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1

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

SciTech Connect

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

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

1998-03-01T23:59:59.000Z

2

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

SciTech Connect

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

Toevs, J.W.

1997-12-31T23:59:59.000Z

3

MOX Fabrication Isolation Considerations  

SciTech Connect

This document provides a technical position on the preferred level of isolation to fabricate demonstration quantities of mixed oxide transmutation fuels. The Advanced Fuel Cycle Initiative should design and construct automated glovebox fabrication lines for this purpose. This level of isolation adequately protects the health and safety of workers and the general public for all mixed oxide (and other transmutation fuel) manufacturing efforts while retaining flexibility, allowing parallel development and setup, and minimizing capital expense. The basis regulations, issues, and advantages/disadvantages of five potential forms of isolation are summarized here as justification for selection of the preferred technical position.

Eric L. Shaber; Bradley J Schrader

2005-08-01T23:59:59.000Z

4

Evaluation of existing United States` facilities for use as a mixed-oxide (MOX) fuel fabrication facility for plutonium disposition  

SciTech Connect

A number of existing US facilities were evaluated for use as a mixed-oxide fuel fabrication facility for plutonium disposition. These facilities include the Fuels Material Examination Facility (FMEF) at Hanford, the Washington Power Supply Unit 1 (WNP-1) facility at Hanford, the Barnwell Nuclear Fuel Plant (BNFP) at Barnwell, SC, the Fuel Processing Facility (FPF) at Idaho National Engineering Laboratory (INEL), the Device Assembly Facility (DAF) at the Nevada Test Site (NTS), and the P-reactor at the Savannah River Site (SRS). The study consisted of evaluating each facility in terms of available process space, available building support systems (i.e., HVAC, security systems, existing process equipment, etc.), available regional infrastructure (i.e., emergency response teams, protective force teams, available transportation routes, etc.), and ability to integrate the MOX fabrication process into the facility in an operationally-sound manner that requires a minimum amount of structural modifications.

Beard, C.A.; Buksa, J.J.; Chidester, K.; Eaton, S.L.; Motley, F.E.; Siebe, D.A.

1995-12-31T23:59:59.000Z

5

MOX  

National Nuclear Security Administration (NNSA)

as MOX fuel will be significantly more expensive than anticipated. Given a lifecycle cost estimate for the program of approximately 30 billion or more and a challenging budget...

6

An integrated approach for the verification of fresh mixed oxide fuel (MOX) assemblies at light water reactor MOX recycle reactors  

SciTech Connect

This paper presents an integrated approach for the verification of mixed oxide (MOX) fuel assemblies prior to their being loaded into the reactor. There is a coupling of the verification approach that starts at the fuel fabrication plant and stops with the transfer of the assemblies into the thermal reactor. The key measurement points are at the output of the fuel fabrication plant, the receipt at the reactor site, and the storage in the water pool as fresh fuel. The IAEA currently has the capability to measure the MOX fuel assemblies at the output of the fuel fabrication plants using a passive neutron coincidence counting systems of the passive neutron collar (PNCL) type. Also. at the MOX reactor pool, the underwater coincidence counter (UWCC) has been developed to measure the MOX assemblies in the water. The UWCC measurement requires that the fuel assembly be lifted about two meters up in the storage rack to avoid interference from the fuel that is stored in the rack. This paper presents a new method to verify the MOX fuel assemblies that are in the storage rack without the necessity of moving the fuel. The detector system is called the Underwater MOX Verification System (UMVS). The integration and relationship of the three measurements systems is described.

Menlove, Howard O [Los Alamos National Laboratory; Lee, Sang - Yoon [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

7

MOX Lead Assembly Fabrication at the Savannah River Site  

SciTech Connect

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

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

1997-12-01T23:59:59.000Z

8

MOX fuel arrangement for nuclear core  

DOE Patents (OSTI)

In order to use up a stockpile of weapons-grade plutonium, the plutonium is converted into a mixed oxide (MOX) fuel form wherein it can be disposed in a plurality of different fuel assembly types. Depending on the equilibrium cycle that is required, a predetermined number of one or more of the fuel assembly types are selected and arranged in the core of the reactor in accordance with a selected loading schedule. Each of the fuel assemblies is designed to produce different combustion characteristics whereby the appropriate selection and disposition in the core enables the resulting equilibrium cycle to closely resemble that which is produced using urania fuel. The arrangement of the MOX rods and burnable absorber rods within each of the fuel assemblies, in combination with a selective control of the amount of plutonium which is contained in each of the MOX rods, is used to tailor the combustion characteristics of the assembly.

Kantrowitz, Mark L. (Portland, CT); Rosenstein, Richard G. (Windsor, CT)

2001-07-17T23:59:59.000Z

9

Mox fuel arrangement for nuclear core  

DOE Patents (OSTI)

In order to use up a stockpile of weapons-grade plutonium, the plutonium is converted into a mixed oxide (MOX) fuel form wherein it can be disposed in a plurality of different fuel assembly types. Depending on the equilibrium cycle that is required, a predetermined number of one or more of the fuel assembly types are selected and arranged in the core of the reactor in accordance with a selected loading schedule. Each of the fuel assemblies is designed to produce different combustion characteristics whereby the appropriate selection and disposition in the core enables the resulting equilibrium cycle to closely resemble that which is produced using urania fuel. The arrangement of the MOX rods and burnable absorber rods within each of the fuel assemblies, in combination with a selective control of the amount of plutonium which is contained in each of the MOX rods, is used to tailor the combustion. characteristics of the assembly.

Kantrowitz, Mark L. (Portland, CT); Rosenstein, Richard G. (Windsor, CT)

2001-05-15T23:59:59.000Z

10

MOX fuel arrangement for nuclear core  

DOE Patents (OSTI)

In order to use up a stockpile of weapons-grade plutonium, the plutonium is converted into a mixed oxide (MOX) fuel form wherein it can be disposed in a plurality of different fuel assembly types. Depending on the equilibrium cycle that is required, a predetermined number of one or more of the fuel assembly types are selected and arranged in the core of the reactor in accordance with a selected loading schedule. Each of the fuel assemblies is designed to produce different combustion characteristics whereby the appropriate selection and disposition in the core enables the resulting equilibrium cycle to closely resemble that which is produced using urania fuel. The arrangement of the MOX rods and burnable absorber rods within each of the fuel assemblies, in combination with a selective control of the amount of plutonium which is contained in each of the MOX rods, is used to tailor the combustion characteristics of the assembly. 38 figs.

Kantrowitz, M.L.; Rosenstein, R.G.

1998-10-13T23:59:59.000Z

11

MOX fuel arrangement for nuclear core  

DOE Patents (OSTI)

In order to use up a stockpile of weapons-grade plutonium, the plutonium is converted into a mixed oxide (MOX) fuel form wherein it can be disposed in a plurality of different fuel assembly types. Depending on the equilibrium cycle that is required, a predetermined number of one or more of the fuel assembly types are selected and arranged in the core of the reactor in accordance with a selected loading schedule. Each of the fuel assemblies is designed to produce different combustion characteristics whereby the appropriate selection and disposition in the core enables the resulting equilibrium cycle to closely resemble that which is produced using urania fuel. The arrangement of the MOX rods and burnable absorber rods within each of the fuel assemblies, in combination with a selective control of the amount of plutonium which is contained in each of the MOX rods, is used to tailor the combustion characteristics of the assembly.

Kantrowitz, Mark L. (Portland, CT); Rosenstein, Richard G. (Windsor, CT)

1998-01-01T23:59:59.000Z

12

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

SciTech Connect

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

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

1998-08-01T23:59:59.000Z

13

Plutonium Consumption Program, CANDU Reactor Project: Feasibility of BNFP Site as MOX Fuel Supply Facility. Final report  

SciTech Connect

An evaluation was made of the technical feasibility, cost, and schedule for converting the existing unused Barnwell Nuclear Fuel Facility (BNFP) into a Mixed Oxide (MOX) CANDU fuel fabrication plant for disposition of excess weapons plutonium. This MOX fuel would be transported to Ontario where it would generate electricity in the Bruce CANDU reactors. Because CANDU MOX fuel operates at lower thermal load than natural uranium fuel, the MOX program can be licensed by AECB within 4.5 years, and actual Pu disposition in the Bruce reactors can begin in 2001. Ontario Hydro will have to be involved in the entire program. Cost is compared between BNFP and FMEF at Hanford for converting to a CANDU MOX facility.

NONE

1995-06-30T23:59:59.000Z

14

Theory of Antineutrino Monitoring of Burning MOX Plutonium Fuels  

E-Print Network (OSTI)

This letter presents the physics and feasibility of reactor antineutrino monitoring to verify the burnup of plutonium loaded in the reactor as a Mixed Oxide (MOX) fuel. It examines the magnitude and temporal variation in the antineutrino signals expected for different MOX fuels, for the purposes of nuclear accountability and safeguards. The antineutrino signals from reactor-grade and weapons-grade MOX are shown to be distinct from those from burning low enriched uranium. Thus, antineutrino monitoring could be used to verify the destruction of plutonium in reactors, though verifying the grade of the plutonium being burned is found to be more challenging.

Hayes, A C; Nieto, Michael Martin; WIlson, W B

2011-01-01T23:59:59.000Z

15

Theory of Antineutrino Monitoring of Burning MOX Plutonium Fuels  

E-Print Network (OSTI)

This letter presents the physics and feasibility of reactor antineutrino monitoring to verify the burnup of plutonium loaded in the reactor as a Mixed Oxide (MOX) fuel. It examines the magnitude and temporal variation in the antineutrino signals expected for different MOX fuels, for the purposes of nuclear accountability and safeguards. The antineutrino signals from reactor-grade and weapons-grade MOX are shown to be distinct from those from burning low enriched uranium. Thus, antineutrino monitoring could be used to verify the destruction of plutonium in reactors, though verifying the grade of the plutonium being burned is found to be more challenging.

A. C. Hayes; H. R. Trellue; Michael Martin Nieto; W. B. WIlson

2011-10-03T23:59:59.000Z

16

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

SciTech Connect

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

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

1998-08-01T23:59:59.000Z

17

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

SciTech Connect

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

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

1998-08-01T23:59:59.000Z

18

Hot Cell Examination of Weapons-Grade MOX Fuel  

SciTech Connect

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

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

2010-01-01T23:59:59.000Z

19

Integration Strategy for DB-MHR TRISO Fuel production in conjunction with MOX Fuel production  

SciTech Connect

One of the nuclear power options for the future involves the evolution of gas cooled reactors to support the likely high temperature operations needed for commercial scale hydrogen production. One such proposed option is to use a Gas Turbine Modular Helium Reactor fueled with uranium based TRISO (coated particle) fuel. It has also been suggested that such a MHR could be operated in a ''Deep Burn'' manner fueled with TRISO fuel produced from recycle spent nuclear fuel. This concept known as a DBMHR must withstand significant development and fuel fabrication cost to be economically viable. The purpose of this report is to consider and propose a strategy where synergy with a parallel MOX fuel to LWR program provides economic or other advantage for either or both programs. A strategy involving three phases has been envisioned with potential for economic benefit relative to a stand-alone TRISO/DBMHR program. Such a strategy and related timing will ultimately be driven by economics, but is offered here for consideration of value to the total AFCI program. Phase I Near-term. Conventional spent fuel aqueous processing, MOX fuel fabrication, and use of present and future LWR/ALWR's with objective of a ''Continuous Recycle'' mode of fuel cycle management. Phase II Intermediate. Augmentation of LWR/ALWR industry with MHR deployment as justified by hydrogen economy and/or electrical demand. Phase III Long-term. Introduction of DBMHR's to offer alternative method for transuranic destruction and associated repository benefits, in addition to Phase II benefits. The basic philosophy of this strategy appears sound. However, the details of the technology plans and economic evaluations should receive additional detail and evaluation in the next fiscal year as funding can support.

MCGUIRE, DAVID

2005-09-30T23:59:59.000Z

20

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...

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


21

All About MOX  

SciTech Connect

In 1999, the Nuclear Nuclear Security Administration (NNSA) signed a contract with a consortium, now called Shaw AREVA MOX Services, LLC to design, build, and operate a Mixed Oxide (MOX) Fuel Fabrication Facility. This facility will be a major component in the United States program to dispose of surplus weapon-grade plutonium. The facility will take surplus weapon-grade plutonium, remove impurities, and mix it with uranium oxide to form MOX fuel pellets for reactor fuel assemblies. These assemblies will be irradiated in commercial nuclear power reactors.

None

2009-07-29T23:59:59.000Z

22

All About MOX  

ScienceCinema (OSTI)

In 1999, the Nuclear Nuclear Security Administration (NNSA) signed a contract with a consortium, now called Shaw AREVA MOX Services, LLC to design, build, and operate a Mixed Oxide (MOX) Fuel Fabrication Facility. This facility will be a major component in the United States program to dispose of surplus weapon-grade plutonium. The facility will take surplus weapon-grade plutonium, remove impurities, and mix it with uranium oxide to form MOX fuel pellets for reactor fuel assemblies. These assemblies will be irradiated in commercial nuclear power reactors.

None

2014-08-06T23:59:59.000Z

23

Transmutation of Transuranic Elements in Advanced MOX and IMF Fuel Assemblies Utilizing Multi-recycling Strategies  

E-Print Network (OSTI)

of nuclear power plants worldwide. To do so efficiently, several new fuel assembly designs are proposed in this Thesis: these include (1) Mixed Oxide Fuel (MOX), (2) MOX fuel with Americium coating, (3) Inert-Matrix Fuel (IMF) with UOX as inner zone, and (4...

Zhang, Yunhuang

2011-02-22T23:59:59.000Z

24

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

SciTech Connect

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

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

1998-08-01T23:59:59.000Z

25

ANL-W MOX fuel lead assemblies data report for the surplus plutonium disposition environmental impact statement  

SciTech Connect

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 (EIS). 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. The paper describes the following: Site map and the LA facility; process descriptions; resource needs; employment requirements; wastes, emissions, and exposures; accident analysis; transportation; qualitative decontamination and decommissioning; post-irradiation examination; LA fuel bundle fabrication; LA EIS data report assumptions; and LA EIS data report supplement.

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

1997-08-01T23:59:59.000Z

26

Process modeling of plutonium conversion and MOX fabrication for plutonium disposition  

SciTech Connect

Two processes are currently under consideration for the disposition of 35 MT of surplus plutonium through its conversion into fuel for power production. These processes are the ARIES process, by which plutonium metal is converted into a powdered oxide form, and MOX fuel fabrication, where the oxide powder is combined with uranium oxide powder to form ceramic fuel. This study was undertaken to determine the optimal size for both facilities, whereby the 35 MT of plutonium metal will be converted into fuel and burned for power. The bounding conditions used were a plutonium concentration of 3--7%, a burnup of 20,000--40,000 MWd/MTHM, a core fraction of 0.1 to 0.4, and the number of reactors ranging from 2--6. Using these boundary conditions, the optimal cost was found with a plutonium concentration of 7%. This resulted in an optimal throughput ranging from 2,000 to 5,000 kg Pu/year. The data showed minimal costs, resulting from throughputs in this range, at 3,840, 2,779, and 3,497 kg Pu/year, which results in a facility lifetime of 9.1, 12.6, and 10.0 years, respectively.

Schwartz, K.L. [Univ. of Texas, Austin, TX (United States). Dept. of Nuclear Engineering

1998-10-01T23:59:59.000Z

27

LANL disassembles "pits," makes mixed-oxide fuel  

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

at the MOX facility in South Carolina, the plutonium oxide from LANL will be blended with depleted uranium, fabricated into MOX fuel, and irradiated in domestic nuclear...

28

Advanced Safeguards Approaches for New TRU Fuel Fabrication Facilities  

SciTech Connect

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

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

2007-12-15T23:59:59.000Z

29

US weapons-useable plutonium disposition policy: implementation of the MOX fuel option  

E-Print Network (OSTI)

US WEAPONS-USEABLE PLUTONIUM DISPOSITION POLICY: IMPLEMENTATION OF THE MOX FUEL OPTION A Thesis by VANESSA L. GONZALEZ Submitted to the Office of Graduate Studies of Texas ARM University in partial fulfillment of the requirements... for the degree of MASTER OF ARTS August 1998 Major Subject: Political Science US WEAPONS-USEABLE PLUTONIUM DISPOSITION POLICY: IMPLEMENTATION OF THE MOX FUEL OPTION A Thesis by VANESSA L. GONZALEZ Submitted to Texas ARM University in partial fulfillment...

Gonzalez, Vanessa L

2012-06-07T23:59:59.000Z

30

A Neutronic Analysis of TRU Recycling in PWRs Loaded with MOX-UE Fuel (MOX with U-235 Enriched U Support)  

SciTech Connect

This report presents the results of a study dealing with the homogeneous recycling of either Pu or Pu+Np or Pu+Np+Am or Pu+Np+Am+Cm in PWRs using MOX-UE fuel, i.e. standard MOX fuel with a U235 enriched uranium support instead of the standard tail uranium (0.25%) for standard MOX fuel. This approach allows to multirecycle Pu or TRU (Pu+MA) as long as U235 is available, by keeping the Pu or TRU content in the fuel constant and at a value ensuring a negative moderator void coefficient (i.e. the loss of the coolant brings imperatively the reactor to a subcritical state). Once this value is determined, the U235 enrichment of the MOX-UE fuel is adjusted in order to reach the target burnup (51 GWd/t in this study).

G. Youinou; S. Bays

2009-05-01T23:59:59.000Z

31

An improved characterization method for international accountancy measurements of fresh and irradiated mixed oxide (MOX) fuel: helping achieve continual monitoring and safeguards through the fuel cycle  

SciTech Connect

Nuclear fuel accountancy measurements are conducted at several points through the nuclear fuel cycle to ensure continuity of knowledge (CofK) of special nuclear material (SNM). Non-destructive assay (NDA) measurements are performed on fresh fuel (prior to irradiation in a reactor) and spent nuclear fuel (SNF) post-irradiation. We have developed a fuel assembly characterization system, based on the novel concept of 'neutron fingerprinting' with multiplicity signatures to ensure detailed CofK of nuclear fuel through the entire fuel cycle. The neutron fingerprint in this case is determined by the measurement of the various correlated neutron signatures, specific to fuel isotopic composition, and therefore offers greater sensitivity to variations in fissile content among fuel assemblies than other techniques such as gross neutron counting. This neutron fingerprint could be measured at the point of fuel dispatch (e.g. from a fuel fabrication plant prior to irradiation, or from a reactor site post-irradiation), monitored during transportation of the fuel assembly, and measured at a subsequent receiving site (e.g. at the reactor site prior to irradiation, or reprocessing facility post-irradiation); this would confirm that no unexpected changes to the fuel composition or amount have taken place during transportation and/ or reactor operations. Changes may indicate an attempt to divert material for example. Here, we present the current state of the practice of fuel measurements for both fresh mixed oxide (MOX) fuel and SNF (both MOX and uranium dioxide). This is presented in the framework of international safeguards perspectives from the US and UK. We also postulate as to how the neutron fingerprinting concept could lead to improved fuel characterization (both fresh MOX and SNF) resulting in: (a) assured CofK of fuel across the nuclear fuel cycle, (b) improved detection of SNM diversion, and (c) greater confidence in safeguards of SNF transportation.

Evans, Louise G [Los Alamos National Laboratory; Croft, Stephen [Los Alamos National Laboratory; Swinhoe, Martyn T [Los Alamos National Laboratory; Tobin, S. J. [Los Alamos National Laboratory; Menlove, H. O. [Los Alamos National Laboratory; Schear, M. A. [Los Alamos National Laboratory; Worrall, Andrew [U.K. NNL

2011-01-13T23:59:59.000Z

32

An improved characterization method for international accountancy measurements of fresh and irradiated mixed oxide (MOX) fuel: helping achieve continual monitoring and safeguards through the fuel cycle  

SciTech Connect

Nuclear fuel accountancy measurements are conducted at several points through the nuclear fuel cycle to ensure continuity of knowledge (CofK) of special nuclear material (SNM). Non-destructive assay (NDA) measurements are performed on fresh fuel (prior to irradiation in a reactor) and spent nuclear fuel (SNF) post-irradiation. We have developed a fuel assembly characterization system, based on the novel concept of 'neutron fingerprinting' with multiplicity signatures to ensure detailed CofK of nuclear fuel through the entire fuel cycle. The neutron fingerprint in this case is determined by the measurement of the various correlated neutron signatures, specific to fuel isotopic composition, and therefore offers greater sensitivity to variations in fissile content among fuel assemblies than other techniques such as gross neutron counting. This neutron fingerprint could be measured at the point of fuel dispatch (e.g. from a fuel fabrication plant prior to irradiation, or from a reactor site post-irradiation), monitored during transportation of the fuel assembly, and measured at a subsequent receiving site (e.g. at the reactor site prior to irradiation, or reprocessing facility post-irradiation); this would confirm that no unexpected changes to the fuel composition or amount have taken place during transportation and/or reactor operations. Changes may indicate an attempt to divert material for example. Here, we present the current state of the practice of fuel measurements for both fresh mixed oxide (MOX) fuel and SNF (both MOX and uranium dioxide). This is presented in the framework of international safeguards perspectives from the US and UK. We also postulate as to how the neutron fingerprinting concept could lead to improved fuel characterization (both fresh MOX and SNF) resulting in: (a) assured CofK of fuel across the nuclear fuel cycle, (b) improved detection of SNM diversion, and (c) greater confidence in safeguards of SNF transportation.

Evans, Louise G [Los Alamos National Laboratory; Croft, Stephen [Los Alamos National Laboratory; Swinhoe, Martyn T [Los Alamos National Laboratory; Tobin, S. J. [Los Alamos National Laboratory; Boyer, B. D. [Los Alamos National Laboratory; Menlove, H. O. [Los Alamos National Laboratory; Schear, M. A. [Los Alamos National Laboratory; Worrall, Andrew [U.K., NNL

2010-11-24T23:59:59.000Z

33

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

SciTech Connect

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

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

2014-01-01T23:59:59.000Z

34

NNSA B-Roll: MOX Facility  

SciTech Connect

In 1999, the National Nuclear Security Administration (NNSA) signed a contract with a consortium, now called Shaw AREVA MOX Services, LLC to design, build, and operate a Mixed Oxide (MOX) Fuel Fabrication Facility. This facility will be a major component in the United States program to dispose of surplus weapon-grade plutonium. The facility will take surplus weapon-grade plutonium, remove impurities, and mix it with uranium oxide to form MOX fuel pellets for reactor fuel assemblies. These assemblies will be irradiated in commercial nuclear power reactors.

2010-05-21T23:59:59.000Z

35

Development of an integrated, unattended assay system for LWR-MOX fuel pellet trays  

SciTech Connect

Four identical unattended plutonium assay systems have been developed for use at the new light-water-reactor mixed oxide (LWR-MOX) fuel fabrication facility at Hanau, Germany. The systems provide quantitative plutonium verification for all MOX pellet trays entering or leaving a large, intermediate store. Pellet-tray transport and storage systems are highly automated. Data from the ``I-Point`` (information point) assay systems will be shared by the Euratom and International Atomic Energy Agency (IAEA) Inspectorates. The I-Point system integrates, for the first time, passive neutron coincidence counting (NCC) with electro-mechanical sensing (EMS) in unattended mode. Also, provisions have been made for adding high-resolution gamma spectroscopy. The system accumulates data for every tray entering or leaving the store between inspector visits. During an inspection, data are analyzed and compared with operator declarations for the previous inspection period, nominally one month. Specification of the I-point system resulted from a collaboration between the IAEA, Euratom, Siemens, and Los Alamos. Hardware was developed by Siemens and Los Alamos through a bilateral agreement between the German Federal Ministry of Research and Technology (BMFT) and the US DOE. Siemens also provided the EMS subsystem, including software. Through the USSupport Program to the IAEA, Los Alamos developed the NCC software (NCC COLLECT) and also the software for merging and reviewing the EMS and NCC data (MERGE/REVIEW). This paper describes the overall I-Point system, but emphasizes the NCC subsystem, along with the NCC COLLECT and MERGE/REVIEW codes. We also summarize comprehensive testing results that define the quality of assay performance.

Stewart, J.E.; Hatcher, C.R.; Pollat, L.L. [and others

1994-08-01T23:59:59.000Z

36

Evaluation of fuel cycle scenarios on MOX fuel recycling in PWRs and SFRs  

SciTech Connect

Prospects on advanced fuel cycle scenario are considered for achieving a progressive integration of Sodium Fast Reactor (SFR) technology within the current French Pressurized Water Reactor (PWR) nuclear fleet, in a view to benefit from fissile material multi-recycling capability. A step by step process is envisioned, and emphasis is put on its potential implementation through the nuclear mass inventory calculations with the COSAC code. The overall time scale is not optimized. The first step, already implemented in several countries, the plutonium coming from the reprocessing of used Light Water Reactor (LWR) fuels is recycled into a small number of LWRs. The second step is the progressive introduction of the first SFRs, in parallel with the continuation of step 1. This second step lets to prepare the optimized multi recycling of MOX fuel which is considered in step 3. Step 3 is characterized by the introduction of a greater number of SFR and MOX management between EPR reactors and SFRs. In the final step 4, all the fleet is formed with SFRs. This study assesses the viability of each step of the overall scenario. The switch from one step to the other one could result from different constrains related to issues such as resources, waste, experience feedback, public acceptance, country policy, etc.

Carlier, B.; Caron-Charles, M.; Van Den Durpel, L. [AREVA, 1 place Jean Millier, Paris La Defense (France); Senentz, G. [AREVA, 33 rue La Lafayette, 75009 Paris (France); Serpantie, J.P. [AREVA, 10 rue Juliette Recamier, Lyon (France)

2013-07-01T23:59:59.000Z

37

Irradiated test fuel shipment plan for the LWR MOX fuel irradiation test project  

SciTech Connect

This document outlines the responsibilities of DOE, DOE contractors, the commercial carrier, and other organizations participating in a shipping campaign of irradiated test specimen capsules containing mixed-oxide (MOX) fuel from the Idaho National Engineering and Environmental Laboratory (INEEL) to the Oak Ridge National Laboratory (ORNL). The shipments described here will be conducted according to applicable regulations of the US Department of Transportation (DOT), US Nuclear Regulatory Commission (NRC), and all applicable DOE Orders. This Irradiated Test Fuel Shipment Plan for the LWR MOX Fuel Irradiation Test Project addresses the shipments of a small number of irradiated test specimen capsules and has been reviewed and agreed to by INEEL and ORNL (as participants in the shipment campaign). Minor refinements to data entries in this plan, such as actual shipment dates, exact quantities and characteristics of materials to be shipped, and final approved shipment routing, will be communicated between the shipper, receiver, and carrier, as needed, using faxes, e-mail, official shipping papers, or other backup documents (e.g., shipment safety evaluations). Any major changes in responsibilities or data beyond refinements of dates and quantities of material will be prepared as additional revisions to this document and will undergo a full review and approval cycle.

Shappert, L.B.; Dickerson, L.S.; Ludwig, S.B.

1998-10-16T23:59:59.000Z

38

Multirecycling of Plutonium from LMFBR Blanket in Standard PWRs Loaded with MOX Fuel  

SciTech Connect

It is now well-known that, from a physics standpoint, Pu, or even TRU (i.e. Pu+M.A.), originating from LEU fuel irradiated in PWRs can be multirecycled also in PWRs using MOX fuel. However, the degradation of the isotopic composition during irradiation necessitates using enriched U in conjunction with the MOX fuel either homogeneously or heterogeneously to maintain the Pu (or TRU) content at a level allowing safe operation of the reactor, i.e. below about 10%. The study is related to another possible utilization of the excess Pu produced in the blanket of a LMFBR, namely in a PWR(MOX). In this case the more Pu is bred in the LMFBR, the more PWR(MOX) it can sustain. The important difference between the Pu coming from the blanket of a LMFBR and that coming from a PWR(LEU) is its isotopic composition. The first one contains about 95% of fissile isotopes whereas the second one contains only about 65% of fissile isotopes. As it will be shown later, this difference allows the PWR fed by Pu from the LMFBR blanket to operate with natural U instead of enriched U when it is fed by Pu from PWR(LEU)

Sonat Sen; Gilles Youinou

2013-02-01T23:59:59.000Z

39

Energy Secretary Bodman Commends Key Milestone In MOX Program | Department  

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

Commends Key Milestone In MOX Program Commends Key Milestone In MOX Program Energy Secretary Bodman Commends Key Milestone In MOX Program April 1, 2005 - 11:28am Addthis WASHINGTON, DC - In response to the Nuclear Regulatory Commission's (NRC) authorization of the construction of a U.S. Mixed-Oxide (MOX) Fuel Fabrication Facility at the Department of Energy's Savannah River Site in South Carolina, Secretary of Energy Samuel W. Bodman today released the following statement: "Issuing the permit for construction of a MOX facility in South Carolina is the crucial next step in the MOX program. It is a key milestone in our efforts to dispose of surplus weapons grade plutonium in the U.S. and Russia," Secretary Bodman said. "We look forward to proceeding with this nonproliferation program that will ultimately eliminate enough

40

The Use of Staff Augmentation Subcontracts at the National Nuclear Security Administration's Mixed Oxide Fuel Fabrication Facility, IG-0887  

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

The Use of Staff Augmentation The Use of Staff Augmentation Subcontracts at National Nuclear Security Administration's Mixed Oxide Fuel Fabrication Facility DOE/IG-0887 May 2013 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 May 15, 2013 MEMORANDUM FOR THE SECRETARY FROM: Gregory H. Friedman Inspector General SUBJECT: INFORMATION: Audit Report on "The Use of Staff Augmentation Subcontracts at the National Nuclear Security Administration's Mixed Oxide Fuel Fabrication Facility" BACKGROUND Shaw AREVA MOX Services, LLC (MOX Services) is responsible for the design and construction of the National Nuclear Security Administration's (NNSA) nearly $5 billion Mixed

Note: This page contains sample records for the topic "mox fuel fabrication" from the National Library of EnergyBeta (NLEBeta).
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41

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

SciTech Connect

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

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

1993-12-31T23:59:59.000Z

42

Verification Calculation Results to Validate the Procedures and Codes for Pin-by-Pin Power Computation in VVER Type Reactors with MOX Fuel Loading  

SciTech Connect

One of the important problems for ensuring the VVER type reactor safety when the reactor is partially loaded with MOX fuel is the choice of appropriate physical zoning to achieve the maximum flattening of pin-by-pin power distribution. When uranium fuel is replaced by MOX one provided that the reactivity due to fuel assemblies is kept constant, the fuel enrichment slightly decreases. However, the average neutron spectrum fission microscopic cross-section for {sup 239}Pu is approximately twice that for {sup 235}U. Therefore power peaks occur in the peripheral fuel assemblies containing MOX fuel which are aggravated by the interassembly water. Physical zoning has to be applied to flatten the power peaks in fuel assemblies containing MOX fuel. Moreover, physical zoning cannot be confined to one row of fuel elements as is the case with a uniform lattice of uranium fuel assemblies. Both the water gap and the jump in neutron absorption macroscopic cross-sections which occurs at the interface of fuel assemblies with different fuels make the problem of calculating space-energy neutron flux distribution more complicated since it increases nondiffusibility effects. To solve this problem it is necessary to update the current codes, to develop new codes and to verify all the codes including nuclear-physical constants libraries employed. In so doing it is important to develop and validate codes of different levels--from design codes to benchmark ones. This paper presents the results of the burnup calculation for a multiassembly structure, consisting of MOX fuel assemblies surrounded by uranium dioxide fuel assemblies. The structure concerned can be assumed to model a fuel assembly lattice symmetry element of the VVER-1000 type reactor in which 1/4 of all fuel assemblies contains MOX fuel.

Chizhikova, Z.N.; Kalashnikov, A.G.; Kapranova, E.N.; Korobitsyn, V.E.; Manturov, G.N.; Tsiboulia, A.A.

1998-12-01T23:59:59.000Z

43

Monte Carlo analysis of burnup-dependent plutonium concentration profiles in UO{sub 2} and MOX fuel pins  

SciTech Connect

The ability to accurately predict fuel performance is an essential requirement for fuel design studies. Prediction of plutonium concentration profiles in an irradiated fuel pin is important for fuel performance analysis and spent-fuel storage. The MCNP coupling with ORIGEN2 (MCWO) burnup calculation code as demonstrated in this paper can analyze the rim effect in UO{sub 2} and mixed-oxide (MOX) fuel pins. Acceptance of a code such as MCWO depends very strongly on its validation. Validation involves the benchmark of the code predictions to the in-pile experimental data and results of post-irradiation examinations (PIEs). In this paper, a validation was made by comparing the MCWO calculated results with the VIM-BURN code, which has been validated against PIE data. The validated MCWO can provide the best-estimate neutronic characteristics of fuel burnup performance analysis. In this paper, Pu concentration (wt%) and fission power profiles versus burnup of UO{sub 2} and reactor-grade (RG)-MOX fuel pins were calculated with MCWO, and results are discussed.

Chang, G.S. [Lockheed Martin Idaho Technologies, Idaho Falls, ID (United States). Idaho National Engineering and Environmental Lab.

1998-09-01T23:59:59.000Z

44

Test plan for the Parallex CANDU-MOX irradiation  

SciTech Connect

One of several options being considered by the United States and the Russian Federation for the disposition of excess plutonium from dismantled weapons is to convert it to mixed-oxide (MOX) fuel for use in Canadian uranium-deuterium (CANDU) reactors. This report describes an irradiation test demonstrating the feasibility of this concept with laboratory quantities of MOX fuel placed in the pressurized loops of the National Research Universal test reactor at the Atomic Energy of Canada, Ltd., Chalk River Laboratories. The objective of the Parallex (for parallel experiment) test is to simultaneously test laboratory-produced quantities of US and R.F. MOX fuel in a test reactor under heat generation rates representing those expected in the CANDU reactors. The MOX fuel will be produced with plutonium from disassembled weapons at the Los Alamos National Laboratory in the United States and at the Bochvar Institute in the Russian Federation. Thus, the test will serve to demonstrate the accomplishment of many parts of the disposition mission: disassembly of weapons, conversion of the plutonium to oxide, fabrication of MOX fuel, assembly of fuel elements and bundles, shipment to a reactor, irradiation, and finally, storage of the spent fuel elements awaiting eventual disposition in a geologic repository in Canada.

Copeland, G.L.

1997-06-01T23:59:59.000Z

45

RADIATION DOSE ASPECTS IN THE HANDLING OF EMERGING NUCLEAR FUELS  

Science Journals Connector (OSTI)

......Prot. (2008) 28:161. 15 NUREG. Standard review plan for the review of an application for a Mixed Oxide (MOX) fuel...fabrication facility. (2000) NUREG-1718, US Nuclear Regulatory Commission. 16 IAEA. Safety of uranium fuel fabrication......

G. Nicolaou

2014-02-01T23:59:59.000Z

46

RELAP5/MOD3.2 analysis of a VVER-1000 reactor with UO[2] fuel and MOX fuel  

E-Print Network (OSTI)

.2 results showed a good agreement with calculations obtained with TECH-M computer program. The cladding temperatures of the MOX assembly have been compared with that of the hot UO? assembly. The peak cladding temperature of MOX assembly is about 55 K higher...

Fu, Chun

2012-06-07T23:59:59.000Z

47

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

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

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

48

Fuel Fabrication Capability Research and Development Plan  

SciTech Connect

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

Senor, David J.; Burkes, Douglas

2014-04-17T23:59:59.000Z

49

E-Print Network 3.0 - atr wg-mox fuel Sample Search Results  

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

Energy, Hydrogen, Fuel Cells and Infrastructure Technologies Program Collection: Energy Storage, Conversion and Utilization ; Renewable Energy 2 Experimental Study to...

50

Update on US High Density Fuel Fabrication Development  

SciTech Connect

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

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

2007-03-01T23:59:59.000Z

51

The United States pit disassembly and conversion project -- Meeting the MOX fuel specification  

SciTech Connect

The US is actively involved in demonstrating the disassembly of nuclear weapons pits to an unclassified form readied for disposition. The MOX option is the most likely path forward for plutonium that originated from nuclear weapon pits. The US demonstration line for pit disassembly and conversion is known as ARIES, the advanced recovery and integrated extraction system. The ARIES demonstration line is being used to gather data in an integrated fashion of the technologies needed for pit disassembly and conversion. These activities include the following modules: pit bisection, hydride-dehydride, oxide conversion, canning, electrolytic decontamination, and nondestructive assay (NDA). Pit bisection swages in a pit in half. Hydride-dehydride converts the pit plutonium metal to an unclassified metal button. To convert the plutonium metal to an oxide the US is investigating a number of options. The primary oxide conversion approach involves variations of combining plutonium hydriding and subsequent oxidation. Another approach is to simply oxidize the metal under controlled conditions-direct metal oxidation (DMO). To remove the gallium from the plutonium oxide, a thermal distillation approach is being used. These pyrochemical approaches will substantially reduce the wastes produced for oxide conversion of weapon plutonium, compared to traditional aqueous processing. The packaging of either the plutonium metal or oxide to long term storage criteria involves the canning and electrolytic decontamination modules. The NDA suite of instruments is then used to assay the material in the containers, which enables international verification without the need to open the containers and repackage them. All of these processes are described.

Nelson, T.O.; James, C.A.; Kolman, D.G.

1998-12-31T23:59:59.000Z

52

U.S. weapons-usable plutonium disposition policy: Implementation of the MOX fuel option  

SciTech Connect

A comprehensive case study was conducted on the policy problem of disposing of US weapons-grade plutonium, which has been declared surplus to strategic defense needs. Specifically, implementation of the mixed-oxide fuel disposition option was examined in the context of national and international nonproliferation policy, and in contrast to US plutonium policy. The study reveals numerous difficulties in achieving effective implementation of the mixed-oxide fuel option including unresolved licensing and regulatory issues, technological uncertainties, public opposition, potentially conflicting federal policies, and the need for international assurances of reciprocal plutonium disposition activities. It is believed that these difficulties can be resolved in time so that the implementation of the mixed-oxide fuel option can eventually be effective in accomplishing its policy objective.

Woods, A.L. [ed.] [Amarillo National Resource Center for Plutonium, TX (United States); Gonzalez, V.L. [Texas A and M Univ., College Station, TX (United States). Dept. of Political Science

1998-10-01T23:59:59.000Z

53

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

SciTech Connect

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

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

1997-12-01T23:59:59.000Z

54

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

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

4: Radioisotope Heat Source Fuel Processing and Fabrication, 4: Radioisotope Heat Source Fuel Processing and Fabrication, Los Alamos, New Mexico EA-0534: Radioisotope Heat Source Fuel Processing and Fabrication, Los Alamos, New Mexico SUMMARY 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 an existing facility at U.S. Department of Energy's Los Alamos National Laboratory. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD July 19, 1991 EA-0534: Finding of No Significant Impact Radioisotope Heat Source Fuel Processing and Fabrication July 19, 1991 EA-0534: Final Environmental Assessment Radioisotope Heat Source Fuel Processing and Fabrication

55

Survey of Worldwide Light Water Reactor Experience with Mixed Uranium-Plutonium Oxide Fuel  

SciTech Connect

The US and the Former Soviet Union (FSU) have recently declared quantities of weapons materials, including weapons-grade (WG) plutonium, excess to strategic requirements. One of the leading candidates for the disposition of excess WG plutonium is irradiation in light water reactors (LWRs) as mixed uranium-plutonium oxide (MOX) fuel. A description of the MOX fuel fabrication techniques in worldwide use is presented. A comprehensive examination of the domestic MOX experience in US reactors obtained during the 1960s, 1970s, and early 1980s is also presented. This experience is described by manufacturer and is also categorized by the reactor facility that irradiated the MOX fuel. A limited summary of the international experience with MOX fuels is also presented. A review of MOX fuel and its performance is conducted in view of the special considerations associated with the disposition of WG plutonium. Based on the available information, it appears that adoption of foreign commercial MOX technology from one of the successful MOX fuel vendors will minimize the technical risks to the overall mission. The conclusion is made that the existing MOX fuel experience base suggests that disposition of excess weapons plutonium through irradiation in LWRs is a technically attractive option.

Cowell, B.S.; Fisher, S.E.

1999-02-01T23:59:59.000Z

56

Licensing issues associated with the use of mixed-oxide fuel in US commercial nuclear reactors  

SciTech Connect

On January 14, 1997, the Department of Energy, as part of its Record of Decision on the storage and disposition of surplus nuclear weapons materials, committed to pursue the use of excess weapons-usable plutonium in the fabrication of mixed-oxide (MOX) fuel for consumption in existing commercial nuclear power plants. Domestic use of MOX fuel has been deferred since the late 1970s, principally due to nuclear proliferation concerns. This report documents a review of past and present literature (i.e., correspondence, reports, etc.) on the domestic use of MOX fuel and provides discussion on the technical and regulatory issues that must be addressed by DOE (and the utility/consortia selected by DOE to effect the MOX fuel consumption strategy) in obtaining approval from the Nuclear Regulatory Commission to use MOX fuel in one or a group of existing commercial nuclear power plants.

Williams, D.L. Jr.

1997-04-01T23:59:59.000Z

57

Environmental assessment for the manufacture and shipment of nuclear reactor fuel from the United States to Canada  

SciTech Connect

The US Department of Energy (DOE) has declared 41.9 tons (38 metric tons) of weapons-usable plutonium surplus to the United States` defense needs. A DOE Programmatic Environmental Impact Statement analyzed strategies for plutonium storage and dispositioning. In one alternative, plutonium as a mixed oxide (MOX) fuel would be irradiated (burned) in a reengineered heavy-water-moderated reactor, such as the Canadian CANDU design. In an Environmental Assessment (EA), DOE proposes to fabricate and transport to Canada a limited amount of MOX fuel as part of the Parallex (parallel experiment) Project. MOX fuel from the US and Russia would be used by Canada to conduct performance tests at Chalk River Laboratories. MOX fuel would be fabricated at Los Alamos National Laboratory and transported in approved container(s) to a Canadian port(s) of entry on one to three approved routes. The EA analyzes the environmental and human health effects from MOX fuel fabrication and transportation. Under the Proposed Action, MOX fuel fabrication would not result in adverse effects to the involved workers or public. Analysis showed that the shipment(s) of MOX fuel would not adversely affect the public, truck crew, and environment along the transportation routes.

Rangel, R.C.

1999-02-01T23:59:59.000Z

58

MONOLITHIC FUEL FABRICATION PROCESS DEVELOPMENT AT THE IDAHO NATIONAL LABORATORY  

SciTech Connect

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

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

2008-10-01T23:59:59.000Z

59

Comments on Americium Volatilization during Fuel Fabrication for Fast Reactors  

SciTech Connect

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

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

2008-01-01T23:59:59.000Z

60

MONOLITHIC FUEL FABRICATION PROCESS DEVELOPMENT AT THE IDAHO NATIONAL LABORATORY_  

SciTech Connect

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).

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

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


61

Coated U(Mo) Fuel: As-Fabricated Microstructures  

SciTech Connect

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.

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

2014-04-01T23:59:59.000Z

62

Comet whole-core solution to a stylized 3-dimensional pressurized water reactor benchmark problem with UO{sub 2}and MOX fuel  

SciTech Connect

A stylized pressurized water reactor (PWR) benchmark problem with UO{sub 2} and MOX fuel was used to test the accuracy and efficiency of the coarse mesh radiation transport (COMET) code. The benchmark problem contains 125 fuel assemblies and 44,000 fuel pins. The COMET code was used to compute the core eigenvalue and assembly and pin power distributions for three core configurations. In these calculations, a set of tensor products of orthogonal polynomials were used to expand the neutron angular phase space distribution on the interfaces between coarse meshes. The COMET calculations were compared with the Monte Carlo code MCNP reference solutions using a recently published an 8-group material cross section library. The comparison showed both the core eigenvalues and assembly and pin power distributions predicated by COMET agree very well with the MCNP reference solution if the orders of the angular flux expansion in the two spatial variables and the polar and azimuth angles on the mesh boundaries are 4, 4, 2 and 2. The mean and maximum differences in the pin fission density distribution ranged from 0.28%-0.44% and 3.0%-5.5%, all within 3-sigma uncertainty of the MCNP solution. These comparisons indicate that COMET can achieve accuracy comparable to Monte Carlo. It was also found that COMET's computational speed is 450 times faster than MCNP. (authors)

Zhang, D.; Rahnema, F. [Georgia Inst. of Technology, 770 State Street, Atlanta, GA 30332-0745 (United States)

2012-07-01T23:59:59.000Z

63

Fabrication and Characterization of Fully Ceramic Microencapsulated Fuels  

SciTech Connect

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

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

2012-01-01T23:59:59.000Z

64

FABRICATION OF URANIUM OXYCARBIDE KERNELS AND COMPACTS FOR HTR FUEL  

SciTech Connect

As part of the program to demonstrate tristructural isotropic (TRISO)-coated fuel for the Next Generation Nuclear Plant (NGNP), Advanced Gas Reactor (AGR) fuel is being irradiation tested in the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL). This testing has led to improved kernel fabrication techniques, the formation of TRISO fuel particles, and upgrades to the overcoating, compaction, and heat treatment processes. Combined, these improvements provide a fuel manufacturing process that meets the stringent requirements associated with testing in the AGR experimentation program. Researchers at Idaho National Laboratory (INL) are working in conjunction with a team from Babcock and Wilcox (B&W) and Oak Ridge National Laboratory (ORNL) to (a) improve the quality of uranium oxycarbide (UCO) fuel kernels, (b) deposit TRISO layers to produce a fuel that meets or exceeds the standard developed by German researches in the 1980s, and (c) develop a process to overcoat TRISO particles with the same matrix material, but applies it with water using equipment previously and successfully employed in the pharmaceutical industry. A primary goal of this work is to simplify the process, making it more robust and repeatable while relying less on operator technique than prior overcoating efforts. A secondary goal is to improve first-pass yields to greater than 95% through the use of established technology and equipment. In the first test, called “AGR-1,” graphite compacts containing approximately 300,000 coated particles were irradiated from December 2006 to November 2009. The AGR-1 fuel was designed to closely replicate many of the properties of German TRISO-coated particles, thought to be important for good fuel performance. No release of gaseous fission product, indicative of particle coating failure, was detected in the nearly 3-year irradiation to a peak burn up of 19.6% at a time-average temperature of 1038–1121°C. Before fabricating AGR-2 fuel, each fabrication process was improved and changed. Changes to the kernel fabrication process included replacing the carbon black powder feed with a surface-modified carbon slurry and shortening the sintering schedule. AGR-2 TRISO particles were produced in a 6-inch diameter coater using a charge size about 21-times that of the 2-inch diameter coater used to coat AGR-1 particles. The compacting process was changed to increase matrix density and throughput by increasing the temperature and pressure of pressing and using a different type of press. AGR-2 fuel began irradiation in the ATR in late spring 2010.

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

2012-10-01T23:59:59.000Z

65

Calibration parameters from Monte Carlo simulations for neutron coincidence assay of MOX (mixed oxide) fuel elements: A substitute for standards  

SciTech Connect

Results from application of a calculational model for the two- parameter (singles and doubles) passive neutron coincidence assay of finished Fast Breeder Reactor (FBR) subassemblies are compared with calibration measurements. Two assay instruments are considered; the Universal Fast Breeder Reactor Subassembly Counter (UFBC) and the Capsule Counter installed at the Japanese Plutonium Fuel Production Facility (PFPF). In the case of US Fast Flux Test Facility (FFTF) fuel, the absolute ratio of calculations to measurements for the multiplication-corrected coincidence calibration constant is +1.1 /+-/ 1.0% (average of four subassemblies) for the UFBC and /minus/1.3 /+-/ 0.6% (average of five subassemblies) for the Capsule Counter. For initial measurements of Japanese fuel in the Capsule Counter, the absolute ratio is /minus/1.0 /+-/ 0.7% for three JOYO subassemblies and +0.8 /+-/ 0.7% for one MONJU subassembly. Calculations of relative effects such as the change in coincidence response from, for example, subassembly can thickness of U enrichment are more accurate (better than 0.5%) than absolute calibration parameters. This very good accuracy offers more effective and less costly inspector verification of finished FBR fuel elements by reducing reliance on physical standards to expand the cross-calibration databases. 11 refs., 8 figs., 5 tabs.

Stewart, J.E.; Ferran, R.R.; Simmonds, S.M.; Menlove, H.O.

1989-01-01T23:59:59.000Z

66

FUEL & TARGET FABRICATION Aiken County, South Carolina  

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

& TARGET FABRICATION & TARGET FABRICATION Aiken County, South Carolina 300/M AREA 300/M AREA SAVANNAH RIVER SITE COLD WAR HISTORIC PROPERTY DOCUMENTATION ii ABSTRACT This documentation was prepared in accordance with a Memorandum of Agreement (MOA) signed by the Department of Energy-Savannah River (DOE-SR) and the South Carolina Historic Preservation Office (SHPO) dated February 27, 2003, as well as the Consolidated MOA of August 2004. The MOA stipulated that a thematic study and photographic documentation be produced that told the story of 300/M Area's genesis, its operational history, and its closure. New South Associates prepared the narrative and Westinghouse Savannah River Company (WSRC) completed the photographic documentation. M Area is the site of Savannah River Plant's fuel and target fabrication facilities operated from 1955

67

Fabrication of small-orifice fuel injectors for diesel engines.  

SciTech Connect

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

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

2005-04-08T23:59:59.000Z

68

Fuel cell collector plate and method of fabrication  

DOE Patents (OSTI)

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.

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

69

Remote-controlled NDA (nondestructive assay) systems for feed and product storage at an automated MOX (mixed oxide) facility  

SciTech Connect

Nondestructive assay (NDA) systems have been developed for use in an automated mixed oxide (MOX) fabrication facility. Unique features have been developed for the NDA systems to accommodate robotic sample handling and remote operation. In addition, the systems have been designed to obtain International Atomic Energy Agency inspection data without the need for an inspector at the facility at the time of the measurements. The equipment is being designed to operate continuously in an unattended mode with data storage for periods of up to one month. The two systems described in this paper include a canister counter for the assay of MOX powder at the input to the facility and a capsule counter for the assay of complete liquid-metal fast breeder reactor fuel assemblies at the output of the plant. The design, performance characteristics, and authentication of the two systems will be described. The data related to reliability, precision, and stability will be presented. 5 refs., 10 figs., 4 tabs.

Menlove, H.O.; Augustson, R.H.; Ohtani, T.; Seya, M.; Takahashi, S.; Abedin-Zadeh, R.; Hassan, B.; Napoli, S.

1989-01-01T23:59:59.000Z

70

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

E-Print Network (OSTI)

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

Tharp, Ronald S

2005-01-01T23:59:59.000Z

71

Fabrication of solid oxide fuel cell by electrochemical vapor deposition  

DOE Patents (OSTI)

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

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

1989-01-01T23:59:59.000Z

72

Environmental assessment for radioisotope heat source fuel processing and fabrication  

SciTech Connect

DOE has prepared an Environmental Assessment (EA) for radioisotope heat source fuel processing and fabrication involving existing facilities at the Savannah River Site (SRS) near Aiken, South Carolina and the Los Alamos National Laboratory (LANL) near Los Alamos, New Mexico. The proposed action is needed to provide Radioisotope Thermoelectric Generators (RTG) to support the National Aeronautics and Space Administration's (NASA) CRAF and Cassini Missions. Based on the analysis in the EA, DOE has determined that the proposed action does not constitute a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) of 1969. Therefore, an Environmental Impact Statement is not required. 30 refs., 5 figs.

Not Available

1991-07-01T23:59:59.000Z

73

Fabrication of solid oxide fuel cell by electrochemical vapor deposition  

DOE Patents (OSTI)

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

Riley, B.; Szreders, B.E.

1988-04-26T23:59:59.000Z

74

New MOX Conservation Garden Features Federally Endangered Plant  

E-Print Network (OSTI)

is located, has been certified as a Leadership in Energy and Environmental Design (LEED) Gold buildingNew MOX Conservation Garden Features Federally Endangered Plant Linda Lee, botanist for the Savannah River Ecology Lab (from left), Clay Ramsey , federal project director of the Mixed Oxide Fuel

Georgia, University of

75

PRIVACY IMPACT ASSESSMENT: Shaw Areva MOX Services, LLC MOX  

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

. . ,-) ')7 73?Â¥i5": )~"'f"YC-:;'~dt?f(~"'f9'FrrZ , . PRIVACY IMPACT ASSESSMENT: Shaw Areva MOX Services, LLC MOX Services Unclassified Information System Template - January 30, 2009, Version 2 Department of Energy Privacy Impact Assessment (pIA) Guidance is provided in the template. See DOE Order 206.1, Department of Energy Privacy Program, Appendix A, Privacy Impact Assessments, for requirements and additional guidance for conducting a PIA: hltp:llwww.directives.doe.gov/pdfs/doe/doetextlneword/206/o2061.pdf Please complete electronically: no hand-written submissions will be accepted. (803) 819-22700 Dstlnson@moxprolect.com Dave Stinson, President and Chief Executive Officer, Shaw AREVA MOX Services, LLC NNSA Shaw AREVA MOX Services Savannah River Site, Aiken SC .. .. . ": .' . ' .... .- ...: ......

76

Fabrication of microfluidic devices with application to membraneless fuel cells.  

E-Print Network (OSTI)

??This thesis is part of an ongoing collaborative research project focused on the development of microstructured enzymatic fuel cells. Both enzymatic fuel cells and co-laminar… (more)

McKechnie, Jon

2009-01-01T23:59:59.000Z

77

Assured Fuel Supply: Potential Conversion and Fabrication Bottlenecks  

E-Print Network (OSTI)

to nuclear fuel. These efforts include: · The Putin Initiative to create a multinational enrichment center

78

Development of metallic substrate supported planar solid oxide fuel cells fabricated by atmospheric plasma spraying  

Science Journals Connector (OSTI)

A planar solid oxide fuel cell (SOFC) consisting of a cell supported with a porous metallic substrate and a metallic separator has been developed. In the fabrication of the cell, anodes and electrolytes were form...

Shunji Takenoiri; Naruaki Kadokawa; Kazuo Koseki

2000-09-01T23:59:59.000Z

79

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

SciTech Connect

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

Schock, Alfred

1995-08-01T23:59:59.000Z

80

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

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

Flexible Manufacturing Capability for the Mixed Fuel Fabrication Facility (MFFF) Flexible Manufacturing Capability for the Mixed Fuel Fabrication Facility (MFFF) The Department of Energy (DOE) is preparing the Surplus Plutonium Disposition Supplemental Environmental Impact Statement (SPD SEIS), DOE/EIS-0283-S2. DOE is evaluating, among many other things, the environmental impacts of any design and operations changes to the MFFF, which is under construction at the Savannah River Site near Aiken, South Carolina. DOE

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


81

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

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

Flexible Manufacturing Capability for the Mixed Fuel Fabrication Facility (MFFF) Flexible Manufacturing Capability for the Mixed Fuel Fabrication Facility (MFFF) The Department of Energy (DOE) is preparing the Surplus Plutonium Disposition Supplemental Environmental Impact Statement (SPD SEIS), DOE/EIS-0283-S2. DOE is evaluating, among many other things, the environmental impacts of any design and operations changes to the MFFF, which is under construction at the Savannah River Site near Aiken, South Carolina. DOE

82

Assessment of uranium-free nitride fuels for spent fuel transmutation in fast reactor systems  

E-Print Network (OSTI)

. ....................................................................................... 18 Fig. 4. Standard PWR ¼ core model with fresh, once- and twice-burned fuel, and the location of MOX fuel assemblies with respect to original layout, 32% MOX loading................................................................................................................ 21 Fig. 5. Control rod locations......................................................................................... 21 Fig. 6. Net change of U, Pu and Am for PWR and 1/3 MOX fueled whole cores, 360 day burn...

Szakaly, Frank Joseph

2004-09-30T23:59:59.000Z

83

Economic Analysis on Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors - I: DUPIC Fuel Fabrication Cost  

SciTech Connect

A preliminary conceptual design of a Direct Use of spent Pressurized water reactor (PWR) fuel In Canada deuterium uranium (CANDU) reactors (DUPIC) fuel fabrication plant was studied, which annually converts spent PWR fuel of 400 tonnes heavy element (HE) into CANDU fuel. The capital and operating costs were estimated from the viewpoint of conceptual design. Assuming that the annual discount rate is 5% during the construction (5 yr) and operation period (40 yr) and contingency is 25% of the capital cost, the levelized unit cost (LUC) of DUPIC fuel fabrication was estimated to be 616 $/kg HE, which is mostly governed by annual operation and maintenance costs that correspond to 63% of LUC. Among the operation and maintenance cost components being considered, the waste disposal cost has the dominant effect on LUC ({approx}49%). From sensitivity analyses of production capacity, discount rate, and contingency, it was found that the production capacity of the plant is the major parameter that affects the LUC.

Choi, Hangbok; Ko, Won Il; Yang, Myung Seung [Korea Atomic Energy Research Institute (Korea, Republic of)

2001-05-15T23:59:59.000Z

84

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

85

Fabrication of Micro-Orifices for Diesel Fuel Injectors  

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

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

86

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

SciTech Connect

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.

Karen L. Shropshire

2008-04-01T23:59:59.000Z

87

The Role of Friction Stir Welding in Nuclear Fuel Plate Fabrication  

SciTech Connect

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

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

2009-02-01T23:59:59.000Z

88

Melting temperatures of the ZrO{sub 2}-MOX system  

SciTech Connect

Severe accidents occurred at the Fukushima Daiichi Nuclear Power Plant Units 1-3 on March 11, 2011. MOX fuels were loaded in the Unit 3. For the thermal analysis of the severe accident, melting temperature and phase state of MOX corium were investigated. The simulated coriums were prepared from 4%Pu-containing MOX, 8%Pu-containing MOX and ZrO{sub 2}. Then X-ray diffraction, density and melting temperature measurements were carried out as a function of zirconium and plutonium contents. The cubic phase was observed in the 25%Zr-containing corium and the tetragonal phase was observed in the 50% and 75%Zr-containing coria. The lattice parameter and density monotonically changed with Pu content. Melting temperature increased with increasing Pu content; melting temperature were estimated to be 2932 K for 4%Pu MOX corium and 3012 K for 8%Pu MOX corium in the 25%ZrO{sub 2}-MOX system. The lowest melting temperature was observed for 50%Zr-containing corium. (authors)

Uchida, T.; Hirooka, S.; Kato, M.; Morimoto, K. [Japan Atomic Energy Agency, 4-33, Muramatsu, Tokai-mura, Naka-gun, Ibaraki 319-1194 (Japan); Sugata, H.; Shibata, K.; Sato, D. [Inspection Development Company, 4-33, Muramatsu, Tokai-mura, Naka-gun, Ibaraki 319-1194 (Japan)

2013-07-01T23:59:59.000Z

89

Implications of Plutonium isotopic separation on closed fuel cycles and repository design  

SciTech Connect

Advances in laser enrichment may enable relatively low-cost plutonium isotopic separation. This would have large impacts on LWR closed fuel cycles and waste management. If Pu-240 is removed before recycling plutonium as mixed oxide (MOX) fuel, it would dramatically reduce the buildup of higher plutonium isotopes, Americium, and Curium. Pu-240 is a fertile material and thus can be replaced by U-238. Eliminating the higher plutonium isotopes in MOX fuel increases the Doppler feedback, simplifies reactor control, and allows infinite recycle of MOX plutonium in LWRs. Eliminating fertile Pu-240 and Pu-242 reduces the plutonium content in MOX fuel and simplifies fabrication. Reducing production of Pu-241 reduces production of Am-241 - the primary heat generator in spent nuclear fuels after several decades. Reducing heat generating Am-241 would reduce repository cost and waste toxicity. Avoiding Am- 241 avoids its decay product Np-237, a nuclide that partly controls long-term oxidizing repository performance. Most of these benefits also apply to LWR plutonium recycled into fast reactors. There are benefits for plutonium isotopic separation in fast reactor fuel cycles (particularly removal of Pu-242) but the benefits are less. (author)

Forsberg, C. [Massachusetts Institute of Technology, 77 Massachusetts Ave. Cambridge, MA 20129 (United States)

2013-07-01T23:59:59.000Z

90

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

SciTech Connect

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.

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

1980-10-11T23:59:59.000Z

91

Analysis of measures to enhance safeguards, and proliferation resistance in thorium based fuel fabrication plants  

Science Journals Connector (OSTI)

Abstract The presence of high energy gamma rays emitted by U232, which is always associated in ppm quantities with reprocessed U233, lends robustness or physical protection to the thorium fuel cycle. India is currently setting up a thorium based fuel cycle for its Advanced Heavy Water Reactor (AHWR). Identification and deployment of suitable extrinsic measures for fuel fabrication facilities would help in strengthening overall proliferation resistance. The extrinsic measures proposed in this paper include several measures which have been identified for the first time. A quantitative assessment of the contribution of these measures to overall safeguardability of the fuel fabrication plant has been carried out. Multi Attribute Utility Analysis (MAUA) has been used to evaluate the Proliferation Resistance (PR) value for two hypothetical facilities, one employing none of these measures and the other employing some or all of these measures. The analysis is based on the expert opinion of designers, operators, quality control managers and implementers of safeguards in fuel cycle facilities. Sensitivity analysis for all the proposed measures has also been carried out to study the effect of the influence of individual measures on the overall proliferation resistance of the fuel fabrication plant. The analysis ranks various safeguards measures based on the importance factor of a measure which is defined as the ratio of overall proliferation resistance with and without the measure. Important measures identified based on ranking are near real time monitoring, automation, safeguards-by-design, dynamic nuclear material accounting, and plant imaging.

Suresh Gangotra; R.B. Grover; K.L. Ramakumar

2014-01-01T23:59:59.000Z

92

Method of fabricating a monolithic solid oxide fuel cell  

DOE Patents (OSTI)

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

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

1994-01-01T23:59:59.000Z

93

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

E-Print Network (OSTI)

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

Zhao, Tianshou

94

Automated catalyst processing for cloud electrode fabrication for fuel cells  

DOE Patents (OSTI)

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

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

1980-01-01T23:59:59.000Z

95

Conductivity fuel cell collector plate and method of fabrication  

DOE Patents (OSTI)

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

Braun, James C. (Juno Beach, FL)

2002-01-01T23:59:59.000Z

96

Nuclear Criticality Control and Safety of Plutonium-Uranium Fuel Mixtures Outside Reactors  

SciTech Connect

The ANSI/ANS 8.12 standard was first approved in July 1978. At that time, this edition was applicable to operations with plutonium-uranium oxide (MOX) fuel mixtures outside reactors and was limited to subcritical limits for homogeneous systems. The next major revision, ANSI/ANS-8.12-1987, included the addition of subcritical limits for heterogeneous systems. The standard was subsequently reaffirmed in February 1993. During late 1990s, substantial work was done by the ANS 8.12 Standard Working Group to re-examine the technical data presented in the standard using the latest codes and cross section sets. Calculations performed showed good agreement with the values published in the standard. This effort resulted in the reaffirmation of the standard in March 2002. The standard is currently in a maintenance mode. After 2002, activities included discussions to determine the future direction of the standard and to follow the MOX standard development by the International Standard Organization (ISO). In 2007, the Working Group decided to revise the standard to extend the areas of applicability by providing a wider range of subcritical data. The intent is to cover a wider domain of MOX fuel fabrication and operations. It was also decided to follow the ISO MOX standard specifications (related to MOX density and isotopics) and develop a new set of subcritical limits for homogeneous systems. This has resulted in the submittal (and subsequent approval) of the project initiation notification system form (PINS) in 2007.

Biswas, D; Mennerdahl, D

2008-06-23T23:59:59.000Z

97

Design, fabrication and testing of a liquid hydrogen fuel tank for a long duration aircraft  

Science Journals Connector (OSTI)

Liquid hydrogen has distinct advantages as an aircraft fuel. These include a specific heat of combustion 2.8 times greater than gasoline or jet fuel and zero carbon emissions. It can be utilized by fuel cells turbine engines and internal combustion engines. The high heat of combustion is particularly important in the design of long endurance aircraft with liquid hydrogen enabling cruise endurance of several days. However the mass advantage of the liquid hydrogen fuel will result in a mass advantage for the fuel system only if the liquid hydrogen tank and insulation mass is a small fraction of the hydrogen mass. The challenge is producing a tank that meets the mass requirement while insulating the cryogenic liquid hydrogen well enough to prevent excessive heat leak and boil off. In this paper we report on the design fabrication and testing of a liquid hydrogen fuel tank for a prototype high altitude long endurance (HALE) demonstration aircraft. Design options on tank geometry tank wall material and insulation systems are discussed. The final design is an aluminum sphere insulated with spray on foam insulation (SOFI). Several steps and organizations were involved in the tank fabrication and test. The tank was cold shocked helium leak checked and proof pressure tested. The overall thermal performance was verified with a boil off test using liquid hydrogen.

Gary L. Mills; Brian Buchholtz; Al Olsen

2012-01-01T23:59:59.000Z

98

A Blueprint for GNEP Advanced Burner Reactor Startup Fuel Fabrication Facility  

SciTech Connect

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

S. Khericha

2010-12-01T23:59:59.000Z

99

Spark Plasma Sintering of Fuel Cermets for Nuclear Reactor Applications  

SciTech Connect

The feasibility of the fabrication of tungsten based nuclear fuel cermets via Spark Plasma Sintering (SPS) is investigated in this work. CeO2 is used to simulate fuel loadings of UO2 or Mixed-Oxide (MOX) fuels within tungsten-based cermets due to the similar properties of these materials. This study shows that after a short time sintering, greater than 90 % density can be achieved, which is suitable to possess good strength as well as the ability to contain fission products. The mechanical properties and the densities of the samples are also investigated as functions of the applied pressures during the sintering.

Yang Zhong; Robert C. O'Brien; Steven D. Howe; Nathan D. Jerred; Kristopher Schwinn; Laura Sudderth; Joshua Hundley

2011-11-01T23:59:59.000Z

100

Accident safety analysis for 300 Area N Reactor Fuel Fabrication and Storage Facility  

SciTech Connect

The purpose of the accident safety analysis is to identify and analyze a range of credible events, their cause and consequences, and to provide technical justification for the conclusion that uranium billets, fuel assemblies, uranium scrap, and chips and fines drums can be safely stored in the 300 Area N Reactor Fuel Fabrication and Storage Facility, the contaminated equipment, High-Efficiency Air Particulate filters, ductwork, stacks, sewers and sumps can be cleaned (decontaminated) and/or removed, the new concretion process in the 304 Building will be able to operate, without undue risk to the public, employees, or the environment, and limited fuel handling and packaging associated with removal of stored uranium is acceptable.

Johnson, D.J.; Brehm, J.R.

1994-01-01T23:59:59.000Z

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


101

The design, construction, and testing of a nuclear fuel rod thermal simulation system to study gallium/Zircaloy interactions  

E-Print Network (OSTI)

friends for their unending support and patience during this project. Thank you so much! NOMENCLATURE Abbreviations and Acronyms WGPu- weapons grade plutonium DOE- Department of Energy MOX- mixed oxide fuel WG MOX- weapons grade MOX fuel LWR- light... to be employed were immobilization and fissioning the WGPu as mixed oxide (MOX) fuel in commercial power reactors. Both approaches have many advantages and disadvantages and are currently being studied by scientists and engineers all over the world. The use...

Allison, Christopher Curtis

2012-06-07T23:59:59.000Z

102

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

SciTech Connect

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

Schock, Alfred

1994-06-01T23:59:59.000Z

103

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

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

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

2002-06-01T23:59:59.000Z

104

PLUTONIUM LOADING CAPACITY OF REILLEX HPQ ANION EXCHANGE COLUMN - AFS-2 PLUTONIUM FLOWSHEET FOR MOX  

SciTech Connect

Radioactive plutonium (Pu) anion exchange column experiments using scaled HB-Line designs were performed to investigate the dependence of column loading performance on the feed composition in the H-Canyon dissolution process for plutonium oxide (PuO{sub 2}) product shipped to the Mixed Oxide (MOX) Fuel Fabrication Facility (MFFF). These loading experiments show that a representative feed solution containing {approx}5 g Pu/L can be loaded onto Reillex{trademark} HPQ resin from solutions containing 8 M total nitrate and 0.1 M KF provided that the F is complexed with Al to an [Al]/[F] molar ratio range of 1.5-2.0. Lower concentrations of total nitrate and [Al]/[F] molar ratios may still have acceptable performance but were not tested in this study. Loading and washing Pu losses should be relatively low (<1%) for resin loading of up to 60 g Pu/L. Loading above 60 g Pu/L resin is possible, but Pu wash losses will increase such that 10-20% of the additional Pu fed may not be retained by the resin as the resin loading approaches 80 g Pu/L resin.

Kyser, E.; King, W.; O'Rourke, P.

2012-07-26T23:59:59.000Z

105

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

SciTech Connect

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

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

1986-02-21T23:59:59.000Z

106

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

SciTech Connect

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

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

1997-11-01T23:59:59.000Z

107

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

SciTech Connect

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

Not Available

1993-09-20T23:59:59.000Z

108

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

SciTech Connect

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.

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

109

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

SciTech Connect

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

Douglas W. Marshall

2014-10-01T23:59:59.000Z

110

HB-LINE ANION EXCHANGE PURIFICATION OF AFS-2 PLUTONIUM FOR MOX  

SciTech Connect

Non-radioactive cerium (Ce) and radioactive plutonium (Pu) anion exchange column experiments using scaled HB-Line designs were performed to investigate the feasibility of using either gadolinium nitrate (Gd) or boric acid (B as H{sub 3}BO{sub 3}) as a neutron poison in the H-Canyon dissolution process. Expected typical concentrations of probable impurities were tested and the removal of these impurities by a decontamination wash was measured. Impurity concentrations are compared to two specifications - designated as Column A or Column B (most restrictive) - proposed for plutonium oxide (PuO{sub 2}) product shipped to the Mixed Oxide (MOX) Fuel Fabrication Facility (MFFF). Use of Gd as a neutron poison requires a larger volume of wash for the proposed Column A specification. Since boron (B) has a higher proposed specification and is more easily removed by washing, it appears to be the better candidate for use in the H-Canyon dissolution process. Some difficulty was observed in achieving the Column A specification due to the limited effectiveness that the wash step has in removing the residual B after ~4 BV's wash. However a combination of the experimental 10 BV's wash results and a calculated DF from the oxalate precipitation process yields an overall DF sufficient to meet the Column A specification. For those impurities (other than B) not removed by 10 BV's of wash, the impurity is either not expected to be present in the feedstock or process, or recommendations have been provided for improvement in the analytical detection/method or validation of calculated results. In summary, boron is recommended as the appropriate neutron poison for H-Canyon dissolution and impurities are expected to meet the Column A specification limits for oxide production in HB-Line.

Kyser, E. A.; King, W. D.

2012-07-31T23:59:59.000Z

111

HB-LINE ANION EXCHANGE PURIFICATION OF AFS-2 PLUTONIUM FOR MOX  

SciTech Connect

Non-radioactive cerium (Ce) and radioactive plutonium (Pu) anion exchange column experiments using scaled HB-Line designs were performed to investigate the feasibility of using either gadolinium nitrate (Gd) or boric acid (B as H{sub 3}BO{sub 3}) as a neutron poison in the H-Canyon dissolution process. Expected typical concentrations of probable impurities were tested and the removal of these impurities by a decontamination wash was measured. Impurity concentrations are compared to two specifications - designated as Column A or Column B (most restrictive) - proposed for plutonium oxide (PuO{sub 2}) product shipped to the Mixed Oxide (MOX) Fuel Fabrication Facility (MFFF). Use of Gd as a neutron poison requires a larger volume of wash for the proposed Column A specification. Since boron (B) has a higher proposed specification and is more easily removed by washing, it appears to be the better candidate for use in the H-Canyon dissolution process. Some difficulty was observed in achieving the Column A specification due to the limited effectiveness that the wash step has in removing the residual B after {approx}4 BV's wash. However a combination of the experimental 10 BV's wash results and a calculated DF from the oxalate precipitation process yields an overall DF sufficient to meet the Column A specification. For those impurities (other than B) not removed by 10 BV's of wash, the impurity is either not expected to be present in the feedstock or process, or recommendations have been provided for improvement in the analytical detection/method or validation of calculated results. In summary, boron is recommended as the appropriate neutron poison for H-Canyon dissolution and impurities are expected to meet the Column A specification limits for oxide production in HB-Line.

Kyser, E.; King, W.

2012-04-25T23:59:59.000Z

112

Update on uranium-molybdenum fuel foil fabrication development activities at the Y-12 National Security Complex in 2007  

SciTech Connect

In support of the RERTR Program, efforts are underway at Y-12 to develop and validate a production oriented, monolithic uranium molybdenum (U-Mo) foil fabrication process adaptable for potential implementation in a manufacturing environment. These efforts include providing full-scale prototype depleted and enriched U-Mo foils in support of fuel qualification testing. The work has three areas of focus; develop and demonstrate a feasible foil fabrication process utilizing depleted uranium-molybdenum (DU-Mo) source material, transition these production techniques to enriched uranium (EU-Mo) source material, and evaluate full-scale implementation of the developed production techniques. In 2006, Y-12 demonstrated successful fabrication of full-size DU-10Mo foils. In 2007, Y-12 activities were expanded to include continued DU-Mo foil fabrication with a focus on process refinement, source material impurity effects (specifically carbon), and the feasibility of physical vapor deposition (PVD) on DU-10Mo mini-foils. FY2007 activities also included a transition to EU-Mo and fabrication of full-size enriched foils. The purpose of this report is to update the RERTR audience on Y-12 efforts in 2007 that support the overall RERTR Program goals. (author)

DeMint, Amy; Gooch, Jack [Technology Development, Y-12 National Security Complex, Oak Ridge, TN 37830 (United States); Dunavant, Randy J.; Andes, Trent C. [National Security Programs, Y-12 National Security Complex, Oak Ridge, TN 37830 (United States)

2008-07-15T23:59:59.000Z

113

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

SciTech Connect

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

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

2009-04-30T23:59:59.000Z

114

LOS ALAMOS, New Mexico, October 7, 2011-Los Alamos National Laboratory  

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

at the MOX facility in South Carolina, the plutonium oxide from LANL will be blended with depleted uranium, fabricated into MOX fuel, and irradiated in domestic nuclear...

115

Nuclear fuels technologies fiscal year 1998 research and development test plan  

SciTech Connect

A number of research and development (R and D) activities are planned at Los Alamos National Laboratory (LANL) in FY98 in support of the Department of Energy Office of Fissile Materials Disposition (DOE-MD). During the past few years, the ability to fabricate mixed oxide (MOX) nuclear fuel using surplus-weapons plutonium has been researched, and various experiments have been performed. This research effort will be continued in FY98 to support further development of the technology required for MOX fuel fabrication for reactor-based plutonium disposition. R and D activities for FY98 have been divided into four major areas: (1) feed qualification/supply, (2) fuel fabrication development, (3) analytical methods development, and (4) gallium removal. Feed qualification and supply activities encompass those associated with the production of both PuO{sub 2} and UO{sub 2} feed materials. Fuel fabrication development efforts include studies with a new UO{sub 2} feed material, alternate sources of PuO{sub 2}, and determining the effects of gallium on the sintering process. The intent of analytical methods development is to upgrade and improve several analytical measurement techniques in support of other R and D and test fuel fabrication tasks. Finally, the purpose of the gallium removal system activity is to develop and integrate a gallium removal system into the Pit Disassembly and Conversion Facility (PDCF) design and the Phase 2 Advanced Recovery and Integrated Extraction System (ARIES) demonstration line. These four activities will be coordinated and integrated appropriately so that they benefit the Fissile Materials Disposition Program. This plan describes the activities that will occur in FY98 and presents the schedule and milestones for these activities.

Alberstein, D.; Blair, H.T.; Buksa, J.J. [and others

1998-06-01T23:59:59.000Z

116

NNSA Holds Groundbreaking at MOX Facility | National Nuclear Security  

National Nuclear Security Administration (NNSA)

Groundbreaking at MOX Facility | National Nuclear Security Groundbreaking at MOX Facility | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Our History > NNSA Timeline > NNSA Holds Groundbreaking at MOX Facility NNSA Holds Groundbreaking at MOX Facility October 14, 2005 Aiken, SC NNSA Holds Groundbreaking at MOX Facility

117

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

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

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

118

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

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

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

119

Fabrication of Yttria stabilized zirconia thin films on poroussubstrates for fuel cell applications  

SciTech Connect

A process for the deposition of yttria stabilized zirconia (YSZ) films, on porous substrates, has been developed. These films have possible applications as electrolyte membranes in fuel cells. The films were deposited from colloidal suspensions through the vacuum infiltration technique. Films were deposited on both fully sintered and partially sintered substrates. A critical cracking thickness for the films was identified and strategies are presented to overcome this barrier. Green film density was also examined, and a method for improving green density by changing suspension pH and surfactant was developed. A dependence of film density on film thickness was observed, and materials interactions are suggested as a possible cause. Non-shorted YSZ films were obtained on co-fired substrates, and a cathode supported solid oxide fuel cell was constructed and characterized.

Leming, Andres

2003-06-16T23:59:59.000Z

120

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

DOE Patents (OSTI)

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.

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

1985-01-01T23:59:59.000Z

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


121

RADIATION DOSE ASPECTS IN THE HANDLING OF EMERGING NUCLEAR FUELS  

Science Journals Connector (OSTI)

......Radiol. Prot. (2008) 28:161. 15 NUREG. Standard review plan for the review of an application for a Mixed Oxide (MOX) fuel...facilities specific safety guide. (2010) IAEA Safety Standards Series No. SSG-6, International Atomic Energy......

G. Nicolaou

2014-02-01T23:59:59.000Z

122

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

SciTech Connect

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

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

2011-02-01T23:59:59.000Z

123

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

E-Print Network (OSTI)

Fabrication 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-CGO cathode 1. Introduction Single-chamber solid oxide fuel cells (SC-SOFCs) have received many attentions

Paris-Sud XI, Université de

124

Compared performances of ENDF/B-VI and JEF-2.2 for MOX core physics  

SciTech Connect

The United States is currently evaluating the use of mixed-oxide (MOX) fuel in commercial light water reactors for reducing weapons-grade Pu stockpiles. The design and licensing processes will require that the validity of the nuclear data libraries and codes used in the effort be demonstrated. Unfortunately, there are only a very limited number of relatively old and nonrepresentative integral experiments freely available to the US programs. This lack of adequate experimental data can be partially remediated by comparing the results of well-validated European codes with the results of candidate US codes. The authors have compared the performances of the JEF-2.2 and ENDF/B-VI.4 libraries for a series of benchmarks for k{sub eff}, void worth, and pin power distributions. Note that JEF-2.2 has been extensively validated for MOX applications. To obtain systematic comparisons between JEF-2.2 and ENDF/B-VI results, the two libraries were implemented with the same processing code options in two independent code systems: (1) VIM, a continuous-energy Monte Carlo code developed at Argonne National Laboratory, with its own processing codes independent of NJOY; and (2) DRAGON, a two-dimensional lattice code developed at Ecole Polytechnique de Montreal. A standard 172-energy-group structure was used in the NJOY processing code.

Finck, P.J.; Laurin-Kovitz, K.; Palmiotti, G.; Stenberg, C. [Argonne National Lab., IL (United States)

1998-12-31T23:59:59.000Z

125

Compared performances of ENDF/B-VI and JEF-2.2 for MOX core physics.  

SciTech Connect

The US is currently evaluating the use of MOX fuel in commercial LWR's for reducing weapons grade Pu stockpiles. The design and licensing processes will require that the validity of the nuclear data libraries and codes used in the effort be demonstrated. Unfortunately, there are only a very limited number of relatively old and non representative integral experiments' freely available to the US programs. This lack of adequate experimental data can be partially remediated by comparing the results of well validated European codes with the results of candidate US codes. The demonstration can actually be divided in two components: a code to code (Monte Carlo) comparison can easily demonstrate the validity and limits of the proposed algorithms; and the performances of nuclear data libraries should be compared, major trends should be observed, and their origins should be explained in terms of differences in evaluated nuclear data; In this paper, we have compared the performances of the JEF-2.2 and ENDF/B-VI.4 libraries for a series of benchmarks for k{sub eff}, void worth, and pin power distributions. Note that JEF-2.2 has been extensively validated for MOX applications.

Finck, P. J.

1998-07-08T23:59:59.000Z

126

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

SciTech Connect

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

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

2006-07-01T23:59:59.000Z

127

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

SciTech Connect

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

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

1982-01-01T23:59:59.000Z

128

Use of curium spontaneous fission neutrons for safeguardability of remotely-handled nuclear facilities: Fuel fabrication in pyroprocessing  

Science Journals Connector (OSTI)

Abstract Advanced nuclear reactor systems (NESs) will utilize remotely-handled facilities in which batch-type processing will occur in hot cells. There are no current formalized criteria for International Atomic Energy Agency (IAEA) safeguards for these systems. This creates new challenges to develop methodologies for demonstrating the safeguardability of these facilities. A High Reliability Safeguards (HRS) approach therefore has been proposed to enhance intrinsic proliferation resistance by establishing an envelope of adaptable functional components as part of a facility design strategy. Additionally, system assessment can be modeled concurrently with safety and physical security by a risk-informed approach. The HRS approach is currently applied to a commercial pyroprocessing facility as an example system. A scoping study is presented as the first in a series of quantitative modeling efforts to extend the HRS approach. These efforts currently focus on investigating the magnitude of neutron fluxes due to spontaneous fission of curium for commercial batch sizes and held up materials for important processes in the system. Here, the fuel fabrication process is studied. The intent of these initial studies is to learn how the intrinsic properties of materials in the pyroprocessing system will affect facility design and safeguards. The model presented in this paper is intended to be adaptable to more practical and complex scenarios in order to evaluate the safeguardability of remotely-handled nuclear facilities.

R.A. Borrelli

2013-01-01T23:59:59.000Z

129

Fuel qualification issues and strategies for reactor-based surplus plutonium disposition  

SciTech Connect

The Department of Energy (DOE) has proposed irradiation of mixed-oxide (MOX) fuel in existing commercial reactors as a disposition method for surplus plutonium from the weapons program. The burning of MOX fuel in reactors is supported by an extensive technology base; however, the infrastructure required to implement reactor-based plutonium disposition does not exist domestically. This report identifies and examines the actions required to qualify and license weapons-grade (WG) plutonium-based MOX fuels for use in domestic commercial light-water reactors (LWRs).

Cowell, B.S.; Copeland, G.L.; Moses, D.L.

1997-08-01T23:59:59.000Z

130

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

SciTech Connect

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

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

2012-09-01T23:59:59.000Z

131

High Speed, Low Cost Fabrication of Gas Diffusion Electrodes for Membrane Electrode Assemblies - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

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

8 8 DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report Emory S. De Castro BASF Fuel Cell, Inc. 39 Veronica Avenue Somerset, NJ 08873 Phone: (732) 545-5100 ext 4114 Email: Emory.DeCastro@BASF.com DOE Managers HQ: Nancy Garland Phone: (202) 586-5673 Email: Nancy.Garland@ee.doe.gov GO: Jesse Adams Phone: (720) 356-1421 Email: Jesse.Adams@go.doe.gov Contract Number: DE-EE0000384 Subcontractor: Dr. Vladimir Gurau Case Western Reserve University, Cleveland, Ohio Project Start Date: July 1, 2009 Project End Date: June 30, 2013 Fiscal Year (FY) 2012 Objectives Reduce cost in fabricating gas diffusion electrodes * through the introduction of high speed coating technology, with a focus on materials used for the high- temperature membrane electrode assemblies (MEAs)

132

Modeling of Solid Oxide Fuel Cell functionally graded electrodes and a feasibility study of fabrication techniques for functionally graded electrodes.  

E-Print Network (OSTI)

??Currently, Solid Oxide Fuel Cell (SOFC) electrodes have not been explored for optimization of graded electrodes and nonlinear functional grading. In this work, a complete… (more)

Flesner, Reuben

2009-01-01T23:59:59.000Z

133

Impact of Fission Products Impurity on the Plutonium Content of Metal- and Oxide- Fuels in Sodium Cooled Fast Reactors  

SciTech Connect

This short report presents the neutronic analysis to evaluate the impact of fission product impurity on the Pu content of Sodium-cooled Fast Reactor (SFR) metal- and oxide- fuel fabrication. The similar work has been previously done for PWR MOX fuel [1]. The analysis will be performed based on the assumption that the separation of the fission products (FP) during the reprocessing of UOX spent nuclear fuel assemblies is not perfect and that, consequently, a certain amount of FP goes into the Pu stream used to fabricate SFR fuels. Only non-gaseous FPs have been considered (see the list of 176 isotopes considered in the calculations in Appendix 1 of Reference 1). Throughout of this report, we define the mixture of Pu and FPs as PuFP. The main objective of this analysis is to quantify the increase of the Pu content of SFR fuels necessary to maintain the same average burnup at discharge independently of the amount of FP in the Pu stream, i.e. independently of the PuFP composition. The FP losses are considered element-independent, i.e., for example, 1% of FP losses mean that 1% of all non-gaseous FP leak into the Pu stream.

Hikaru Hiruta; Gilles Youinou

2013-09-01T23:59:59.000Z

134

LMFBR fuel component costs  

SciTech Connect

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

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

1981-10-29T23:59:59.000Z

135

Fuels  

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

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

136

Development of Self-Interrogation Neutron Resonance Densitometry (SINRD) to Measure the Fissile Content in Nuclear Fuel  

E-Print Network (OSTI)

the diversion of 6% of fuel pins within 3? from LWR spent LEU and MOX fuel. 3) SINRD is insensitive to the boron concentration and initial fuel enrichment and can therefore be used at multiple spent fuel storage facilities. 4) The calibration of SINRD at one...

Lafleur, Adrienne

2011-10-21T23:59:59.000Z

137

Risk analysis of shipping plutonium pits and mixed oxide fuel  

E-Print Network (OSTI)

, one possible option that has been identified for disposition of excess U.S. weapons plutonium is the transformation into mixed oxide (MOX) fuel, that then would be used as fuel in a commercial nuclear power plant. Any such process will involve...

Caldwell, Amy Baker

2012-06-07T23:59:59.000Z

138

Fabrication and electrical properties of La8.33Sb(SiO4)6O2 thick films for solid oxide fuel cells  

Science Journals Connector (OSTI)

In this study Sb-substituted La8.33Sb(SiO4)6O2 apatite thick films were fabricated by using a screen printing method and the structural and electrical properties of these materials with variation in sintering temperature for solid oxide fuel cells were investigated. With increased sintering temperatures the second phase La2SiO5 phase decreased and the specimens sintered at over 1350?°C showed typical X-ray diffraction patterns of apatite polycrystalline structure. The grain size increased and porosity decreased with increasing sintering temperatures. The thickness of all films was approximately 25–30??m. La8.33Sb(SiO4)6O2 thick films sintered at 1350?°C showed good conductivity and activation energy characteristics at 9.87?×?10?5 S cm?1and 1.24?eV respectively.

Dae-Young Kim; Sung-Gap Lee

2013-01-01T23:59:59.000Z

139

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)

proposed full test using prototypic mixed-oxide fuel (MOX) containing plutonium from converted nuclear weapons. Bayesian reliability analysis methods were used to determine the expected heater failure rate because of the expected short test duration...

O'Kelly, David Sean

2012-06-07T23:59:59.000Z

140

Radio-toxicity of spent fuel of the advanced heavy water reactor  

Science Journals Connector (OSTI)

......plutonium-thorium-uranium fuel with a...of which the inventory and rate of...types (low-enriched MOX fuel for AHWR and natural uranium fuel for PHWR...input and a highly flexible and...Radioactivity The total inventory of an average-rated......

S. Anand; K. D. S. Singh; V. K. Sharma

2010-01-01T23:59:59.000Z

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


141

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

E-Print Network (OSTI)

for the continuous (a) and dispersed (b) types [16]. 2.3 Silicon Carbide as a High Conductivity Additive Solomon et al. explored the feasibility of increasing the thermal conductivity of oxide fuels by the addition of a second, higher thermal conductivity solid... methodology used to restrict the CO or SiO gases. All processing, therefore, must take place below this temperature. Because of ! "# Table 2.3. Samples used in the thermal conductivity measurements $%&'()&*! $(+!%,-.&/! 0...

Naramore, Michael J

2010-08-03T23:59:59.000Z

142

http://srsweb2.srs.gov/InSiteApp/assets/xml/articles/574.html  

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

Oxide Fuel Fabrication Facility for the National Nuclear Security Administration, and Kelly Trice, president and chief operating officer of Shaw AREVA MOX Services, place the...

143

Sustainability Considerations in Spent Light-water Nuclear Fuel Retrievability  

SciTech Connect

This paper examines long-term cost differences between two competing Light Water Reactor (LWR) fuels: Uranium Oxide (UOX) and Mixed Uranium Oxide-Plutonium Oxide (MOX). Since these costs are calculated on a life-cycle basis, expected savings from lower future MOX fuel prices can be used to value the option of substituting MOX for UOX, including the value of maintaining access to the used UOX fuel that could be reprocessed to make MOX. The two most influential cost drivers are the price of natural uranium and the cost of reprocessing. Significant and sustained reductions in reprocessing costs and/or sustained increases in uranium prices are required to give positive value to the retrievability of Spent Nuclear Fuel. While this option has positive economic value, it might not be exercised for 50 to 200 years. Therefore, there are many years for a program during which reprocessing technology can be researched, developed, demonstrated, and deployed. Further research is required to determine whether the cost of such a program would yield positive net present value and/or increases the sustainability of LWR energy systems.

Wood, Thomas W.; Rothwell, Geoffrey

2012-01-10T23:59:59.000Z

144

Fabrication technology for ODS Alloy MA957  

SciTech Connect

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

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

2000-03-16T23:59:59.000Z

145

Systems Analysis of an Advanced Nuclear Fuel Cycle Based on a Modified UREX+3c Process  

SciTech Connect

The research described in this report was performed under a grant from the U.S. Department of Energy (DOE) to describe and compare the merits of two advanced alternative nuclear fuel cycles -- named by this study as the “UREX+3c fuel cycle” and the “Alternative Fuel Cycle” (AFC). Both fuel cycles were assumed to support 100 1,000 MWe light water reactor (LWR) nuclear power plants operating over the period 2020 through 2100, and the fast reactors (FRs) necessary to burn the plutonium and minor actinides generated by the LWRs. Reprocessing in both fuel cycles is assumed to be based on the UREX+3c process reported in earlier work by the DOE. Conceptually, the UREX+3c process provides nearly complete separation of the various components of spent nuclear fuel in order to enable recycle of reusable nuclear materials, and the storage, conversion, transmutation and/or disposal of other recovered components. Output of the process contains substantially all of the plutonium, which is recovered as a 5:1 uranium/plutonium mixture, in order to discourage plutonium diversion. Mixed oxide (MOX) fuel for recycle in LWRs is made using this 5:1 U/Pu mixture plus appropriate makeup uranium. A second process output contains all of the recovered uranium except the uranium in the 5:1 U/Pu mixture. The several other process outputs are various waste streams, including a stream of minor actinides that are stored until they are consumed in future FRs. For this study, the UREX+3c fuel cycle is assumed to recycle only the 5:1 U/Pu mixture to be used in LWR MOX fuel and to use depleted uranium (tails) for the makeup uranium. This fuel cycle is assumed not to use the recovered uranium output stream but to discard it instead. On the other hand, the AFC is assumed to recycle both the 5:1 U/Pu mixture and all of the recovered uranium. In this case, the recovered uranium is reenriched with the level of enrichment being determined by the amount of recovered plutonium and the combined amount of the resulting MOX. The study considered two sub-cases within each of the two fuel cycles in which the uranium and plutonium from the first generation of MOX spent fuel (i) would not be recycled to produce a second generation of MOX for use in LWRs or (ii) would be recycled to produce a second generation of MOX fuel for use in LWRs. The study also investigated the effects of recycling MOX spent fuel multiple times in LWRs. The study assumed that both fuel cycles would store and then reprocess spent MOX fuel that is not recycled to produce a next generation of LWR MOX fuel and would use the recovered products to produce FR fuel. The study further assumed that FRs would begin to be brought on-line in 2043, eleven years after recycle begins in LWRs, when products from 5-year cooled spent MOX fuel would be available. Fuel for the FRs would be made using the uranium, plutonium, and minor actinides recovered from MOX. For the cases where LWR fuel was assumed to be recycled one time, the 1st generation of MOX spent fuel was used to provide nuclear materials for production of FR fuel. For the cases where the LWR fuel was assumed to be recycled two times, the 2nd generation of MOX spent fuel was used to provide nuclear materials for production of FR fuel. The number of FRs in operation was assumed to increase in successive years until the rate that actinides were recovered from permanently discharged spent MOX fuel equaled the rate the actinides were consumed by the operating fleet of FRs. To compare the two fuel cycles, the study analyzed recycle of nuclear fuel in LWRs and FRs and determined the radiological characteristics of irradiated nuclear fuel, nuclear waste products, and recycle nuclear fuels. It also developed a model to simulate the flows of nuclear materials that could occur in the two advanced nuclear fuel cycles over 81 years beginning in 2020 and ending in 2100. Simulations projected the flows of uranium, plutonium, and minor actinides as these nuclear fuel materials were produced and consumed in a fleet of 100 1,000 MWe LWRs and in FRs. The model als

E. R. Johnson; R. E. Best

2009-12-28T23:59:59.000Z

146

ANALYTICAL RESULTS FOR MOX COLEMANITE SAMPLES RECEIVED ON JULY 22, 2013  

SciTech Connect

The Mixed Oxide Fuel Fabrication Facility (MFFF) will use colemanite bearing concrete neutron absorber panels credited with attenuating neutron flux in the criticality design analyses and shielding operators from radiation. The Savannah River National Laboratory (SRNL) is tasked with measuring the boron oxide content of the colemanite raw aggregate material prior to it being mixed into the concrete. SRNL received ten samples of colemanite for analysis on July 22, 2013. The elemental boron content of each sample was measured according to ASTM C 1301. The boron oxide content was calculated using the oxide conversion factor for boron.

Reigel, M.; Best, D.

2013-08-13T23:59:59.000Z

147

ANALYTICAL RESULTS FOR MOX COLEMANITE SAMPLES RECEIVED ON JULY 22, 2013  

SciTech Connect

The Mixed Oxide Fuel Fabrication Facility (MFFF) will use colemanite bearing concrete neutron absorber panels credited with attenuating neutron flux in the criticality design analyses and shielding operators from radiation. The Savannah River National Laboratory (SRNL) is tasked with measuring the boron oxide content of the colemanite raw aggregate material prior to it being mixed into the concrete. SRNL received ten samples of colemanite for analysis on July 22, 2013. The elemental boron content of each sample was measured according to ASTM C 1301. The boron oxide content was calculated using the oxide conversion factor for boron.

Reigel, M.; Best, D.

2014-05-19T23:59:59.000Z

148

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

E-Print Network (OSTI)

The COMETHE 4D Release 23 computer code was used to evaluate the thermal, chemical and mechanical performance of weapons-grade MOX fuel irradiated under U.S. light water reactor typical conditions. Comparisons were made to and UO? fuels exhibited...

Bellanger, Philippe

2012-06-07T23:59:59.000Z

149

Fuel cycle cost uncertainty from nuclear fuel cycle comparison  

SciTech Connect

This paper examined the uncertainty in fuel cycle cost (FCC) calculation by considering both model and parameter uncertainty. Four different fuel cycle options were compared in the analysis including the once-through cycle (OT), the DUPIC cycle, the MOX cycle and a closed fuel cycle with fast reactors (FR). The model uncertainty was addressed by using three different FCC modeling approaches with and without the time value of money consideration. The relative ratios of FCC in comparison to OT did not change much by using different modeling approaches. This observation was consistent with the results of the sensitivity study for the discount rate. Two different sets of data with uncertainty range of unit costs were used to address the parameter uncertainty of the FCC calculation. The sensitivity study showed that the dominating contributor to the total variance of FCC is the uranium price. In general, the FCC of OT was found to be the lowest followed by FR, MOX, and DUPIC. But depending on the uranium price, the FR cycle was found to have lower FCC over OT. The reprocessing cost was also found to have a major impact on FCC.

Li, J.; McNelis, D. [Institute for the Environment, University of North Carolina, Chapel Hill (United States); Yim, M.S. [Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology (Korea, Republic of)

2013-07-01T23:59:59.000Z

150

Radiation protection potential of MOX-fuel doped with 231Pa and Cs radioisotopes  

Science Journals Connector (OSTI)

......paper is devoted to analysis of special measures...of light-water reactors. At present, the...Simplicity and reliability of the technological...for fast breeder reactors with vibro-packed...standardized computer analyses for licensing evaluation...elements in nuclear reactors. (Moscow: Atomizdat......

E. F. Kryuchkov; V. B. Glebov; V. A. Apse; A. N. Shmelev

2005-12-20T23:59:59.000Z

151

Over 9600 Small Business Subcontracts Critical to the Success of NNSA's  

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

Over 9600 Small Business Subcontracts Critical to the Success of Over 9600 Small Business Subcontracts Critical to the Success of NNSA's MOX Fuel Fabrication Facility Over 9600 Small Business Subcontracts Critical to the Success of NNSA's MOX Fuel Fabrication Facility January 3, 2013 - 10:38am Addthis Top: MOX Services President Kelly Trice, left, presents a certificate to Wise President and Owner David Abney and Wise Marketing Director Renee Abney. Wise was recognized as a 2012 MOX Gold Supplier during a special presentation in Dayton. Bottom: Byers Precision Fabricators was recognized as a 2012 MOX Gold Supplier during a special presentation in North Carolina. Steve Marr of MOX Services (left) and Kevin Hall of NNSA (right) present Roger Byers (center) with the award. Top: MOX Services President Kelly Trice, left, presents a certificate to

152

Over 9600 Small Business Subcontracts Critical to the Success of NNSA's  

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

Over 9600 Small Business Subcontracts Critical to the Success of Over 9600 Small Business Subcontracts Critical to the Success of NNSA's MOX Fuel Fabrication Facility Over 9600 Small Business Subcontracts Critical to the Success of NNSA's MOX Fuel Fabrication Facility January 3, 2013 - 10:38am Addthis Top: MOX Services President Kelly Trice, left, presents a certificate to Wise President and Owner David Abney and Wise Marketing Director Renee Abney. Wise was recognized as a 2012 MOX Gold Supplier during a special presentation in Dayton. Bottom: Byers Precision Fabricators was recognized as a 2012 MOX Gold Supplier during a special presentation in North Carolina. Steve Marr of MOX Services (left) and Kevin Hall of NNSA (right) present Roger Byers (center) with the award. Top: MOX Services President Kelly Trice, left, presents a certificate to

153

User Guide for VISION 3.4.7 (Verifiable Fuel Cycle Simulation) Model  

SciTech Connect

The purpose of this document is to provide a guide for using the current version of the Verifiable Fuel Cycle Simulation (VISION) model. This is a complex model with many parameters and options; the user is strongly encouraged to read this user guide before attempting to run the model. This model is an R&D work in progress and may contain errors and omissions. It is based upon numerous assumptions. This model is intended to assist in evaluating 'what if' scenarios and in comparing fuel, reactor, and fuel processing alternatives at a systems level. The model is not intended as a tool for process flow and design modeling of specific facilities nor for tracking individual units of fuel or other material through the system. The model is intended to examine the interactions among the components of a fuel system as a function of time varying system parameters; this model represents a dynamic rather than steady-state approximation of the nuclear fuel system. VISION models the nuclear cycle at the system level, not individual facilities, e.g., 'reactor types' not individual reactors and 'separation types' not individual separation plants. Natural uranium can be enriched, which produces enriched uranium, which goes into fuel fabrication, and depleted uranium (DU), which goes into storage. Fuel is transformed (transmuted) in reactors and then goes into a storage buffer. Used fuel can be pulled from storage into either separation or disposal. If sent to separations, fuel is transformed (partitioned) into fuel products, recovered uranium, and various categories of waste. Recycled material is stored until used by its assigned reactor type. VISION is comprised of several Microsoft Excel input files, a Powersim Studio core, and several Microsoft Excel output files. All must be co-located in the same folder on a PC to function. You must use Powersim Studio 8 or better. We have tested VISION with the Studio 8 Expert, Executive, and Education versions. The Expert and Education versions work with the number of reactor types of 3 or less. For more reactor types, the Executive version is currently required. The input files are Excel2003 format (xls). The output files are macro-enabled Excel2007 format (xlsm). VISION 3.4 was designed with more flexibility than previous versions, which were structured for only three reactor types - LWRs that can use only uranium oxide (UOX) fuel, LWRs that can use multiple fuel types (LWR MF), and fast reactors. One could not have, for example, two types of fast reactors concurrently. The new version allows 10 reactor types and any user-defined uranium-plutonium fuel is allowed. (Thorium-based fuels can be input but several features of the model would not work.) The user identifies (by year) the primary fuel to be used for each reactor type. The user can identify for each primary fuel a contingent fuel to use if the primary fuel is not available, e.g., a reactor designated as using mixed oxide fuel (MOX) would have UOX as the contingent fuel. Another example is that a fast reactor using recycled transuranic (TRU) material can be designated as either having or not having appropriately enriched uranium oxide as a contingent fuel. Because of the need to study evolution in recycling and separation strategies, the user can now select the recycling strategy and separation technology, by year.

Jacob J. Jacobson; Robert F. Jeffers; Gretchen E. Matthern; Steven J. Piet; Wendell D. Hintze

2011-07-01T23:59:59.000Z

154

Reduction in Fabrication Costs of Gas Diffusion Layers | Department...  

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

Layers Reduction in Fabrication Costs of Gas Diffusion Layers 2011 DOE Hydrogen and Fuel Cells Program, and Vehicle Technologies Program Annual Merit Review and Peer Evaluation...

155

Cryogenic Fabric  

Science Journals Connector (OSTI)

The distinct soil micromorphology is produced due to the effects of freezing and thawing processes and is termed as cryogenic fabric. Layers, lenses, and streaks of segregation ice are typical elements of the cryogenic

P. Pradeep Kumar

2014-08-01T23:59:59.000Z

156

Fabric Facts.  

E-Print Network (OSTI)

's Sewing Book. Stanford, Conn: Coats and Clark's, Inc., 1976. Complete Sewing Guide. Pleasantville, NY: The Reader's Digest Association, Inc;, 1976. "Giving Conventional Fabrics a Run for the Money." Clothes Etc. New York: Prads, Inc., April 15, 1978...

Saunders, Becky

1980-01-01T23:59:59.000Z

157

Fuel Cycle Scenario Definition, Evaluation, and Trade-offs  

SciTech Connect

This report aims to clarify many of the issues being discussed within the AFCI program, including Inert Matrix Fuel (IMF) versus Mixed Oxide (MOX) fuel, single-pass versus multi-pass recycling, thermal versus fast reactors, potential need for transmutation of technetium and iodine, and the value of separating cesium and strontium. It documents most of the work produced by INL, ANL, and SNL personnel under their Simulation, Evaluation, and Trade Study (SETS) work packages during FY2005 and the first half of FY2006. This report represents the first attempt to calculate a full range of metrics, covering all four AFCI program objectives - waste management, proliferation resistance, energy recovery, and systematic management/economics/safety - using a combination of "static" calculations and a system dynamic model, DYMOND. In many cases, we examine the same issue both dynamically and statically to determine the robustness of the observations. All analyses are for the U.S. reactor fleet. This is a technical report, not aimed at a policy-level audience. A wide range of options are studied to provide the technical basis for identifying the most attractive options and potential improvements. Option improvement could be vital to accomplish before the AFCI program publishes definitive cost estimates. Information from this report will be extracted and summarized in future policy-level reports. Many dynamic simulations of deploying those options are included. There are few "control knobs" for flying or piloting the fuel cycle system into the future, even though it is dark (uncertain) and controls are sluggish with slow time response: what types of reactors are built, what types of fuels are used, and the capacity of separation and fabrication plants. Piloting responsibilities are distributed among utilities, government, and regulators, compounding the challenge of making the entire system work and respond to changing circumstances. We identify four approaches that would increase our ability to pilot the fuel cycle system: (1) have a recycle strategy that could be implemented before the 2030-2050 approximate period when current reactors retire so that replacement reactors fit into the strategy, (2) establish an option such as multi-pass blended-core IMF as a downward plutonium control knob and accumulate waste management benefits early, (3) establish fast reactors with flexible conversion ratio as a future control knob that slowly becomes available if/when fast reactors are added to the fleet, and (4) expand exploration of blended assemblies and cores, which appear to have advantages and agility. Initial results suggest multi-pass full-core MOX appears to be a less effective way than multi-pass blended core IMF to manage the fuel cycle system because it requires higher TRU throughput while more slowly accruing waste management benefits. Single-pass recycle approaches for LWRs (we did not study the VHTR) do not meet AFCI program objectives and could be considered a "dead end". Fast reactors appear to be effective options but a significant number of fast reactors must be deployed before the benefit of such strategies can be observed.

Steven J. Piet; Gretchen E. Matthern; Jacob J. Jacobson; Christopher T. Laws; Lee C. Cadwallader; Abdellatif M. Yacout; Robert N. Hill; J. D. Smith; Andrew S. Goldmann; George Bailey

2006-08-01T23:59:59.000Z

158

ANALYTICAL RESULTS FOR MOX COLEMANITE CONCRETE SAMPLES RECEIVED ON NOVEMBER 21, 2013  

SciTech Connect

The Mixed Oxide Fuel Fabrication Facility (MFFF) will use colemanite bearing concrete neutron absorber panels credited with attenuating neutron flux in the criticality design analyses and shielding operators from radiation. The Savannah River National Laboratory (SRNL) is tasked with measuring the total density, partial hydrogen density, and partial boron density of the colemanite concrete. SRNL received two samples of colemanite concrete for analysis on November 21, 2013. The average total density of each of the samples measured by the ASTM method C 642, the average partial hydrogen density was measured using method ASTM E 1131, and the average partial boron density of each sample was measured according to ASTM C 1301. The lower limits and measured values for the total density, hydrogen partial density, and boron partial density are presented. For all the samples tested, the total density and the boron partial density met or exceeded the specified limit. None of the samples met the lower limit for hydrogen partial density.

Reigel, M.

2014-05-19T23:59:59.000Z

159

ANALYTICAL RESULTS FOR MOX COLEMANITE CONCRETE SAMPLES RECEIVED ON SEPTEMBER 4, 2013  

SciTech Connect

The Mixed Oxide Fuel Fabrication Facility (MFFF) will use colemanite bearing concrete neutron absorber panels credited with attenuating neutron flux in the criticality design analyses and shielding operators from radiation. The Savannah River National Laboratory (SRNL) is tasked with measuring the total density, partial hydrogen density, and partial boron density of the colemanite concrete. SRNL received three samples of colemanite concrete for analysis on September 4, 2013. The average total density of each of the samples measured by the ASTM method C 642, the average partial hydrogen density was measured using method ASTM E 1131, and the average partial boron density of each sample was measured according to ASTM C 1301. The lower limits and measured values for the total density, hydrogen partial density, and boron partial density are presented. For all the samples tested, the total density and the boron partial density met or exceeded the specified limit. None of the samples met the lower limit for hydrogen partial density.

Reigel, M.

2014-05-19T23:59:59.000Z

160

LLNL Contribution to Sandia Used Fuel Disposition - Security March 2011 Deliverable  

SciTech Connect

Cleary [2007] divides the proliferation pathway into stages: diversion, facility misuse, transportation, transformation, and weapons fabrication. King [2010], using Cleary's methodology, compares a deepburn fusion-driven blanket containing weapons-grade plutonium with a PWR burning MOX fuel enrichments of 5-9%. King considers the stages of theft, transportation, transformation, and nuclear explosive fabrication. In the current study of used fuel storage security, a similar approach is appropriate. First, one must consider the adversary's objective, which can be categorized as on-site radionuclide dispersion, theft of material for later radionuclide dispersion, and theft of material for later processing and fabrication into a nuclear explosive. For on-site radionuclide dispersion, only a single proliferation pathway stage is appropriate: dispersion. That situation will be addressed in future reports. For later radionuclide dispersion, the stages are theft, transportation, and transformation (from oxide spent fuel containing both fission products and actinides to a material size and shape suitable for dispersion). For later processing and fabrication into a nuclear explosive, the stages are theft (by an outsider or by facility misuse by an insider), transportation, transformation (from oxide spent fuel containing both fission products and actinides to a metal alloy), and fabrication (of the alloy into a weapon). It should be noted that the theft and transportation stages are similar, and possibly identical, for later radionuclide dispersion and later processing and fabrication into a nuclear explosive. Each stage can be evaluated separately, and the methodology can vary for each stage. For example, King starts with the methodology of Cleary for the theft, transportation, transformation, and fabrication stages. Then, for each stage, King assembles and modifies the attributes and inputs suggested by Cleary. In the theft (also known as diversion) stage, Cleary has five high-level categories (material handling during diversion, difficulty of evading detection by the accounting system, difficulty of evading detection by the material control system, difficulty of conducting undeclared facility modifications for the purpose of diverting nuclear material, and difficulty of evading detection of the facility modifications for the purposes of diverting nuclear material). Each category has one or more subcategories. For example, the first category includes mass per significant quantity (SQ) of nuclear material, volume/SQ of nuclear material, number of items/SQ, material form (solid, liquid, powder, gas), radiation level in terms of dose, chemical reactivity, heat load, and process temperature. King adds the following two subcategories to that list: SQs available for theft, and interruptions/changes (normal and unexpected) in material stocks and flows. For the situation of an orphaned surface storage facility, this approach is applicable, with some of the categories and subcategories being modified to reflect the static situation (no additions or removals of fuel or containers). In addition, theft would require opening a large overpack and either removing a full container or opening that sealed container and then removing one or more spent nuclear fuel assemblies. These activities would require time without observation (detection), heavy-duty equipment, and some degree of protection of the thieves from radiological dose. In the transportation stage, Cleary has two high-level categories (difficulty of handling material during transportation, and difficulty of evading detection during transport). Each category has a number of subcategories. For the situation of an orphaned surface storage facility, these categories are applicable. The transformation stage of Cleary has three high-level categories (facilities and equipment needed to process diverted materials; knowledge, skills, and workforce needed to process diverted materials; and difficulty of evading detection of transformation activities). Again, there are subcategories. King [2007

Blink, J A

2011-03-23T23:59:59.000Z

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


161

International trade and waste and fuel managment issue, 2006  

SciTech Connect

The focus of the January-February issue is on international trade and waste and fuel managment. Major articles/reports in this issue include: HLW management in France, by Michel Debes, EDF, France; Breakthroughs from future reactors, by Jacques Bouchard, CEA, France; 'MOX for peace' a reality, by Jean-Pierre Bariteau, AREVA Group, France; Swedish spent fuel and radwaste, by Per H. Grahn and Marie Skogsberg, SKB, Sweden; ENC2005 concluding remarks, by Larry Foulke, 'Nuclear Technology Matters'; Fuel crud formation and behavior, by Charles Turk, Entergy; and, Plant profile: major vote of confidence for NP, by Martti Katka, TVO, Finland.

Agnihotri, Newal (ed.)

2006-01-15T23:59:59.000Z

162

Thermal-Hydraulic Analysis of Seed-Blanket Unit Duplex Fuel Assemblies with VIPRE-01  

E-Print Network (OSTI)

nucleate boiling ratio EFIT European Facility for Industrial Transmutation EMT Effective Medium Theory EOL end-of-life EURO-TRANS EUROpean research program for the TRANSmutation of high level nuclear waste in ADS EPRI Electric Power Research... MA minor actinides ME Maxwell-Eucken viii MDNBR minimum departure from nucleate boiling ratio MNFI modified Nuclear Fuels Industries Mo molybdenum MOX mixed-oxide M-R multi-recycling NFI Nuclear Fuels Industries Np neptunium NPP nuclear...

McDermott, Patrick 1987-

2012-11-15T23:59:59.000Z

163

Vessel Design and Fabrication Technology for Stationary High-Pressure Hydrogen Storage - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

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

7 7 FY 2012 Annual Progress Report DOE Hydrogen and Fuel Cells Program Zhili Feng (Primary Contact), Wei Zhang, John Wang and Fei Ren Oak Ridge National Laboratory (ORNL) 1 Bethel Valley Rd, PO Box 2008, MS 6095 Oak Ridge, TN 37831 Phone: (865) 576-3797 Email: fengz@ornl.gov DOE Manager HQ: Sara Dillich Phone: (202) 586-7925 Email: Sara.Dillich@ee.doe.gov Subcontractors: * Global Engineering and Technology LLC, Camas, WA * Ben C. Gerwick Inc., Oakland, CA * MegaStir Technologies LLC, Provo, UT * University of Michigan, Ann Arbor, MI Project Start Date: October 1, 2010 Project End Date: Project continuation and direction

164

Comparative analysis of LWR and FBR spent fuels for nuclear forensics evaluation  

SciTech Connect

Some interesting issues are attributed to nuclide compositions of spent fuels from thermal reactors as well as fast reactors such as a potential to reuse as recycled fuel, and a possible capability to be manage as a fuel for destructive devices. In addition, analysis on nuclear forensics which is related to spent fuel compositions becomes one of the interesting topics to evaluate the origin and the composition of spent fuels from the spent fuel foot-prints. Spent fuel compositions of different fuel types give some typical spent fuel foot prints and can be estimated the origin of source of those spent fuel compositions. Some technics or methods have been developing based on some science and technological capability including experimental and modeling or theoretical aspects of analyses. Some foot-print of nuclear forensics will identify the typical information of spent fuel compositions such as enrichment information, burnup or irradiation time, reactor types as well as the cooling time which is related to the age of spent fuels. This paper intends to evaluate the typical spent fuel compositions of light water (LWR) and fast breeder reactors (FBR) from the view point of some foot prints of nuclear forensics. An established depletion code of ORIGEN is adopted to analyze LWR spent fuel (SF) for several burnup constants and decay times. For analyzing some spent fuel compositions of FBR, some coupling codes such as SLAROM code, JOINT and CITATION codes including JFS-3-J-3.2R as nuclear data library have been adopted. Enriched U-235 fuel composition of oxide type is used for fresh fuel of LWR and a mixed oxide fuel (MOX) for FBR fresh fuel. Those MOX fuels of FBR come from the spent fuels of LWR. Some typical spent fuels from both LWR and FBR will be compared to distinguish some typical foot-prints of SF based on nuclear forensic analysis.

Permana, Sidik; Suzuki, Mitsutoshi; Su'ud, Zaki [Department of Science and Technology for Nuclear Material Management (STNM), Japan Atomic Energy Agency (JAEA), 2-4 Shirane, Shirakata, Tokai Mura, Naka-gun, Ibaraki 319-1195 Nuclear Physics and Bio (Indonesia); Department of Science and Technology for Nuclear Material Management (STNM), Japan Atomic Energy Agency (JAEA), 2-4 Shirane, Shirakata, Tokai Mura, Naka-gun, Ibaraki 319-1195 (Japan); Nuclear Physics and Bio Physics Research Group, Department of Physics, Bandung Institute of Technology, Gedung Fisika, Jl. Ganesha 10, Bandung 40132 (Indonesia)

2012-06-06T23:59:59.000Z

165

Audit Report: IG-0887 | Department of Energy  

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

7 7 Audit Report: IG-0887 May 15, 2013 The Use of Staff Augmentation Subcontracts at the National Nuclear Security Administration's Mixed Oxide Fuel Fabrication Facility Shaw AREVA MOX Services, LLC (MOX Services) is responsible for the design and construction of the National Nuclear Security Administration's (NNSA) nearly $5 billion Mixed Oxide Fuel Fabrication Facility (MOX Project) at the Savannah River Site near Aiken, South Carolina. The facility will remove impurities from surplus weapons-grade plutonium and mix it with depleted uranium oxide to form fuel pellets for commercial nuclear power reactors. MOX Services used staff augmentation subcontracts to fill professional, technical and administrative support service positions on an as-needed basis on the MOX Project. According to MOX Services officials, a shortage

166

Proliferation resistance of small modular reactors fuels  

SciTech Connect

In this paper the proliferation resistance of different types of Small Modular Reactors (SMRs) has been examined and classified with criteria available in the literature. In the first part of the study, the level of proliferation attractiveness of traditional low-enriched UO{sub 2} and MOX fuels to be used in SMRs based on pressurized water technology has been analyzed. On the basis of numerical simulations both cores show significant proliferation risks. Although the MOX core is less proliferation prone in comparison to the UO{sub 2} core, it still can be highly attractive for diversion or undeclared production of nuclear material. In the second part of the paper, calculations to assess the proliferation attractiveness of fuel in typical small sodium cooled fast reactor show that proliferation risks from spent fuel cannot be neglected. The core contains a highly attractive plutonium composition during the whole life cycle. Despite some aspects of the design like the sealed core that enables easy detection of unauthorized withdrawal of fissile material and enhances proliferation resistance, in case of open Non-Proliferation Treaty break-out, weapon-grade plutonium in sufficient quantities could be extracted from the reactor core.

Polidoro, F.; Parozzi, F. [RSE - Ricerca sul Sistema Energetico,Via Rubattino 54, 20134, Milano (Italy); Fassnacht, F.; Kuett, M.; Englert, M. [IANUS, Darmstadt University of Technology, Alexanderstr. 35, D-64283 Darmstadt (Germany)

2013-07-01T23:59:59.000Z

167

Waste Form Development for the Solidification of PDCF/MOX Liquid Waste Streams  

SciTech Connect

At the Savannah River Site, part of the Department of Energy's nuclear materials complex located in South Carolina, cementation has been selected as the solidification method for high-alpha and low-activity waste streams generated in the planned plutonium disposition facilities. A Waste Solidification Building (WSB) that will be used to treat and solidify three radioactive liquid waste streams generated by the Pit Disassembly and Conversion Facility) and the Mixed Oxide Fuel Fabrication Facility is in the preliminary design stage. The WSB is expected to treat a transuranic (TRU) waste stream composed primarily of americium and two low-level waste (LLW) streams. The acidic wastes will be concentrated in the WSB evaporator and neutralized in a cement head tank prior to solidification. A series of TRU mixes were prepared to produce waste forms exhibiting a range of processing and cured properties. The LLW mixes were prepared using the premix from the preferred TRU waste form. All of the waste forms tested passed the Toxicity Characteristic Leaching Procedure. After processing in the WSB, current plans are to dispose of the solidified TRU waste at the Waste Isolation Pilot Plant in New Mexico and the solidified LLW waste at an approved low-level waste disposal facility.

COZZI, ALEX

2004-02-18T23:59:59.000Z

168

ANALYTICAL RESULTS FOR MOX COLEMANITE CONCRETE SAMPLES RECEIVED ON JANUARY 15, 2013  

SciTech Connect

The Mixed Oxide Fuel Fabrication Facility (MFFF) will use colemanite bearing concrete neutron absorber panels credited with attenuating neutron flux in the criticality design analyses and shielding operators from radiation. The Savannah River National Laboratory (SRNL) is tasked with measuring the total density, partial hydrogen density, and partial boron density of the colemanite concrete. SRNL received twelve samples of colemanite concrete for analysis on January 15, 2013. The average total density of each of the samples measured by the ASTM method C 642, the average partial hydrogen density was measured using method ASTM E 1131, and the average partial boron density of each sample was measured according to ASTM C 1301. The lower limits and measured values for the total density, hydrogen partial density, and boron partial density are presented. For all the samples tested, the total density and the hydrogen partial density met or exceeded the specified limit. All of the samples met or exceeded the boron partial density lower bound with the exception of samples G3-M11-2000-H, G3-M11-3000-M, and G5-M1-3000-H which are below the limit of 1.65E-01 g/cm{sup 3}.

Reigel, M.

2014-05-19T23:59:59.000Z

169

ANALYTICAL RESULTS OF MOX COLEMANITE CONCRETE SAMPLE POURED MAY 4, 2012  

SciTech Connect

The Mixed Oxide Fuel Fabrication Facility (MFFF) will use Colemanite bearing concrete neutron absorber panels credited with attenuating neutron flux in the criticality design analyses. The Savannah River National Laboratory is tasked with measuring the total density, partial hydrogen density, and partial boron density of the colemanite concrete. Sample 04 May 12/Test/S1-1, S1-2, and S1-3 was received on 5/9/2012 and analyzed. The total density measure by the ASTM method C 642 was 2.00 g/cm{sup 3}, within the lower bound of 1.88 g/cm{sup 3}. The partial hydrogen density of 6.35E-02 g/cm{sup 3} as measured using method ASTM E 1311 met the lower bound of 6.04E-02 g/cm{sup 3}. The measured partial boron density of 1.88E-01 g/cm{sup 3} exceeded the lower bound of 1.65E-01 g/cm{sup 3} when the sodium peroxide fusion dissolution method was used in place of the prescribed ASTM C 1301 method.

Cozzi, A.; Best, D.; Reigel, M.

2012-06-14T23:59:59.000Z

170

Status of Transuranic Bearing Metallic Fuel Development  

SciTech Connect

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

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

2009-09-01T23:59:59.000Z

171

FUEL CYCLE POTENTIAL WASTE FOR DISPOSITION  

SciTech Connect

The United States (U.S.) currently utilizes a once-through fuel cycle where used nuclear fuel (UNF) is stored on-site in either wet pools or in dry storage systems with ultimate disposal in a deep mined geologic repository envisioned. Within the Department of Energy's (DOE) Office of Nuclear Energy (DOE-NE), the Fuel Cycle Research and Development Program (FCR&D) develops options to the current commercial fuel cycle management strategy to enable the safe, secure, economic, and sustainable expansion of nuclear energy while minimizing proliferation risks by conducting research and development of advanced fuel cycles, including modified open and closed cycles. The safe management and disposition of used nuclear fuel and/or nuclear waste is a fundamental aspect of any nuclear fuel cycle. Yet, the routine disposal of used nuclear fuel and radioactive waste remains problematic. Advanced fuel cycles will generate different quantities and forms of waste than the current LWR fleet. This study analyzes the quantities and characteristics of potential waste forms including differing waste matrices, as a function of a variety of potential fuel cycle alternatives including: (1) Commercial UNF generated by uranium fuel light water reactors (LWR). Four once through fuel cycles analyzed in this study differ by varying the assumed expansion/contraction of nuclear power in the U.S. (2) Four alternative LWR used fuel recycling processes analyzed differ in the reprocessing method (aqueous vs. electro-chemical), complexity (Pu only or full transuranic (TRU) recovery) and waste forms generated. (3) Used Mixed Oxide (MOX) fuel derived from the recovered Pu utilizing a single reactor pass. (4) Potential waste forms generated by the reprocessing of fuels derived from recovered TRU utilizing multiple reactor passes.

Carter, J.

2011-01-03T23:59:59.000Z

172

FUEL CYCLE POTENTIAL WASTE FOR DISPOSITION  

SciTech Connect

The United States (U.S.) currently utilizes a once-through fuel cycle where used nuclear fuel (UNF) is stored on-site in either wet pools or in dry storage systems with ultimate disposal in a deep mined geologic repository envisioned. Within the Department of Energy's (DOE) Office of Nuclear Energy (DOE-NE), the Fuel Cycle Research and Development Program (FCR&D) develops options to the current commercial fuel cycle management strategy to enable the safe, secure, economic, and sustainable expansion of nuclear energy while minimizing proliferation risks by conducting research and development of advanced fuel cycles, including modified open and closed cycles. The safe management and disposition of used nuclear fuel and/or nuclear waste is a fundamental aspect of any nuclear fuel cycle. Yet, the routine disposal of used nuclear fuel and radioactive waste remains problematic. Advanced fuel cycles will generate different quantities and forms of waste than the current LWR fleet. This study analyzes the quantities and characteristics of potential waste forms including differing waste matrices, as a function of a variety of potential fuel cycle alternatives including: (1) Commercial UNF generated by uranium fuel light water reactors (LWR). Four once through fuel cycles analyzed in this study differ by varying the assumed expansion/contraction of nuclear power in the U.S; (2) Four alternative LWR used fuel recycling processes analyzed differ in the reprocessing method (aqueous vs. electro-chemical), complexity (Pu only or full transuranic (TRU) recovery) and waste forms generated; (3) Used Mixed Oxide (MOX) fuel derived from the recovered Pu utilizing a single reactor pass; and (4) Potential waste forms generated by the reprocessing of fuels derived from recovered TRU utilizing multiple reactor passes.

Jones, R.; Carter, J.

2010-10-13T23:59:59.000Z

173

Fabrication and Characterization of Uranium-based High Temperature Reactor  

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

Fabrication and Characterization of Uranium-based High Temperature Reactor 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 and characterization of uranium-based high temperature reactor fuel. A laboratory-scale coater manufactures tri-isotropic (TRISO) coated fuel particles (CFPs), state-of-the-art materials property characterization is performed, and the CFPs are then pressed into fuel compacts for irradiation testing, all under a NQA-1 compliant Quality Assurance Program. After fuel kernel size and shape are measured by optical shadow imaging, the TRISO coatings are deposited via fluidized bed chemical vapor deposition in a 50-mm diameter conical chamber within the coating furnace. Computer control of temperature and gas composition ensures reproducibility

174

HTR Fuel Development in Europe  

SciTech Connect

In the frame of the European Network HTR-TN and in the 5. EURATOM RTD Framework Programme (FP5) European programmes have been launched to consolidate advanced modular HTR technology in Europe. This paper gives an overall description and first results of this programme. The major tasks covered concern a complete recovery of the past experience on fuel irradiation behaviour in Europe, qualification of HTR fuel by irradiating of fuel elements in the HFR reactor, understanding of fuel behaviour with the development of a fuel particle code and finally a recover of the fuel fabrication capability. (authors)

Languille, Alain [CEA Cadarache, 13108 Saint-Paul-lez-Durance BP1 (France); Conrad, R. [CEC/JRC/IE Petten (Netherlands); Guillermier, P. [Framatome-ANP/ Lyon (France); Nabielek, H. [FZJ/Juelich (Germany); Bakker, K. [NRG/Petten (Netherlands); Abram, T. [BNFL UK (United Kingdom); Haas, D. [JRC/ITU/Karlsruhe (Germany)

2002-07-01T23:59:59.000Z

175

Fabricate PHEV Cells for Testing & Diagnostics | Department of...  

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

1 DOE Hydrogen and Fuel Cells Program, and Vehicle Technologies Program Annual Merit Review and Peer Evaluation es030jansen2011p.pdf More Documents & Publications Fabricate PHEV...

176

Fabrication of Small Diesel Fuel Injector Orifices  

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

Presentation from the U.S. DOE Office of Vehicle Technologies "Mega" Merit Review 2008 on February 25, 2008 in Bethesda, Maryland.

177

Fabrication of Small Diesel Fuel Injector Orifices  

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

(if applicable) - NA Barriers Approach Performance Measures and Accomplishments Technology Transfer PublicationsPatents Plans for Next Fiscal Year Summary 3 Purpose of Work...

178

Polymorphous computing fabric  

DOE Patents (OSTI)

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

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

2011-01-18T23:59:59.000Z

179

IFR fuel cycle  

SciTech Connect

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.

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

180

Gallium interactions with Zircaloy  

E-Print Network (OSTI)

of weapons-grade plutonium (WGPu) in the United States is the conversion of weapons-grade plutonium into mixed-oxide (MOX) reactor fuel. MOX fuel fabricated in this way must be compatible with currently used nuclear fuel components. Since US WGPu contains... that gallium may have on zircaloy cladding during reactor operation. As a result of the reprocessing of spent fuel used in European nuclear programs, many studies have been conducted on the production and behavior of MOX fuel in traditional reactors [5...

West, Michael Keith

2012-06-07T23:59:59.000Z

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


181

Blog Archive | Department of Energy  

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

9, 2013 9, 2013 A Shining Example of Dr. King's legacy Editor's Note: This blog was originally posted on OSTI's blog. January 3, 2013 Top: MOX Services President Kelly Trice, left, presents a certificate to Wise President and Owner David Abney and Wise Marketing Director Renee Abney. Wise was recognized as a 2012 MOX Gold Supplier during a special presentation in Dayton. Bottom: Byers Precision Fabricators was recognized as a 2012 MOX Gold Supplier during a special presentation in North Carolina. Steve Marr of MOX Services (left) and Kevin Hall of NNSA (right) present Roger Byers (center) with the award. Over 9600 Small Business Subcontracts Critical to the Success of NNSA's MOX Fuel Fabrication Facility NNSA and MOX Services are committed to increasing the contracting

182

ElectronicFabrication  

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

Fabrication Fabrication Manufacturing Technologies Electronic Fabrication provides our cus- tomers solutions for the packaging design, production acceptable prototype fabrica- tion, or deliverable production fabrication. Capabilities * Final electronic product packaging from sketches and verbal instructions * Provide CAD drawing package after project completion if no formal prints are available * Complete system development and fab- rication through concurrent engineering * Concurrent engineering in prototype and production fabrication * Integrate commercial equipment into prototype system design * Implementation and modification of commercial equipment * Packaging of prototype into finalized product assembly Resources * Customer assistance from fabrication, to testing, to complete system installation

183

Development of a Criticality Evaluation Method Considering the Particulate Behavior of Nuclear Fuel  

SciTech Connect

In conventional criticality evaluations of nuclear powder systems, effects of particulate behavior were not considered. In other words, it is difficult to take into account the particle motion in the criticality evaluations. We have developed a novel criticality evaluation code to resolve this problem. The criticality evaluation code, coupling a discrete element method simulation code with a continuous-energy Monte Carlo transport code, makes it possible to study the effects of the particulate dynamics on criticality. This criticality evaluation code is applied to the mixed-oxide (MOX) fuel powder agitation process. The criticality evaluations are performed while mixing the MOX fuel powder and an additive powder in a stirred vessel to investigate the effects of the powder free surface deformation and the particulate mixture state on the effective multiplication factor. The evaluation results reveal that the effective multiplication factor decreases due to the powder boundary deformation while it increases as the mixture condition of MOX powder and Zn-St powder is close to homogeneous.

Sakai, Mikio; Yamamoto, Toshihiro; Murazaki, Minoru; Miyoshi, Yoshinori [Japan Atomic Energy Research Institute (Japan)

2005-02-15T23:59:59.000Z

184

RADIATION DOSE ASPECTS IN THE HANDLING OF EMERGING NUCLEAR FUELS  

Science Journals Connector (OSTI)

......transmutation in LMFBR, and uranium (U) matrix fuels...161. 15 NUREG. Standard review plan for the review of an application...16 IAEA. Safety of uranium fuel fabrication facilities...2010) IAEA Safety Standards Series No. SSG-6......

G. Nicolaou

2014-02-01T23:59:59.000Z

185

MECS 2006- Fabricated Metals  

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

Manufacturing Energy and Carbon Footprint for Fabricated Metals (NAICS 332) Sector with Total Energy Input, October 2012 (MECS 2006)

186

Computational Fuel Cell Research and SOFC Modeling at Penn State  

E-Print Network (OSTI)

Materials Research and Component Fabrication Kinetics and Thermal Transport Fuel Cell/Battery Simulation multidisciplinary research on fuel cells and advanced batteries for vehicle propulsion, distributed power generation, DMFC, and SOFC #12;ECEC Facilities (>5,000 sq ft) Fuel Cell/Battery Experimental Labs Fuel Cell

187

Raman and XPS characterization of fuel-cladding interactions using miniature specimens  

SciTech Connect

Laser Raman spectroscopy was evaluated as a tool for studying fuel-cladding chemical interactions at elevated temperatures. Materials and conditions were selected to simulate the interface of oxide fuels and fission products with high-temperature cladding materials for TRU-MOX fueled reactors. Both ex-situ and in-situ spectroscopy measurements were performed using polished HT-9 disks, uncoated and coated with yttria-stabilized zirconia, that were exposed to air oxidation at temperatures between 873-973K. Ex-situ measurements (under ambient conditions) were conducted to identify oxide phases, determine oxidation mechanisms and approximate film growth rates with an optimal signal-to-noise for the equipment used. Subsequently performed in-situ measurements were used to evaluate the sensitivity of the technique for measurements at elevated temperature in a hot-stage. Raman spectra were supported with x-ray photoelectron spectroscopy depth profiling. The results, which are for non-fueled materials in this study, illustrated a method for fast screening of candidate alloys with actinide-based MOX fuel mixtures.

Windisch, Charles F.; Henager, Charles H.; Engelhard, Mark H.; Bennett, Wendy D.

2009-01-01T23:59:59.000Z

188

Pyroprocessing of Light Water Reactor Spent Fuels Based on an Electrochemical Reduction Technology  

SciTech Connect

A concept of pyroprocessing light water reactor (LWR) spent fuels based on an electrochemical reduction technology is proposed, and the material balance of the processing of mixed oxide (MOX) or high-burnup uranium oxide (UO{sub 2}) spent fuel is evaluated. Furthermore, a burnup analysis for metal fuel fast breeder reactors (FBRs) is conducted on low-decontamination materials recovered by pyroprocessing. In the case of processing MOX spent fuel (40 GWd/t), UO{sub 2} is separately collected for {approx}60 wt% of the spent fuel in advance of the electrochemical reduction step, and the product recovered through the rare earth (RE) removal step, which has the composition uranium:plutonium:minor actinides:fission products (FPs) = 76.4:18.4:1.7:3.5, can be applied as an ingredient of FBR metal fuel without a further decontamination process. On the other hand, the electroreduced alloy of high-burnup UO{sub 2} spent fuel (48 GWd/t) requires further decontamination of residual FPs by an additional process such as electrorefining even if RE FPs are removed from the alloy because the recovered plutonium (Pu) is accompanied by almost the same amount of FPs in addition to RE. However, the amount of treated materials in the electrorefining step is reduced to {approx}10 wt% of the total spent fuel owing to the prior UO{sub 2} recovery step. These results reveal that the application of electrochemical reduction technology to LWR spent oxide fuel is a promising concept for providing FBR metal fuel by a rationalized process.

Ohta, Hirokazu; Inoue, Tadashi; Sakamura, Yoshiharu; Kinoshita, Kensuke

2005-05-15T23:59:59.000Z

189

Fluidic fuel feed system  

SciTech Connect

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

Badgley, P.

1990-06-01T23:59:59.000Z

190

Fabricated Metals (2010 MECS)  

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

Manufacturing Energy and Carbon Footprint for Fabricated Metals Sector (NAICS 332) Energy use data source: 2010 EIA MECS (with adjustments) Footprint Last Revised: February 2014

191

Method of preparation of bonded polyimide fuel cell package  

DOE Patents (OSTI)

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

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

2011-04-26T23:59:59.000Z

192

Coated Particle Fuel Development Lab (CPFDL) | ORNL  

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

Coated Particle Fuel Development Lab Coated Particle Fuel Development Lab May 30, 2013 Computer controlled fluidized bed CVD particle coating system The Coated Particle Fuel Development Laboratory is a modern, integrated facility for laboratory scale fabrication and characterization of uranium-bearing coated particle fuel (CPF). Within this facility, tri-isotropic (TRISO) coatings are deposited on various fuel kernels by chemical vapor deposition (CVD), particles are pressed into fuel compacts for irradiation, and state-of-the-art materials property characterization is performed, all under an NQA-1 compliant Quality Assurance program. Current work includes fabrication and characterization of coated particle fuels to support the Next Generation Nuclear Plant, Advanced Small Modular Reactors, Nuclear Thermal Propulsion, and Advanced Light Water Reactor

193

Dry Process Electrode Fabrication  

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

2012 DOE Hydrogen and Fuel Cells Program and Vehicle Technologies Program Annual Merit Review and Peer Evaluation Meeting

194

Dry Process Electrode Fabrication  

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

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

195

Microsoft Word - Document in Microsoft Internet Explorer  

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

Status of the Mixed Oxide Fuel Status of the Mixed Oxide Fuel Fabrication Facility DOE/IG-0713 December 2005 STATUS OF THE MIXED OXIDE FUEL FABRICATION FACILITY TABLE OF CONTENTS MOX Facility Design Costs Details of Finding 1 Recommendations 5 Comments 6 Appendices Objective, Scope, and Methodology 9 Prior Audit Reports 11 Management Comments 12 MOX Facility Design Costs Page 1 Details of Finding Design and The audit disclosed that the cost of the Mixed Oxide Fuel Construction Budget Facility (MOX) will significantly exceed the amounts reported to Congress. As of July 2005, the National Nuclear Security Administration's (NNSA's) unvalidated estimate for the design and construction of the MOX Facility was about $3.5 billion, which is

196

Alternative Fuels Data Center: Alternative Fuel and Fueling Infrastructure  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fuel and Fuel and Fueling Infrastructure Incentives to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel and Fueling Infrastructure Incentives on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel and Fueling Infrastructure Incentives on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel and Fueling Infrastructure Incentives on Google Bookmark Alternative Fuels Data Center: Alternative Fuel and Fueling Infrastructure Incentives on Delicious Rank Alternative Fuels Data Center: Alternative Fuel and Fueling Infrastructure Incentives on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuel and Fueling Infrastructure Incentives on AddThis.com... More in this section... Federal State Advanced Search

197

Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fuel Fuel Vehicle (AFV) and Fueling Infrastructure Loans to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Loans on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Loans on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Loans on Google Bookmark Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Loans on Delicious Rank Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Loans on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Loans on AddThis.com...

198

IDENTIFYING IMPURITIES IN SURPLUS NON PIT PLUTONIUM FEEDS FOR MOX OR ALTERNATIVE DISPOSITION  

SciTech Connect

This report provides a technical basis for estimating the level of corrosion products in materials stored in DOE-STD-3013 containers based on extrapolating available chemical sample results. The primary focus is to estimate the levels of nickel, iron, and chromium impurities in plutonium-bearing materials identified for disposition in the United States Mixed Oxide fuel process.

Allender, J; Moore, E

2010-07-14T23:59:59.000Z

199

Recovery of weapon plutonium as feed material for reactor fuel  

SciTech Connect

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

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

1994-03-16T23:59:59.000Z

200

Fabrication development for the Advanced Neutron Source Reactor  

SciTech Connect

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

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

1995-08-01T23:59:59.000Z

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


201

Nuclear Fuel Cycle Integrated System Analysis  

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

Fuel Cycle Integrated System Analysis Fuel Cycle Integrated System Analysis Abdellatif M. Yacout Argonne National Laboratory Nuclear Engineering Division The nuclear fuel cycle is a complex system with multiple components and activities that are combined to provide nuclear energy to a variety of end users. The end uses of nuclear energy are diverse and include electricity, process heat, water desalination, district heating, and possibly future hydrogen production for transportation and energy storage uses. Components of the nuclear fuel cycle include front end components such as uranium mining, conversion and enrichment, fuel fabrication, and the reactor component. Back end of the fuel cycle include used fuel coming out the reactor, used fuel temporary and permanent storage, and fuel reprocessing. Combined with those components there

202

Alternative Fuels Data Center: Alternative Fuel Use and Alternative Fuel  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fuel Use Fuel Use and Alternative Fuel Vehicle (AFV) Acquisition Requirements to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel Use and Alternative Fuel Vehicle (AFV) Acquisition Requirements on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel Use and Alternative Fuel Vehicle (AFV) Acquisition Requirements on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel Use and Alternative Fuel Vehicle (AFV) Acquisition Requirements on Google Bookmark Alternative Fuels Data Center: Alternative Fuel Use and Alternative Fuel Vehicle (AFV) Acquisition Requirements on Delicious Rank Alternative Fuels Data Center: Alternative Fuel Use and Alternative Fuel Vehicle (AFV) Acquisition Requirements on Digg Find More places to share Alternative Fuels Data Center: Alternative

203

Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fuel Fuel Vehicle (AFV) and Fueling Infrastructure Grants and Loans to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Grants and Loans on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Grants and Loans on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Grants and Loans on Google Bookmark Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Grants and Loans on Delicious Rank Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Grants and Loans on Digg Find More places to share Alternative Fuels Data Center: Alternative

204

Evaluation of fuel rod characterization for transient fuel modeling  

E-Print Network (OSTI)

-L, developed by Belgonucleaire, was the steady state fuel performance computer code employed to determine these sensitivities. To determine code uncertainties and differences during steady state operation, Maine Yankee Unit 1 and Oconee Unit 2 fuel rods were... CHAPI'ER VI. CONCLUSIONS Page V1 1X 14 21 21 21 25 27 37 37 38 40 46 54 Page REFERENCES APPENDIX A APPENDIX B VITA S7 LIST OF TABLES Table Page Pellet fabrication parameters for Maine Yankee Unit I and Oconee Unit 2 fuel rods 22...

Bechler, Eric Wayne

2012-06-07T23:59:59.000Z

205

Advanced Gas Reactor Fuel Program's TRISO Particle Fuel Sets A New World  

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

Advanced Gas Reactor Fuel Program's TRISO Particle Fuel Sets A New Advanced Gas Reactor Fuel Program's TRISO Particle Fuel Sets A New World Record For Irradiation Performance Advanced Gas Reactor Fuel Program's TRISO Particle Fuel Sets A New World Record For Irradiation Performance November 16, 2009 - 1:12pm Addthis As part of the Office of Nuclear Energy's Next Generation Nuclear Plant (NGNP) Program, the Advanced Gas Reactor (AGR) Fuel Development Program has achieved a new international record for irradiation testing of next-generation particle fuel for use in high temperature gas reactors (HTGRs). The AGR Fuel Development Program was initiated by the Department of Energy in 2002 to develop the advanced fabrication and characterization technologies, and provide irradiation and safety performance data required to license TRISO particle fuel for the NGNP and future HTGRs. The AGR

206

Biologically inspired digital fabrication  

E-Print Network (OSTI)

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

Han, Sarah (Sarah J.)

2013-01-01T23:59:59.000Z

207

Fabricated torque shaft  

DOE Patents (OSTI)

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

Mashey, Thomas Charles (Anderson, SC)

2002-01-01T23:59:59.000Z

208

Nuclear Fabrication Consortium  

SciTech Connect

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.

Levesque, Stephen

2013-04-05T23:59:59.000Z

209

Equipment specifications for an electrochemical fuel reprocessing plant  

SciTech Connect

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

Hemphill, Kevin P [Los Alamos National Laboratory

2010-01-01T23:59:59.000Z

210

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

E-Print Network (OSTI)

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

Desrosiers, Kevin Campbell

2002-01-01T23:59:59.000Z

211

Fuel pin  

DOE Patents (OSTI)

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

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

1987-11-24T23:59:59.000Z

212

Career Map: Assembler and Fabricator  

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

The Wind Program's Career Map provides job description information for Assembler and Fabricator positions.

213

Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

and Fueling Infrastructure Funding and Technical Assistance and Fueling Infrastructure Funding and Technical Assistance to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Funding and Technical Assistance on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Funding and Technical Assistance on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Funding and Technical Assistance on Google Bookmark Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Funding and Technical Assistance on Delicious Rank Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Funding and Technical Assistance on Digg

214

Fuel System and Fuel Measurement  

Science Journals Connector (OSTI)

Fuel management provides optimal solutions to reduce fuel consumption. Merchant vessels, such as container ships, drive at a reduced speed to save fuel since the reduction of the speed from...?1 lowers consumption

Michael Palocz-Andresen

2013-01-01T23:59:59.000Z

215

Alternative Fuels Data Center: Alternative Fuel and Special Fuel  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fuel and Fuel and Special Fuel Definitions to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel and Special Fuel Definitions on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel and Special Fuel Definitions on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel and Special Fuel Definitions on Google Bookmark Alternative Fuels Data Center: Alternative Fuel and Special Fuel Definitions on Delicious Rank Alternative Fuels Data Center: Alternative Fuel and Special Fuel Definitions on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuel and Special Fuel Definitions on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Alternative Fuel and Special Fuel Definitions

216

Alternative Fuels Data Center: Alternative Fuel Motor Carrier Fuel Tax  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fuel Motor Fuel Motor Carrier Fuel Tax to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel Motor Carrier Fuel Tax on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel Motor Carrier Fuel Tax on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel Motor Carrier Fuel Tax on Google Bookmark Alternative Fuels Data Center: Alternative Fuel Motor Carrier Fuel Tax on Delicious Rank Alternative Fuels Data Center: Alternative Fuel Motor Carrier Fuel Tax on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuel Motor Carrier Fuel Tax on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Alternative Fuel Motor Carrier Fuel Tax Effective January 1, 2014, a person who operates a commercial motor vehicle

217

Covering Walls With Fabrics.  

E-Print Network (OSTI)

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

Anonymous,

1979-01-01T23:59:59.000Z

218

A global approach of the representativity concept: Application on a high-conversion light water reactor MOX lattice case  

SciTech Connect

The development of new types of reactor and the increase in the safety specifications and requirements induce an enhancement in both nuclear data knowledge and a better understanding of the neutronic properties of the new systems. This enhancement is made possible using ad hoc critical mock-up experiments. The main difficulty is to design these experiments in order to obtain the most valuable information. Its quantification is usually made by using representativity and transposition concepts. These theories enable to extract some information about a quantity of interest (an integral parameter) on a configuration, but generally a posteriori. This paper presents a more global approach of this theory, with the idea of optimizing the representativity of a new experiment, and its transposition a priori, based on a multiparametric approach. Using a quadratic sum, we show the possibility to define a global representativity which permits to take into account several quantities of interest at the same time. The maximization of this factor gives information about all quantities of interest. An optimization method of this value in relation to technological parameters (over-clad diameter, atom concentration) is illustrated on a high-conversion light water reactor MOX lattice case. This example tackles the problematic of plutonium experiment for the plutonium aging and a solution through the optimization of both the over-clad and the plutonium content. (authors)

Santos, N. D.; Blaise, P.; Santamarina, A. [CEA, DEN/DER/SPRC Cadarache, F-13108 Saint Paul-lez-Durance (France)

2013-07-01T23:59:59.000Z

219

Microstructured Hydrogen Fuel Cells  

Science Journals Connector (OSTI)

Micro fuel cells ; Polymer electrolyte membrane fuel cells ; Proton exchange membrane fuel cells ...

Luc G. Frechette

2014-05-01T23:59:59.000Z

220

Alternative Fuels Data Center: Alternative Fuel Definition  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fuel Fuel Definition to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel Definition on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel Definition on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel Definition on Google Bookmark Alternative Fuels Data Center: Alternative Fuel Definition on Delicious Rank Alternative Fuels Data Center: Alternative Fuel Definition on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuel Definition on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Alternative Fuel Definition The definition of an alternative fuel includes natural gas, liquefied petroleum gas, electricity, hydrogen, fuel mixtures containing not less

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


221

Alternative Fuels Data Center: Ethanol Fueling Stations  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fueling Fueling Stations to someone by E-mail Share Alternative Fuels Data Center: Ethanol Fueling Stations on Facebook Tweet about Alternative Fuels Data Center: Ethanol Fueling Stations on Twitter Bookmark Alternative Fuels Data Center: Ethanol Fueling Stations on Google Bookmark Alternative Fuels Data Center: Ethanol Fueling Stations on Delicious Rank Alternative Fuels Data Center: Ethanol Fueling Stations on Digg Find More places to share Alternative Fuels Data Center: Ethanol Fueling Stations on AddThis.com... More in this section... Ethanol Basics Benefits & Considerations Stations Locations Infrastructure Development Vehicles Laws & Incentives Ethanol Fueling Stations Photo of an ethanol fueling station. Thousands of ethanol fueling stations are available in the United States.

222

Alternative Fuels Data Center: Alternative Fuel Promotion  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Alternative Fuel Alternative Fuel Promotion to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel Promotion on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel Promotion on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel Promotion on Google Bookmark Alternative Fuels Data Center: Alternative Fuel Promotion on Delicious Rank Alternative Fuels Data Center: Alternative Fuel Promotion on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuel Promotion on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Alternative Fuel Promotion The Missouri Alternative Fuels Commission (Commission) promotes the continued production and use of alternative transportation fuels in

223

Alternative Fuels Data Center: Hydrogen Fueling Stations  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fueling Fueling Stations to someone by E-mail Share Alternative Fuels Data Center: Hydrogen Fueling Stations on Facebook Tweet about Alternative Fuels Data Center: Hydrogen Fueling Stations on Twitter Bookmark Alternative Fuels Data Center: Hydrogen Fueling Stations on Google Bookmark Alternative Fuels Data Center: Hydrogen Fueling Stations on Delicious Rank Alternative Fuels Data Center: Hydrogen Fueling Stations on Digg Find More places to share Alternative Fuels Data Center: Hydrogen Fueling Stations on AddThis.com... More in this section... Hydrogen Basics Benefits & Considerations Stations Locations Infrastructure Development Vehicles Laws & Incentives Hydrogen Fueling Stations Photo of a hydrogen fueling station. A handful of hydrogen fueling stations are available in the United States

224

Alternative Fuels Data Center: Biodiesel Fueling Stations  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fueling Fueling Stations to someone by E-mail Share Alternative Fuels Data Center: Biodiesel Fueling Stations on Facebook Tweet about Alternative Fuels Data Center: Biodiesel Fueling Stations on Twitter Bookmark Alternative Fuels Data Center: Biodiesel Fueling Stations on Google Bookmark Alternative Fuels Data Center: Biodiesel Fueling Stations on Delicious Rank Alternative Fuels Data Center: Biodiesel Fueling Stations on Digg Find More places to share Alternative Fuels Data Center: Biodiesel Fueling Stations on AddThis.com... More in this section... Biodiesel Basics Benefits & Considerations Stations Locations Infrastructure Development Vehicles Laws & Incentives Biodiesel Fueling Stations Photo of a biodiesel fueling station. Hundreds of biodiesel fueling stations are available in the United States.

225

Design and Testing of Prototypic Elements Containing Monolithic Fuel  

SciTech Connect

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

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

2011-10-01T23:59:59.000Z

226

Lithographic fabrication of nanoapertures  

DOE Patents (OSTI)

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

Fleming, James G. (Albuquerque, NM)

2003-01-01T23:59:59.000Z

227

Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Alternative Fuel Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Loans to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Loans on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Loans on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Loans on Google Bookmark Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Loans on Delicious Rank Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Loans on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Loans on AddThis.com...

228

Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Alternative Fuel Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Grants to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Grants on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Grants on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Grants on Google Bookmark Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Grants on Delicious Rank Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Grants on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Grants on AddThis.com...

229

Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Alternative Fuel Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Tax Credit to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Tax Credit on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Tax Credit on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Tax Credit on Google Bookmark Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Tax Credit on Delicious Rank Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Tax Credit on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Tax Credit on AddThis.com...

230

Alternative Fuels Data Center: Alternative Fuel and Alternative Fuel  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Alternative Fuel and Alternative Fuel and Alternative Fuel Vehicle (AFV) Fund to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel and Alternative Fuel Vehicle (AFV) Fund on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel and Alternative Fuel Vehicle (AFV) Fund on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel and Alternative Fuel Vehicle (AFV) Fund on Google Bookmark Alternative Fuels Data Center: Alternative Fuel and Alternative Fuel Vehicle (AFV) Fund on Delicious Rank Alternative Fuels Data Center: Alternative Fuel and Alternative Fuel Vehicle (AFV) Fund on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuel and Alternative Fuel Vehicle (AFV) Fund on AddThis.com... More in this section...

231

Alternative Fuels Data Center: Alternative Fuel and Alternative Fuel  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fuel and Fuel and Alternative Fuel Vehicle (AFV) Tax Exemption to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel and Alternative Fuel Vehicle (AFV) Tax Exemption on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel and Alternative Fuel Vehicle (AFV) Tax Exemption on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel and Alternative Fuel Vehicle (AFV) Tax Exemption on Google Bookmark Alternative Fuels Data Center: Alternative Fuel and Alternative Fuel Vehicle (AFV) Tax Exemption on Delicious Rank Alternative Fuels Data Center: Alternative Fuel and Alternative Fuel Vehicle (AFV) Tax Exemption on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuel and Alternative Fuel Vehicle (AFV) Tax Exemption on AddThis.com...

232

RERTR Fuel Developmemt and Qualification Plan  

SciTech Connect

In late 2003 it became evident that U-Mo aluminum fuels under development exhibited significant fuel performance problems under the irradiation conditions required for conversion of most high-powered research reactors. Solutions to the fuel performance issue have been proposed and show promise in early testing. Based on these results, a Reduced Enrichment Research and Test Reactor (RERTR) program strategy has been mapped to allow generic fuel qualification to occur prior to the end of FY10 and reactor conversion to occur prior to the end of FY14. This strategy utilizes a diversity of technologies, test conditions, and test types. Scoping studies using miniature fuel plates will be completed in the time frame of 2006-2008. Irradiation of larger specimens will occur in the Advanced Test Reactor (ATR) in the United States, the Belgian Reactor-2 (BR2) reactor in Belgium, and in the OSIRIS reactor in France in 2006-2009. These scoping irradiation tests provide a large amount of data on the performance of advanced fuel types under irradiation and allow the down selection of technology for larger scale testing during the final stages of fuel qualification. In conjunction with irradiation testing, fabrication processes must be developed and made available to commercial fabricators. The commercial fabrication infrastructure must also be upgraded to ensure a reliable low enriched uranium (LEU) fuel supply. Final qualification of fuels will occur in two phases. Phase I will obtain generic approval for use of dispersion fuels with density less than 8.5 g-U/cm3. In order to obtain this approval, a larger scale demonstration of fuel performance and fabrication technology will be necessary. Several Materials Test Reactor (MTR) plate-type fuel assemblies will be irradiated in both the High Flux Reactor (HFR) and the ATR (other options include the BR2 and Russian Research Reactor, Dmitrovgrad, Russia [MIR] reactors) in 2008-2009. Following postirradiation examination, a report detailing very-high density fuel behavior will be submitted to the U.S. Nuclear Regulatory Commission (NRC). Assuming acceptable fuel behavior, it is anticipated that NRC will issue a Safety Evaluation Report granting generic approval of the developed fuels based on the qualification report. It is anticipated that Phase I of fuel qualification will be completed prior to the end of FY10. Phase II of the fuel qualification requires development of fuels with density greater than 8.5 g-U/cm3. This fuel is required to convert the remaining few reactors that have been identified for conversion. The second phase of the fuel qualification effort includes both dispersion fuels with fuel particle volume loading on the order of 65 percent, and monolithic fuels. Phase II presents a larger set of technical unknowns and schedule uncertainties than phase I. The final step in the fuel qualification process involves insertion of lead test elements into the converting reactors. Each reactor that plans to convert using the developed high-density fuels will develop a reactor specific conversion plan based upon the reactor safety basis and operating requirements. For some reactors (FRM-II, High-Flux Isotope Reactor [HFIR], and RHF) conversion will be a one-step process. In addition to the U.S. fuel development effort, a Russian fuel development strategy has been developed. Contracts with Russian Federation institutes in support of fuel development for Russian are in place.

Dan Wachs

2007-01-01T23:59:59.000Z

233

Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fueling Infrastructure Grants to someone by E-mail Fueling Infrastructure Grants to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Grants on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Grants on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Grants on Google Bookmark Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Grants on Delicious Rank Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Grants on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Fueling Infrastructure Grants on AddThis.com...

234

Recent developments in MEMS-based miniature fuel cells  

Science Journals Connector (OSTI)

Micro fuel cells (?-FCs) represent promising power sources for portable applications. Today, one of the technological ways to make ?-FCs is to have recourse to standard microfabrication techniques used in the fabrication of micro-electro-mechanical ...

Tristan Pichonat; Bernard Gauthier-Manuel

2007-05-01T23:59:59.000Z

235

Synthetic Fuel  

ScienceCinema (OSTI)

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

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

2010-01-08T23:59:59.000Z

236

ME 4171 Environmentally Conscious Design & Manufacturing (Bras) Assignment Aircraft Fuel Tank Production Pollution Prevention  

E-Print Network (OSTI)

ME 4171 ­ Environmentally Conscious Design & Manufacturing (Bras) Assignment ­ Aircraft Fuel Tank Production Pollution Prevention A local company manufactures a wide variety of fabric fuel tanks for use mainly in the aircraft industry. The main reasons for using fabric in the construction of these tanks

237

Transmutation Dynamics: Impacts of Multi-Recycling on Fuel Cycle Performances  

SciTech Connect

From a physics standpoint, it is feasible to sustain continuous multi-recycle in either thermal or fast reactors. In Fiscal Year 2009, transmutaton work at INL provided important new insight, caveats, and tools on multi-recycle. Multi-recycle of MOX, even with all the transuranics, is possible provided continuous enrichment of the uranium phase to ~6.5% and also limitting the transuranic enrichment to slightly less than 8%. Multi-recycle of heterogeneous-IMF assemblies is possible with continuous enrichment of the UOX pins to ~4.95% and having =60 of the 264 fuel pins being inter-matrix. A new tool enables quick assessment of the impact of different cooling times on isotopic evolution. The effect of cooling time was found to be almost as controlling on higher mass actinide concentrations in fuel as the selection of thermal versus fast neutron spectra. A new dataset was built which provides on-the-fly estimates of gamma and neutron dose in MOX fuels as a function of the isotopic evolution. All studies this year focused on the impact of dynamic feedback due to choices made in option space. Both the equilibrium fuel cycle concentrations and the transient time to reach equilibrium for each isotope were evaluated over a range of reactor, reprocessing and cooling time combinations. New bounding cases and analysis methods for evaluating both reactor safety and radiation worker safety were established. This holistic collection of physics analyses and methods gives improved resolution of fuel cycle options, and impacts thereof, over that of previous ad-hoc and single-point analyses.

S. Bays; S. Piet; M. Pope; G. Youinou; A. Dumontier; D. Hawn

2009-09-01T23:59:59.000Z

238

New developments and prospects on COSI, the simulation software for fuel cycle analysis  

SciTech Connect

COSI, software developed by the Nuclear Energy Direction of the CEA, is a code simulating a pool of nuclear power plants with its associated fuel cycle facilities. This code has been designed to study various short, medium and long term options for the introduction of various types of nuclear reactors and for the use of associated nuclear materials. In the frame of the French Act for waste management, scenario studies are carried out with COSI, to compare different options of evolution of the French reactor fleet and options of partitioning and transmutation of plutonium and minor actinides. Those studies aim in particular at evaluating the sustainability of Sodium cooled Fast Reactors (SFR) deployment and the possibility to transmute minor actinides. The COSI6 version is a completely renewed software released in 2006. COSI6 is now coupled with the last version of CESAR (CESAR5.3 based on JEFF3.1.1 nuclear data) allowing the calculations on irradiated fuel with 200 fission products and 100 heavy nuclides. A new release is planned in 2013, including in particular the coupling with a recommended database of reactors. An exercise of validation of COSI6, carried out on the French PWR historic nuclear fleet, has been performed. During this exercise quantities like cumulative natural uranium consumption, or cumulative depleted uranium, or UOX/MOX spent fuel storage, or stocks of reprocessed uranium, or plutonium content in fresh MOX fuel, or the annual production of high level waste, have been computed by COSI6 and compared to industrial data. The results have allowed us to validate the essential phases of the fuel cycle computation, and reinforces the credibility of the results provided by the code.

Eschbach, R.; Meyer, M.; Coquelet-Pascal, C.; Tiphine, M.; Krivtchik, G.; Cany, C. [Atomic Energy and Alternative Energies Commission - CEA, CEA-Cadarache, DEN, DER, SPRC, F-13108 Saint-Paul-lez-Durance (France)

2013-07-01T23:59:59.000Z

239

Alternative Fuels Data Center: Alternative Fueling Infrastructure  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Alternative Fueling Alternative Fueling Infrastructure Development to someone by E-mail Share Alternative Fuels Data Center: Alternative Fueling Infrastructure Development on Facebook Tweet about Alternative Fuels Data Center: Alternative Fueling Infrastructure Development on Twitter Bookmark Alternative Fuels Data Center: Alternative Fueling Infrastructure Development on Google Bookmark Alternative Fuels Data Center: Alternative Fueling Infrastructure Development on Delicious Rank Alternative Fuels Data Center: Alternative Fueling Infrastructure Development on Digg Find More places to share Alternative Fuels Data Center: Alternative Fueling Infrastructure Development on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type

240

Alternative Fuels Data Center: Emerging Fuels  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Emerging Fuels Emerging Fuels Printable Version Share this resource Send a link to Alternative Fuels Data Center: Emerging Fuels to someone by E-mail Share Alternative Fuels Data Center: Emerging Fuels on Facebook Tweet about Alternative Fuels Data Center: Emerging Fuels on Twitter Bookmark Alternative Fuels Data Center: Emerging Fuels on Google Bookmark Alternative Fuels Data Center: Emerging Fuels on Delicious Rank Alternative Fuels Data Center: Emerging Fuels on Digg Find More places to share Alternative Fuels Data Center: Emerging Fuels on AddThis.com... More in this section... Biobutanol Drop-In Biofuels Methanol P-Series Renewable Natural Gas xTL Fuels Emerging Alternative Fuels Several emerging alternative fuels are under development or already developed and may be available in the United States. These fuels may

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


241

Fuel Cells  

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

Fuel Cells 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 as the space shuttle. Although fuel cells have been successfully used in such applications, they have proven difficult to make more cost-effective and durable for commercial applications, particularly for the rigors of daily transportation. Since the 1970s, scientists at Los Alamos have managed to make various scientific breakthroughs that have contributed to the development of modern fuel cell systems. Specific efforts include the following: * Finding alternative and more cost-effective catalysts than platinum. * Enhancing the durability of fuel cells by developing advanced materials and

242

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

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

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

243

IT IS 5 MINUTES TO MIDNIGHT www.thebulletin.org  

E-Print Network (OSTI)

in the environmental impact of uranium mining. Additionally, if the United States considers building fast reactors that the high cost of reprocessing spent fuel and fabricating mixed-oxide (MOX) fuel rods--a mixture of uranium volumetric reduction in nuclear waste, conservation of uranium re- sources, and a reduction

Holmes, Christopher D.

244

Intraocular lens fabrication  

DOE Patents (OSTI)

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

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

1997-07-08T23:59:59.000Z

245

Intraocular lens fabrication  

DOE Patents (OSTI)

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

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

1997-01-01T23:59:59.000Z

246

Life cycle costs for the domestic reactor-based plutonium disposition option  

SciTech Connect

Projected constant dollar life cycle cost (LCC) estimates are presented for the domestic reactor-based plutonium disposition program being managed by the US Department of Energy Office of Fissile Materials Disposition (DOE/MD). The scope of the LCC estimate includes: design, construction, licensing, operation, and deactivation of a mixed-oxide (MOX) fuel fabrication facility (FFF) that will be used to purify and convert weapons-derived plutonium oxides to MOX fuel pellets and fabricate MOX fuel bundles for use in commercial pressurized-water reactors (PWRs); fuel qualification activities and modification of facilities required for manufacture of lead assemblies that will be used to qualify and license this MOX fuel; and modification, licensing, and operation of commercial PWRs to allow irradiation of a partial core of MOX fuel in combination with low-enriched uranium fuel. The baseline cost elements used for this document are the same as those used for examination of the preferred sites described in the site-specific final environmental impact statement and in the DOE Record of Decision that will follow in late 1999. Cost data are separated by facilities, government accounting categories, contract phases, and expenditures anticipated by the various organizations who will participate in the program over a 20-year period. Total LCCs to DOE/MD are projected at approximately $1.4 billion for a 33-MT plutonium disposition mission.

Williams, K.A.

1999-10-01T23:59:59.000Z

247

Method of electrode fabrication for solid oxide electrochemical cells  

DOE Patents (OSTI)

A process for fabricating cermet electrodes for solid oxide electrochemical cells by sintering is disclosed. First, a porous metal electrode is fabricated on a solid oxide cell, such as a fuel cell by, for example, sintering, and is then infiltrated with a high volume fraction stabilized zirconia suspension. A second sintering step is used to sinter the infiltrated zirconia to a high density in order to more securely attach the electrode to the solid oxide electrolyte of the cell. High performance fuel electrodes can be obtained with this process. Further electrode performance enhancement may be achieved if stabilized zirconia doped with cerium oxide, chromium oxide, titanium oxide, and/or praseodymium oxide for electronic conduction is used.

Jensen, Russell R. (Murrysville, PA)

1990-01-01T23:59:59.000Z

248

Method of electrode fabrication for solid oxide electrochemical cells  

DOE Patents (OSTI)

A process for fabricating cermet electrodes for solid oxide electrochemical cells by sintering is disclosed. First, a porous metal electrode is fabricated on a solid oxide cell, such as a fuel cell by, for example, sintering, and is then infiltrated with a high volume fraction stabilized zirconia suspension. A second sintering step is used to sinter the infiltrated zirconia to a high density in order to more securely attach the electrode to the solid oxide electrolyte of the cell. High performance fuel electrodes can be obtained with this process. Further electrode performance enhancement may be achieved if stabilized zirconia doped with cerium oxide, chromium oxide, titanium oxide, and/or praseodymium oxide for electronic conduction is used. 5 figs.

Jensen, R.R.

1990-11-20T23:59:59.000Z

249

U-Mo Foil/Cladding Interactions in Friction Stir Welded Monolithic RERTR Fuel Plates  

SciTech Connect

Interaction between U-Mo fuel and Al has proven to dramatically impact the overall irradiation performance of RERTR dispersion fuels. It is of interest to better understand how similar interactions may affect the performance of monolithic fuel plates, where a uranium alloy fuel is sandwiched between aluminum alloy cladding. The monolithic fuel plate removes the fuel matrix entirely, which reduces the total surface area of the fuel that is available to react with the aluminum and moves the interface between the fuel and cladding to a colder region of the fuel plate. One of the major fabrication techniques for producing monolithic fuel plates is friction stir welding. This paper will discuss the interactions that can occur between the U-Mo foil and 6061 Al cladding when applying this fabrication technique. It has been determined that the time at high temperatures should be limited as much as is possible during fabrication or any post-fabrication treatment to reduce as much as possible the interactions between the foil and cladding. Without careful control of the fabrication process, significant interaction between the U-Mo foil and Al alloy cladding can result. The reaction layers produced from such interactions can exhibit notably different morphologies vis-à-vis those typically observed for dispersion fuels.

D.D. Keiser; J.F. Jue; C.R. Clark

2006-10-01T23:59:59.000Z

250

Advanced Fuels Campaign FY 2010 Accomplishments Report  

SciTech Connect

The Fuel Cycle Research and Development (FCRD) Advanced Fuels Campaign (AFC) Accomplishment Report documents the high-level research and development results achieved in fiscal year 2010. The AFC program has been given responsibility to develop advanced fuel technologies for the Department of Energy (DOE) using a science-based approach focusing on developing a microstructural understanding of nuclear fuels and materials. The science-based approach combines theory, experiments, and multi-scale modeling and simulation aimed at a fundamental understanding of the fuel fabrication processes and fuel and clad performance under irradiation. The scope of the AFC includes evaluation and development of multiple fuel forms to support the three fuel cycle options described in the Sustainable Fuel Cycle Implementation Plan4: Once-Through Cycle, Modified-Open Cycle, and Continuous Recycle. The word “fuel” is used generically to include fuels, targets, and their associated cladding materials. This document includes a brief overview of the management and integration activities; but is primarily focused on the technical accomplishments for FY-10. Each technical section provides a high level overview of the activity, results, technical points of contact, and applicable references.

Lori Braase

2010-12-01T23:59:59.000Z

251

Fuel Cells  

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

Materials Science » Materials Science » Fuel Cells Fuel Cells Research into alternative forms of energy, especially energy security, is one of the major national security imperatives of this century. Get Expertise Melissa Fox Applied Energy Email Catherine Padro Sensors & Electrochemical Devices Email Fernando Garzon Sensors & Electrochemical Devices Email Piotr Zelenay Sensors & Electrochemical Devices Email Rod Borup Sensors & Electrochemical Devices Email Karen E. Kippen Experimental Physical Sciences Email Like a battery, a fuel cell consists of two electrodes separated by an electrolyte-in polymer electrolyte fuel cells, the separator is made of a thin polymeric membrane. Unlike a battery, a fuel cell does not need recharging-it continues to produce electricity as long as fuel flows

252

Alternative Fuels Data Center: Fuel Prices  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Vehicles Vehicles Printable Version Share this resource Send a link to Alternative Fuels Data Center: Fuel Prices to someone by E-mail Share Alternative Fuels Data Center: Fuel Prices on Facebook Tweet about Alternative Fuels Data Center: Fuel Prices on Twitter Bookmark Alternative Fuels Data Center: Fuel Prices on Google Bookmark Alternative Fuels Data Center: Fuel Prices on Delicious Rank Alternative Fuels Data Center: Fuel Prices on Digg Find More places to share Alternative Fuels Data Center: Fuel Prices on AddThis.com... Fuel Prices As gasoline prices increase, alternative fuels appeal more to vehicle fleet managers and consumers. Like gasoline, alternative fuel prices can fluctuate based on location, time of year, and political climate. Alternative Fuel Price Report

253

Alternative Fuels Data Center: Alternative Fuel License  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fuel Fuel License to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel License on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel License on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel License on Google Bookmark Alternative Fuels Data Center: Alternative Fuel License on Delicious Rank Alternative Fuels Data Center: Alternative Fuel License on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuel License on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Alternative Fuel License Any person acting as an alternative fuels dealer must hold a valid alternative fuel license and certificate from the Wisconsin Department of Administration. Except for alternative fuels that a dealer delivers into a

254

Alternative Fuels Data Center: Alternative Fuel License  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fuel Fuel License to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel License on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel License on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel License on Google Bookmark Alternative Fuels Data Center: Alternative Fuel License on Delicious Rank Alternative Fuels Data Center: Alternative Fuel License on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuel License on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Alternative Fuel License Alternative fuel providers, bulk users, and retailers, or any person who fuels an alternative fuel vehicle from a private source that does not pay

255

Fuel Cells  

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

Fuel Cells Fuel Cells The Solid State Energy Conversion Alliance (SECA) program is responsible for coordinating Federal efforts to facilitate development of a commercially relevant and robust solid oxide fuel cell (SOFC) system. Specific objectives include achieving an efficiency of greater than 60 percent, meeting a stack cost target of $175 per kW, and demonstrating lifetime performance degradation of less than 0.2 percent per

256

Economic prospects of the Integral Fast Reactor (IFR) fuel cycle  

SciTech Connect

The IFR fuel cycle based on pyroprocessing involves only few operational steps and the batch-oriented process equipment systems are compact. This results in major cost reductions in all of three areas of reprocessing, fabrication, and waste treatment. This document discusses the economic aspects of this fuel cycle.

Chang, Y.I.; Till, C.E.

1991-01-01T23:59:59.000Z

257

Alternative fuels  

SciTech Connect

This paper presents the preliminary results of a review, of the experiences of Brazil, Canada, and New Zealand, which have implemented programs to encourage the use of alternative motor fuels. It will also discuss the results of a separate completed review of the Department of Energy's (DOE) progress in implementing the Alternative Motor Fuels Act of 1988. The act calls for, among other things, the federal government to use alternative-fueled vehicles in its fleet. The Persian Gulf War, environmental concerns, and the administration's National Energy Strategy have greatly heightened interest in the use of alternative fuels in this country.

Not Available

1991-07-01T23:59:59.000Z

258

Fuel Cells  

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

Fuel Cells The Solid State Energy Conversion Alliance (SECA) program is responsible for coordinating Federal efforts to facilitate development of a commercially relevant and robust...

259

Alternative Fuels Data Center: Electricity Fuel Basics  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Electricity Fuel Electricity Fuel Basics to someone by E-mail Share Alternative Fuels Data Center: Electricity Fuel Basics on Facebook Tweet about Alternative Fuels Data Center: Electricity Fuel Basics on Twitter Bookmark Alternative Fuels Data Center: Electricity Fuel Basics on Google Bookmark Alternative Fuels Data Center: Electricity Fuel Basics on Delicious Rank Alternative Fuels Data Center: Electricity Fuel Basics on Digg Find More places to share Alternative Fuels Data Center: Electricity Fuel Basics on AddThis.com... More in this section... Electricity Basics Production & Distribution Research & Development Related Links Benefits & Considerations Stations Vehicles Laws & Incentives Electricity Fuel Basics Photo of a plug-in hybrid vehicle fueling. Electricity is considered an alternative fuel under the Energy Policy Act

260

Alternative Fuels Data Center: Alternative Fuel Definition  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Alternative Fuel Alternative Fuel Definition to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel Definition on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel Definition on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel Definition on Google Bookmark Alternative Fuels Data Center: Alternative Fuel Definition on Delicious Rank Alternative Fuels Data Center: Alternative Fuel Definition on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuel Definition on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Alternative Fuel Definition The following fuels are defined as alternative fuels by the Energy Policy Act (EPAct) of 1992: pure methanol, ethanol, and other alcohols; blends of

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


261

Alternative Fuels Data Center: Alternative Fuels Tax  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fuels Tax Fuels Tax to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuels Tax on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuels Tax on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuels Tax on Google Bookmark Alternative Fuels Data Center: Alternative Fuels Tax on Delicious Rank Alternative Fuels Data Center: Alternative Fuels Tax on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuels Tax on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Alternative Fuels Tax A state excise tax is imposed on the use of alternative fuels. Alternative fuels include liquefied petroleum gas (LPG or propane), compressed natural gas (CNG), and liquefied natural gas (LNG). The current tax rates are as

262

Alternative Fuels Data Center: Renewable Fuel Standard  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Renewable Fuel Renewable Fuel Standard to someone by E-mail Share Alternative Fuels Data Center: Renewable Fuel Standard on Facebook Tweet about Alternative Fuels Data Center: Renewable Fuel Standard on Twitter Bookmark Alternative Fuels Data Center: Renewable Fuel Standard on Google Bookmark Alternative Fuels Data Center: Renewable Fuel Standard on Delicious Rank Alternative Fuels Data Center: Renewable Fuel Standard on Digg Find More places to share Alternative Fuels Data Center: Renewable Fuel Standard on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Renewable Fuel Standard RFS Volumes by Year Enlarge illustration The Renewable Fuel Standard (RFS) is a federal program that requires transportation fuel sold in the U.S. to contain a minimum volume of

263

Alternative Fuels Data Center: Alternative Fuels Tax  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Alternative Fuels Tax Alternative Fuels Tax to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuels Tax on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuels Tax on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuels Tax on Google Bookmark Alternative Fuels Data Center: Alternative Fuels Tax on Delicious Rank Alternative Fuels Data Center: Alternative Fuels Tax on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuels Tax on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Alternative Fuels Tax Excise taxes on alternative fuels are imposed on a gasoline gallon equivalent basis. The tax rate for each alternative fuel type is based on the number of motor vehicles licensed in the state that use the specific

264

Alternative Fuels Data Center: Alternative Fuel Loans  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fuel Loans Fuel Loans to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel Loans on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel Loans on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel Loans on Google Bookmark Alternative Fuels Data Center: Alternative Fuel Loans on Delicious Rank Alternative Fuels Data Center: Alternative Fuel Loans on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuel Loans on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Alternative Fuel Loans The Oregon Department of Energy administers the State Energy Loan Program (SELP) which offers low-interest loans for qualified projects. Eligible alternative fuel projects include fuel production facilities, dedicated

265

Alternative Fuels Data Center: Alternative Fuels Tax  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fuels Tax Fuels Tax to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuels Tax on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuels Tax on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuels Tax on Google Bookmark Alternative Fuels Data Center: Alternative Fuels Tax on Delicious Rank Alternative Fuels Data Center: Alternative Fuels Tax on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuels Tax on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Alternative Fuels Tax Alternative fuels are subject to an excise tax at a rate of $0.205 per gasoline gallon equivalent, with a variable component equal to at least 5% of the average wholesale price of the fuel. (Reference Senate Bill 454,

266

Alternative Fuels Data Center: Alternative Fuels Tax  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fuels Tax Fuels Tax to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuels Tax on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuels Tax on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuels Tax on Google Bookmark Alternative Fuels Data Center: Alternative Fuels Tax on Delicious Rank Alternative Fuels Data Center: Alternative Fuels Tax on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuels Tax on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Alternative Fuels Tax The excise tax imposed on an alternative fuel distributed in New Mexico is $0.12 per gallon. Alternative fuels subject to the excise tax include liquefied petroleum gas (or propane), compressed natural gas, and liquefied

267

Alternative Fuels Data Center: Alternative Fuel Tax  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Alternative Fuel Tax Alternative Fuel Tax to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel Tax on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel Tax on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel Tax on Google Bookmark Alternative Fuels Data Center: Alternative Fuel Tax on Delicious Rank Alternative Fuels Data Center: Alternative Fuel Tax on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuel Tax on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Alternative Fuel Tax The Minnesota Department of Revenue imposes an excise tax on the first licensed distributor that receives E85 fuel products in the state and on distributors, special fuel dealers, or bulk purchasers of other alternative

268

Development of alkaline fuel cells.  

SciTech Connect

This project focuses on the development and demonstration of anion exchange membrane (AEM) fuel cells for portable power applications. Novel polymeric anion exchange membranes and ionomers with high chemical stabilities were prepared characterized by researchers at Sandia National Laboratories. Durable, non-precious metal catalysts were prepared by Dr. Plamen Atanassov's research group at the University of New Mexico by utilizing an aerosol-based process to prepare templated nano-structures. Dr. Andy Herring's group at the Colorado School of Mines combined all of these materials to fabricate and test membrane electrode assemblies for single cell testing in a methanol-fueled alkaline system. The highest power density achieved in this study was 54 mW/cm2 which was 90% of the project target and the highest reported power density for a direct methanol alkaline fuel cell.

Hibbs, Michael R.; Jenkins, Janelle E.; Alam, Todd Michael; Janarthanan, Rajeswari [Colorado School of Mines, Golden, CO; Horan, James L. [Colorado School of Mines, Golden, CO; Caire, Benjamin R. [Colorado School of Mines, Golden, CO; Ziegler, Zachary C. [Colorado School of Mines, Golden, CO; Herring, Andrew M. [Colorado School of Mines, Golden, CO; Yang, Yuan [Colorado School of Mines, Golden, CO; Zuo, Xiaobing [Argonne National Laboratory, Argonne, IL; Robson, Michael H. [University of New Mexico, Albuquerque, NM; Artyushkova, Kateryna [University of New Mexico, Albuquerque, NM; Patterson, Wendy [University of New Mexico, Albuquerque, NM; Atanassov, Plamen Borissov [University of New Mexico, Albuquerque, NM

2013-09-01T23:59:59.000Z

269

MCWO - Linking MCNP And ORIGEN2 For Fuel Burnup Analysis  

SciTech Connect

The UNIX BASH (Bourne Again Shell) script MCWO has been developed at the Idaho National Engineering and Environment Laboratory (INEEL) to couple the Monte Carlo transport code MCNP with the depletion and buildup code ORIGEN2. MCWO is a fully automated tool that links the Monte Carlo transport code MCNP with the radioactive decay and burnup code ORIGEN2. MCWO can handle a large number of fuel burnup and material loading specifications, Advanced Test Reactor (ATR) powers, and irradiation time intervals. The program processes input from the user that specifies the system geometry, initial material compositions, feed/removal specifications, and other code-specific parameters. Calculated results from MCNP, ORIGEN2, and data process module calculations are then output successively as the code runs. The principal function of MCWO is to transfer one-group cross-section and flux values from MCNP to ORIGEN2, and then transfer the resulting material compositions (after irradiation and/or decay) from ORIGEN2 back to MCNP in a repeated, cyclic fashion. The basic requirement of the code is that the user have a working MCNP input file and other input parameters; all interaction with ORIGEN2 and other calculations are performed by UNIX BASH script MCWO. This paper presents the MCWO-calculated results of the RERTR-1 and -2 , and the Weapons-Grade Mixed Oxiide fuel (Wg-MOX) fuel experiments in ATR and compares the MCWO-calculated results with the measured data.

Gray S Chang

2005-04-01T23:59:59.000Z

270

Tenth target fabrication specialists` meeting: Proceedings  

SciTech Connect

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

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

1995-11-01T23:59:59.000Z

271

Fuel Research  

Science Journals Connector (OSTI)

... FUEL research was discussed by Sir Harry McGowan, who succeeds Sir William Larke as president of the Institute of Fuel, in ... has a ragged front, and new knowledge is continually changing relative national positions. Sir Harry McGowan referred to the domestic use of raw coal, which is still preferred to ...

1934-11-24T23:59:59.000Z

272

Determination of Plutonium Content in Spent Fuel with Nondestructive Assay  

E-Print Network (OSTI)

SMOPY a new NDA tool for safeguards of LEU and MOX spenton Facility Operations – Safeguards Interface, Portland, (on International Safeguards: Addressing Verification

Tobin, S. J.

2010-01-01T23:59:59.000Z

273

Sulfonated Polysulfone/POSS Nanofiber Composite Membranes for PEM Fuel Cells  

E-Print Network (OSTI)

Sulfonated Polysulfone/POSS Nanofiber Composite Membranes for PEM Fuel Cells Jonghyun Choi. Historically, most of the research work on Nafion replacements for proton exchange membrane PEM fuel cells has in H2/air fuel cells that operate at low humidity. The membranes were fabricated from electrospun

Mather, Patrick T.

274

Fabrication of Micro-Orifices for Diesel Fuel Injectors  

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

Scuffing resistance of a MoN-Cu nano-composite coating under exteme loading condidtions do not show scuffing within the load limit of the testing device.

275

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

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

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

276

Alternative Fuels Data Center: Renewable Fuels Assessment  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Renewable Fuels Renewable Fuels Assessment to someone by E-mail Share Alternative Fuels Data Center: Renewable Fuels Assessment on Facebook Tweet about Alternative Fuels Data Center: Renewable Fuels Assessment on Twitter Bookmark Alternative Fuels Data Center: Renewable Fuels Assessment on Google Bookmark Alternative Fuels Data Center: Renewable Fuels Assessment on Delicious Rank Alternative Fuels Data Center: Renewable Fuels Assessment on Digg Find More places to share Alternative Fuels Data Center: Renewable Fuels Assessment on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Renewable Fuels Assessment The U.S. Department of Defense (DOD) prepared a report, Opportunities for DOD Use of Alternative and Renewable Fuels, on the use and potential use of

277

Alternative Fuels Data Center: Biodiesel Fuel Basics  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fuel Basics Fuel Basics to someone by E-mail Share Alternative Fuels Data Center: Biodiesel Fuel Basics on Facebook Tweet about Alternative Fuels Data Center: Biodiesel Fuel Basics on Twitter Bookmark Alternative Fuels Data Center: Biodiesel Fuel Basics on Google Bookmark Alternative Fuels Data Center: Biodiesel Fuel Basics on Delicious Rank Alternative Fuels Data Center: Biodiesel Fuel Basics on Digg Find More places to share Alternative Fuels Data Center: Biodiesel Fuel Basics on AddThis.com... More in this section... Biodiesel Basics Blends Production & Distribution Specifications Related Links Benefits & Considerations Stations Vehicles Laws & Incentives Biodiesel Fuel Basics Related Information National Biofuels Action Plan Biodiesel is a domestically produced, renewable fuel that can be

278

Alternative Fuels Data Center: Renewable Fuel Standard  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Renewable Fuel Renewable Fuel Standard to someone by E-mail Share Alternative Fuels Data Center: Renewable Fuel Standard on Facebook Tweet about Alternative Fuels Data Center: Renewable Fuel Standard on Twitter Bookmark Alternative Fuels Data Center: Renewable Fuel Standard on Google Bookmark Alternative Fuels Data Center: Renewable Fuel Standard on Delicious Rank Alternative Fuels Data Center: Renewable Fuel Standard on Digg Find More places to share Alternative Fuels Data Center: Renewable Fuel Standard on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Renewable Fuel Standard At least 2% of all diesel fuel sold in Washington must be biodiesel or renewable diesel. This requirement will increase to 5% 180 days after the

279

Alternative Fuels Data Center: Biodiesel Fuel Use  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Biodiesel Fuel Use to Biodiesel Fuel Use to someone by E-mail Share Alternative Fuels Data Center: Biodiesel Fuel Use on Facebook Tweet about Alternative Fuels Data Center: Biodiesel Fuel Use on Twitter Bookmark Alternative Fuels Data Center: Biodiesel Fuel Use on Google Bookmark Alternative Fuels Data Center: Biodiesel Fuel Use on Delicious Rank Alternative Fuels Data Center: Biodiesel Fuel Use on Digg Find More places to share Alternative Fuels Data Center: Biodiesel Fuel Use on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Biodiesel Fuel Use The Iowa Department of Transportation (IDOT) may purchase biodiesel for use in IDOT vehicles through the biodiesel fuel revolving fund created in the state treasury. The fund consists of money received from the sale of Energy

280

Alternative Fuels Data Center: Alternative Fuel Tax  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fuel Tax Fuel Tax to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel Tax on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel Tax on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel Tax on Google Bookmark Alternative Fuels Data Center: Alternative Fuel Tax on Delicious Rank Alternative Fuels Data Center: Alternative Fuel Tax on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuel Tax on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Alternative Fuel Tax Special fuels, including biodiesel, biodiesel blends, biomass-based diesel, biomass-based diesel blends, and liquefied natural gas, have a reduced tax rate of $0.27 per gallon. Liquefied petroleum gas (LPG or propane) and

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


281

Alternative Fuels Data Center: Special Fuel Tax  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Special Fuel Tax to Special Fuel Tax to someone by E-mail Share Alternative Fuels Data Center: Special Fuel Tax on Facebook Tweet about Alternative Fuels Data Center: Special Fuel Tax on Twitter Bookmark Alternative Fuels Data Center: Special Fuel Tax on Google Bookmark Alternative Fuels Data Center: Special Fuel Tax on Delicious Rank Alternative Fuels Data Center: Special Fuel Tax on Digg Find More places to share Alternative Fuels Data Center: Special Fuel Tax on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Special Fuel Tax Effective January 1, 2014, certain special fuels sold or used to propel motor vehicles are subject to a license tax. Liquefied natural gas is subject to a tax of $0.16 per diesel gallon equivalent. Compressed natural

282

Alternative Fuels Data Center: Ethanol Fuel Basics  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fuel Basics to Fuel Basics to someone by E-mail Share Alternative Fuels Data Center: Ethanol Fuel Basics on Facebook Tweet about Alternative Fuels Data Center: Ethanol Fuel Basics on Twitter Bookmark Alternative Fuels Data Center: Ethanol Fuel Basics on Google Bookmark Alternative Fuels Data Center: Ethanol Fuel Basics on Delicious Rank Alternative Fuels Data Center: Ethanol Fuel Basics on Digg Find More places to share Alternative Fuels Data Center: Ethanol Fuel Basics on AddThis.com... More in this section... Ethanol Basics Blends Specifications Production & Distribution Feedstocks Related Links Benefits & Considerations Stations Vehicles Laws & Incentives Ethanol Fuel Basics Related Information National Biofuels Action Plan Ethanol is a renewable fuel made from various plant materials collectively

283

Alternative Fuels Data Center: Biodiesel Fuel Use  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fuel Use to Fuel Use to someone by E-mail Share Alternative Fuels Data Center: Biodiesel Fuel Use on Facebook Tweet about Alternative Fuels Data Center: Biodiesel Fuel Use on Twitter Bookmark Alternative Fuels Data Center: Biodiesel Fuel Use on Google Bookmark Alternative Fuels Data Center: Biodiesel Fuel Use on Delicious Rank Alternative Fuels Data Center: Biodiesel Fuel Use on Digg Find More places to share Alternative Fuels Data Center: Biodiesel Fuel Use on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Biodiesel Fuel Use The South Dakota Department of Transportation and employees using state diesel vehicles must stock and use fuel blends containing a minimum of 2% biodiesel (B2) that meets or exceeds the most current ASTM specification

284

Alternative Fuels Data Center: Hydrogen Fuel Specifications  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Hydrogen Fuel Hydrogen Fuel Specifications to someone by E-mail Share Alternative Fuels Data Center: Hydrogen Fuel Specifications on Facebook Tweet about Alternative Fuels Data Center: Hydrogen Fuel Specifications on Twitter Bookmark Alternative Fuels Data Center: Hydrogen Fuel Specifications on Google Bookmark Alternative Fuels Data Center: Hydrogen Fuel Specifications on Delicious Rank Alternative Fuels Data Center: Hydrogen Fuel Specifications on Digg Find More places to share Alternative Fuels Data Center: Hydrogen Fuel Specifications on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Hydrogen Fuel Specifications The California Department of Food and Agriculture, Division of Measurement Standards (DMS) established interim specifications for hydrogen fuels for

285

Alternative Fuels Data Center: Flexible Fuel Vehicles  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Ethanol Ethanol Printable Version Share this resource Send a link to Alternative Fuels Data Center: Flexible Fuel Vehicles to someone by E-mail Share Alternative Fuels Data Center: Flexible Fuel Vehicles on Facebook Tweet about Alternative Fuels Data Center: Flexible Fuel Vehicles on Twitter Bookmark Alternative Fuels Data Center: Flexible Fuel Vehicles on Google Bookmark Alternative Fuels Data Center: Flexible Fuel Vehicles on Delicious Rank Alternative Fuels Data Center: Flexible Fuel Vehicles on Digg Find More places to share Alternative Fuels Data Center: Flexible Fuel Vehicles on AddThis.com... More in this section... Ethanol Basics Benefits & Considerations Stations Vehicles Availability Conversions Emissions Laws & Incentives Flexible Fuel Vehicles Photo of a flexible fuel vehicle.

286

Alternative Fuels Data Center: Alternative Fuel Use  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fuel Use Fuel Use to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel Use on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel Use on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel Use on Google Bookmark Alternative Fuels Data Center: Alternative Fuel Use on Delicious Rank Alternative Fuels Data Center: Alternative Fuel Use on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuel Use on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Alternative Fuel Use All state employees operating flexible fuel or diesel vehicles as part of the state fleet must use E85 or biodiesel blends whenever reasonably available. Additionally, the Nebraska Transportation Services Bureau and

287

Alternative Fuels Data Center: Alternative Fuels Tax  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fuels Tax Fuels Tax to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuels Tax on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuels Tax on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuels Tax on Google Bookmark Alternative Fuels Data Center: Alternative Fuels Tax on Delicious Rank Alternative Fuels Data Center: Alternative Fuels Tax on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuels Tax on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Alternative Fuels Tax Alternative fuels used to propel vehicles of any kind on public highways are taxed at a rate determined on a gasoline gallon equivalent basis. The tax rates are posted in the Pennsylvania Bulletin. (Reference Title 75

288

California Fuel Cell Partnership: Alternative Fuels Research  

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

This presentation by Chris White of the California Fuel Cell Partnership provides information about alternative fuels research.

289

Fuel Processing Valri Lightner  

E-Print Network (OSTI)

, ORNL, NETL #12;Accomplishments · Demonstrated in the lab an advanced fuel flexible fuel processor

290

Investigation of the Performance of D2O-Cooled High-Conversion Reactors for Fuel Cycle Calculations  

SciTech Connect

This report presents FY13 activities for the analysis of D2O cooled tight-pitch High-Conversion PWRs (HCPWRs) with U-Pu and Th-U fueled cores aiming at break-even or near breeder conditions while retaining the negative void reactivity. The analyses are carried out from several aspects which could not be covered in FY12 activities. SCALE 6.1 code system is utilized, and a series of simple 3D fuel pin-cell models are developed in order to perform Monte Carlo based criticality and burnup calculations. The performance of U-Pu fueled cores with axial and internal blankets is analyzed in terms of their impact on the relative fissile Pu mass balance, initial Pu enrichment, and void coefficient. In FY12, Pu conversion performances of D2O-cooled HCPWRs fueled with MOX were evaluated with small sized axial/internal DU blankets (approximately 4cm of axial length) in order to ensure the negative void reactivity, which evidently limits the conversion performance of HCPWRs. In this fiscal year report, the axial sizes of DU blankets are extended up to 30 cm in order to evaluate the amount of DU necessary to reach break-even and/or breeding conditions. Several attempts are made in order to attain the milestone of the HCPWR designs (i.e., break-even condition and negative void reactivity) by modeling of HCPWRs under different conditions such as boiling of D2O coolant, MOX with different 235U enrichment, and different target burnups. A similar set of analyses are performed for Th-U fueled cores. Several promising characteristics of 233U over other fissile like 239Pu and 235U, most notably its higher fission neutrons per absorption in thermal and epithermal ranges combined with lower ___ in the fast range than 239Pu allows Th-U cores to be taller than MOX ones. Such an advantage results in 4% higher relative fissile mass balance than that of U-Pu fueled cores while retaining the negative void reactivity until the target burnup of 51 GWd/t. Several other distinctions between U-Pu and Th-U fueled cores are identified by evaluating the sensitivity coefficients of keff, mass balance, and void coefficient. The effect of advanced iron alloy cladding (i.e., FeCrAl) on the performance of Pu conversion in MOX fueled cores is studied instead of using standard stainless-steel cladding. Variations in clad thickness and coolant-to-fuel volume ratio are also exercised. The use of FeCrAl instead of SS as a cladding alloy reduces the required Pu enrichment and improves the Pu conversion rate primarily due to the absence of nickel in the cladding alloy that results in the reduction of the neutron absorption. Also the difference in void coefficients between SS and FeCrAl alloys is nearly 500 pcm over the entire burnup range. The report also shows sensitivity and uncertainty analyses in order to characterize D2O cooled HCPWRs from different aspects. The uncertainties of integral parameters (keff and void coefficient) for selected reactor cores are evaluated at different burnup points in order to find similarities and trends respect to D2O-HCPWR.

Hikaru Hiruta; Gilles Youinou

2013-09-01T23:59:59.000Z

291

Alternative Fuels Data Center: Renewable Fuels Mandate  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Renewable Fuels Renewable Fuels Mandate to someone by E-mail Share Alternative Fuels Data Center: Renewable Fuels Mandate on Facebook Tweet about Alternative Fuels Data Center: Renewable Fuels Mandate on Twitter Bookmark Alternative Fuels Data Center: Renewable Fuels Mandate on Google Bookmark Alternative Fuels Data Center: Renewable Fuels Mandate on Delicious Rank Alternative Fuels Data Center: Renewable Fuels Mandate on Digg Find More places to share Alternative Fuels Data Center: Renewable Fuels Mandate on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Renewable Fuels Mandate All gasoline sold in the state must be blended with 10% ethanol (E10). Gasoline with an octane rating of 91 or above is exempt from this mandate,

292

Alternative Fuels Data Center: Renewable Fuels Promotion  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Renewable Fuels Renewable Fuels Promotion to someone by E-mail Share Alternative Fuels Data Center: Renewable Fuels Promotion on Facebook Tweet about Alternative Fuels Data Center: Renewable Fuels Promotion on Twitter Bookmark Alternative Fuels Data Center: Renewable Fuels Promotion on Google Bookmark Alternative Fuels Data Center: Renewable Fuels Promotion on Delicious Rank Alternative Fuels Data Center: Renewable Fuels Promotion on Digg Find More places to share Alternative Fuels Data Center: Renewable Fuels Promotion on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Renewable Fuels Promotion Recognizing that biofuels such as ethanol and biodiesel will be an important part of the state's energy economy and advanced research in

293

Alternative Fuels Data Center: Fuel Quality Standards  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fuel Quality Standards Fuel Quality Standards to someone by E-mail Share Alternative Fuels Data Center: Fuel Quality Standards on Facebook Tweet about Alternative Fuels Data Center: Fuel Quality Standards on Twitter Bookmark Alternative Fuels Data Center: Fuel Quality Standards on Google Bookmark Alternative Fuels Data Center: Fuel Quality Standards on Delicious Rank Alternative Fuels Data Center: Fuel Quality Standards on Digg Find More places to share Alternative Fuels Data Center: Fuel Quality Standards on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Fuel Quality Standards The South Dakota Department of Public Safety may promulgate rules establishing: Standards for the maximum volume percentages of ethanol and methanol

294

Alternative Fuels Data Center: Renewable Fuels Mandate  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Renewable Fuels Renewable Fuels Mandate to someone by E-mail Share Alternative Fuels Data Center: Renewable Fuels Mandate on Facebook Tweet about Alternative Fuels Data Center: Renewable Fuels Mandate on Twitter Bookmark Alternative Fuels Data Center: Renewable Fuels Mandate on Google Bookmark Alternative Fuels Data Center: Renewable Fuels Mandate on Delicious Rank Alternative Fuels Data Center: Renewable Fuels Mandate on Digg Find More places to share Alternative Fuels Data Center: Renewable Fuels Mandate on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Renewable Fuels Mandate One year after in-state production has reached 350 million gallons of cellulosic ethanol and sustained this volume for three months, all gasoline

295

Alternative Fuels Data Center: Alternative Fuels Promotion  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Alternative Fuels Alternative Fuels Promotion to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuels Promotion on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuels Promotion on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuels Promotion on Google Bookmark Alternative Fuels Data Center: Alternative Fuels Promotion on Delicious Rank Alternative Fuels Data Center: Alternative Fuels Promotion on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuels Promotion on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Alternative Fuels Promotion The state of Hawaii has signed a memorandum of understanding (MOU) with the U.S. Department of Energy to collaborate to produce 70% of the state's

296

Alternative Fuels Data Center: Alternative Fuel Tax  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Alternative Fuel Tax Alternative Fuel Tax to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel Tax on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel Tax on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel Tax on Google Bookmark Alternative Fuels Data Center: Alternative Fuel Tax on Delicious Rank Alternative Fuels Data Center: Alternative Fuel Tax on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuel Tax on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Alternative Fuel Tax The excise tax imposed on compressed natural gas (CNG), liquefied natural gas (LNG), and liquefied petroleum gas (LPG or propane) used to operate a vehicle can be paid through an annual flat rate sticker tax based on the

297

Alternative Fuels Data Center: Renewable Fuel Promotion  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Renewable Fuel Renewable Fuel Promotion to someone by E-mail Share Alternative Fuels Data Center: Renewable Fuel Promotion on Facebook Tweet about Alternative Fuels Data Center: Renewable Fuel Promotion on Twitter Bookmark Alternative Fuels Data Center: Renewable Fuel Promotion on Google Bookmark Alternative Fuels Data Center: Renewable Fuel Promotion on Delicious Rank Alternative Fuels Data Center: Renewable Fuel Promotion on Digg Find More places to share Alternative Fuels Data Center: Renewable Fuel Promotion on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Renewable Fuel Promotion The Texas Bioenergy Policy Council and the Texas Bioenergy Research Committee were established to promote the goal of making biofuels a

298

Alternative Fuels Data Center: Renewable Fuel Standard  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Renewable Fuel Renewable Fuel Standard to someone by E-mail Share Alternative Fuels Data Center: Renewable Fuel Standard on Facebook Tweet about Alternative Fuels Data Center: Renewable Fuel Standard on Twitter Bookmark Alternative Fuels Data Center: Renewable Fuel Standard on Google Bookmark Alternative Fuels Data Center: Renewable Fuel Standard on Delicious Rank Alternative Fuels Data Center: Renewable Fuel Standard on Digg Find More places to share Alternative Fuels Data Center: Renewable Fuel Standard on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Renewable Fuel Standard Within six months following the point at which monthly production of denatured ethanol produced in Louisiana equals or exceeds a minimum annualized production volume of 50 million gallons, at least 2% of the

299

Alternative Fuels Data Center: Alternative Fuel Tax  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fuel Tax Fuel Tax to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel Tax on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel Tax on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel Tax on Google Bookmark Alternative Fuels Data Center: Alternative Fuel Tax on Delicious Rank Alternative Fuels Data Center: Alternative Fuel Tax on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuel Tax on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Alternative Fuel Tax The state road tax for vehicles that operate on propane (liquefied petroleum gas, or LPG) or natural gas is paid through the purchase of an annual flat fee sticker, and the amount is based on the vehicle's gross

300

Alternative Fuels Data Center: Propane Fueling Stations  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Stations to someone by E-mail Stations to someone by E-mail Share Alternative Fuels Data Center: Propane Fueling Stations on Facebook Tweet about Alternative Fuels Data Center: Propane Fueling Stations on Twitter Bookmark Alternative Fuels Data Center: Propane Fueling Stations on Google Bookmark Alternative Fuels Data Center: Propane Fueling Stations on Delicious Rank Alternative Fuels Data Center: Propane Fueling Stations on Digg Find More places to share Alternative Fuels Data Center: Propane Fueling Stations on AddThis.com... More in this section... Propane Basics Benefits & Considerations Stations Locations Infrastructure Development Vehicles Laws & Incentives Propane Fueling Stations Photo of a liquefied petroleum gas fueling station. Thousands of liquefied petroleum gas (propane) fueling stations are

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


301

Alternative Fuels Data Center: Alternative Fuel Study  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Alternative Fuel Study Alternative Fuel Study to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel Study on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel Study on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel Study on Google Bookmark Alternative Fuels Data Center: Alternative Fuel Study on Delicious Rank Alternative Fuels Data Center: Alternative Fuel Study on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuel Study on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Alternative Fuel Study As directed by the Nevada Legislature, the Legislative Commission (Commission) conducted an interim study in 2011 concerning the production and use of energy in the state. The study included information on the use

302

The behaviour of transuranic mixed oxide fuel in a Candu-900 reactor  

SciTech Connect

The production of transuranic actinide fuels for use in current thermal reactors provides a useful intermediary step in closing the nuclear fuel cycle. Extraction of actinides reduces the longevity, radiation and heat loads of spent material. The burning of transuranic fuels in current reactors for a limited amount of cycles reduces the infrastructure demand for fast reactors and provides an effective synergy that can result in a reduction of as much as 95% of spent fuel waste while reducing the fast reactor infrastructure needed by a factor of almost 13.5 [1]. This paper examines the features of actinide mixed oxide fuel, TRUMOX, in a CANDU{sup R}* nuclear reactor. The actinide concentrations used were based on extraction from 30 year cooled spent fuel and mixed with natural uranium in 3.1 wt% actinide MOX fuel. Full lattice cell modeling was performed using the WIMS-AECL code, super-cell calculations were analyzed in DRAGON and full core analysis was executed in the RFSP 2-group diffusion code. A time-average full core model was produced and analyzed for reactor coefficients, reactivity device worth and online fuelling impacts. The standard CANDU operational limits were maintained throughout operations. The TRUMOX fuel design achieved a burnup of 27.36 MWd/kg HE. A full TRUMOX fuelled CANDU was shown to operate within acceptable limits and provided a viable intermediary step for burning actinides. The recycling, reprocessing and reuse of spent fuels produces a much more sustainable and efficient nuclear fuel cycle. (authors)

Morreale, A. C.; Ball, M. R.; Novog, D. R.; Luxat, J. C. [Dept. of Engineering Physics, McMaster Univ., 1280 Main St. W, Hamilton, ON (Canada)

2012-07-01T23:59:59.000Z

303

Fuels - Biodiesel  

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

* Biodiesel * Biodiesel * Butanol * Ethanol * Hydrogen * Natural Gas * Fischer-Tropsch Batteries Cross-Cutting Assessments Engines GREET Hybrid Electric Vehicles Hydrogen & Fuel Cells Materials Modeling, Simulation & Software Plug-In Hybrid Electric Vehicles PSAT Smart Grid Student Competitions Transportation Research and Analysis Computing Center Working With Argonne Contact TTRDC Clean Diesel Fuels Background Reducing our country's dependence on foreign oil and the rising costs of crude oil are primary reasons for a renewed interest in alternative fuels for the transportation sector. Stringent emissions regulations and public concern about mobile sources of air pollution provide additional incentives to develop fuels that generate fewer emissions, potentially reducing the need for sophisticated, expensive exhaust after-treatment devices.

304

Nuclear Fuels  

Science Journals Connector (OSTI)

The core of a nuclear reactor is composed of a controlled critical configuration of a fissile material, which in strict a sense is the fuel. This fissile material is contained in a matrix, normally a ceramic c...

Rudy J. M. Konings; Thierry Wiss…

2011-01-01T23:59:59.000Z

305

Fuel economizer  

SciTech Connect

A fuel economizer device for use with an internal combustion engine fitted with a carburetor is disclosed. The fuel economizer includes a plate member which is mounted between the carburetor and the intake portion of the intake manifold. The plate member further has at least one aperture formed therein. One tube is inserted through the at least one aperture in the plate member. The one tube extends longitudinally in the passage of the intake manifold from the intake portion toward the exit portion thereof. The one tube concentrates the mixture of fuel and air from the carburetor and conveys the mixture of fuel and air to a point adjacent but spaced away from the inlet port of the internal combustion engine.

Zwierzelewski, V.F.

1984-06-26T23:59:59.000Z

306

Micro-optic fabrication with subdomain masking  

Science Journals Connector (OSTI)

An innovative fabrication technique is introduced that is based on multiple-exposure techniques for micro-optics fabrication. This approach is compatible with conventional lithography...

Pitchumani, Mahesh; Brown, Jeremiah; Mohammed, Waleed; Johnson, Eric G

2004-01-01T23:59:59.000Z

307

Enforcement Letter, Parsons Technology Development & Fabrication...  

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

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

308

High Performance Fuel Desing for Next Generation Pressurized Water Reactors  

SciTech Connect

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

Mujid S. Kazimi; Pavel Hejzlar

2006-01-31T23:59:59.000Z

309

Alternative Fuels Data Center: Alternative Fuel Definition  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Definition to someone by E-mail Definition to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel Definition on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel Definition on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel Definition on Google Bookmark Alternative Fuels Data Center: Alternative Fuel Definition on Delicious Rank Alternative Fuels Data Center: Alternative Fuel Definition on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuel Definition on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Alternative Fuel Definition Alternative fuel is defined as compressed natural gas, propane, ethanol, or any mixture containing 85% or more ethanol (E85) with gasoline or other

310

Methods for making a porous nuclear fuel element  

SciTech Connect

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

Youchison, Dennis L; Williams, Brian E; Benander, Robert E

2014-12-30T23:59:59.000Z

311

Digital materials for digital fabrication  

E-Print Network (OSTI)

This thesis introduces digital materials by analogy with digital computation and digital communications. Traditional fabrication techniques include pick-and-place, roll-to-roll, molding, patterning and more. Current research ...

Popescu, George A

2007-01-01T23:59:59.000Z

312

Effect of reduced enrichment on the fuel cycle for research reactors  

SciTech Connect

The new fuels developed by the RERTR Program and by other international programs for application in research reactors with reduced uranium enrichment (<20% EU) are discussed. It is shown that these fuels, combined with proper fuel-element design and fuel-management strategies, can provide at least the same core residence time as high-enrichment fuels in current use, and can frequently significantly extend it. The effect of enrichment reduction on other components of the research reactor fuel cycle, such as uranium and enrichment requirements, fuel fabrication, fuel shipment, and reprocessing are also briefly discussed with their economic implications. From a systematic comparison of HEU and LEU cores for the same reference research reactor, it is concluded that the new fuels have a potential for reducing the research reactor fuel cycle costs while reducing, at the same time, the uranium enrichment of the fuel.

Travelli, A.

1982-01-01T23:59:59.000Z

313

Coal-fueled diesel technology development: Nozzle development for coal-fueled diesel engines  

SciTech Connect

Direct injection of a micronized coal water mixture fuel into the combustion chambers of a diesel engine requires atomizing an abrasive slurry fuel with accurately sized orifices. Five injector orifice materials were evaluated: diamond compacts, chemical vapor deposited diamond tubes, thermally stabilized diamond, tungsten carbide with cobalt binder, and tungsten carbide with nickel binder with brazed and mechanically mounted orifice inserts. Nozzle bodies were fabricated of Armco 17-4 precipitation hardening stainless steel and Stellite 6B in order to withstand cyclic injection pressures and elevated temperatures. Based on a total of approximately 200 cylinder hours of engine operation with coal water mixture fuel diamond compacts were chosen for the orifice material.

Johnson, R.N.; Lee, M.; White, R.A.

1994-01-01T23:59:59.000Z

314

Stationary Fuel Cells: Overview of Hydrogen and Fuel Cell Activities...  

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

Stationary Fuel Cells: Overview of Hydrogen and Fuel Cell Activities Stationary Fuel Cells: Overview of Hydrogen and Fuel Cell Activities Presentation covers stationary fuel cells...

315

Fuel Cell Technologies Overview: 2011 Fuel Cell Seminar | Department...  

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

Fuel Cell Technologies Overview: 2011 Fuel Cell Seminar Fuel Cell Technologies Overview: 2011 Fuel Cell Seminar Presentation by Sunita Satyapal at the Fuel Cell Seminar on November...

316

Fuel Cell Technologies Overview: 2011 Fuel Cell Seminar | Department...  

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

Overview: 2011 Fuel Cell Seminar Fuel Cell Technologies Overview: 2011 Fuel Cell Seminar Presentation by Sunita Satyapal at the Fuel Cell Seminar on November 1, 2011. Fuel Cell...

317

Fuel Processing Valri Lightner  

E-Print Network (OSTI)

of Hydrogen · Fuel Processors for PEM Fuel Cells Nuvera Fuel Cells, Inc. GE Catalytica ANL PNNL University-Board Fuel Processing Barriers $35/kW Fuel Processor $10/kW Fuel Cell Power Systems $45/kW by 2010 BARRIERS · Fuel processor start-up/ transient operation · Durability · Cost · Emissions and environmental issues

318

Conditions of utilization of coal mining and processing sludges as slurry fuel  

SciTech Connect

The results of this study have shown that coal sludge can be used as slurry fuel (like coal-water fuel (CWF)) providing that its ash content does not exceed 30% and the amount in the fuel is at least 55%. The conventional CWF preparation technologies are inapplicable to the fabrication of water-sludge fuel; therefore, special technologies with allowance for the ash content, the particle size, and the water content of coal sludge are demanded.

E.G. Gorlov; A.I. Seregin; G.S. Khodakov [Institute for Fossil Fuels, Moscow (Russian Federation)

2007-12-15T23:59:59.000Z

319

Reforming of fuel inside fuel cell generator  

DOE Patents (OSTI)

Disclosed is an improved method of reforming a gaseous reformable fuel within a solid oxide fuel cell generator, wherein the solid oxide fuel cell generator has a plurality of individual fuel cells in a refractory container, the fuel cells generating a partially spent fuel stream and a partially spent oxidant stream. The partially spent fuel stream is divided into two streams, spent fuel stream I and spent fuel stream II. Spent fuel stream I is burned with the partially spent oxidant stream inside the refractory container to produce an exhaust stream. The exhaust stream is divided into two streams, exhaust stream I and exhaust stream II, and exhaust stream I is vented. Exhaust stream II is mixed with spent fuel stream II to form a recycle stream. The recycle stream is mixed with the gaseous reformable fuel within the refractory container to form a fuel stream which is supplied to the fuel cells. Also disclosed is an improved apparatus which permits the reforming of a reformable gaseous fuel within such a solid oxide fuel cell generator. The apparatus comprises a mixing chamber within the refractory container, means for diverting a portion of the partially spent fuel stream to the mixing chamber, means for diverting a portion of exhaust gas to the mixing chamber where it is mixed with the portion of the partially spent fuel stream to form a recycle stream, means for injecting the reformable gaseous fuel into the recycle stream, and means for circulating the recycle stream back to the fuel cells.

Grimble, Ralph E. (Finleyville, PA)

1988-01-01T23:59:59.000Z

320

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

motor fuel containing at least 10% alcohol) or alternative fuels whenever feasible and cost effective. DOA must place a list of gasohol and alternative fueling station locations...

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


321

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

special fuels. Special fuels include compressed and liquefied natural gas, liquefied petroleum gas (propane), hydrogen, and fuel suitable for use in diesel engines. In addition,...

322

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

alternative fuel vehicles (AFVs) capable of operating on natural gas or liquefied petroleum gas (propane), or bi-fuel vehicles capable of operating on conventional fuel or...

323

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Use and Fuel-Efficient Vehicle Requirements State-owned vehicle fleets must implement petroleum displacement plans to increase the use of alternative fuels and fuel-efficient...

324

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

and Special Fuel Definitions The definition of alternative fuel includes liquefied petroleum gas (propane). Special fuel is defined as all combustible gases and liquids that are...

325

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Renewable Fuel Labeling Requirement Biodiesel, biobutanol, and ethanol blend dispensers must be affixed with decals identifying the type of fuel blend. If fuel blends containing...

326

Saving Fuel, Reducing Emissions  

E-Print Network (OSTI)

would in turn lower PHEV fuel costs and make them morestretches from fossil-fuel- powered conventional vehiclesbraking, as do Saving Fuel, Reducing Emissions Making Plug-

Kammen, Daniel M.; Arons, Samuel M.; Lemoine, Derek M.; Hummel, Holmes

2009-01-01T23:59:59.000Z

327

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

and alternative fuel vehicles; promotes the development, sale, distribution, and consumption of alternative fuels; promotes the development and use of alternative fuel vehicles...

328

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

providers to install biofuel fueling facilities. Fueling facilities include storage tanks and fuel pumps dedicated to dispensing E85 and biodiesel blends of 20% (B20). TDOT...

329

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

interest in the qualified property. Renewable fuel is defined as a fuel produced from biomass that is used to replace or reduce conventional fuel use. (Reference Florida Statutes...

330

Alternative Fuel Vehicle Resources  

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

Alternative fuel vehicles use fuel types other than petroleum and include such fuels as electricity, ethanol, biodiesel, natural gas, hydrogen, and propane. Compared to petroleum, these...

331

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Alternative Fuel Grants and Rebates The Arkansas Alternative Fuels Development Program (Program) provides grants to alternative fuel producers, feedstock processors, and...

332

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fuel Exclusivity Contract Regulation Motor fuel franchise dealers may obtain alternative fuels from a supplier other than a franchise distributor. Any franchise provision that...

333

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Hydrogen Production and Retail Requirements All hydrogen fuel produced and sold in Michigan must meet state fuel quality requirements. Any retailer offering hydrogen fuel for sale...

334

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

that operate using at least 90% alternative fuel. Eligible alternative fuels include electricity, propane, natural gas, or hydrogen fuel. Medium-duty hybrid electric vehicles also...

335

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fuels Promotion and Information The Center for Alternative Fuels (Center) promotes alternative fuels as viable energy sources in the state. The Center must assess the...

336

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fuel Definition The following fuels are defined as alternative fuels by the Energy Policy Act (EPAct) of 1992: pure methanol, ethanol, and other alcohols; blends of 85%...

337

Low Carbon Fuel Standards  

E-Print Network (OSTI)

in 1990. These many alternative-fuel initiatives failed tolow-cost, low-carbon alternative fuels would thrive. Theto introduce low-carbon alternative fuels. Former Federal

Sperling, Dan; Yeh, Sonia

2009-01-01T23:59:59.000Z

338

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Alternative Fuels Labeling Requirement Retailers must display ratings on fueling pumps that are consistent with the percentage by volume of the alternative fuel being dispensed....

339

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

is defined as a renewable transportation fuel, transportation fuel additive, heating oil, or jet fuel that meets the definition of either biodiesel or non-ester renewable...

340

Interim report spent nuclear fuel retrieval system fuel handling development testing  

SciTech Connect

Fuel handling development testing was performed in support of the Fuel Retrieval System (FRS) Sub-Project at the Hanford Site. The project will retrieve spent nuclear fuel, clean and remove fuel from canisters, repackage fuel into baskets, and load fuel into a multi-canister overpack (MCO) for vacuum drying and interim dry storage. The FRS is required to retrieve basin fuel canisters, clean fuel elements sufficiently of uranium corrosion products (or sludge), empty fuel from canisters, sort debris and scrap from whole elements, and repackage fuel in baskets in preparation for MCO loading. The purpose of fuel handling development testing was to examine the systems ability to accomplish mission activities, optimization of equipment layouts for initial process definition, identification of special needs/tools, verification of required design changes to support performance specification development, and validation of estimated activity times/throughput. The test program was set up to accomplish this purpose through cold development testing using simulated and prototype equipment; cold demonstration testing using vendor expertise and systems; and graphical computer modeling to confirm feasibility and throughput. To test the fuel handling process, a test mockup that represented the process table was fabricated and installed. The test mockup included a Schilling HV series manipulator that was prototypic of the Schilling Hydra manipulator. The process table mockup included the tipping station, sorting area, disassembly and inspection zones, fuel staging areas, and basket loading stations. The test results clearly indicate that the Schilling Hydra arm cannot effectively perform the fuel handling tasks required unless it is attached to some device that can impart vertical translation, azimuth rotation, and X-Y translation. Other test results indicate the importance of camera locations and capabilities, and of the jaw and end effector tool design. 5 refs., 35 figs., 3 tabs.

Ketner, G.L.; Meeuwsen, P.V.; Potter, J.D.; Smalley, J.T.; Baker, C.P.; Jaquish, W.R.

1997-06-01T23:59:59.000Z

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


341

SAFEGUARDS EXPERIENCE ON THE DUPIC FUEL CYCLE PROCESS  

SciTech Connect

Safeguards have been applied to the R and D process for directly fabricating CANDU fuel with PWR spent fuel material. Safeguards issues to be resolved were identified in the areas such as international cooperation on handling foreign origin nuclear material, technology development of operator's measurement system of the bulk handling process of spent fuel material, and a built-in C/S system for independent verification of material flow. The fuel cycle concept (Direct Use of PWR spent fuel in CANDU, DUPIC) was developed in consideration of reutilization of over-flowing spent fuel resources at PWR sites and a reduction of generated high level wastes. All those safeguards issues have been finally resolved, and the first batch of PWR spent fuel material was successfully introduced in the DUPIC lab facility and has been in use for routine process development.

J. HONG; H. KIM; ET AL

2001-02-01T23:59:59.000Z

342

Alternative Fuels Data Center: Alternative Fuel Vehicle Acquisition and  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fuel Fuel Vehicle Acquisition and Alternative Fuel Use Requirements to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel Vehicle Acquisition and Alternative Fuel Use Requirements on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel Vehicle Acquisition and Alternative Fuel Use Requirements on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel Vehicle Acquisition and Alternative Fuel Use Requirements on Google Bookmark Alternative Fuels Data Center: Alternative Fuel Vehicle Acquisition and Alternative Fuel Use Requirements on Delicious Rank Alternative Fuels Data Center: Alternative Fuel Vehicle Acquisition and Alternative Fuel Use Requirements on Digg Find More places to share Alternative Fuels Data Center: Alternative

343

Stability Study of the RERTR Fuel Microstructure  

SciTech Connect

The irradiation stability of the interaction phases at the interface of fuel and Al alloy matrix as well as the stability of the fission gas bubble superlattice is believed to be very important to the U-Mo fuel performance. In this paper the recent result from TEM characterization of Kr ion irradiated U-10Mo-5Zr alloy will be discussed. The focus will be on the phase stability of Mo2-Zr, a dominated second phase developed at the interface of U-10Mo and the Zr barrier in a monolithic fuel plate from fuel fabrication. The Kr ion irradiations were conducted at a temperature of 200 degrees C to an ion fluence of 2.0E+16 ions/cm2. To investigate the thermal stability of the fission gas bubble superlattice, a key microstructural feature in both irradiated dispersion U-7Mo fuel and monolithic U-10Mo fuel, a FIB-TEM sample of the irradiated U-10Mo fuel (3.53E+21 fission/cm3) was used for a TEM in-situ heating experiment. The preliminary result showed extraordinary thermal stability of the fission gas bubble superlattice. The implication of the TEM observation from these two experiments on the fuel microstructural evolution under irradiation will be discussed.

Jian Gan; Dennis Keiser; Brandon Miller; Daniel Wachs

2014-04-01T23:59:59.000Z

344

The integral fast reactor fuel cycle  

SciTech Connect

The liquid-metal reactor (LMR) has the potential to extend the uranium resource by a factor of 50 to 100 over current commercial light water reactors (LWRs). In the integral fast reactor (IFR) development program, the entire reactor system - reactor, fuel cycle, and waste process - is being developed and optimized at the same time as a single integral entity. A key feature of the IFR concept is the metallic fuel. The lead irradiation tests on the new U-Pu-Zr metallic fuel in the Experimental Breeder Reactor II have surpassed 185000 MWd/t burnup, and its high burnup capability has now been fully demonstrated. The metallic fuel also allows a radically improved fuel cycle technology. Pyroprocessing, which utilizes high temperatures and molten salt and molten metal solvents, can be advantageously utilized for processing metal fuels because the product is metal suitable for fabrication into new fuel elements. Direct production of a metal product avoids expensive and cumbersome chemical conversion steps that would result from use of the conventional Purex solvent extraction process. The key step in the IFR process is electrorefining, which provides for recovery of the valuable fuel constituents, uranium and plutonium, and for removal of fission products. A notable feature of the IFR process is that the actinide elements accompany plutonium through the process. This results in a major advantage in the high-level waste management.

Chang, Y.I. (Argonne National Lab., IL (United States))

1990-01-01T23:59:59.000Z

345

Effect of Hydrogen Inlets on Planar μPEM Fuel Cell Stacks.  

E-Print Network (OSTI)

??Planar μPEM Fuel Cell Stacks are designed and fabricated in-house through a deep UV lithography technique, with SU 8 photoresist used as the microstructure mold… (more)

Yeh, Jian-liang

2010-01-01T23:59:59.000Z

346

Fuel Cells & Alternative Fuels | Department of Energy  

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

Cells & Alternative Fuels Fuel Cells & Alternative Fuels Presentation given at DEER 2006, August 20-24, 2006, Detroit, Michigan. Sponsored by the U.S. DOE's EERE FreedomCar and...

347

Reactor-Based Plutonium Disposition: Opportunities, Options, and Issues  

SciTech Connect

The end of the Cold War has created a legacy of surplus fissile materials (plutonium and highly enriched uranium) in the United States (U.S.) and the former Soviet Union. These materials pose a danger to national and international security. During the past few years, the U.S. and Russia have engaged in an ongoing dialog concerning the safe storage and disposition of surplus fissile material stockpiles. In January 1997, the Department of Energy (DOE) announced the U. S. would pursue a dual track approach to rendering approximately 50 metric tons of plutonium inaccessible for use in nuclear weapons. One track involves immobilizing the plutonium by combining it with high-level radioactive waste in glass or ceramic ''logs''. The other method, referred to as reactor-based disposition, converts plutonium into mixed oxide (MOX) fuel for nuclear reactors. The U.S. and Russia are moving ahead rapidly to develop and demonstrate the technology required to implement the MOX option in their respective countries. U.S. MOX fuel research and development activities were started in the 1950s, with irradiation of MOX fuel rods in commercial light water reactors (LWR) from the 1960s--1980s. In all, a few thousand MOX fuel rods were successfully irradiated. Though much of this work was performed with weapons-grade or ''near'' weapons-grade plutonium--and favorable fuel performance was observed--the applicability of this data for licensing and use of weapons-grade MOX fuel manufactured with modern fuel fabrication processes is somewhat limited. The U.S. and Russia are currently engaged in an intensive research, development, and demonstration program to support implementation of the MOX option in our two countries. This paper focuses on work performed in the U.S. and provides a brief summary of joint U.S./Russian work currently underway.

Greene, S.R.

1999-07-17T23:59:59.000Z

348

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Diesel Fuel Blend Tax Exemption The biodiesel or ethanol portion of blended fuel containing taxable diesel is exempt from the diesel fuel tax. The biodiesel or ethanol fuel blend...

349

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

fuels include liquid non-petroleum based fuel that can be placed in motor vehicle fuel tanks and used to operate on-road vehicles, including all forms of fuel commonly or...

350

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

fuel blends of at least 20% biodiesel fuel or that mix fuel from separate storage tanks and allow the user to select the percentage of renewable fuel. The maximum credit...

351

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

License Alternative fuel providers, bulk users, and retailers, or any person who fuels an alternative fuel vehicle from a private source that does not pay the alternative fuels tax...

352

Performance and Fabrication Status of TREAT LEU Conversion Conceptual Design Concepts  

SciTech Connect

Resumption of transient testing at the TREAT facility was approved in February 2014 to meet U.S. Department of Energy (DOE) objectives. The National Nuclear Security Administration’s Global Threat Reduction Initiative Convert Program is evaluating conversion of TREAT from its existing highly enriched uranium (HEU) core to a new core containing low enriched uranium (LEU). This paper describes briefly the initial pre-conceptual designs screening decisions with more detailed discussions on current feasibility, qualification and fabrication approaches. Feasible fabrication will be shown for a LEU fuel element assembly that can meet TREAT design, performance, and safety requirements. The statement of feasibility recognizes that further development, analysis, and testing must be completed to refine the conceptual design. Engineering challenges such as cladding oxidation, high temperature material properties, and fuel block fabrication along with neutronics performance, will be highlighted. Preliminary engineering and supply chain evaluation provided confidence that the conceptual designs can be achieved.

IJ van Rooyen; SR Morrell; AE Wright; E. P Luther; K Jamison; AL Crawford; HT III Hartman

2014-10-01T23:59:59.000Z

353

Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) Acquisition,  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fuel Fuel Vehicle (AFV) Acquisition, Fuel Use, and Emissions Reductions Requirements to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) Acquisition, Fuel Use, and Emissions Reductions Requirements on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) Acquisition, Fuel Use, and Emissions Reductions Requirements on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) Acquisition, Fuel Use, and Emissions Reductions Requirements on Google Bookmark Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) Acquisition, Fuel Use, and Emissions Reductions Requirements on Delicious Rank Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) Acquisition, Fuel Use, and Emissions Reductions Requirements on Digg

354

Fuel reforming for fuel cell application.  

E-Print Network (OSTI)

??Fossil fuels, such as natural gas, petroleum, and coal are currently the primary source of energy that drives the world economy. However, fossil fuel is… (more)

Hung, Tak Cheong

2006-01-01T23:59:59.000Z

355

International Atomic Energy Agency (IAEA) activities on spent fuel management options  

SciTech Connect

Many countries have in the past several decades opted for storage of spent fuel for undefined periods of time. They have adopted the 'wait and see' strategy for spent fuel management. A relatively small number of countries have adopted reprocessing and use of MOX fuel as part of their strategy in spent fuel management. From the 10, 000 tonnes of heavy metal that is removed annually from nuclear reactors throughout the world, only approximately 30 % is currently being reprocessed. Continuous re-evaluation of world energy resources, announcement of the Global Nuclear Energy Partnership (GNEP) and the Russian initiative to form international nuclear centers, including reprocessing, are changing the stage for future development of nuclear energy. World energy demand is expected to more than double by 2050, and expansion of nuclear energy is a key to meeting this demand while reducing pollution and greenhouse gases. Since its foundation, the International Atomic Energy Agency (IAEA) has served as an interface between countries in exchanging information on the peaceful development of nuclear energy and at the same time guarding against proliferation of materials that could be used for nuclear weapons. The IAEA's Department of Nuclear Energy has been generating technical documents, holding meetings and conferences, and supporting technical cooperation projects to facilitate this exchange of information. This paper focuses on the current status of IAEA activities in the field of spent fuel management being carried out by the Division of Nuclear Fuel Cycle and Waste Technology. Information on those activities could be found on the web site link www.iaea.org/OurWork/ST/NE/NEFW/nfcms. To date, the IAEA has given priority in its spent fuel management activities to supporting Member States in their efforts to deal with growing accumulations of spent power reactor fuel. There is technical consensus that the present technologies for spent fuel storage, wet and dry, provide adequate protection to people and environment. As storage durations grow, the IAEA has expanded its work related to the implications of extended storage periods. Operation and maintenance of containers for storage and transport have also been investigated related to long term storage periods. In addition, as international interest in reprocessing of spent fuel increases, the IAEA continues to serve as a crossroads for sharing the latest developments in spent fuel treatment options. A Coordinated Research Project is currently addressing spent fuel performance assessment and research to evaluate long term effects of storage on spent fuel. The effect of increased burnup and mixed oxide fuels on spent fuel management is also the focus of interest as it follows the trend in optimizing the use of nuclear fuel. Implications of damaged fuel on storage and transport as well as burnup credit in spent fuel applications are areas that the IAEA is also investigating. Since spent fuel management considerations require social stability and institutional control, those aspects are taken into account in most IAEA activities. Data requirements and records management as storage durations extend were also investigated as well as the potential for regional spent fuel storage facilities. Spent fuel management activities continue to be coordinated with others in the IAEA to ensure compliance and consistency with efforts in the Department of Safety and Security and the Department of Safeguards, as well as with activities related to geologic disposal. Either disposal of radioactive waste or spent fuel will be an ultimate consideration in all spent fuel management options. Updated information on spent fuel treatment options that include fuel reprocessing as well as transmutation of minor actinides are investigated to optimize the use of nuclear fuel and minimize impact on environment. Tools for spent fuel management economics are also investigated to facilitate assessment of industrial applicability for these options. Most IAEA spent fuel management activities will ultimately be reported in o

Lovasic, Z.; Danker, W. [International Atomic Energy Agency (IAEA) Vienna (Austria)

2007-07-01T23:59:59.000Z

356

Fabric composite heat pipe technology development  

SciTech Connect

Testing has been performed on a variety of fabric composite technology feasibility issues. These include an evaluation of the effective radiation heat transfer rate from a heated metallic surface covered by a ceramic fabric with the intent of determining the effective emissivity'' of the combination of materials, studies of the wicking properties of ceramic fabrics, and the construction of fabric composite heat pipes to test their working properties under both steady state and transient conditions. Results of these experiments shown that fabric composite combinations have greatly enhanced effective emissivities'' resulting from the increases surface area of the fabric, ceramic fabrics can work very well as the wick for heat pipes, ceramic fabric heat pipes have been demonstrated to operate under typical space conditions, and large mass reductions are possible by using fabric composite heat pipes for heat rejection radiator systems.

Klein, A.C.; Gulshan-Ara, Z.; Kiestler, W.; Snuggerud, R.; Marks, T.S. (Department of Nuclear Engineering, Oregon State University, Corvallis, Oregon 97331 (United States))

1993-01-10T23:59:59.000Z

357

Fabrication of Cerium Oxide and Uranium Oxide Microspheres for Space Nuclear Power Applications  

SciTech Connect

Cerium oxide and uranium oxide microspheres are being produced via an internal gelation sol-gel method to investigate alternative fabrication routes for space nuclear fuels. Depleted uranium and non-radioactive cerium are being utilized as surrogates for plutonium-238 (Pu-238) used in radioisotope thermoelectric generators and for enriched uranium required by nuclear thermal rockets. While current methods used to produce Pu-238 fuels at Los Alamos National Laboratory (LANL) involve the generation of fine powders that pose a respiratory hazard and have a propensity to contaminate glove boxes, the sol-gel route allows for the generation of oxide microsphere fuels through an aqueous route. The sol-gel method does not generate fine powders and may require fewer processing steps than the LANL method with less operator handling. High-quality cerium dioxide microspheres have been fabricated in the desired size range and equipment is being prepared to establish a uranium dioxide microsphere production capability.

Jeffrey A. Katalenich; Michael R. Hartman; Robert C. O'Brien

2013-02-01T23:59:59.000Z

358

Coal based fuels, fuel systems and alternative fuels  

SciTech Connect

The introduction of coal based fuel systems such as coal/air and coal water mixtures was an attempt to minimize the use of heavy fuel oils in large scale power generation processes. This need was based on forecasts of fuel reserves and future pricing of fuel oils, therefore economic considerations predominated over environmental benefits, if any, which could result from widespread use of these fuels. Coal continued as the major fuel used in the power generation industry and combustion systems were developed to minimize gaseous emissions, such as NOx. Increasing availability of natural gas led to consideration of its use in combination with coal in fuel systems involving combined cycle or topping cycle operations. Dual fuel coal natural gas operations also offered the possibility of improved performance in comparison to 100% coal based fuel systems. Economic considerations have more recently looked at emulsification of heavy residual liquid fuels for consumption in power generation boiler and Orimulsion has emerged as a prime example of this alternative fuel technology. The paper will discuss some aspects of the burner technology related to the application of these various coal based fuels, fuel systems and alternative fuels in the power generation industry.

Allen, J.W.; Beal, P.R.

1998-07-01T23:59:59.000Z

359

Coal based fuels, fuel systems and alternative fuels  

SciTech Connect

The introduction of coal based fuel systems such as coal/air and coal water mixtures was an attempt to minimise the use of heavy fuel oils in large scale power generation processes. This need was based on forecasts of fuel reserves and future pricing of fuel oils, therefore economic considerations predominated over environmental benefits, if any, which could result from widespread use of these fuels. Coal continued as the major fuel used in the power generation industry and combustion systems were developed to minimise gaseous emissions, such as NO{sub x}. Increasing availability of natural gas led to consideration of its use in combination with coal in fuel systems involving combined cycle or topping cycle operations. Dual fuel coal natural gas operations also offered the possibility of improved performance in comparison to 100% coal based fuel systems. Economic considerations have more recently looked at emulsification of heavy residual liquid fuels for consumption in power generation boiler and Orimulsion has emerged as a prime example of this alternative fuel technology. The next sections of the paper will discuss some aspects of the burner technology related to the application of these various coal based fuels, fuel systems and alternative fuels in the power generation industry.

Allen, J.W.; Beal, P.R. [ABB Combustion Services Limited, Derby (United Kingdom)

1998-04-01T23:59:59.000Z

360

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

SciTech Connect

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

Venkatesan, Krishna

2011-11-30T23:59:59.000Z

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


361

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Tools Tools Printable Version Share this resource Send a link to Alternative Fuels Data Center to someone by E-mail Share Alternative Fuels Data Center on Facebook Tweet about Alternative Fuels Data Center on Twitter Bookmark Alternative Fuels Data Center on Google Bookmark Alternative Fuels Data Center on Delicious Rank Alternative Fuels Data Center on Digg Find More places to share Alternative Fuels Data Center on AddThis.com... Fuel Properties Search Fuel Properties Comparison Create a custom chart comparing fuel properties and characteristics for multiple fuels. Select the fuel and properties of interest. Select Fuels Clear all All Fuels Gasoline Diesel (No. 2) Biodiesel Compressed Natural Gas (CNG) Electricity Ethanol Hydrogen Liquefied Natural Gas (LNG) Propane (LPG)

362

Fuel cell generating plant  

SciTech Connect

This paper discusses a fuel cell generating plant. It comprises a compressed fuel supply; a fuel cell system including fuel conditioning apparatus and fuel cells; a main fuel conduit for conveying fuel from the fuel supply to the fuel cell system; a turbo compressor having a turbine receiving exhaust products from the fuel cell system and a compressor for compressing air; a main air conduit for conveying air from the compressor to the fuel cell system; an auxiliary burner having a primary burner and a pilot; an auxiliary air conduit for conveying air from the compressed fuel supply to the auxiliary burner; an auxiliary exhaust conduit for conveying exhaust products from the auxiliary burner to the turbine; a check valve located between the fuel supply and the pilot; and a gas accumulator in the auxiliary fuel conduit located between the check valve and the pilot.

Sanderson, R.A.

1990-11-27T23:59:59.000Z

363

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

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

2009 DOE Hydrogen Program and Vehicle Technologies Program Annual Merit Review and Peer Evaluation Meeting, May 18-22, 2009 -- Washington D.C.

364

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

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

for loss of flow when orifice area is reduced by a factor of 4 - Compensate for reduced penetration distance of smaller orifice - Enable greater flexibility to control...

365

Metallic Fuel Casting Development and Parameter Optimization Simulations  

SciTech Connect

One of the advantages of metallic fuel is the abilility to cast the fuel slugs to near net shape with little additional processing. However, the high aspect ratio of the fuel is not ideal for casting. EBR-II fuel was cast using counter gravity injection casting (CGIC) but, concerns have been raised concerning the feasibility of this process for americium bearing alloys. The Fuel Cycle Research and Development program has begun developing gravity casting techniques suitable for fuel production. Compared to CGIC gravity casting does not require a large heel that then is recycled, does not require application of a vacuum during melting, and is conducive to re-usable molds. Development has included fabrication of two separate benchscale, approximately 300 grams, systems. To shorten development time computer simulations have been used to ensure mold and crucible designs are feasible and to identify which fluid properties most affect casting behavior and therefore require more characterization.

R.S. Fielding; J. Crapps; C. Unal; J.R. Kennedy

2013-03-01T23:59:59.000Z

366

Reference Alloy Waste Form Fabrication and Initiation of Reducing Atmosphere and Reductive Additives Study on Alloy Waste Form Fabrication  

SciTech Connect

This report describes the fabrication of two reference alloy waste forms, RAW-1(Re) and RAW-(Tc) using an optimized loading and heating method. The composition of the alloy materials was based on a generalized formulation to process various proposed feed streams resulting from the processing of used fuel. Waste elements are introduced into molten steel during alloy fabrication and, upon solidification, become incorporated into durable iron-based intermetallic phases of the alloy waste form. The first alloy ingot contained surrogate (non-radioactive), transition-metal fission products with rhenium acting as a surrogate for technetium. The second alloy ingot contained the same components as the first ingot, but included radioactive Tc-99 instead of rhenium. Understanding technetium behavior in the waste form is of particular importance due the longevity of Tc-99 and its mobility in the biosphere in the oxide form. RAW-1(Re) and RAW-1(Tc) are currently being used as test specimens in the comprehensive testing program investigating the corrosion and radionuclide release mechanisms of the representative alloy waste form. Also described in this report is the experimental plan to study the effects of reducing atmospheres and reducing additives to the alloy material during fabrication in an attempt to maximize the oxide content of waste streams that can be accommodated in the alloy waste form. Activities described in the experimental plan will be performed in FY12. The first aspect of the experimental plan is to study oxide formation on the alloy by introducing O2 impurities in the melt cover gas or from added oxide impurities in the feed materials. Reducing atmospheres will then be introduced to the melt cover gas in an attempt to minimize oxide formation during alloy fabrication. The second phase of the experimental plan is to investigate melting parameters associated with alloy fabrication to allow the separation of slag and alloy components of the melt.

S.M. Frank; T.P. O'Holleran; P.A. Hahn

2011-09-01T23:59:59.000Z

367

High-pressure coal fuel processor development  

SciTech Connect

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

Greenhalgh, M.L.

1992-11-01T23:59:59.000Z

368

Alternative Fuels Data Center: Flexible Fuel Vehicle Conversions  

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

Conversions to someone by E-mail Share Alternative Fuels Data Center: Flexible Fuel Vehicle Conversions on Facebook Tweet about Alternative Fuels Data Center: Flexible Fuel Vehicle...

369

Vehicle Certification Test Fuel and Ethanol Flex Fuel Quality...  

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

Vehicle Certification Test Fuel and Ethanol Flex Fuel Quality Vehicle Certification Test Fuel and Ethanol Flex Fuel Quality Breakout Session 2: Frontiers and Horizons Session 2-B:...

370

Texas Hydrogen Highway - Fuel Cell Hybrid Bus and Fueling Infrastructu...  

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

Texas Hydrogen Highway - Fuel Cell Hybrid Bus and Fueling Infrastructure Technology Showcase Texas Hydrogen Highway - Fuel Cell Hybrid Bus and Fueling Infrastructure Technology...

371

Light Duty Fuel Cell Electric Vehicle Hydrogen Fueling Protocol...  

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

Light Duty Fuel Cell Electric Vehicle Hydrogen Fueling Protocol Light Duty Fuel Cell Electric Vehicle Hydrogen Fueling Protocol Download the webinar slides from the U.S. Department...

372

Hydrogen and Fuel Cell Technologies Update: 2010 Fuel Cell Seminar...  

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

Hydrogen and Fuel Cell Technologies Update: 2010 Fuel Cell Seminar and Exposition Hydrogen and Fuel Cell Technologies Update: 2010 Fuel Cell Seminar and Exposition Presentation by...

373

Flexible Fuel Vehicles: Providing a Renewable Fuel Choice, Vehicle...  

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

Flexible Fuel Vehicles: Providing a Renewable Fuel Choice, Vehicle Technologies Program (VTP) (Fact Sheet) Flexible Fuel Vehicles: Providing a Renewable Fuel Choice, Vehicle...

374

DOE Fuel Cell Technologies Office: 2013 Fuel Cell Seminar and...  

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

DOE Fuel Cell Technologies Office: 2013 Fuel Cell Seminar and Energy Exposition DOE Fuel Cell Technologies Office: 2013 Fuel Cell Seminar and Energy Exposition Overview of DOE's...

375

DOE Fuel Cell Technologies Office Record 13012: Fuel Cell System...  

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

Fuel Cell Technologies Office Record 13012: Fuel Cell System Cost - 2013 DOE Fuel Cell Technologies Office Record 13012: Fuel Cell System Cost - 2013 This program record from the...

376

Digital fabrication in the architectural design process  

E-Print Network (OSTI)

Digital fabrication is affecting the architectural design process due to the increasingly important role it has in the fabrication of architectural models. Many design professionals, professors, and students have experienced ...

Seely, Jennifer C. K., 1975-

2004-01-01T23:59:59.000Z

377

Reproducible Tip Fabrication and Cleaning for UHV STM . | EMSL  

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

Reproducible Tip Fabrication and Cleaning for UHV STM . Reproducible Tip Fabrication and Cleaning for UHV STM . Abstract: Several technical modifications related to the fabrication...

378

Atomic Diffusion in the Uranium-50wt% Zirconium Nuclear Fuel System  

E-Print Network (OSTI)

Atomic diffusion phenomena were examined in a metal-alloy nuclear fuel system composed of ?-phase U-50wt%Zr fuel in contact with either Zr-10wt%Gd or Zr-10wt%Er. Each alloy was fabricated from elemental feed material via melt-casting, and diffusion...

Eichel, Daniel

2013-06-17T23:59:59.000Z

379

Highly Stable, Anion Conductive, Comb-Shaped Copolymers for Alkaline Fuel Cells  

Science Journals Connector (OSTI)

Further device optimization studies are needed to optimize catalysts and MEA fabrication procedure to improve the compatibility between the interface of catalyst and ionomer. ... membrane fuel cells - performances are currently limited by the electrode architectures that have been optimized for use in PEM fuel cells but not alk. ...

Nanwen Li; Yongjun Leng; Michael A. Hickner; Chao-Yang Wang

2013-05-30T23:59:59.000Z

380

Chemical Kinetic Modeling of Fuels  

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

petroleum based fuels * Non-petroleum based fuels: - Biodiesel and new generation biofuels - Fischer-Tropsch (F-T) fuels - Oil sand derived fuels Reduce mechanisms for...

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


381

Fuel Cell Links  

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

Fuel Cell Links Fuel Cell Links The links below are provided as additional resources for fuel-cell-related information. Most of the linked sites are not part of, nor affiliated with, fueleconomy.gov. We do not endorse or vouch for the accuracy of the information found on such sites. Fuel Cell Vehicles and Manufacturers Chevrolet General Motors press release about the Chevrolet Fuel Cell Equinox Ford Ford overview of their hydrogen fuel cell vehicles Honda FCX Clarity official site Hyundai Hyundai press release announcing the upcoming Tucson Fuel Cell Mercedes-Benz Ener-G-Force Fuel-cell-powered concept SUV Nissan Nissan TeRRA concept SUV Toyota Overview of Toyota fuel cell technology Hydrogen- and Fuel-Cell-Related Information and Tools Fuel Cell Vehicles Brief overview of fuel cell vehicles provided by DOE's Alternative Fuels Data Center (AFDC)

382

Fuel Guide Economy  

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

1 1 MODEL YEAR 2000 FUEL ECONOMY LEADERS IN POPULAR VEHICLE CLASSES Listed below are the vehicles with the highest fuel economy for the most popular classes, including both automatic and manual transmissions and gasoline and diesel vehicles. Please be aware that many of these vehicles come in a range of engine sizes and trim lines, resulting in different fuel economy values. Check the fuel economy guide or the fuel economy sticker on new vehicles to find the values for a particular version of a vehicle. CONTENTS MODEL YEAR 2000 FUEL ECONOMY LEADERS ................. 1 HOW TO USE THIS GUIDE ..................................................... 2 FUEL ECONOMY AND YOUR ANNUAL FUEL COSTS .......... 3 WHY FUEL ECONOMY IS IMPORTANT .................................

383

Tutorial: Hot Topics in Personal Fabrication Research  

Science Journals Connector (OSTI)

In this tutorial, we survey novel ways for interacting with personal fabrication machines, such as laser cutters, milling machines, and 3D printers. The goal is to provide attendees with an overview of recent HCI re- search in personal fabrication and ... Keywords: 3d printing, laser cutting, milling machines, personal fabrication, rapid prototyping

Stefanie Mueller, Alexandra Ion, Patrick Baudisch

2014-11-01T23:59:59.000Z

384

Fuels options conference  

SciTech Connect

The proceedings of the Fuels Options Conference held May 9-10, 1995 in Atlanta, Georgia are presented. Twenty-three papers were presented at the conference that dealt with fuels outlook; unconventional fuels; fuel specification, purchasing, and contracting; and waste fuels applications. A separate abstract was prepared for each paper for inclusion in the Energy Science and Technology Database.

NONE

1995-09-01T23:59:59.000Z

385

Chapter 3 - Fuels for Fuel Cells  

Science Journals Connector (OSTI)

Publisher Summary This chapter deals with various types of liquid fuels and the relevant chemical and physical properties of these fuels as a means of comparison to the fuels of the future. It gives an overview of the manufacture and properties of the common fuels as well as a description of various biofuels. A fuel mixture usually contains a wide range of organic compounds (usually hydrocarbons). The specific mixture of hydrocarbons gives a fuel its characteristic properties, such as boiling point, melting point, density, viscosity, and a host of other properties. Depending on the application (stationary, central power, remote, auxiliary, transportation, military, etc.), there are a wide range of conventional fuels, such as natural gas, liquefied petroleum gas, light distillates, methanol, ethanol, dimethyl ether, naphtha, gasoline, kerosene, jet fuels, diesel, and biodiesel, that could be used in reforming processes to produce hydrogen (or hydrogen-rich synthesis gas) to power fuel cells. Fossils fuels include gaseous fuels, gasoline, kerosene, diesel fuel, and jet fuels. Gaseous fuels include natural gas and liquefied petroleum gas. Types of gasoline include automotive gasoline, aviation gasoline, and gasohol. Some additives added into gasoline are antioxidants, corrosion inhibitors, demulsifiers, anti-icing, dyes and markers, drag reducers, and oxygenates.

James G. Speight

2011-01-01T23:59:59.000Z

386

Alternative Fuels Data Center: Alternative Fueling Infrastructure Grants  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Alternative Fueling Alternative Fueling Infrastructure Grants to someone by E-mail Share Alternative Fuels Data Center: Alternative Fueling Infrastructure Grants on Facebook Tweet about Alternative Fuels Data Center: Alternative Fueling Infrastructure Grants on Twitter Bookmark Alternative Fuels Data Center: Alternative Fueling Infrastructure Grants on Google Bookmark Alternative Fuels Data Center: Alternative Fueling Infrastructure Grants on Delicious Rank Alternative Fuels Data Center: Alternative Fueling Infrastructure Grants on Digg Find More places to share Alternative Fuels Data Center: Alternative Fueling Infrastructure Grants on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Alternative Fueling Infrastructure Grants

387

Alternative Fuels Data Center: Alternative Fuel Vehicle Replacement Grants  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

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

388

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

Alternative Fuels and Advanced Vehicles Data Center (EERE)

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

389

Alternative Fuels Data Center: Alternative Fueling Infrastructure Tax  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fueling Fueling Infrastructure Tax Credit to someone by E-mail Share Alternative Fuels Data Center: Alternative Fueling Infrastructure Tax Credit on Facebook Tweet about Alternative Fuels Data Center: Alternative Fueling Infrastructure Tax Credit on Twitter Bookmark Alternative Fuels Data Center: Alternative Fueling Infrastructure Tax Credit on Google Bookmark Alternative Fuels Data Center: Alternative Fueling Infrastructure Tax Credit on Delicious Rank Alternative Fuels Data Center: Alternative Fueling Infrastructure Tax Credit on Digg Find More places to share Alternative Fuels Data Center: Alternative Fueling Infrastructure Tax Credit on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Alternative Fueling Infrastructure Tax Credit

390

Alternative Fuels Data Center: Alternative Fuel Vehicle Labeling  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

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

391

Alternative Fuels Data Center: Biofuel Fueling Infrastructure Tax Credit  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Biofuel Fueling Biofuel Fueling Infrastructure Tax Credit to someone by E-mail Share Alternative Fuels Data Center: Biofuel Fueling Infrastructure Tax Credit on Facebook Tweet about Alternative Fuels Data Center: Biofuel Fueling Infrastructure Tax Credit on Twitter Bookmark Alternative Fuels Data Center: Biofuel Fueling Infrastructure Tax Credit on Google Bookmark Alternative Fuels Data Center: Biofuel Fueling Infrastructure Tax Credit on Delicious Rank Alternative Fuels Data Center: Biofuel Fueling Infrastructure Tax Credit on Digg Find More places to share Alternative Fuels Data Center: Biofuel Fueling Infrastructure Tax Credit on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Biofuel Fueling Infrastructure Tax Credit

392

Alternative Fuels Data Center: Alternative Fuels Promotion and Information  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fuels Fuels Promotion and Information to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuels Promotion and Information on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuels Promotion and Information on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuels Promotion and Information on Google Bookmark Alternative Fuels Data Center: Alternative Fuels Promotion and Information on Delicious Rank Alternative Fuels Data Center: Alternative Fuels Promotion and Information on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuels Promotion and Information on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Alternative Fuels Promotion and Information

393

Alternative Fuels Data Center: Ethanol Fuel Blend Dispensing Regulations  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Ethanol Fuel Blend Ethanol Fuel Blend Dispensing Regulations to someone by E-mail Share Alternative Fuels Data Center: Ethanol Fuel Blend Dispensing Regulations on Facebook Tweet about Alternative Fuels Data Center: Ethanol Fuel Blend Dispensing Regulations on Twitter Bookmark Alternative Fuels Data Center: Ethanol Fuel Blend Dispensing Regulations on Google Bookmark Alternative Fuels Data Center: Ethanol Fuel Blend Dispensing Regulations on Delicious Rank Alternative Fuels Data Center: Ethanol Fuel Blend Dispensing Regulations on Digg Find More places to share Alternative Fuels Data Center: Ethanol Fuel Blend Dispensing Regulations on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Ethanol Fuel Blend Dispensing Regulations

394

Alternative Fuels Data Center: Alternative Fuels Taxation Study Commission  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fuels Fuels Taxation Study Commission to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuels Taxation Study Commission on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuels Taxation Study Commission on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuels Taxation Study Commission on Google Bookmark Alternative Fuels Data Center: Alternative Fuels Taxation Study Commission on Delicious Rank Alternative Fuels Data Center: Alternative Fuels Taxation Study Commission on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuels Taxation Study Commission on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Alternative Fuels Taxation Study Commission

395

Alternative Fuels Data Center: Alternative Fueling Infrastructure Tax  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Alternative Fueling Alternative Fueling Infrastructure Tax Credit to someone by E-mail Share Alternative Fuels Data Center: Alternative Fueling Infrastructure Tax Credit on Facebook Tweet about Alternative Fuels Data Center: Alternative Fueling Infrastructure Tax Credit on Twitter Bookmark Alternative Fuels Data Center: Alternative Fueling Infrastructure Tax Credit on Google Bookmark Alternative Fuels Data Center: Alternative Fueling Infrastructure Tax Credit on Delicious Rank Alternative Fuels Data Center: Alternative Fueling Infrastructure Tax Credit on Digg Find More places to share Alternative Fuels Data Center: Alternative Fueling Infrastructure Tax Credit on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Alternative Fueling Infrastructure Tax Credit

396

Alternative Fuels Data Center: Alternative Fuel and Conversion Definitions  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Alternative Fuel and Alternative Fuel and Conversion Definitions to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel and Conversion Definitions on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel and Conversion Definitions on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel and Conversion Definitions on Google Bookmark Alternative Fuels Data Center: Alternative Fuel and Conversion Definitions on Delicious Rank Alternative Fuels Data Center: Alternative Fuel and Conversion Definitions on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuel and Conversion Definitions on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Alternative Fuel and Conversion Definitions

397

Alternative Fuels Data Center: Ethanol Flexible Fuel Vehicle Conversions  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Ethanol Flexible Fuel Ethanol Flexible Fuel Vehicle Conversions to someone by E-mail Share Alternative Fuels Data Center: Ethanol Flexible Fuel Vehicle Conversions on Facebook Tweet about Alternative Fuels Data Center: Ethanol Flexible Fuel Vehicle Conversions on Twitter Bookmark Alternative Fuels Data Center: Ethanol Flexible Fuel Vehicle Conversions on Google Bookmark Alternative Fuels Data Center: Ethanol Flexible Fuel Vehicle Conversions on Delicious Rank Alternative Fuels Data Center: Ethanol Flexible Fuel Vehicle Conversions on Digg Find More places to share Alternative Fuels Data Center: Ethanol Flexible Fuel Vehicle Conversions on AddThis.com... Ethanol Flexible Fuel Vehicle Conversions Updated July 29, 2011 Rising gasoline prices and concerns about climate change have greatly

398

Alternative Fuels Data Center: Alternative Fuel Production Subsidy  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fuel Fuel Production Subsidy Prohibition to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel Production Subsidy Prohibition on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel Production Subsidy Prohibition on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel Production Subsidy Prohibition on Google Bookmark Alternative Fuels Data Center: Alternative Fuel Production Subsidy Prohibition on Delicious Rank Alternative Fuels Data Center: Alternative Fuel Production Subsidy Prohibition on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuel Production Subsidy Prohibition on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Alternative Fuel Production Subsidy Prohibition

399

Alternative Fuels Data Center: Alternative Fueling Infrastructure Tax  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fueling Fueling Infrastructure Tax Credit to someone by E-mail Share Alternative Fuels Data Center: Alternative Fueling Infrastructure Tax Credit on Facebook Tweet about Alternative Fuels Data Center: Alternative Fueling Infrastructure Tax Credit on Twitter Bookmark Alternative Fuels Data Center: Alternative Fueling Infrastructure Tax Credit on Google Bookmark Alternative Fuels Data Center: Alternative Fueling Infrastructure Tax Credit on Delicious Rank Alternative Fuels Data Center: Alternative Fueling Infrastructure Tax Credit on Digg Find More places to share Alternative Fuels Data Center: Alternative Fueling Infrastructure Tax Credit on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Alternative Fueling Infrastructure Tax Credit

400

Alternative Fuels Data Center: Alternative Fuel Infrastructure Tax Credit  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Alternative Fuel Alternative Fuel Infrastructure Tax Credit to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel Infrastructure Tax Credit on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel Infrastructure Tax Credit on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel Infrastructure Tax Credit on Google Bookmark Alternative Fuels Data Center: Alternative Fuel Infrastructure Tax Credit on Delicious Rank Alternative Fuels Data Center: Alternative Fuel Infrastructure Tax Credit on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuel Infrastructure Tax Credit on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Alternative Fuel Infrastructure Tax Credit

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


401

Alternative Fuels Data Center: Ethanol Fueling Infrastructure Grants  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Ethanol Fueling Ethanol Fueling Infrastructure Grants to someone by E-mail Share Alternative Fuels Data Center: Ethanol Fueling Infrastructure Grants on Facebook Tweet about Alternative Fuels Data Center: Ethanol Fueling Infrastructure Grants on Twitter Bookmark Alternative Fuels Data Center: Ethanol Fueling Infrastructure Grants on Google Bookmark Alternative Fuels Data Center: Ethanol Fueling Infrastructure Grants on Delicious Rank Alternative Fuels Data Center: Ethanol Fueling Infrastructure Grants on Digg Find More places to share Alternative Fuels Data Center: Ethanol Fueling Infrastructure Grants on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Ethanol Fueling Infrastructure Grants The Minnesota Corn Research & Promotion Council and the Minnesota

402

Alternative Fuels Data Center: Alternative Fuels Feasibility Study  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Alternative Fuels Alternative Fuels Feasibility Study to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuels Feasibility Study on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuels Feasibility Study on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuels Feasibility Study on Google Bookmark Alternative Fuels Data Center: Alternative Fuels Feasibility Study on Delicious Rank Alternative Fuels Data Center: Alternative Fuels Feasibility Study on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuels Feasibility Study on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Alternative Fuels Feasibility Study The North Carolina State Energy Office, Department of Administration,

403

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

Alternative Fuels and Advanced Vehicles Data Center (EERE)

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

404

Alternative Fuels Data Center: Alternative Fueling Infrastructure Tax  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fueling Fueling Infrastructure Tax Credit to someone by E-mail Share Alternative Fuels Data Center: Alternative Fueling Infrastructure Tax Credit on Facebook Tweet about Alternative Fuels Data Center: Alternative Fueling Infrastructure Tax Credit on Twitter Bookmark Alternative Fuels Data Center: Alternative Fueling Infrastructure Tax Credit on Google Bookmark Alternative Fuels Data Center: Alternative Fueling Infrastructure Tax Credit on Delicious Rank Alternative Fuels Data Center: Alternative Fueling Infrastructure Tax Credit on Digg Find More places to share Alternative Fuels Data Center: Alternative Fueling Infrastructure Tax Credit on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Alternative Fueling Infrastructure Tax Credit

405

Multi-objective fuel policies: Renewable fuel standards versus Fuel greenhouse gas intensity standards  

E-Print Network (OSTI)

Gas Reductions under Low Carbon Fuel Standards? Americanto Implement the Low Carbon Fuel Standard, Volume I Sta?Paper Series Multi-objective fuel policies: Renewable fuel

Rajagopal, Deepak

2010-01-01T23:59:59.000Z

406

Multi-objective fuel policies: Renewable fuel standards versus Fuel greenhouse gas intensity standards  

E-Print Network (OSTI)

to policy makers such as fuel price, GHG emission (bothdimensions, namely, fuel price, GHG emissions and marketa FGIS results in higher fuel price, lower fuel consumption,

Rajagopal, Deepak

2010-01-01T23:59:59.000Z

407

Fuel elements of thermionic converters  

SciTech Connect

Work on thermionic nuclear power systems has been performed in Russia within the framework of the TOPAZ reactor program since the early 1960s. In the TOPAZ in-core thermionic convertor reactor design, the fuel element`s cladding is also the thermionic convertor`s emitter. Deformation of the emitter can lead to short-circuiting and is the primary cause of premature TRC failure. Such deformation can be the result of fuel swelling, thermocycling, or increased unilateral pressure on the emitter due to the release of gaseous fission products. Much of the work on TRCs has concentrated on preventing or mitigating emitter deformation by improving the following materials and structures: nuclear fuel; emitter materials; electrical insulators; moderator and reflector materials; and gas-exhaust device. In addition, considerable effort has been directed toward the development of experimental techniques that accurately mimic operational conditions and toward the creation of analytical and numerical models that allow operational conditions and behavior to be predicted without the expense and time demands of in-pile tests. New and modified materials and structures for the cores of thermionic NPSs and new fabrication processes for the materials have ensured the possibility of creating thermionic NPSs for a wide range of powers, from tens to several hundreds of kilowatts, with life spans of 5 to 10 years.

Hunter, R.L. [ed.] [Sandia National Labs., Albuquerque, NM (United States). Environmental Systems Assessment Dept.; Gontar, A.S.; Nelidov, M.V.; Nikolaev, Yu.V.; Schulepov, L.N. [RI SIA Lutch, Podolsk (Russian Federation)

1997-01-01T23:59:59.000Z

408

Developing and Implementing a Simple, Affordable Hydrogen Fuel Cell Laboratory in Introductory Chemistry  

Science Journals Connector (OSTI)

This laboratory involves a PEM fuel cell that uses hydrogen gas to power a small cell phone vibrator and a model car. ... It is necessary to have an affordable and high-throughput fuel cell laboratory that works well with limited lab and lecture hours; introduces students to cutting-edge research and technology, such as hydrogen fuel cells, FCVs, and clean energy concepts; and stimulates their interest in science. ... goals consisted of design, fabrication, and operation of a hydrogen fueled, 10 kW proton exchange membrane fuel cell driving a one-third scale locomotive pulling two passenger coaches. ...

Kristina Klara; Ning Hou; Allison Lawman; Liheng Wu; Drew Morrill; Alfred Tente; Li-Qiong Wang

2014-08-14T23:59:59.000Z

409

Silicon Based Solid Oxide Fuel Cell Chip for Portable Consumer Electronics -- Final Technical Report  

SciTech Connect

LSI’s fuel cell uses efficient Solid Oxide Fuel Cell (“SOFC”) technology, is manufactured using Micro Electrical Mechanical System (“MEMS”) fabrication methods, and runs on high energy fuels, such as butane and ethanol. The company’s Fuel Cell on a Chip™ technology enables a form-factor battery replacement for portable electronic devices that has the potential to provide an order-of-magnitude run-time improvement over current batteries. Further, the technology is clean and environmentally-friendly. This Department of Energy funded project focused on accelerating the commercialization and market introduction of this technology through improvements in fuel cell chip power output, lifetime, and manufacturability.

Alan Ludwiszewski

2009-06-29T23:59:59.000Z

410

A comparative assessment of the economics of plutonium disposition including comparison with other nuclear fuel cycles  

SciTech Connect

DOE has been evaluating three technologies for the disposition of approximately 50 metric tons of surplus plutonium from defense-related programs: reactors, immobilization, and deep boreholes. As part of the process supporting an early CY 1997 Record of Decision (ROD), a comprehensive assessment of technical viability, cost, and schedule has been conducted. Oak Ridge National Laboratory has managed and coordinated the life-cycle cost (LCC) assessment effort for this program. This paper discusses the economic analysis methodology and the results prior to ROD. Other objectives of the paper are to discuss major technical and economic issues that impact plutonium disposition cost and schedule. Also to compare the economics of a once-through weapons-derived MOX nuclear fuel cycle to other fuel cycles, such as those utilizing spent fuel reprocessing. To evaluate the economics of these technologies on an equitable basis, a set of cost estimating guidelines and a common cost-estimating format were utilized by all three technology teams. This paper also includes the major economic analysis assumptions and the comparative constant-dollar and discounted-dollar LCCs.

Williams, K.A.; Miller, J.W.; Reid, R.L.

1997-05-01T23:59:59.000Z

411

NUCLEAR MATERIAL ATTRACTIVENESS: AN ASSESSMENT OF MATERIAL ASSOCIATED WITH A CLOSED FUEL CYCLE  

SciTech Connect

This paper examines the attractiveness of materials mixtures containing special nuclear materials (SNM) associated with the various processing steps required for a closed fuel cycle. This paper combines the results from earlier studies that examined the attractiveness of SNM associated with the processing of spent light water reactor (LWR) fuel by various reprocessing schemes and the recycle of plutonium as a mixed oxide (MOX) fuel in LWR with new results for the final, repeated burning of SNM in fast-spectrum reactors: fast reactors and accelerator driven systems (ADS). The results of this paper suggest that all reprocessing products evaluated so far need to be rigorously safeguarded and provided moderate to high levels of physical protection. These studies were performed at the request of the United States Department of Energy (DOE), and are based on the calculation of "attractiveness levels" that has been couched in terms chosen for consistency with those normally used for nuclear materials in DOE nuclear facilities. The methodology and key findings will be presented. Additionally, how these attractiveness levels relate to proliferation resistance (e.g. by increasing impediments to the diversion, theft, or undeclared production of SNM for the purpose of acquiring a nuclear weapon), and how they could be used to help inform policy makers, will be discussed.

Bathke, C. G.; Ebbinghaus, B.; Sleaford, Brad W.; Wallace, R. K.; Collins, Brian A.; Hase, Kevin R.; Robel, Martin; Jarvinen, G. D.; Bradley, Keith S.; Ireland, J. R.; Johnson, M. W.; Prichard, Andrew W.; Smith, Brian W.

2010-06-11T23:59:59.000Z

412

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

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Alternative Fuel Alternative Fuel Vehicle (AFV) and Alternative Fuel Rebates to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Alternative Fuel Rebates on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Alternative Fuel Rebates on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Alternative Fuel Rebates on Google Bookmark Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Alternative Fuel Rebates on Delicious Rank Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Alternative Fuel Rebates on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) and Alternative Fuel Rebates on AddThis.com...

413

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

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Alternative Fuel Alternative Fuel Vehicle (AFV) Acquisition and Fuel Use Requirements to someone by E-mail Share Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) Acquisition and Fuel Use Requirements on Facebook Tweet about Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) Acquisition and Fuel Use Requirements on Twitter Bookmark Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) Acquisition and Fuel Use Requirements on Google Bookmark Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) Acquisition and Fuel Use Requirements on Delicious Rank Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) Acquisition and Fuel Use Requirements on Digg Find More places to share Alternative Fuels Data Center: Alternative Fuel Vehicle (AFV) Acquisition and Fuel Use Requirements on AddThis.com...

414

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

for sale fuel labeled as pure biodiesel unless the fuel contains no other type of petroleum product, is registered as biodiesel fuel with the federal government, and meets all...

415

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Ethanol Fuel Blend Tax Rate The tax rate on fuel containing ethanol is 0.06 per gallon less than the tax rate on other motor fuels in certain geographic areas. This reduced rate...

416

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

E85 Definition E85 motor fuel is defined as an alternative fuel that is a blend of ethanol and hydrocarbon, of which the ethanol portion is 75-85% denatured fuel ethanol by volume...

417

Low Carbon Fuel Standards  

E-Print Network (OSTI)

S O N I A YE H Low Carbon Fuel Standards The most direct andalternative transportation fuels is to spur innovation withstandard for upstream fuel producers. hen it comes to energy

Sperling, Dan; Yeh, Sonia

2009-01-01T23:59:59.000Z

418

Fuel Processing [and Discussion  

Science Journals Connector (OSTI)

28 June 1990 research-article Fuel Processing [and Discussion] R. H. Allardice R. S...efficiently, reliably and economically through the reactor and fuel cycle facilities. Thus the fuel cycle is an integral and essential part of the system...

1990-01-01T23:59:59.000Z

419

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Alternative Fuel Excise Tax Compressed natural gas (CNG) motor fuel is subject to the state fuel excise tax at the rate of 0.30 per 120 cubic feet, measured at 14.73 pounds per...

420

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Reduced Compressed Natural Gas (CNG) Fueling Infrastructure Lease - AGL Atlanta Gas Light (AGL) offers a reduced cost lease on the BRC FuelMaker Phill CNG vehicle home fueling...

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


421

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Deregulation of Compressed Natural Gas (CNG) as a Motor Fuel The sale of CNG by a fueling station for use as fuel to operate a motor vehicle is deregulated; however, separate...

422

Hydrogen Fuel Cell Vehicles  

E-Print Network (OSTI)

the membrane for a PEM fuel cell would cost $5/ft (1990$) inmass-produced PEM fuel cell could cost $10/kW or less. Totalparameter for PEM fuel cells: thinner membranes cost less

Delucchi, Mark

1992-01-01T23:59:59.000Z

423

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Biodiesel Blender Tax Credit A licensed fuel supplier who blends biodiesel or green diesel with diesel fuel may claim an income tax credit of 0.05 per gallon for fuel containing...

424

Hydrogen Fuel Cell Vehicles  

E-Print Network (OSTI)

$ b materials cost, % a Fuel cell stack cost only. Includesof the cost of fuel-cell stacks, 1990$° Cost item GE Swan cAnnual maintenance cost of fuel cell stack and auxiliaries (

Delucchi, Mark

1992-01-01T23:59:59.000Z

425

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

0.33 times the rate for diesel For other alternative fuels, the rate is based on the energy content of the fuels as compared to diesel fuel, using a lower heating value of...

426

Hydrogen Fuel Cell Vehicles  

E-Print Network (OSTI)

Hydrogen Fuel Cell Vehicles UCD-ITS-RR-92-14 September byet al. , 1988,1989 HYDROGEN FUEL-CELL VEHICLES: TECHNICALIn the FCEV, the hydrogen fuel cell could supply the "net"

Delucchi, Mark

1992-01-01T23:59:59.000Z

427

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Tools Tools Printable Version Share this resource Send a link to Alternative Fuels Data Center to someone by E-mail Share Alternative Fuels Data Center on Facebook Tweet about Alternative Fuels Data Center on Twitter Bookmark Alternative Fuels Data Center on Google Bookmark Alternative Fuels Data Center on Delicious Rank Alternative Fuels Data Center on Digg Find More places to share Alternative Fuels Data Center on AddThis.com... Data Included in the Alternative Fuel Stations Download The following data fields are provided in the downloadable files for alternative fuel stations. Field Value Description fuel_type_code Type: string The type of alternative fuel the station provides. Fuel types are given as code values as described below: Value Description BD Biodiesel (B20 and above)

428

Precious Metal Recovery from Fuel Cell MEA's  

SciTech Connect

One of the next-generation power sources is the proton exchange membrane (PEM) fuel cell, which runs on pure hydrogen or hydrogen-rich reformate. At the heart of the PEM fuel cell is a membrane electrode assembly (MEA). The MEA is a laminate composed of electrode layers sandwiched between outer layers, fabricated from either carbon fiber or fabric and which control the diffusion of reactant gases, and the inner polymer mebrane. Hydrogen is oxidized at the anode to form protons, which migrate through the membrane and react with oxygen at the cathode to form water. In this type of fuel cell, platinum catalyzes the reactions at both electrodes. Realization of a future that includes ubiquitous use of hydrogen fuel cell-powered vehicles will be partially contingent on a process for recycling components of the fuel cell membrane electrode assemblies. In aggregate, the platinum used for the fuel cell will represent a large pool of this precious metal, and the efficient recycling of Pt from MEA's will be a cost-enabling factor for success of this technology. Care must be taken in the reclamation process because of the presence of fluoropolymers in the MEA. While Pt is normally recovered with high yield, the combustion process commonly applied to remove an organic matrix will also liberate a large volume of HF, a gas which is both toxic and corrosive. Carbonyl fluoride, which has a recommended exposure limit of 2ppmv, is another undesirable product of fluoroploymer combustion. In 2003, the Department of Energy awarded Engelhard Corporation an 80% cost share grant for a five-year project budgeted at $5.9MM. The principal objective is reclaiming platinum from fuel cell MEA's without producing fluorine-containing emissions. Over the last three years, Engelhard has approached the problem from several directions in balancing the two goals: a commercially-viable recycling process and an environmentally favorable one. Working with both fresh and aged fuel cells, it has been shown that precious metals can be liberated at high yield using microwave assisted acid digestion, but exposure of the gas diffusion electrode surfaces is required. A low-cost solvent-stripping process has been identified for two geometries of fuel cell MEA's: GDL and GDE. This paper will detail progress made in realizing a practical, "green" process for recovery of Pt from PEM fuel cell MEA's

Lawrence Shore

2006-11-16T23:59:59.000Z

429

Diesel fuel qualities  

SciTech Connect

As a result of rising fuel costs, many ship operators are turning to less expensive, heavier grade fuels for their diesel engines. Use of these lower quality fuels without adequate preparation can cause increased engine wear and damage to fuel systems. The oil properties which affect pretreatment and cleaning requirements, specifications that should be used when purchasing these fuels, and procedures for confirming that bought fuels meet purchase specifications are discussed. (LCL)

Blenkey, N.

1981-02-01T23:59:59.000Z

430

Fuel processor for fuel cell power system  

DOE Patents (OSTI)

A catalytic organic fuel processing apparatus, which can be used in a fuel cell power system, contains within a housing a catalyst chamber, a variable speed fan, and a combustion chamber. Vaporized organic fuel is circulated by the fan past the combustion chamber with which it is in indirect heat exchange relationship. The heated vaporized organic fuel enters a catalyst bed where it is converted into a desired product such as hydrogen needed to power the fuel cell. During periods of high demand, air is injected upstream of the combustion chamber and organic fuel injection means to burn with some of the organic fuel on the outside of the combustion chamber, and thus be in direct heat exchange relation with the organic fuel going into the catalyst bed.

Vanderborgh, Nicholas E. (Los Alamos, NM); Springer, Thomas E. (Los Alamos, NM); Huff, James R. (Los Alamos, NM)

1987-01-01T23:59:59.000Z

431

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

school districts must pay for the alternative fueling infrastructure, the incremental cost between a conventional and alternative fuel bus, and training for bus maintenance...

432

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

biodiesel fuel will be considered commercially available if the incremental purchase cost compared to conventional diesel fuel is not more than 0.25. To the maximum extent...

433

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

blend being sold. The labeling must follow established labeling specifications for petroleum-based fuels. An alternative fuel producer may provide the retailer with a label...

434

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

tax is imposed on the use of alternative fuels. Alternative fuels include liquefied petroleum gas (LPG or propane), compressed natural gas (CNG), and liquefied natural gas (LNG)....

435

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fuels Tax Alternative fuels subject to the New Mexico excise tax include liquefied petroleum gas (propane), compressed natural gas (CNG), and liquefied natural gas (LNG). The...

436

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Ethanol Blend Dispenser Requirement A retail motor fuel dispenser that dispenses fuel containing more than 10% ethanol by volume must be labeled with the capital letter "E"...

437

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Labeling Requirement All equipment used to dispense motor fuel containing at least 1% ethanol or methanol must be clearly labeled to inform customers that the fuel contains...

438

Fuel Cells at NASCAR  

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

Fuel Cells at NASCAR Ned Stetson U.S. Department of Energy Fuel Cell Technologies Office Catherine Kummer - NASCAR Green Norm Bessette - Acumentrics Question and Answer * Please...

439

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Utility District Natural Gas Fueling Station Regulation Utility districts may own and operate natural gas fueling stations provided that the operation of the station is not...

440

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Alternative Fuel Tax Exemption Propane, compressed natural gas, liquefied natural gas, and electricity used to operate motor vehicles are exempt from state fuel taxes. The Utah...

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441

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Compressed Natural Gas (CNG) Fueling Infrastructure Development The Oklahoma Legislature intends to increase the amount of CNG fueling infrastructure in the state, with the overall...

442

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Natural Gas Fueling Station Air Quality Permit Exemption Natural gas fueling stations are exempt from the requirement to file Air Pollutant Emission Notices, as they have a...

443

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Natural Gas and Propane Fuel Tax Any individual using or selling compressed natural gas (CNG), liquefied natural gas (LNG), or liquefied petroleum gas (propane) as a motor fuel...

444

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

medium- and heavy-duty vehicles must implement strategies to reduce petroleum consumption and emissions by using alternative fuels and improving vehicle fleet fuel...

445

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Alternative Fuel Tax Exemption The retail sale, use, storage, and consumption of alternative fuels is exempt from the state retail sales and use tax. (Reference North Carolina...

446

Automotive Fuel Cell Corporation  

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

with AFCC, a private joint venture company in Canada, formed by combining the automotive fuel cell business of Ballard Power Systems with the fuel cell stack development...

447

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fuels Taxation Study Commission The Taxation of Alternative Fuel and Electric-Powered Vehicles Commission (Commission) was established to study and report findings and...

448

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fuel Vehicle (AFV) and Hybrid Electric Vehicle (HEV) Funding The Alternative Fuels Incentive Grant (AFIG) Program provides financial assistance for qualified projects; information...

449

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Acquisition, Fuel Use, and Emissions Reductions Requirements All state agencies and transit districts must purchase AFVs and use alternative fuels to operate those vehicles to the...

450

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

and other renewable, biodegradable mono alkyl ester combustible fuel derived from biomass. Waivers to the B2 requirement for state agency vehicles may be granted if the fuel...

451

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

fuel. Liquefied petroleum gas (propane) is exempt from LCFS requirements, as are non-biomass-based alternative fuels that are supplied in California for use in transportation at...

452

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

No county, city, village, town, or other political subdivision may levy or collect any excise, license, privilege, or occupational tax on motor vehicle fuel or alternative fuels,...

453

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fuel Economy Test Procedures and Labeling The U.S. Environmental Protection Agency (EPA) is responsible for motor vehicle fuel economy testing. Manufacturers test their own...

454

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Fueling Infrastructure Tax Credit An income tax credit is available to eligible taxpayers who construct or purchase and install qualified alternative fueling infrastructure. The...

455

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

fuel, fuel-efficient, or low emission vehicles, unless such a purchase compromises health, safety, or law enforcement needs. Additionally, the state must develop procedures for...

456

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

of these requirements, alternative fuels include propane, natural gas, electricity, hydrogen, qualified diesel fuel substitutes, E85, and a blend of hydrogen with propane or...

457

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

the purpose of these requirements, alternative fuels include propane, natural gas, electricity, hydrogen, qualified diesel fuel substitutes, E85, and a blend of hydrogen with...

458

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

but will be forfeited if a tax credit recipient stops dispensing alternative fuel or electricity for vehicle charging. Eligible fuels include any mixture of biodiesel and diesel...

459

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

air quality nonattainment areas. Qualified alternative fuels include biodiesel, electricity, natural gas, hydrogen, propane, and fuel mixtures containing at least 85% methanol...

460

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

duly licensed distributors, and sales of exported motor fuel. For taxation purposes, electricity is not considered an alternative fuel. (Reference House Bill 1142, 2014, and New...

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