLAN Approved as to sty1e and content by: airman of Committee Head of D a ment Member...

  17. Nuclear Fabrication Consortium

    SciTech Connect (OSTI)

    Levesque, Stephen

    2013-04-05T23:59:59.000Z

    This report summarizes the activities undertaken by EWI while under contract from the Department of Energy (DOE) � 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 : � Identifying and removing impediments to the implementation of new construction and fabrication techniques and approaches for nuclear equipment, including system components and nuclear plants. � 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. � Analyzing and disseminating information about future nuclear fabrication technologies and how they could impact the North American and the International Nuclear Marketplace. � Facilitating dialog and initiate alignment among fabricators, owners, trade associations, and government agencies. � Supporting industry in helping to create a larger qualified nuclear supplier network. � Acting as an unbiased technology resource to evaluate, develop, and demonstrate new manufacturing technologies. � Creating welder and inspector training programs to help enable the necessary workforce for the upcoming construction work. � 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.

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

    SciTech Connect (OSTI)

    Allison E Ray; Amber Hoover; Gary Gresham

    2012-07-01T23:59:59.000Z

    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.

  19. 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 onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directed off Energy.gov. Are you sureReportsofDepartmentSeriesDepartment of Energy Wondering What All

  20. NRW Pellets GmbH | 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 onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directedAnnual SiteofEvaluatingGroup |JilinLu anMicrogreenMoonNASA/Ames

  1. New England Wood Pellet LLC | 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 onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directedAnnual SiteofEvaluatingGroup |JilinLuOpen EnergyNelsoniX LtdNew Energy Opportunities IncNew England

  2. German Pellets GmbH | 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 onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directedAnnual SiteofEvaluating AGeothermal/Exploration < Geothermal Jump to:GeprowindGermanGerman

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

    SciTech Connect (OSTI)

    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

    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)

  4. Lithium pellet injection experiments on the Alcator C-Mod tokamak

    SciTech Connect (OSTI)

    Garnier, D.T.

    1996-06-01T23:59:59.000Z

    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.

  5. Metal hydride fuel storage and method thereof

    DOE Patents [OSTI]

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

    2006-10-17T23:59:59.000Z

    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.

  6. Metal hydride fuel storage and method thereof

    DOE Patents [OSTI]

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

    2009-05-05T23:59:59.000Z

    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.

  7. SNAP and AI Fuel Summary Report

    SciTech Connect (OSTI)

    Lords, R.E.

    1994-08-01T23:59:59.000Z

    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.

  8. Fuel Cells

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

    Fuel Cells Converting chemical energy of hydrogenated fuels into electricity Project Description Invented in 1839, fuels cells powered the Gemini and Apollo space missions, as well...

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

    E-Print Network [OSTI]

    Boyer, Edmond

    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

  10. 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

  11. Tensile Hoop Behavior of Irradiated Zircaloy-4 Nuclear Fuel Cladding

    SciTech Connect (OSTI)

    Jaramillo, Roger A [ORNL; Hendrich, WILLIAM R [ORNL; Packan, Nicolas H [ORNL

    2007-03-01T23:59:59.000Z

    A method for evaluating the room temperature ductility behavior of irradiated Zircaloy-4 nuclear fuel cladding has been developed and applied to evaluate tensile hoop strength of material irradiated to different levels. The test utilizes a polyurethane plug fitted within a tubular cladding specimen. A cylindrical punch is used to compress the plug axially, which generates a radial displacement that acts upon the inner diameter of the specimen. Position sensors track the radial displacement of the specimen outer diameter as the compression proceeds. These measurements coupled with ram force data provide a load-displacement characterization of the cladding response to internal pressurization. The development of this simple, cost-effective, highly reproducible test for evaluating tensile hoop strain as a function of internal pressure for irradiated specimens represents a significant advance in the mechanical characterization of irradiated cladding. In this project, nuclear fuel rod assemblies using Zircaloy-4 cladding and two types of mixed uranium-plutonium oxide (MOX) fuel pellets were irradiated to varying levels of burnup. Fuel pellets were manufactured with and without thermally induced gallium removal (TIGR) processing. Fuel pellets manufactured by both methods were contained in fuel rod assemblies and irradiated to burnup levels of 9, 21, 30, 40, and 50 GWd/MT. These levels of fuel burnup correspond to fast (E > 1 MeV) fluences of 0.27, 0.68, 0.98, 1.4 and 1.7 1021 neutrons/cm2, respectively. Following irradiation, fuel rod assemblies were disassembled; fuel pellets were removed from the cladding; and the inner diameter of cladding was cleaned to remove residue materials. Tensile hoop strength of this cladding material was tested using the newly developed method. Unirradiated Zircaloy-4 cladding was also tested. With the goal of determining the effect of the two fuel types and different neutron fluences on clad ductility, tensile hoop strength tests were performed on cladding for these varying conditions. Experimental data revealed negligible performance differences for cladding containing TIGR vs non-TIGR processed fuel pellets. Irradiation hardening was observed in tensile hoop data as the strength of the cladding increased with increasing neutron dose and appeared to saturate for a fast fluence of 1.7 1021 neutrons/cm2.

  12. Natural Fueling of a Tokamak Fusion Reactor

    E-Print Network [OSTI]

    Wan, Weigang; Chen, Yang; Perkins, Francis W

    2009-01-01T23:59:59.000Z

    A natural fueling mechanism that helps to maintain the main core deuterium and tritium (DT) density profiles in a tokamak fusion reactor is discussed. In H-mode plasmas dominated by ion- temperature gradient (ITG) driven turbulence, cold DT ions near the edge will naturally pinch radially inward towards the core. This mechanism is due to the quasi-neutral heat flux dominated nature of ITG turbulence and still applies when trapped and passing kinetic electron effects are included. Fueling using shallow pellet injection or supersonic gas jets is augmented by an inward pinch of could DT fuel. The natural fueling mechanism is demonstrated using the three-dimensional toroidal electromagnetic gyrokinetic turbulence code GEM and is analyzed using quasilinear theory. Profiles similar to those used for conservative ITER transport modeling that have a completely flat density profile are examined and it is found that natural fueling actually reduces the linear growth rates and energy transport.

  13. Mixed Oxide Fresh Fuel Package Auxiliary Equipment

    SciTech Connect (OSTI)

    Yapuncich, F.; Ross, A. [AREVA Federal Services (AFS), Tacoma WA (United States); Clark, R.H. [Shaw AREVA MOX Services, Savannah River Site, Aiken, SC (United States); Ammerman, D. [Sandia National Laboratories, Albuquerque, NM (United States)

    2008-07-01T23:59:59.000Z

    The United States Department of Energy's National Nuclear Security Administration (NNSA) is overseeing the construction the Mixed Oxide (MOX) Fuel Fabrication Facility (MFFF) on the Savannah River Site. The new facility, being constructed by NNSA's contractor Shaw AREVA MOX Services, will fabricate fuel assemblies utilizing surplus plutonium as feedstock. The fuel will be used in designated commercial nuclear reactors. The MOX Fresh Fuel Package (MFFP), which has recently been licensed by the Nuclear Regulatory Commission (NRC) as a type B package (USA/9295/B(U)F-96), will be utilized to transport the fabricated fuel assemblies from the MFFF to the nuclear reactors. It was necessary to develop auxiliary equipment that would be able to efficiently handle the high precision fuel assemblies. Also, the physical constraints of the MFFF and the nuclear power plants require that the equipment be capable of loading and unloading the fuel assemblies both vertically and horizontally. The ability to reconfigure the load/unload evolution builds in a large degree of flexibility for the MFFP for the handling of many types of both fuel and non fuel payloads. The design and analysis met various technical specifications including dynamic and static seismic criteria. The fabrication was completed by three major fabrication facilities within the United States. The testing was conducted by Sandia National Laboratories. The unique design specifications and successful testing sequences will be discussed. (authors)

  14. Liquid fuel reformer development: Autothermal reforming of Diesel fuel

    SciTech Connect (OSTI)

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

    2000-07-24T23:59:59.000Z

    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.

  15. 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

  16. Fluidic fuel feed system

    SciTech Connect (OSTI)

    Badgley, P.

    1990-06-01T23:59:59.000Z

    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.

  17. Gas and Pellet Injection Systems for JT-60 and JT-60U

    SciTech Connect (OSTI)

    Kizu, K.; Hiratsuka, H.; Miyo, Y.; Ichige, H.; Sasajima, T.; Nishiyama, T.; Masaki, K.; Honda, M.; Miya, N.; Hosogane, N. [Japan Atomic Energy Research Institute (Japan)

    2002-09-15T23:59:59.000Z

    Designs and operations of the gas system and pellet injection systems for JT-60 and JT-60U are described. A gas injection valve that is a key component of the gas injection system was developed using a multilayer piezoelectric element. The maximum flow rate of this system is 43.3 Pa.m{sup 3}/s. The valve has mechanism for adjustment at atmospheric side meaning that a repair and an adjustment can be conducted without ventilation inside a vacuum vessel. It was confirmed that the effect of magnetic field and temperature change on the valves in the JT-60U environment was negligible.In JT-60U, two systems of pellet injector - a pneumatic drive and a centrifugal one - were developed. The pneumatic type attained a pellet velocity of 2.3 km/s, which was the world record at the time in 1988. On the other hand, the centrifugal one was developed in 1998. This injector can eject trains of up to 40 cubic (2.1 mm{sup 3}) pellets at frequencies of 1 to 10 Hz and speed of 0.1 to 1.0 km/s. A guide tube for a magnetic high field side injection (HFS) (top) was also developed in 1999. The pellet injection experiment with the HFS system started in 2000. In addition, another guide tube for HFS(mid) injection was newly developed and installed in March 2001. These systems are working well.

  18. Updated NGNP Fuel Acquisition Strategy

    SciTech Connect (OSTI)

    David Petti; Tim Abram; Richard Hobbins; Jim Kendall

    2010-12-01T23:59:59.000Z

    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.

  19. Lithographic fabrication of nanoapertures

    DOE Patents [OSTI]

    Fleming, James G. (Albuquerque, NM)

    2003-01-01T23:59:59.000Z

    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.

  20. A Technique for Producing Large Dual-Layer Pellets in Support of Disruption Mitigation Experiments

    SciTech Connect (OSTI)

    Combs, Stephen Kirk [ORNL; Leachman, J. W. [Washington State University; Meitner, Steven J [ORNL; Baylor, Larry R [ORNL; Foust, Charles R [ORNL; Commaux, Nicolas JC [ORNL; Jernigan, Thomas C [ORNL

    2011-01-01T23:59:59.000Z

    A special single-shot pellet injection system that produces and accelerates large cryogenic pellets (~16 mm diameter and composed of D2 or Ne) to relatively high speeds (>300 and 600 m/s, respectively) was previously developed at the Oak Ridge National Laboratory. Subsequently, a similar system was installed on DIII-D and used successfully in disruption mitigation experiments. To circumvent some operational issues with injecting the large Ne pellets, a technique has been developed in which a relatively thin layer (0.1 to 1.0 mm) of D2 is frozen on the inner wall of the pipe-gun barrel, followed by filling the core with solid Ne. The technique and the initial laboratory tests are described, as well as the implementation and operational issues for fusion experiments.

  1. High-temperature aerosol formation in wood pellets flames: Spatially resolved measurements

    SciTech Connect (OSTI)

    Wiinikka, Henrik; Gebart, Rikard [Energy Technology Centre, Box 726, S-941 28 Piteaa (Sweden); Boman, Christoffer; Bostroem, Dan; Nordin, Anders; OEhman, Marcus [Energy Technology and Thermal Process Chemistry, Umeaa University, S-901 87 Umeaa (Sweden)

    2006-12-15T23:59:59.000Z

    The formation and evolution of high-temperature aerosols during fixed bed combustion of wood pellets in a realistic combustion environment were investigated through spatially resolved experiments. The purpose of this work was to investigate the various stages of aerosol formation from the hot flame zone to the flue gas channel. The investigation is important both for elucidation of the formation mechanisms and as a basis for development and validation of particle formation models that can be used for design optimization. Experiments were conducted in an 8-kW-updraft fired-wood-pellets combustor. Particle samples were withdrawn from the centerline of the combustor through 10 sampling ports by a rapid dilution sampling probe. The corresponding temperatures at the sampling positions were in the range 200-1450{sup o}C. The particle sample was size-segregated in a low-pressure impactor, allowing physical and chemical resolution of the fine particles. The chemical composition of the particles was investigated by SEM/EDS and XRD analysis. Furthermore, the experimental results were compared to theoretical models for aerosol formation processes. The experimental data show that the particle size distribution has two peaks, both of which are below an aerodynamic diameter of 2.5 {mu}m (PM{sub 2.5}). The mode diameters of the fine and coarse modes in the PM{sub 2.5} region were {approx}0.1 and {approx}0.8 {mu}m, respectively. The shape of the particle size distribution function continuously changes with position in the reactor due to several mechanisms. Early, in the flame zone, both the fine mode and the coarse mode in the PM{sub 2.5} region were dominated by particles from incomplete combustion, indicated by a significant amount of carbon in the particles. The particle concentrations of both the fine and the coarse mode decrease rapidly in the hot oxygen-rich flame due to oxidation of the carbon-rich particles. After the hot flame, the fine mode concentration and particle diameter increase gradually when the temperature of the flue gas drops. The main contribution to this comes from condensation on preexisting particles in the gas of alkali sulfates, alkali chlorides, and Zn species formed from constituents vaporized in the fuel bed. The alkali sulfates were found to condense at a temperature of {approx}950{sup o} and alkali chlorides condensed later at {approx}600{sup o}. This agrees well with results of chemical equilibrium calculation of the gas-to-particle conversion temperature. After the hot flame the coarse mode concentration decreased very little when the flue gas was cooled. In addition to carbon, the coarse mode consists of refractory metals and also considerable amounts of alkali. (author)

  2. Method of preparation of bonded polyimide fuel cell package

    DOE Patents [OSTI]

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

    2011-04-26T23:59:59.000Z

    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.

  3. Bonded polyimide fuel cell package and method thereof

    DOE Patents [OSTI]

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

    2005-11-01T23:59:59.000Z

    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.

  4. Changes of O/M, dimension and microstructure of MOX pellet during heat treatment

    SciTech Connect (OSTI)

    Watanabe, M.; Kato, M. [Nuclear Fuel Cycle Engineering Laboratories, Japan Atomic Energy Agency, 4-33, Tokai-mura, Nakagun, Ibaraki 319-1194 (Japan); Sunaoshi, T. [Inspection Development Company, Tokai-mura, Ibaraki, 319-1194 (Japan)

    2013-07-01T23:59:59.000Z

    The oxidation and reduction behaviors of sintered (Pu{sub 0.3}U{sub 0.7})O{sub 2-x} pellets have been studied at 1873 K under a controlled oxygen partial pressure. From the results of oxygen-to-metal (O/M) ratio changes, dimensional and structural changes, it was concluded that the crack nucleation-propagation and the local density change of pores were caused by the tensile and compressive stresses due to the O/M ratio distribution in the direction of the pellet radius. (authors)

  5. Long-term survival and maturation of spinally grafted human fetal and embryonic stem cellderived neural precursors in implantable tacrolimus pellet- immunosuppressed ALS SOD1-G93A model rat

    E-Print Network [OSTI]

    Goldberg, Danielle S.

    2012-01-01T23:59:59.000Z

    pellets represents a novel alternative to subcutaneous injectionsinjection (not published data) that is not observed in pellet-pellets represent a novel alternative to currently implemented labor intensive and unreliable delivery methods (such as repetitive daily subcutaneous injections).

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

    DOE Patents [OSTI]

    Lloyd, Milton H. (Oak Ridge, TN)

    1983-01-01T23:59:59.000Z

    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.

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

    DOE Patents [OSTI]

    Lloyd, M.H.

    1981-01-09T23:59:59.000Z

    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.

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

    DOE Patents [OSTI]

    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

    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.

  9. 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625govInstrumentstdmadapInactiveVisiting the TWP TWPAlumniComplex historian ...BES UserDOEprogramJ U LY 2 9 - AU G

  10. 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625govInstrumentstdmadapInactiveVisiting the TWP TWPAlumniComplex historian ...BES UserDOEprogramJ U LY 2 9 - AU

  11. 22.251 / 22.351 Systems Analysis of the Nuclear Fuel Cycle, Fall 2005

    E-Print Network [OSTI]

    Kazimi, Mujid S.

    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, ...

  12. 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

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

    SciTech Connect (OSTI)

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

    2004-12-14T23:59:59.000Z

    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.

  14. Fuel pin

    DOE Patents [OSTI]

    Christiansen, David W. (Kennewick, WA); Karnesky, Richard A. (Richland, WA); Leggett, Robert D. (Richland, WA); Baker, Ronald B. (Richland, WA)

    1989-01-01T23:59:59.000Z

    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.

  15. Fuel pin

    DOE Patents [OSTI]

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

    1987-11-24T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

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

    1980-02-01T23:59:59.000Z

    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)

  17. 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...

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

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2005-01-01T23:59:59.000Z

    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.

  19. 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...

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

    E-Print Network [OSTI]

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

    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 700µm x 700µm were taken...

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

    SciTech Connect (OSTI)

    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

    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.

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

    SciTech Connect (OSTI)

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

    1985-01-01T23:59:59.000Z

    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.

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

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    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 Avguštin2,J Wood1 KP Scott, G of this group from rumen- extracted DNA. Restriction enzyme cleav- age of the PCR product yields profiles

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

    SciTech Connect (OSTI)

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

    1995-12-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

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

    1995-12-01T23:59:59.000Z

    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.

  6. Influence of the low order rational q surfaces on the pellet deposition profile

    SciTech Connect (OSTI)

    Commaux, Nicolas JC [ORNL; Pegourie, B. [CEA-Cadarache, St. Paul lex Durance, France; Baylor, Larry R [ORNL; Kochi, F. [Austrian Academy of Sciences, Vienna, Austria; Parks, P. B. [General Atomics; Jernigan, T. C. [Oak Ridge National Laboratory (ORNL); Geraud, A. [CEA-Cadarache, St. Paul lex Durance, France; Nehme, H. [CEA-Cadarache, St. Paul lex Durance, France

    2010-02-01T23:59:59.000Z

    Pellet injection is planned to be the main fuelling method on ITER. The high temperature of the plasma during a fusion burn will limit the penetration of the pellet to the outer third of the minor radius. This limited penetration is expected to be compensated by a polarization drift, which will deposit the particles deeper in the plasma for the pellets injected from the high field side. In order to evaluate the expected depth of the fuelling on ITER, a good understanding of this drift effect is important. Experimental data acquired on the DIII-D (USA) and Tore Supra (France) tokamaks show that the polarization drift is influenced by the low order rational q surfaces. These surfaces appear to attenuate the polarization mechanism as the drifting particles cross them. In this paper, a correlation between the maximum of the pellet mass deposition profile and the positions of the q = 2 and q = 3 surfaces on DIII-D and Tore Supra is shown for high field side and low field side injection. A model is proposed to explain this effect and compared with the experimental results. To conclude, the possible consequences of this phenomenon on the fuelling in ITER are described.

  7. Recent Progress on IGNITOR High-Speed Pellet Injector For several years, researchers from ORNL and ENEA-Frascati in Italy have

    E-Print Network [OSTI]

    Recent Progress on IGNITOR High-Speed Pellet Injector For several years, researchers from ORNL and ENEA-Frascati in Italy have been working together on development of a new four-barrel high-speed pellet system for freezing the pellets from deuterium gas at temperatures of ~10 K and the diagnostics

  8. 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

  9. 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

  10. 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

  11. Carbonation as a binding mechanism for coal/calcium hydroxide pellets. Final technical report, 1 September, 1992--31 August, 1993

    SciTech Connect (OSTI)

    Rapp, D.; Lytle, J.; Hackley, K.; Dagamac, M. [Illinois State Geological Survey, Champaign, IL (United States); Berger, R. [Univ. of Illinois, Urbana, IL (United States); Schanche, G. [Army Construction Engineering Research Lab., Champaign, IL (United States)

    1993-12-31T23:59:59.000Z

    This research was an investigation of calcium hydroxide, a sulfur-capturing sorbent, as a binder for coal fines. The reaction of carbon dioxide with calcium hydroxide, referred to as carbonation, was studied as a method for improving pellet quality. Carbonation forms a cementitious matrix of calcium carbonate. Research has demonstrated that calcium hydroxide is a viable binder for coal fines and that a roller-and-die pellet mill is an effective method of pellet formation. From a minus 28 mesh preparation plant fine coal sample, a roller-and-die pellet mill produced strong pellets when 5 and 10% calcium hydroxide was used as a binder. The pellets containing 10% calcium hydroxide strengthened considerably when air cured. This increase in strength was attributed to carbonation via atmospheric carbon dioxide. Pellets containing 10 wt% calcium hydroxide were produced using an extruder but pellets formed in this manner were much weaker than pellets produced with the roller-and-die mill. In tests performed using a laboratory hydraulic press, the effect of particle size and compaction pressure on pellet strength was studied. Particle distributions with mean sizes of 200, 90 and 40 microns were tested. The results indicate that pellet strength increased with decreasing particle size and increasing compaction pressure when calcium hydroxide was used as a binder. Pellets containing 10 wt% calcium hydroxide increased in strength by approximately 40% when air dried for one day. As above, this increase in strength was attributed to carbonation of the calcium hydroxide via atmospheric carbon dioxide.

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

    SciTech Connect (OSTI)

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

    1986-01-01T23:59:59.000Z

    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.

  13. Canadian Photonics Fabrication Center CPFC | 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 onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand Jump to:EzfeedflagBiomassSustainableCSL GasPermits Manual JumpEnergyPhotonics Fabrication Center CPFC

  14. Sandia Energy - Fabrication of AMI Demonstration Blade Begun

    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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Scienceand RequirementsCoatingsUltra-High-Voltage SiliconEnergy CouncilEnergySheddingFabrication

  15. Intraocular lens fabrication

    DOE Patents [OSTI]

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

    1997-01-01T23:59:59.000Z

    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.

  16. Intraocular lens fabrication

    DOE Patents [OSTI]

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

    1997-07-08T23:59:59.000Z

    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.

  17. Electrochemical fabrication of capacitors

    DOE Patents [OSTI]

    Mansour, Azzam N. (Fairfax Sta., VA); Melendres, Carlos A. (Lemont, IL)

    1999-01-01T23:59:59.000Z

    A film of nickel oxide is anodically deposited on a graphite sheet held in osition 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.

  18. Electrochemical fabrication of capacitors

    SciTech Connect (OSTI)

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

    1999-12-14T23:59:59.000Z

    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.

  19. Mask fabrication process

    DOE Patents [OSTI]

    Cardinale, Gregory F. (Oakland, CA)

    2000-01-01T23:59:59.000Z

    A method for fabricating masks and reticles useful for projection lithography systems. An absorber layer is conventionally patterned using a pattern and etch process. Following the step of patterning, the entire surface of the remaining top patterning photoresist layer as well as that portion of an underlying protective photoresist layer where absorber material has been etched away is exposed to UV radiation. The UV-exposed regions of the protective photoresist layer and the top patterning photoresist layer are then removed by solution development, thereby eliminating the need for an oxygen plasma etch and strip and chances for damaging the surface of the substrate or coatings.

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

    SciTech Connect (OSTI)

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

    2002-09-01T23:59:59.000Z

    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.