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1

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...

2

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

3

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

4

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

5

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

6

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

7

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

8

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

9

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

10

NETL - Fuel Reforming Facilities  

ScienceCinema (OSTI)

Research using NETL's Fuel Reforming Facilities explores catalytic issues inherent in fossil-energy related applications, including catalyst synthesis and characterization, reaction kinetics, catalyst activity and selectivity, catalyst deactivation, and stability.

None

2014-06-27T23:59:59.000Z

11

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

12

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

13

Alternative Fuels Data Center: Renewable Fuel Production Facility Tax  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

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

14

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...

15

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

16

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

17

DOE Permitting Hydrogen Facilities: Hydrogen Fueling Stations  

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

Stations Stations Public-use hydrogen fueling stations are very much like gasoline ones. In fact, sometimes, hydrogen and gasoline cars can be fueled at the same station. These stations offer self-service pumps, convenience stores, and other services in high-traffic locations. Photo of a Shell fueling station showing the site convenience store and hydrogen and gasoline fuel pumps. This fueling station in Washington, D.C., provides drivers with both hydrogen and gasoline fuels Many future hydrogen fueling stations will be expansions of existing fueling stations. These facilities will offer hydrogen pumps in addition to gasoline or natural gas pumps. Other hydrogen fueling stations will be "standalone" operations. These stations will be designed and constructed to

18

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

19

Alternative Fuels Data Center: Biofuels Production Facility Grants  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Biofuels Production Biofuels Production Facility Grants to someone by E-mail Share Alternative Fuels Data Center: Biofuels Production Facility Grants on Facebook Tweet about Alternative Fuels Data Center: Biofuels Production Facility Grants on Twitter Bookmark Alternative Fuels Data Center: Biofuels Production Facility Grants on Google Bookmark Alternative Fuels Data Center: Biofuels Production Facility Grants on Delicious Rank Alternative Fuels Data Center: Biofuels Production Facility Grants on Digg Find More places to share Alternative Fuels Data Center: Biofuels Production Facility Grants on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Biofuels Production Facility Grants The Renewable Fuels Development Program provides grants for the

20

Alternative Fuels Data Center: Ethanol Production Facility Environmental  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Ethanol Production Ethanol Production Facility Environmental Assessment Exemption to someone by E-mail Share Alternative Fuels Data Center: Ethanol Production Facility Environmental Assessment Exemption on Facebook Tweet about Alternative Fuels Data Center: Ethanol Production Facility Environmental Assessment Exemption on Twitter Bookmark Alternative Fuels Data Center: Ethanol Production Facility Environmental Assessment Exemption on Google Bookmark Alternative Fuels Data Center: Ethanol Production Facility Environmental Assessment Exemption on Delicious Rank Alternative Fuels Data Center: Ethanol Production Facility Environmental Assessment Exemption on Digg Find More places to share Alternative Fuels Data Center: Ethanol Production Facility Environmental Assessment Exemption on AddThis.com...

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

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

22

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

23

Concept for a small, colocated fuel cycle facility for oxide breeder fuels  

SciTech Connect

As part of a United States Department of Energy (USDOE) program to examine innovative liquid-metal reactor (LMR) system designs over the past three years, the Oak Ridge National Laboratory (ORNL) and the Westinghouse Hanford Company (WHC) collaborated on studies of mixed oxide fuel cycle options. A principal effort was an advanced concept for a small integrated fuel cycle colocated with a 1300-MW(e) reactor station. The study provided a scoping design and a basis on which to proceed with implementation of such a facility if future plans so dictate. The facility integrated reprocessing, waste management, and refabrication functions in a single facility of nominal 35-t/year capacity utilizing the latest technology developed in fabrication programs at WHC and in reprocessing at ORNL. The concept was based on many years of work at both sites and extensive design studies of prior years.

Burch, W.D.; Stradley, J.G.; Lerch, R.E.

1987-01-01T23:59:59.000Z

24

Hot Fuel Examination Facility/South  

SciTech Connect

This document describes the potential environmental impacts associated with proposed modifications to the Hot Fuel Examination Facility/South (HFEF/S). The proposed action, to modify the existing HFEF/S at the Argonne National Laboratory-West (ANL-W) on the Idaho National Engineering Laboratory (INEL) in southeastern Idaho, would allow important aspects of the Integral Fast Reactor (IFR) concept, offering potential advantages in nuclear safety and economics, to be demonstrated. It would support fuel cycle experiments and would supply fresh fuel to the Experimental Breeder Reactor-II (EBR-II) at the INEL. 35 refs., 12 figs., 13 tabs.

Not Available

1990-05-01T23:59:59.000Z

25

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

26

President Reagan Calls for a National Spent Fuel Storage Facility...  

National Nuclear Security Administration (NNSA)

Spent Fuel Storage Facility Washington, DC The Reagan Administration announces a nuclear energy policy that anticipates the establishment of a facility for the storage of...

27

Behind the Scenes at Berkeley Lab - The Mechanical Fabrication Facility  

ScienceCinema (OSTI)

Part of the Behind the Scenes series at Berkeley Lab, this video highlights the lab's mechanical fabrication facility and its exceptional ability to produce unique tools essential to the lab's scientific mission. Through a combination of skilled craftsmanship and precision equipment, machinists and engineers work with scientists to create exactly what's needed - whether it's measured in microns or meters.

Wells, Russell; Chavez, Pete; Davis, Curtis; Bentley, Brian

2014-09-15T23:59:59.000Z

28

Behind the Scenes at Berkeley Lab - The Mechanical Fabrication Facility  

SciTech Connect

Part of the Behind the Scenes series at Berkeley Lab, this video highlights the lab's mechanical fabrication facility and its exceptional ability to produce unique tools essential to the lab's scientific mission. Through a combination of skilled craftsmanship and precision equipment, machinists and engineers work with scientists to create exactly what's needed - whether it's measured in microns or meters.

Wells, Russell; Chavez, Pete; Davis, Curtis; Bentley, Brian

2013-05-17T23:59:59.000Z

29

Nano Fab Lab, Stockholm Sweden The Albanova Nano Fabrication Facility  

E-Print Network (OSTI)

Nano Fab Lab, Stockholm Sweden The Albanova Nano Fabrication Facility Nano technology for basic research and small commercial enterprises Director: Prof. David Haviland #12;Nano Fab Lab, Stockholm Sweden Nano-Lab Philosophy · Nanometer scale patterning and metrology · Broad spectrum of user research

Haviland, David

30

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

31

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

32

Alternative Fuels Data Center: Biofuel Production Facility Tax Credit  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Biofuel Production Biofuel Production Facility Tax Credit to someone by E-mail Share Alternative Fuels Data Center: Biofuel Production Facility Tax Credit on Facebook Tweet about Alternative Fuels Data Center: Biofuel Production Facility Tax Credit on Twitter Bookmark Alternative Fuels Data Center: Biofuel Production Facility Tax Credit on Google Bookmark Alternative Fuels Data Center: Biofuel Production Facility Tax Credit on Delicious Rank Alternative Fuels Data Center: Biofuel Production Facility Tax Credit on Digg Find More places to share Alternative Fuels Data Center: Biofuel Production Facility Tax Credit on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Biofuel Production Facility Tax Credit Companies that invest in the development of a biofuel production facility

33

Alternative Fuels Data Center: Biofuels Production Facility Tax Credit  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Production Production Facility Tax Credit to someone by E-mail Share Alternative Fuels Data Center: Biofuels Production Facility Tax Credit on Facebook Tweet about Alternative Fuels Data Center: Biofuels Production Facility Tax Credit on Twitter Bookmark Alternative Fuels Data Center: Biofuels Production Facility Tax Credit on Google Bookmark Alternative Fuels Data Center: Biofuels Production Facility Tax Credit on Delicious Rank Alternative Fuels Data Center: Biofuels Production Facility Tax Credit on Digg Find More places to share Alternative Fuels Data Center: Biofuels Production Facility Tax Credit on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Biofuels Production Facility Tax Credit A taxpayer that constructs and places into service a commercial facility

34

Alternative Fuels Data Center: Biofuel Production Facility Tax Exemption  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Production Production Facility Tax Exemption to someone by E-mail Share Alternative Fuels Data Center: Biofuel Production Facility Tax Exemption on Facebook Tweet about Alternative Fuels Data Center: Biofuel Production Facility Tax Exemption on Twitter Bookmark Alternative Fuels Data Center: Biofuel Production Facility Tax Exemption on Google Bookmark Alternative Fuels Data Center: Biofuel Production Facility Tax Exemption on Delicious Rank Alternative Fuels Data Center: Biofuel Production Facility Tax Exemption on Digg Find More places to share Alternative Fuels Data Center: Biofuel Production Facility Tax Exemption on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Biofuel Production Facility Tax Exemption Any newly constructed or expanded biomass-to-energy facility is exempt from

35

Albanova Nano Fabrication Facility: Activity Report D. B. Haviland Activity Report  

E-Print Network (OSTI)

Albanova Nano Fabrication Facility: Activity Report D. B. Haviland Activity Report Albanova contains a report of the activity carried out in the Albanova Nano- Fabrication Facility, located...................................................................................................... 5 Appendix 1: Nano-Lab projects

Haviland, David

36

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

37

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

38

Alternative Fuel Production Facility Incentives (Kentucky) | Department of  

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

Alternative Fuel Production Facility Incentives (Kentucky) Alternative Fuel Production Facility Incentives (Kentucky) Alternative Fuel Production Facility Incentives (Kentucky) < Back Eligibility Commercial Developer Utility Program Info State Kentucky Program Type Corporate Tax Incentive The Kentucky Economic Development and Finance Authority (KEDFA) provides tax incentives to construct, retrofit, or upgrade an alternative fuel production or gasification facility that uses coal or biomass as a feedstock. Beginning Aug. 1, 2010, tax incentives are also available for energy-efficient alternative fuel production facilities and up to five alternative fuel production facilities that use natural gas or natural gas liquids as a feedstock. Energy-efficient alternative fuels are defined as homogeneous fuels that are produced from processes designed to densify

39

Alternative Fuels Data Center: Biofuel Production Facility Tax Credit  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Biofuel Production Biofuel Production Facility Tax Credit to someone by E-mail Share Alternative Fuels Data Center: Biofuel Production Facility Tax Credit on Facebook Tweet about Alternative Fuels Data Center: Biofuel Production Facility Tax Credit on Twitter Bookmark Alternative Fuels Data Center: Biofuel Production Facility Tax Credit on Google Bookmark Alternative Fuels Data Center: Biofuel Production Facility Tax Credit on Delicious Rank Alternative Fuels Data Center: Biofuel Production Facility Tax Credit on Digg Find More places to share Alternative Fuels Data Center: Biofuel Production Facility Tax Credit on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Biofuel Production Facility Tax Credit A taxpayer who processes biodiesel, ethanol, or gasoline blends consisting

40

Alternative Fuels Data Center: Ethanol Production Facility Fee  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Ethanol Production Ethanol Production Facility Fee to someone by E-mail Share Alternative Fuels Data Center: Ethanol Production Facility Fee on Facebook Tweet about Alternative Fuels Data Center: Ethanol Production Facility Fee on Twitter Bookmark Alternative Fuels Data Center: Ethanol Production Facility Fee on Google Bookmark Alternative Fuels Data Center: Ethanol Production Facility Fee on Delicious Rank Alternative Fuels Data Center: Ethanol Production Facility Fee on Digg Find More places to share Alternative Fuels Data Center: Ethanol Production Facility Fee on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Ethanol Production Facility Fee The cost to submit an air quality permit application for an ethanol production plant is $1,000. An annual renewal fee is also required for the

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


41

Alternative Fuels Data Center: Biodiesel Production Facility Tax Credit  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Production Production Facility Tax Credit to someone by E-mail Share Alternative Fuels Data Center: Biodiesel Production Facility Tax Credit on Facebook Tweet about Alternative Fuels Data Center: Biodiesel Production Facility Tax Credit on Twitter Bookmark Alternative Fuels Data Center: Biodiesel Production Facility Tax Credit on Google Bookmark Alternative Fuels Data Center: Biodiesel Production Facility Tax Credit on Delicious Rank Alternative Fuels Data Center: Biodiesel Production Facility Tax Credit on Digg Find More places to share Alternative Fuels Data Center: Biodiesel Production Facility Tax Credit on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Biodiesel Production Facility Tax Credit Businesses and individuals are eligible for a tax credit of up to 15% of

42

Alternative Fuels Data Center: Biodiesel Blending Facility Tax Credit  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Biodiesel Blending Biodiesel Blending Facility Tax Credit to someone by E-mail Share Alternative Fuels Data Center: Biodiesel Blending Facility Tax Credit on Facebook Tweet about Alternative Fuels Data Center: Biodiesel Blending Facility Tax Credit on Twitter Bookmark Alternative Fuels Data Center: Biodiesel Blending Facility Tax Credit on Google Bookmark Alternative Fuels Data Center: Biodiesel Blending Facility Tax Credit on Delicious Rank Alternative Fuels Data Center: Biodiesel Blending Facility Tax Credit on Digg Find More places to share Alternative Fuels Data Center: Biodiesel Blending Facility Tax Credit on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Biodiesel Blending Facility Tax Credit A tax credit is available for up to 30% of the cost of purchasing or

43

Alternative Fuels Data Center: Ethanol and Hydrogen Production Facility  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

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

44

Alternative Fuels Data Center: Ethanol Production Facility Property Tax  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

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

45

Proposed strontium radiosotope thermoelectric generator fuel encapsulation facility  

SciTech Connect

The proposed Fuel Encapsulation Facility is a fully equipped facility for processing and encapsulating strontium Radioisotope Thermoelectric Generator (RTG) fuel from presently available Waste Encapsulation and Storage Facility (WESF) capsules. The facility location is on the second building level below ground of the Fuels and Materials Examination Facility (FMEF), Cells 142, 143, and 145. Capsules containing strontium fluoride (SrF[sub 2]) would be received from the WESF in Cell 145 and transferred to the three adjacent cells for processing and encapsulation into the final RTG fuel configuration.

Adkins, H.E. (Westinghouse Hanford Company, P.O. Box 1970, Mail Stop N1-42, Richland, Washington 99352 (United States))

1993-01-10T23:59:59.000Z

46

UNIT NAME: C-751 Fuel Facility REGULATORY STATUS: AOC  

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

,93 186 UNIT NUMBER : UNIT NAME: C-751 Fuel Facility REGULATORY STATUS: AOC LOCATION: Inside plant security fence, immediately south of C-720 building. APPROXIMATE DIMENSION: Two...

47

Nuclear fuel cycle facility accident analysis handbook  

SciTech Connect

The purpose of this Handbook is to provide guidance on how to calculate the characteristics of releases of radioactive materials and/or hazardous chemicals from nonreactor nuclear facilities. In addition, the Handbook provides guidance on how to calculate the consequences of those releases. There are four major chapters: Hazard Evaluation and Scenario Development; Source Term Determination; Transport Within Containment/Confinement; and Atmospheric Dispersion and Consequences Modeling. These chapters are supported by Appendices, including: a summary of chemical and nuclear information that contains descriptions of various fuel cycle facilities; details on how to calculate the characteristics of source terms for releases of hazardous chemicals; a comparison of NRC, EPA, and OSHA programs that address chemical safety; a summary of the performance of HEPA and other filters; and a discussion of uncertainties. Several sample problems are presented: a free-fall spill of powder, an explosion with radioactive release; a fire with radioactive release; filter failure; hydrogen fluoride release from a tankcar; a uranium hexafluoride cylinder rupture; a liquid spill in a vitrification plant; and a criticality incident. Finally, this Handbook includes a computer model, LPF No.1B, that is intended for use in calculating Leak Path Factors. A list of contributors to the Handbook is presented in Chapter 6. 39 figs., 35 tabs.

NONE

1998-03-01T23:59:59.000Z

48

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

49

NREL: Hydrogen and Fuel Cells Research - Other Research Facilities  

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

Other Research Facilities Other Research Facilities In addition to the laboratories dedicated to hydrogen and fuel cell research, other facilities at NREL provide space for scientists developing hydrogen and fuel cell technologies along with other renewable energy technologies. Distributed Energy Resources Test Facility NREL's Distributed Energy Resources (DER) Test Facility is a working laboratory to test and improve interconnections among renewable energy generation technologies, energy storage systems, and electrical conversion equipment. Research being conducted includes improving the system efficiency of hydrogen production by electrolysis using wind or other renewable energy. This research highlights a promising option for encouraging higher penetrations of renewable energy generation as well as

50

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

51

Nuclear-fuel-cycle risk assessment: descriptions of representative non-reactor facilities. Sections 1-14  

SciTech Connect

The Fuel Cycle Risk Assessment Program was initiated to provide risk assessment methods for assistance in the regulatory process for nuclear fuel cycle facilities other than reactors. This report, the first from the program, defines and describes fuel cycle elements that are being considered in the program. One type of facility (and in some cases two) is described that is representative of each element of the fuel cycle. The descriptions are based on real industrial-scale facilities that are current state-of-the-art, or on conceptual facilities where none now exist. Each representative fuel cycle facility is assumed to be located on the appropriate one of four hypothetical but representative sites described. The fuel cycles considered are for Light Water Reactors with once-through flow of spent fuel, and with plutonium and uranium recycle. Representative facilities for the following fuel cycle elements are described for uranium (or uranium plus plutonium where appropriate): mining, milling, conversion, enrichment, fuel fabrication, mixed-oxide fuel refabrication, fuel reprocessing, spent fuel storage, high-level waste storage, transuranic waste storage, spent fuel and high-level and transuranic waste disposal, low-level and intermediate-level waste disposal, and transportation. For each representative facility the description includes: mainline process, effluent processing and waste management, facility and hardware description, safety-related information and potential alternative concepts for that fuel cycle element. The emphasis of the descriptive material is on safety-related information. This includes: operating and maintenance requirements, input/output of major materials, identification and inventories of hazardous materials (particularly radioactive materials), unit operations involved, potential accident driving forces, containment and shielding, and degree of hands-on operation.

Schneider, K.J.

1982-09-01T23:59:59.000Z

52

Summary of Off-Normal Events in US Fuel Cycle Facilities for AFCI Applications  

SciTech Connect

This report is a collection and review of system operation and failure experiences for facilities comprising the fission reactor fuel cycle, with the exception of reactor operations. This report includes mines, mills, conversion plants, enrichment plants, fuel fabrication plants, transportation of fuel materials between these centers, and waste storage facilities. Some of the facilities discussed are no longer operating; others continue to produce fuel for the commercial fission power plant industry. Some of the facilities discussed have been part of the military’s nuclear effort; these are included when the processes used are similar to those used for commercial nuclear power. When reading compilations of incidents and accidents, after repeated entries it is natural to form an opinion that there exists nothing but accidents. For this reason, production or throughput values are described when available. These adverse operating experiences are compiled to support the design and decisions needed for the Advanced Fuel Cycle Initiative (AFCI). The AFCI is to weigh options for a new fission reactor fuel cycle that is efficient, safe, and productive for US energy security.

L. C. Cadwallader; S. J. Piet; S. O. Sheetz; D. H. McGuire; W. B. Boore

2005-09-01T23:59:59.000Z

53

Pyroprocessing of fast flux test facility nuclear fuel  

SciTech Connect

Used nuclear fuel from the Fast Flux Test Facility (FFTF) was recently transferred to the Idaho National Laboratory and processed by pyroprocessing in the Fuel Conditioning Facility. Approximately 213 kg of uranium from sodium-bonded metallic FFTF fuel was processed over a one year period with the equipment previously used for the processing of EBR-II used fuel. The peak burnup of the FFTF fuel ranged from 10 to 15 atom% for the 900+ chopped elements processed. Fifteen low-enriched uranium ingots were cast following the electrorefining and distillation operations to recover approximately 192 kg of uranium. A material balance on the primary fuel constituents, uranium and zirconium, during the FFTF campaign will be presented along with a brief description of operating parameters. Recoverable uranium during the pyroprocessing of FFTF nuclear fuel was greater than 95% while the purity of the final electro-refined uranium products exceeded 99%. (authors)

Westphal, B.R.; Wurth, L.A.; Fredrickson, G.L.; Galbreth, G.G.; Vaden, D.; Elliott, M.D.; Price, J.C.; Honeyfield, E.M.; Patterson, M.N. [Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID, 83415 (United States)

2013-07-01T23:59:59.000Z

54

NREL: Hydrogen and Fuel Cells Research - Research Facilities  

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

Characterization Laboratory. Photo by Dennis Schroeder, NREL NREL conducts hydrogen and fuel cell R&D at a variety of research facilities at our main 327-acre campus in Golden,...

55

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

56

Fuel Storage Facility Final Safety Analysis Report. Revision 1  

SciTech Connect

The Fuel Storage Facility (FSF) is an integral part of the Fast Flux Test Facility. Its purpose is to provide long-term storage (20-year design life) for spent fuel core elements used to provide the fast flux environment in FFTF, and for test fuel pins, components and subassemblies that have been irradiated in the fast flux environment. This Final Safety Analysis Report (FSAR) and its supporting documentation provides a complete description and safety evaluation of the site, the plant design, operations, and potential accidents.

Linderoth, C.E.

1984-03-01T23:59:59.000Z

57

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

58

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

59

Cell Fabrication Facility Team Production and Research Activities  

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

60

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

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

Facile Fabrication of Free-Standing Light Emitting Diode by Combination of Wet Chemical Etchings  

Science Journals Connector (OSTI)

Facile Fabrication of Free-Standing Light Emitting Diode by Combination of Wet Chemical Etchings ... Free-standing GaN light-emitting diode (LED) structure with high crystalline quality was fabricated by combining electrochemical and photoelectrochemical etching followed by regrowth of LED structure and subsequent mechanical detachment from a substrate. ...

Lee-Woon Jang; Dae-Woo Jeon; Tae-Hoon Chung; Alexander Y. Polyakov; Han-Su Cho; Jin-Hyeon Yun; Jin-Woo Ju; Jong-Hyeob Baek; Joo-Won Choi; In-Hwan Lee

2013-12-25T23:59:59.000Z

62

President Reagan Calls for a National Spent Fuel Storage Facility |  

National Nuclear Security Administration (NNSA)

Reagan Calls for a National Spent Fuel Storage Facility | Reagan Calls for a National Spent Fuel Storage 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 > President Reagan Calls for a National Spent ... President Reagan Calls for a National Spent Fuel Storage Facility October 08, 1981

63

W-1 Sodium Loop Safety Facility experiment centerline fuel thermocouple performance. [LMFBR  

SciTech Connect

The W-1 Sodium Loop Safety Facility (SLSF) experiment is the fifth in a series of experiments sponsored by the Department of Energy (DOE) as part of the National Fast Breeder Reactor (FBR) Safety Assurance Program. The experiments are being conducted under the direction of Argonne National Laboratory (ANL) and Hanford Engineering Development Laboratory (HEDL). The irradiation phase of the W-1 SLSF experiment was conducted between May 27 and July 20, 1979, and terminated with incipient fuel pin cladding failure during the final boiling transient. Experimental hardware and facility performed as designed, allowing completion of all planned tests and test objectives. This paper focuses on high temperature in-fuel thermocouples and discusses their development, fabrication, and performance in the W-1 experiment.

Meyers, S.C.; Henderson, J.M.

1980-05-01T23:59:59.000Z

64

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

65

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

66

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

67

EARTHQUAKE CAUSED RELEASES FROM A NUCLEAR FUEL CYCLE FACILITY  

SciTech Connect

The fuel cycle facility (FCF) at the Idaho National Laboratory is a nuclear facility which must be licensed in order to operate. A safety analysis is required for a license. This paper describes the analysis of the Design Basis Accident for this facility. This analysis involves a model of the transient behavior of the FCF inert atmosphere hot cell following an earthquake initiated breach of pipes passing through the cell boundary. The hot cell is used to process spent metallic nuclear fuel. Such breaches allow the introduction of air and subsequent burning of pyrophoric metals. The model predicts the pressure, temperature, volumetric releases, cell heat transfer, metal fuel combustion, heat generation rates, radiological releases and other quantities. The results show that releases from the cell are minimal and satisfactory for safety. This analysis method should be useful in other facilities that have potential for damage from an earthquake and could eliminate the need to back fit facilities with earthquake proof boundaries or lessen the cost of new facilities.

Charles W. Solbrig; Chad Pope; Jason Andrus

2014-08-01T23:59:59.000Z

68

Summary engineering description of underwater fuel storage facility for foreign research reactor spent nuclear fuel  

SciTech Connect

This document is a summary description for an Underwater Fuel Storage Facility (UFSF) for foreign research reactor (FRR) spent nuclear fuel (SNF). A FRR SNF environmental Impact Statement (EIS) is being prepared and will include both wet and dry storage facilities as storage alternatives. For the UFSF presented in this document, a specific site is not chosen. This facility can be sited at any one of the five locations under consideration in the EIS. These locations are the Idaho National Engineering Laboratory, Savannah River Site, Hanford, Oak Ridge National Laboratory, and Nevada Test Site. Generic facility environmental impacts and emissions are provided in this report. A baseline fuel element is defined in Section 2.2, and the results of a fission product analysis are presented. Requirements for a storage facility have been researched and are summarized in Section 3. Section 4 describes three facility options: (1) the Centralized-UFSF, which would store the entire fuel element quantity in a single facility at a single location, (2) the Regionalized Large-UFSF, which would store 75% of the fuel element quantity in some region of the country, and (3) the Regionalized Small-UFSF, which would store 25% of the fuel element quantity, with the possibility of a number of these facilities in various regions throughout the country. The operational philosophy is presented in Section 5, and Section 6 contains a description of the equipment. Section 7 defines the utilities required for the facility. Cost estimates are discussed in Section 8, and detailed cost estimates are included. Impacts to worker safety, public safety, and the environment are discussed in Section 9. Accidental releases are presented in Section 10. Standard Environmental Impact Forms are included in Section 11.

Dahlke, H.J.; Johnson, D.A.; Rawlins, J.K.; Searle, D.K.; Wachs, G.W.

1994-10-01T23:59:59.000Z

69

EIS-0432: Medicine Bow Fuel & Power Coal-to-Liquid Facility in...  

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

2: Medicine Bow Fuel & Power Coal-to-Liquid Facility in Carbon County, WY EIS-0432: Medicine Bow Fuel & Power Coal-to-Liquid Facility in Carbon County, WY Documents Available for...

70

Facile fabrication of spherical nanoparticle-tipped AFM probes for plasmonic applications  

E-Print Network (OSTI)

for reliably producing metallic spherical nanoparticle tips using only a simple electrochemical cell. Fabrication of Au spherical nanoparticle (AuNP) tips onto commercial AFM probes is achieved using single-pulse high- fi eld electrochemical growth... is employed for growth since both the cell geometry and electrodeposition solution are kept the same between fabrications. AFM probes are attached to fl u- orine-doped tin oxide (FTO) conductive glass, used as a working DOI: 10.1002/ppsc.201400104 Facile...

Sanders, Alan; Zhang, Liwu; Bowman, Richard W.; Herrmann, Lars O.; Baumberg, Jeremy J.

2014-07-16T23:59:59.000Z

71

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...

72

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

73

Impacts of criticality safety on hot fuel examination facility operations  

SciTech Connect

The Hot Fuel Examination Facility (HFEF) complex comprises four large hot cells. These cells are used to support the nation's nuclear energy program, especially the liquid-metal fast breeder reactor, by providing nondestructive and destructive testing of irradiated reactor fuels and furnishing the hot cell services required for operation of Experimental Breeder Reactor II (EBR-II). Because it is a research rather than a production facility, HFEF assignments are varied and change from time to time to meet the requirements of our experimenters. Such a variety of operations presents many challenges, especially for nuclear criticality safety. The following operations are reviewed to assure that accidental criticality is not possible, and that all rules and regulations are met: transportation, temporary storage, examinations, and disposition.

Garcia, A.S.; Courtney, J.C.; Bacca, J.P.

1985-11-01T23:59:59.000Z

74

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

75

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

76

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

77

Fabrication of the First US ITER TF Conductor Sample for Qualification in SULTAN Facility  

E-Print Network (OSTI)

A pair of 3.5 m long ITER TF size straight conductors has been fabricated into a conductor short sample and submitted to the SULTAN facility at CRPP for cold test. The sample used a triplet-based cabling pattern in one leg ...

Miller, John R.

78

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

79

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

80

DOE to Build Hydrogen Fuel Test Facility at West Virginia Airport |  

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

DOE to Build Hydrogen Fuel Test Facility at West Virginia Airport DOE to Build Hydrogen Fuel Test Facility at West Virginia Airport DOE to Build Hydrogen Fuel Test Facility at West Virginia Airport March 25, 2009 - 1:00pm Addthis Washington, DC - The Office of Fossil Energy's National Energy Technology Laboratory (NETL) today announced plans to construct and operate a hydrogen fuel production plant and vehicle fueling station at the Yeager Airport in Charleston, W.Va. The facility will use grid electricity to split water to produce pure hydrogen fuel. The fuel will be used by the airport's operations and the 130th Air Wing of the West Virginia Air National Guard. NETL will begin operations at the Yeager Airport facility in August 2009 and plans to conduct two years of testing and evaluation. The facility will be designed using "open architecture," allowing the capability to add

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

USCG Energy Program Resource Management, Fuel Logistics, and Facility Energy  

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

Energy Program Energy Program Resource Management, Fuel Logistics, and Facility Energy Presented by Daniel Gore USCG Energy Program Manager Office of Resource Management 1 1 2 Presentation Contents * Overview CG Energy Program * Highlights * Interesting Projects for Utilities * Alternatively Financed Projects Discussion 2 3 Overview 3 USCG Energy Program Growth * CG represents 80% of DHS energy consumption * Obligations up 210% from FY 2000 * Energy = 25% of O&M budget 4 4 Energy Program Dynamics Increasing Expenditures Increasing Politics & Mandates Increasing Scrutiny & Reporting Procurement & Credit Card Transformations Accounting System Improvements Organizational Strategic Transformations 5 5 What is CG Energy Management? * Policies impacting $306M annual obligations

82

Financing Strategies For A Nuclear Fuel Cycle Facility  

SciTech Connect

To help meet the nation’s energy needs, recycling of partially used nuclear fuel is required to close the nuclear fuel cycle, but implementing this step will require considerable investment. This report evaluates financing scenarios for integrating recycling facilities into the nuclear fuel cycle. A range of options from fully government owned to fully private owned were evaluated using DPL (Decision Programming Language 6.0), which can systematically optimize outcomes based on user-defined criteria (e.g., lowest lifecycle cost, lowest unit cost). This evaluation concludes that the lowest unit costs and lifetime costs are found for a fully government-owned financing strategy, due to government forgiveness of debt as sunk costs. However, this does not mean that the facilities should necessarily be constructed and operated by the government. The costs for hybrid combinations of public and private (commercial) financed options can compete under some circumstances with the costs of the government option. This analysis shows that commercial operations have potential to be economical, but there is presently no incentive for private industry involvement. The Nuclear Waste Policy Act (NWPA) currently establishes government ownership of partially used commercial nuclear fuel. In addition, the recently announced Global Nuclear Energy Partnership (GNEP) suggests fuels from several countries will be recycled in the United States as part of an international governmental agreement; this also assumes government ownership. Overwhelmingly, uncertainty in annual facility capacity led to the greatest variations in unit costs necessary for recovery of operating and capital expenditures; the ability to determine annual capacity will be a driving factor in setting unit costs. For private ventures, the costs of capital, especially equity interest rates, dominate the balance sheet; and the annual operating costs, forgiveness of debt, and overnight costs dominate the costs computed for the government case. The uncertainty in operations, leading to lower than optimal processing rates (or annual plant throughput), is the most detrimental issue to achieving low unit costs. Conversely, lowering debt interest rates and the required return on investments can reduce costs for private industry.

David Shropshire; Sharon Chandler

2006-07-01T23:59:59.000Z

83

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...

84

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

85

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

86

NETL: News Release - NETL Opens Fuel Cell/Turbine Hybrid Research Facility  

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

May 20, 2004 May 20, 2004 NETL Opens Fuel Cell/Turbine Hybrid Research Facility MORGANTOWN, WV - The Hybrid Performance Facility - called the Hyper facility - is now fully operational at the Department of Energy's National Energy Technology Laboratory (NETL). This one-of-a-kind facility, developed by NETL's Office of Science and Technology, will be used to develop control strategies for the reliable operation of fuel cell/turbine hybrids. - NETL's Fuel Cell/Turbine Hybrid Facility - The Hyper facility allows assessment of dynamic control and performance issues in fuel cell/turbine hybrid systems. Combined systems of turbines and fuel cells are expected to meet power efficiency targets that will help eliminate, at competitive costs, environmental concerns associated with the use of fossil fuels for

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

Webinar: Procuring Fuel Cells for Stationary Power: A Guide for Federal Facility Decision Makers  

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

Video recording and text version of the webinar titled, Procuring Fuel Cells for Stationary Power: A Guide for Federal Facility Decision Makers, originally presented on May 8, 2012.

89

Material Control and Accountability Experience at the Fuel Conditioning Facility  

SciTech Connect

The Fuel Conditioning Facility (FCF) at the Idaho National Laboratory (INL) treats spent nuclear fuel using an electrometallurgical process that separates the uranium from the fission products, sodium thermal bond, and cladding materials. Material accountancy is necessary at FCF for two reasons: 1) it provides a mechanism for detecting a potential loss of nuclear material for safeguards and security, and 2) it provides a periodic check of inventories to ensure that processes and materials are within control limits. Material Control and Accountability is also a Department of Energy (DOE) requirement (DOE Order 474.1). The FCF employs a computer based Mass Tracking (MTG) System to collect, store, retrieve, and process data on all operations that directly affect the flow of materials through the FCF. The MTG System is important for the operations of the FCF because it supports activities such as material control and accountability, criticality safety, and process modeling. To conduct material control and accountability checks and to monitor process performance, mass balances are routinely performed around the process equipment. The equipment used in FCF for pyro-processing consists of two mechanical choppers and two electro-refiners (the Mark-IV with the accompanying element chopper and Mark-V with the accompanying blanket chopper for processing driver fuel and blanket, respectively), and a cathode processor (used for processing both driver fuel and blanket) and casting furnace (mostly used for processing driver fuel). Performing mass balances requires the measurement of the masses and compositions of several process streams and equipment inventories. The masses of process streams are obtained via in-cell balances (i.e., load cells) that weigh containers entering and leaving the process equipment. Samples taken at key locations are analyzed to determine the composition of process streams and equipment inventories. In cases where equipment or containers cannot be placed on a balance, others methods (e.g., level measurements, volume calibration equations, calculated density via additive volumes) are utilized to measure the inventory mass. This paper will discuss the material control and accountability experience at the FCF after ten-plus years of processing spent nuclear fuel. A particular area of discussion is the calculated electrolyte density via additive volumes and its importance in determining the mass and composition in the FCF electro-refiners for material control and accountability of special nuclear material. (authors)

Vaden, D.; Fredrickson, G.L. [Idaho National Laboratory, Idaho Falls ID 83415 (United States)

2007-07-01T23:59:59.000Z

90

Revised Analyses of Decommissioning Reference Non-Fuel-Cycle Facilities  

SciTech Connect

Cost information is developed for the conceptual decommissioning of non-fuel-cycle nuclear facilities that represent a significant decommissioning task in terms of decontamination and disposal activities. This study is a re-evaluation of the original study (NUREG/CR-1754 and NUREG/CR-1754, Addendum 1). The reference facilities examined in this study are the same as in the original study and include: a laboratory for the manufacture of {sup 3}H-labeled compounds; a laboratory for the manufacture of {sup 14}C-labeled compounds; a laboratory for the manufacture of {sup 123}I-labeled compounds; a laboratory for the manufacture of {sup 137}Cs sealed sources; a laboratory for the manufacture of {sup 241}Am sealed sources; and an institutional user laboratory. In addition to the laboratories, three reference sites that require some decommissioning effort were also examined. These sites are: (1) a site with a contaminated drain line and hold-up tank; (2) a site with a contaminated ground surface; and (3) a tailings pile containing uranium and thorium residues. Decommissioning of these reference facilities and sites can be accomplished using techniques and equipment that are in common industrial use. Essentially the same technology assumed in the original study is used in this study. For the reference laboratory-type facilities, the study approach is to first evaluate the decommissioning of individual components (e.g., fume hoods, glove boxes, and building surfaces) that are common to many laboratory facilities. The information obtained from analyzing the individual components of each facility are then used to determine the cost, manpower requirements and dose information for the decommissioning of the entire facility. DECON, the objective of the 1988 Rulemaking for materials facilities, is the decommissioning alternative evaluated for the reference laboratories because it results in the release of the facility for restricted or unrestricted use as soon as possible. For a facility, DECON requires that contaminated components either be: (1) decontaminated to restricted or unrestricted release levels or (2) packaged and shipped to an authorized disposal site. This study considers unrestricted release only. The new decommissioning criteria of July 1997 are too recent for this study to include a cost analysis of the restricted release option, which is now allowed under these new criteria. The costs of decommissioning facility components are generally estimated to be in the range of $140 to $27,000, depending on the type of component, the type and amount of radioactive contamination, the remediation options chosen, and the quantity of radioactive waste generated from decommissioning operations. Estimated costs for decommissioning the example laboratories range from $130,000 to $205,000, assuming aggressive low-level waste (LLW) volume reduction. If only minimal LLW volume reduction is employed, decommissioning costs range from $150,000 to $270,000 for these laboratories. On the basis of estimated decommissioning costs for facility components, the costs of decommissioning typical non-fuel-cycle laboratory facilities are estimated to range from about $25,000 for the decommissioning of a small room containing one or two fume hoods to more than $1 million for the decommissioning of an industrial plant containing several laboratories in which radiochemicals and sealed radioactive sources are prepared. For the reference sites of this study, the basic decommissioning alternatives are: (1) site stabilization followed by long-term care and (2) removal of the waste or contaminated soil to an authorized disposal site. Cost estimates made for decommissioning three reference sites range from about $130,000 for the removal of a contaminated drain line and hold-up tank to more than $23 million for the removal of a tailings pile that contains radioactive residue from ore-processing operations in which tin slag is processed for the recovery of rare metals. Total occupational radiation doses generally range from 0.00007 person-rem to 13 person-rem for

MC Bierschbach; DR Haffner; KJ Schneider; SM Short

2002-12-01T23:59:59.000Z

91

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

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

Fuel conditioning facility zone-to-zone transfer administrative controls.  

SciTech Connect

The administrative controls associated with transferring containers from one criticality hazard control zone to another in the Argonne National Laboratory (ANL) Fuel Conditioning Facility (FCF) are described. FCF, located at the ANL-West site near Idaho Falls, Idaho, is used to remotely process spent sodium bonded metallic fuel for disposition. The process involves nearly forty widely varying material forms and types, over fifty specific use container types, and over thirty distinct zones where work activities occur. During 1999, over five thousand transfers from one zone to another were conducted. Limits are placed on mass, material form and type, and container types for each zone. Ml material and containers are tracked using the Mass Tracking System (MTG). The MTG uses an Oracle database and numerous applications to manage the database. The database stores information specific to the process, including material composition and mass, container identification number and mass, transfer history, and the operators involved in each transfer. The process is controlled using written procedures which specify the zone, containers, and material involved in a task. Transferring a container from one zone to another is called a zone-to-zone transfer (ZZT). ZZTs consist of four distinct phases, select, request, identify, and completion.

Pope, C. L.

2000-06-21T23:59:59.000Z

94

Independent Oversight Review of the Idaho National Laboratory Fuel Conditioning Facility Safety Basis  

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

INDEPENDENT OVERSIGHT INDEPENDENT OVERSIGHT REVIEW OF THE IDAHO NATIONAL LABORATORY FUEL CONDITIONING FACILITY SAFETY BASIS April 2010 U.S. Department of Energy Office of Health, Safety and Security Office of Independent Oversight i INDEPENDENT OVERSIGHT REVIEW OF THE IDAHO NATIONAL LABORATORY FUEL CONDITIONING FACILITY SAFETY BASIS Table of Contents Acronyms ............................................................................................................................ ii Executive Summary ........................................................................................................... iii 1.0 Introduction ..................................................................................................................1

95

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

96

Integrated Safety Analysis: Why It Is Appropriate for Fuel Recycling Facilities  

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

Integrated Safety Analysis: Why It Is Appropriate for Fuel Recycling Facilities Executive Summary This paper addresses why the use of an Integrated Safety Analysis ("ISA") is appropriate for fuel recycling facilities 1 which would be licensed under new regulations currently being considered by NRC. The use of the ISA for fuel facilities under Part 70 is described and compared to the use of a Probabilistic Risk Assessment ("PRA") for reactor facilities. A basis is provided for concluding that future recycling facilities - which will possess characteristics similar to today's fuel cycle facilities and distinct from reactors - can best be assessed using established qualitative or semi-quantitative ISA techniques to achieve and demonstrate safety in an effective and efficient manner.

97

Instructions for CEC-1250E-4 Biomass and Fossil Fuel Usage Report for Biomass Facilities  

E-Print Network (OSTI)

Instructions for CEC-1250E-4 Biomass and Fossil Fuel Usage Report for Biomass Facilities Biomass energy input basis in the upcoming calendar year? - Please check "yes" or "no." 12. Types of Biomass Fuel Used - Please report the quantity and supplier of the following types of biomass fuel used

98

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

99

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

100

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

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

American Ref-Fuel of SE CT Biomass Facility | Open Energy Information  

Open Energy Info (EERE)

American Ref-Fuel of SE CT Biomass Facility American Ref-Fuel of SE CT Biomass Facility Jump to: navigation, search Name American Ref-Fuel of SE CT Biomass Facility Facility American Ref-Fuel of SE CT Sector Biomass Facility Type Municipal Solid Waste Location New London County, Connecticut Coordinates 41.5185189°, -72.0468164° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":41.5185189,"lon":-72.0468164,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

102

DOE Hydrogen and Fuel Cells Program: Permitting Hydrogen Facilities Home  

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

Hydrogen Fueling Stations Telecommunication Fuel Cell Use Hazard and Risk Analysis U.S. Department of Energy Hydrogen Fueling Stations Telecommunication Fuel Cell Use Hazard and Risk Analysis U.S. Department of Energy The objective of this U.S. Department of Energy Hydrogen Permitting Web site is to help local permitting officials deal with proposed hydrogen fueling stations, fuel cell installations for telecommunications backup power, and other hydrogen projects. Resources for local permitting officials who are looking to address project proposals include current citations for hydrogen fueling stations and a listing of setback requirements on the Alternative Fuels & Advanced Vehicle Data Center Web site. In addition, this overview of telecommunications fuel cell use and an animation that demonstrates telecommunications site layout using hydrogen fuel cells for backup power should provide helpful

103

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...

104

Preoperational Environmental Survey for the Spent Nuclear Fuel (SNF) Project Facilities  

SciTech Connect

This document represents the report for environmental sampling of soil, vegetation, litter, cryptograms, and small mammals at the Spent Nuclear Fuel Project facilities located in 100 K and 200 East Areas in support of the preoperational environmental survey.

MITCHELL, R.M.

2000-09-28T23:59:59.000Z

105

Research and Development of a PEM Fuel Cell, Hydrogen Reformer, and Vehicle Refueling Facility  

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

Technical paper on the development of a hydrogen reformer, vehicle refueling facility, and PEM fuel cell for Las Vegas, NV presented at the 2002 Annual Hydrogen Review held May 6-8, 2002 in Golden, CO.

106

Improving operational efficiency of fuel oil facilities used at gas-and-oil-fired power stations  

Science Journals Connector (OSTI)

Results obtained from experimental investigations of energy consumption are described, and ways for considerably reducing it are proposed taking as an example the fuel oil facility at the 2400-MW Lukoml District ...

A. K. Vnukov; F. A. Rozanova; A. A. Bazylenko; V. L. Zhurbilo…

2009-09-01T23:59:59.000Z

107

Receiving Basin for Offsite Fuels and the Resin Regeneration Facility Safety Analysis Report, Executive Summary  

SciTech Connect

The Safety Analysis Report documents the safety authorization basis for the Receiving Basin for Offsite Fuels (RBOF) and the Resin Regeneration Facility (RRF) at the Savannah River Site (SRS). The present mission of the RBOF and RRF is to continue in providing a facility for the safe receipt, storage, handling, and shipping of spent nuclear fuel assemblies from power and research reactors in the United States, fuel from SRS and other Department of Energy (DOE) reactors, and foreign research reactors fuel, in support of the nonproliferation policy. The RBOF and RRF provide the capability to handle, separate, and transfer wastes generated from nuclear fuel element storage. The DOE and Westinghouse Savannah River Company, the prime operating contractor, are committed to managing these activities in such a manner that the health and safety of the offsite general public, the site worker, the facility worker, and the environment are protected.

Shedrow, C.B.

1999-11-29T23:59:59.000Z

108

Effects of an oxidizing atmosphere in a spent fuel packaging facility  

SciTech Connect

Sufficient oxidation of spent fuel can cause a cladding breach to propagate, resulting in dispersion of fuel particulates and gaseous radionuclides. The literature for spent fuel oxidation in storage and disposal programs was reviewed to evaluate the effect of an oxidizing atmosphere in a preclosure packaging facility on (1) physical condition of the fuel and (2) operations in the facility. Effects such as cladding breach propagation, cladding oxidation, rod dilation, fuel dispersal, {sup 14}C and {sup 85}Kr release, and crud release were evaluated. The impact of these effects, due to oxidation, upon a spent fuel handling facility is generally predicted to be less than the impact of similar effects due to fuel rod breached during handling in an inert-atmosphere facility. Preliminary temperature limits of 240{degree}C and 227{degree}C for a 2-week or 4-week handling period and 175{degree}C for 2-year lag storage would prevent breach propagation and fuel dispersal. Additional data that are needed to support the assumptions in this analysis or complete the database were identified.

Einziger, R.E.

1991-09-01T23:59:59.000Z

109

Interim Safety Basis for Fuel Supply Shutdown Facility  

SciTech Connect

This ISB, in conjunction with the IOSR, provides the required basis for interim operation or restrictions on interim operations and administrative controls for the facility until a SAR is prepared in accordance with the new requirements or the facility is shut down. It is concluded that the risks associated with tha current and anticipated mode of the facility, uranium disposition, clean up, and transition activities required for permanent closure, are within risk guidelines.

BENECKE, M.W.

2000-09-07T23:59:59.000Z

110

Recovery of Information from the Fast Flux Test Facility for the Advanced Fuel Cycle Initiative  

SciTech Connect

The Fast Flux Test Facility is the most recent Liquid Metal Reactor to operate in the United States. Information from the design, construction, and operation of this reactor was at risk as the facilities associated with the reactor are being shut down. The Advanced Fuel Cycle Initiative is a program managed by the Office of Nuclear Energy of the U.S. Department of Energy with a mission to develop new fuel cycle technologies to support both current and advanced reactors. Securing and preserving the knowledge gained from operation and testing in the Fast Flux Test Facility is an important part of the Knowledge Preservation activity in this program.

Nielsen, Deborah L.; Makenas, Bruce J.; Wootan, David W.; Butner, R. Scott; Omberg, Ronald P.

2009-09-30T23:59:59.000Z

111

American Ref-Fuel of Hempstead Biomass Facility | Open Energy Information  

Open Energy Info (EERE)

American Ref-Fuel of Hempstead Biomass Facility American Ref-Fuel of Hempstead Biomass Facility Facility American Ref-Fuel of Hempstead Sector Biomass Facility Type Municipal Solid Waste Location Nassau County, New York Coordinates 40.6546145°, -73.5594128° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":40.6546145,"lon":-73.5594128,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

112

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

113

American Ref-Fuel of Niagara Biomass Facility | Open Energy Information  

Open Energy Info (EERE)

Niagara Biomass Facility Niagara Biomass Facility Jump to: navigation, search Name American Ref-Fuel of Niagara Biomass Facility Facility American Ref-Fuel of Niagara Sector Biomass Facility Type Municipal Solid Waste Location Niagara County, New York Coordinates 43.3119496°, -78.7476208° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":43.3119496,"lon":-78.7476208,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

114

American Ref-Fuel of Delaware Valley Biomass Facility | Open Energy  

Open Energy Info (EERE)

Biomass Facility Biomass Facility Jump to: navigation, search Name American Ref-Fuel of Delaware Valley Biomass Facility Facility American Ref-Fuel of Delaware Valley Sector Biomass Facility Type Municipal Solid Waste Location Delaware County, Pennsylvania Coordinates 39.907793°, -75.3878525° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":39.907793,"lon":-75.3878525,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

115

American Ref-Fuel of Essex Biomass Facility | Open Energy Information  

Open Energy Info (EERE)

Essex Biomass Facility Essex Biomass Facility Jump to: navigation, search Name American Ref-Fuel of Essex Biomass Facility Facility American Ref-Fuel of Essex Sector Biomass Facility Type Municipal Solid Waste Location Essex County, New Jersey Coordinates 40.7947466°, -74.2648829° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":40.7947466,"lon":-74.2648829,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

116

Fuel Cells for Backup Power in Telecommunications Facilities (Fact Sheet)  

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

Telecommunications providers rely on backup power to maintain a constant power supply, to prevent power outages, and to ensure the operability of cell towers, equipment, and networks. The backup power supply that best meets these objectives is fuel cell technology.

117

Fuel Cells for Backup Power in Telecommunications Facilities (Fact Sheet)  

SciTech Connect

Telecommunications providers rely on backup power to maintain a constant power supply, to prevent power outages, and to ensure the operability of cell towers, equipment, and networks. The backup power supply that best meets these objectives is fuel cell technology.

Not Available

2009-04-01T23:59:59.000Z

118

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

119

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

120

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

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

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

122

Criticality experiments with fast flux test facility fuel pins  

SciTech Connect

A United States Department of Energy program was initiated during the early seventies at the Hanford Critical Mass Laboratory to obtain experimental criticality data in support of the Liquid Metal Fast Breeder Reactor Program. The criticality experiments program was to provide basic physics data for clean well defined conditions expected to be encountered in the handling of plutonium-uranium fuel mixtures outside reactors. One task of this criticality experiments program was concerned with obtaining data on PuO{sub 2}-UO{sub 2} fuel rods containing 20--30 wt % plutonium. To obtain this data a series of experiments were performed over a period of about twelve years. The experimental data obtained during this time are summarized and the associated experimental assemblies are described. 8 refs., 7 figs.

Bierman, S.R.

1990-11-01T23:59:59.000Z

123

Author's personal copy Cost analysis of the US spent nuclear fuel reprocessing facility  

E-Print Network (OSTI)

of this, a 1987 amendment to the US Nuclear Waste Policy Act mandates the Secretary of Energy to report on a site for a second repository by 2010 (Nuclear Waste Policy Amendments Act, 1987). HoweverAuthor's personal copy Cost analysis of the US spent nuclear fuel reprocessing facility E

Deinert, Mark

124

Alternative and Renewable fuels and Vehicle Technology Program Subject Area: Biofuels production Facilities  

E-Print Network (OSTI)

Alternative and Renewable fuels and Vehicle Technology Program Subject Area: Biofuels production: Commercial Facilities · Applicant's Legal Name: Yokayo Biofuels, Inc. · Name of project: A Catalyst for Success · Project Description: Yokayo Biofuels, an industry veteran with over 10 years experience

125

MORTALITY AMONG WORKERS AT THE SAVANNAH RIVER NUCLEAR FUELS PRODUCTION FACILITY  

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

MORTALITY AMONG WORKERS AT THE SAVANNAH RIVER NUCLEAR FUELS MORTALITY AMONG WORKERS AT THE SAVANNAH RIVER NUCLEAR FUELS PRODUCTION FACILITY Donna L. Cragle and Janice P. Watkins, Center for Epidemiologic Research; Kathryn Robertson-DeMers, Bechtel Hanford, Inc. Donna Cragle, Oak Ridge Associated Universities, P.O. Box 117, Oak Ridge, TN 37831-0117 Key Words: mortality study, radiation exposure, leukemia, occupational cohort, trend test INTRODUCTION Since 1952 the Savannah River Site (SRS), located in Aiken, South Carolina, has operated as a Department of Energy (DOE) production facility for nuclear fuels and other materials. A previous study 1 through 1980 of 9,860 white males employed at least 90 consecutive days at the SRS between 1952 and 1974 found an increased number of leukemia deaths among

126

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

127

An electronic procedure system for WSRC fuel material facility  

SciTech Connect

The production of naval fuel, like many production processes within the Westinghouse complex, depends very heavily on strict procedure compliance. Thus operators need to have quick access to procedures and they need to have some assurance that they are using the most current revision. This is often both difficult and time consuming on a production floor. In order to resolve some of these problems two members of the Naval Fuel Product Team are currently developing an electronic procedure system. It is the intent of the system to have workstations on the production floor. These workstations will be networked to a centralized computer used exclusively as a file server for holding the current revision of each procedure. By simply clicking a mouse on the appropriate icon, a user will be able to access any procedure required in his portion of the process. In this user friendly environment the operator can either read the procedure on the workstation screen or print a copy of the procedure at a nearby printer. Since it is often the case that a graphic is used in one procedure is also used in other procedures, we plan to store individual graphics separately from a given procedure. In this way when a graphic changes, only one correction needs to be made in order for that graphic to be automatically updated in every procedure in which it is used. In the future we plan to expand the system so that the operator will be able to enter procedure data into the procedure. We have plans for this to be a platform for both the Distributive Control and Nuclear Accountability Systems. Farther down the road we envision operating in a real-time environment were the workstation would be able to read data directly from equipment in the process. 14 figs.

Derr, S.M.; Sloan, C.W.

1989-01-01T23:59:59.000Z

128

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

129

Sodium Loop Safety Facility W-2 experiment fuel pin rupture detection system. [LMFBR  

SciTech Connect

The objective of the Sodium Loop Safety Facility (SLSF) W-2 experiment is to characterize the combined effects of a preconditioned full-length fuel column and slow transient overpower (TOP) conditions on breeder reactor (BR) fuel pin cladding failures. The W-2 experiment will meet this objective by providing data in two technological areas: (1) time and location of cladding failure, and (2) early post-failure test fuel behavior. The test involves a seven pin, prototypic full-length fast test reactor (FTR) fuel pin bundle which will be subjected to a simulated unprotected 5 cents/s reactivity transient overpower event. The outer six pins will provide the necessary prototypic thermal-hydraulic environment for the center pin.

Hoffman, M.A.; Kirchner, T.L.; Meyers, S.C.

1980-05-01T23:59:59.000Z

130

U.S. Army Energy and Environmental Requirements and Goals: Opportunities for Fuel Cells and Hydrogen- Facility Locations and Hydrogen Storage/Delivery Logistics  

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

Overview of DoD Energy Use, Federal Facilities Goals and Requirements, Federal Vehicles and Fuel Goals, Opportunities & Conclusions

131

Spent nuclear fuel project cold vacuum drying facility vacuum and purge system design description  

SciTech Connect

This document provides the System Design Description (SDD) for the Cold Vacuum Drying Facility (CVDF) Vacuum and Purge System (VPS) . The SDD was developed in conjunction with HNF-SD-SNF-SAR-O02, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998), The HNF-SD-SNF-DRD-002, 1998, Cold Vacuum Drying Facility Design Requirements, and the CVDF Design Summary Report. The SDD contains general descriptions of the VPS equipment, the system functions, requirements and interfaces. The SDD provides references for design and fabrication details, operation sequences and maintenance. This SDD has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

IRWIN, J.J.

1998-11-30T23:59:59.000Z

132

Measurement of Atmospheric Sea Salt Concentration in the Dry Storage Facility of the Spent Nuclear Fuel  

SciTech Connect

Spent nuclear fuel coming from a Japanese nuclear power plant is stored in the interim storage facility before reprocessing. There are two types of the storage methods which are wet and dry type. In Japan, it is anticipated that the dry storage facility will increase compared with the wet type facility. The dry interim storage facility using the metal cask has been operated in Japan. In another dry storage technology, there is a concrete overpack. Especially in USA, a lot of concrete overpacks are used for the dry interim storage. In Japan, for the concrete cask, the codes of the Japan Society of Mechanical Engineers and the governmental technical guidelines are prepared for the realization of the interim storage as well as the code for the metal cask. But the interim storage using the concrete overpack has not been in progress because the evaluation on the stress corrosion cracking (SCC) of the canister is not sufficient. Japanese interim storage facilities would be constructed near the seashore. The metal casks and concrete overpacks are stored in the storage building in Japan. On the other hand, in USA they are stored outside. It is necessary to remove the decay heat of the spent nuclear fuel in the cask from the storage building. Generally, the heat is removed by natural cooling in the dry storage facility. Air including the sea salt particles goes into the dry storage facility. Concerning the concrete overpack, air goes into the cask body and cools the canister. Air goes along the canister surface and is in contact with the surface directly. In this case, the sea salt in the air attaches to the surface and then there is the concern about the occurrence of the SCC. For the concrete overpack, the canister including the spent fuel is sealed by the welding. The loss of sealability caused by the SCC has to be avoided. To evaluate the SCC for the canister, it is necessary to make clear the amount of the sea salt particles coming into the storage building and the concentration on the canister. In present, the evaluation on that point is not sufficient. In this study, the concentration of the sea salt particles in the air and on the surface of the storage facility are measured inside and outside of the building. For the measurement, two sites of the dry storage facility using the metal cask are chosen. This data is applicable for the evaluation on the SCC of the canister to realize the interim storage using the concrete overpack. (authors)

Masumi Wataru; Hisashi Kato; Satoshi Kudo; Naoko Oshima; Koji Wada [Central Research Institute of Electric Power Industry - CRIEPI (Japan); Hirofumi Narutaki [Electric Power Engineering Systems Co. Ltd. (Japan)

2006-07-01T23:59:59.000Z

133

Initial concepts on energetics and mass releases during nonnuclear explosive events in fuel cycle facilities  

SciTech Connect

Non-nuclear explosions are one of the initiating events (accidents) considered in the US Nuclear Regulatory Commission study of formal methods for estimating the airborne release of radionuclides from fuel cycle facilities. Methods currently available to estimate the energetics and mass airborne release from the four types of non-nuclear explosive events (fast and slow physical explosions and fast and slow chemical explosions) are reviewed. The likelihood that fast physical explosions will occur in fuel cycle facilities appears to be remote and this type of explosion is not considered. Methods to estimate the consequences of slow physical and fast chemical explosions are available. Methods to estimate the consequences of slow chemical explosions are less well defined.

Halverson, M.A.; Mishima, J.

1986-09-01T23:59:59.000Z

134

Materials and Fuels Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables  

SciTech Connect

Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Materials and Fuels Complex facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

Lisa Harvego; Brion Bennett

2011-09-01T23:59:59.000Z

135

Facile monomer stabilization approach to fabricate iron/vinyl ester resin nanocomposites  

E-Print Network (OSTI)

such as photovol- taic (solar) cells [11], polymer-electrolyte membrane fuel cells [12], and magnetic data storage in the marine (Naval sub- marine) industry [18] due to its good mechanical properties such as large Young

Guo, John Zhanhu

136

Philips' LED Luminaires Brighten the Rensselaer Engineering Fabrication & Prototyping Facility (also known as the Machine Shop)  

E-Print Network (OSTI)

of existing power distribution in the ceiling to minimize installation costs and replaced existing fluorescent with the Smart Lighting ERC and RPI Facilities to implement both bulb replacement and lighting redesign across

Linhardt, Robert J.

137

Procuring Fuel Cells for Stationary Power: A Guide for Federal Facility Decision Makers  

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

Procuring Fuel Cells for Stationary Power: Procuring Fuel Cells for Stationary Power: A Guide for Federal Facility Decision Makers OCTOBER 2011 Fuel Cell Technologies Program Oak Ridge National Laboratory 2 October 2011 NOTICE This report was prepared as an account of work sponsored by an agency of the United States government. Neither the United States government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily

138

Radioactive Waste Management at the New Conversion Facility of 'TVEL'{sup R} Fuel Company - 13474  

SciTech Connect

The project on the new conversion facility construction is being implemented by Joint Stock Company (JSC) 'Siberian Group of Chemical Enterprises' (SGChE) within TVEL{sup R} Fuel Company. The objective is to construct the up-to-date facility ensuring the industrial and environmental safety with the reduced impact on the community and environment in compliance with the Russian new regulatory framework on radioactive waste (RW) management. The history of the SGChE development, as well as the concepts and approaches to RW management implemented by now are shown. The SGChE future image is outlined, together with its objectives and concept on RW management in compliance with the new act 'On radioactive waste management' adopted in Russia in 2011. Possible areas of cooperation with international companies are discussed in the field of RW management with the purpose of deploying the best Russian and world practices on RW management at the new conversion facility. (authors)

Indyk, S.I.; Volodenko, A.V. [JSC 'TVEL', Russia, Moscow, 49 Kashirskoye Shosse, 115409 (Russian Federation)] [JSC 'TVEL', Russia, Moscow, 49 Kashirskoye Shosse, 115409 (Russian Federation); Tvilenev, K.A.; Tinin, V.V.; Fateeva, E.V. [JSC 'Siberian Group of Chemical Enterprises', Russia, Seversk, 1 Kurchatov Street, 636000 (Russian Federation)] [JSC 'Siberian Group of Chemical Enterprises', Russia, Seversk, 1 Kurchatov Street, 636000 (Russian Federation)

2013-07-01T23:59:59.000Z

139

The potential utilization of nuclear hydrogen for synthetic fuels production at a coal–to–liquid facility / Steven Chiuta.  

E-Print Network (OSTI)

??The production of synthetic fuels (synfuels) in coal–to–liquids (CTL) facilities has contributed to global warming due to the huge CO2 emissions of the process. This… (more)

Chiuta, Steven

2010-01-01T23:59:59.000Z

140

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

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

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

142

RELAP5 Model of a Two-phase ThermoSyphon Experimental Facility for Fuels and Materials Irradiation  

SciTech Connect

The High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL) does not have a separate materials-irradiation flow loop and requires most materials and all fuel experiments to be placed inside a containment. This is necessary to ensure that internal contaminants such as fission products cannot be released into the primary coolant. As part of the safety basis justification, HFIR also requires that all experiments be able to withstand various accident conditions (e.g., loss of coolant) without generating vapor bubbles on the surface of the experiment in the primary coolant. As with any parallel flow system, HFIR is vulnerable to flow excursion events when vapor is generated in one of those flow paths. The effects of these requirements are to artificially increase experiment temperatures by introducing a barrier between the experimental materials and the HFIR coolant and to reduce experiment heat loads to ensure boiling doesn t occur. A new experimental facility for materials irradiation and testing in the HFIR is currently being developed to overcome these limitations. The new facility is unique in that it will have its own internal cooling flow totally independent of the reactor primary coolant and boiling is permitted. The reactor primary coolant will cool the outside of this facility without contacting the materials inside. The ThermoSyphon Test Loop (TSTL), a full scale prototype of the proposed irradiation facility to be tested outside the reactor, is being designed and fabricated (Ref. 1). The TSTL is a closed system working as a two-phase thermosyphon. A schematic is shown in Fig. 1. The bottom central part is the boiler/evaporator and contains three electric heaters. The vapor generated by the heaters will rise and be condensed in the upper condenser, the condensate will drain down the side walls and be circulated via a downcomer back into the bottom of the boiler. An external flow system provides coolant that simulates the HFIR primary coolant. The two-phase flow code RELAP5-3D (Ref. 2) is the main tool employed in this design. The model has multiple challenges: boiling, condensation and natural convection flows need to be modeled accurately.

Carbajo, Juan J [ORNL] [ORNL; McDuffee, Joel Lee [ORNL] [ORNL

2013-01-01T23:59:59.000Z

143

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

144

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

145

Experience With Damaged Spent Nuclear Fuel at U.S. DOE Facilities  

SciTech Connect

This report summarizes some of the challenges encountered and solutions implemented to ensure safe storage and handling of damaged spent nuclear fuels (SNF). It includes a brief summary of some SNF storage environments and resulting SNF degradation, experience with handling and repackaging significantly degraded SNFs, and the associated lessons learned. This work provides useful insight and resolutions to many engineering challenges facing SNF handling and storage facilities. The context of this report is taken from a report produced at Idaho National Laboratory and further detailed information, such as equipment design and usage, can be found in the appendices to that report. (authors)

Carlsen, Brett; Fillmore, Denzel; Woolstenhulme, Eric [Idaho National Laboratory, P.O. Box 1625 Idaho Falls, ID 83415 (United States); McCormack, Roger L. [Fluor Hanford Site, Richland, Wash. (United States); Sindelar, Robert; Spieker, Timothy [Savannah River National Laboratory, Savannah River Site Aiken, SC 29808 (United States)

2006-07-01T23:59:59.000Z

146

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

147

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

148

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...

149

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...

150

Assessment of External Hazards at Radioactive Waste and Used Fuel Management Facilities - 13505  

SciTech Connect

One of the key lessons from the Fukushima accident is the importance of having a comprehensive identification and evaluation of risks posed by external events to nuclear facilities. While the primary focus has been on nuclear power plants, the Canadian nuclear industry has also been updating hazard assessments for radioactive waste and used fuel management facilities to ensure that lessons learnt from Fukushima are addressed. External events are events that originate either physically outside the nuclear site or outside its control. They include natural events, such as high winds, lightning, earthquakes or flood due to extreme rainfall. The approaches that have been applied to the identification and assessment of external hazards in Canada are presented and analyzed. Specific aspects and considerations concerning hazards posed to radioactive waste and used fuel management operations are identified. Relevant hazard identification techniques are described, which draw upon available regulatory guidance and standard assessment techniques such as Hazard and Operability Studies (HAZOPs) and 'What-if' analysis. Consideration is given to ensuring that hazard combinations (for example: high winds and flooding due to rainfall) are properly taken into account. Approaches that can be used to screen out external hazards, through a combination of frequency and impact assessments, are summarized. For those hazards that cannot be screened out, a brief overview of methods that can be used to conduct more detailed hazard assessments is also provided. The lessons learnt from the Fukushima accident have had a significant impact on specific aspects of the approaches used to hazard assessment for waste management. Practical examples of the effect of these impacts are provided. (authors)

Gerchikov, Mark; Schneider, Glenn; Khan, Badi; Alderson, Elizabeth [AMEC NSS, 393 University Ave., Toronto, ON (Canada)] [AMEC NSS, 393 University Ave., Toronto, ON (Canada)

2013-07-01T23:59:59.000Z

151

Results of initial operation of the Jupiter Oxygen Corporation oxy-fuel 15 MWth burner test facility  

SciTech Connect

Jupiter Oxygen Corporation (JOC), in cooperation with the National Energy Technology Laboratory (NETL), constructed a 15 MWth oxy-fuel burner test facility with Integrated Pollutant Removal (IPRTM) to test high flame temperature oxy-fuel combustion and advanced carbon capture. Combustion protocols include baseline air firing with natural gas, oxygen and natural gas firing with and without flue gas recirculation, and oxygen and pulverized coal firing with flue gas recirculation. Testing focuses on characterizing burner performance, determining heat transfer characteristics, optimizing CO2 capture, and maximizing heat recovery, with an emphasis on data traceability to address retrofit of existing boilers by directly transforming burner systems to oxy-fuel firing.

Thomas Ochs, Danylo Oryshchyn, Rigel Woodside, Cathy Summers, Brian Patrick, Dietrich Gross, Mark Schoenfield, Thomas Weber and Dan O'Brien

2009-04-01T23:59:59.000Z

152

Facilities  

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

Facilities Facilities Facilities LANL's mission is to develop and apply science and technology to ensure the safety, security, and reliability of the U.S. nuclear deterrent; reduce global threats; and solve other emerging national security and energy challenges. Contact Operator Los Alamos National Laboratory (505) 667-5061 Some LANL facilities are available to researchers at other laboratories, universities, and industry. Unique facilities foster experimental science, support LANL's security mission DARHT accelerator DARHT's electron accelerators use large, circular aluminum structures to create magnetic fields that focus and steer a stream of electrons down the length of the accelerator. Tremendous electrical energy is added along the way. When the stream of high-speed electrons exits the accelerator it is

153

Relative age-specific radiation dose commitment factors for major radionuclides released from nuclear fuel facilities  

SciTech Connect

During the licensing process for nuclear fuel facilities, committed dose equivalents must be calculated for potential exposures to people in the area around these facilities. These committed dose equivalents are usually calculated from tabulated dose-conversion factors that convert the quantity of radioactive material potentially taken in by individuals through ingestion or inhalation. For calculating committed dose equivalents to children, the Nuclear Regulatory Commission has in the past appealed to age-specific dose-conversion factors listed in NUREG-0172 (1977), which is based on a computational methodology found in ICRP Publication 2 (1959). Since the publication of NUREG-0172 new models and new concepts of risk have been provided in ICRP Publications 26 and 30 (1977, 1979). These documents provide a detailed methodology for calculating dose-conversion factors for the various radionuclides for an adult reference man. In this report are tabulated age-specific dose-conversion factors, given as multiples of the adult values, for inhalation or ingestion of each of the following isotopes: U-234, U-235, U-238, Th-228, Th-230, Th-232, Ra-226, Ra-228, Pb-210, or Po-210. Our methodology is consistent as far as practical with that of ICRP Publications 26 and 30, but we have modified and extended the ICRP methodology as necessary to include age dependence and to include metabolic and dosimetric information that has been developed since the issuance of these ICRP documents.

Cristy, M.; Leggett, R.W.; Dunning, D.E. Jr.; Eckerman, K.F.

1986-06-01T23:59:59.000Z

154

Review of K Basin and Cold Vacuum Drying Facility Found Fuel Multi-Canister Overpack Operatioons, August 2012  

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

K Basin and Cold Vacuum Drying Facility Found Fuel Multi-Canister Overpack Operations May 2011 August 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy i Table of Contents 1.0 Purpose ................................................................................................................................................... 1 2.0 Background ............................................................................................................................................ 1 3.0 Scope ...................................................................................................................................................... 2

155

Review of K Basin and Cold Vacuum Drying Facility Found Fuel Multi-Canister Overpack Operatioons, August 2012  

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

K Basin and Cold Vacuum Drying Facility Found Fuel Multi-Canister Overpack Operations May 2011 August 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy i Table of Contents 1.0 Purpose ................................................................................................................................................... 1 2.0 Background ............................................................................................................................................ 1 3.0 Scope ...................................................................................................................................................... 2

156

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...

157

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

158

Monodispersed biocompatible Ag2S nanoparticles: Facile extracellular bio-fabrication using the gamma-proteobacterium, S. oneidensis  

SciTech Connect

Interest in engineered metal and semiconductor nanocrystallites continues to grow due to their unique size and or shape dependent optoelectronic, physicochemical and biological properties. Therefore identifying novel non-hazardous nanoparticle synthesis routes that address hydrophilicity, size and shape control and production costs have become a priority. In the present illustration we report for the first time the efficient generation of extracellular Ag2S nanoparticles by the metal reducing bacterium, Shewanella oneidensis. The particles are nearly monodispersed with homogeneous shape distributions and are produced under ambient temperatures and pressures at high yield, 85 % theoretical maximum. UV-vis and Fourier transform infrared spectroscopy, dynamic light scattering, X-ray diffraction, transmission electron microscopy and X-ray photoelectron spectroscopy measurements confirmed the formation, optical properties, purity, and crystallinity of the as-synthesized particles. Further characterization revealed that the particles consist of spheres in the size range of 1-22 nm, with an average size of 9 3 nm and are capped by a detachable protein/peptide surface coat. Toxicity assessments of these silver sulfide nanoparticles on Gram-negative Escherichia coli and Shewanella oneidensis and Gram-positive Bacillus subtilis bacterial systems as well as eukaryotic; mouse lung epithelial (C 10) and macrophage (RAW-264.7) cells showed that the particles were non-inhibitory or non-cytotoxic to both these systems. Our results provide a facile, eco-friendly and economical route for the fabrication of technologically important semiconducting Ag2S nanoparticles which are dispersible and biocompatible; thus providing excellent potential for their uses in optical imaging and electronic devices, and solar cell applications.

Suresh, Anil K [ORNL; Doktycz, Mitchel John [ORNL; Wang, Wei [ORNL; Moon, Ji Won [ORNL; Gu, Baohua [ORNL; Meyer III, Harry M [ORNL; Hensley, Dale K [ORNL; Retterer, Scott T [ORNL; Allison, David P [ORNL; Phelps, Tommy Joe [ORNL; Pelletier, Dale A [ORNL

2011-01-01T23:59:59.000Z

159

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

160

Letter from Nuclear Energy Institute regarding Integrated Safety Analysis: Why it is Appropropriate for Fuel Recycling Facilities  

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

082 l F: 202.533.0166 l rxm@nei.org l www.nei.org 082 l F: 202.533.0166 l rxm@nei.org l www.nei.org Rod McCullum DIRECTOR FUEL CYCLE PROJECTS NUCLEAR GENERATION DIVISION September 10, 2010 Ms. Catherine Haney Director Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Subject: Integrated Safety Analysis: Why It Is Appropriate for Fuel Recycling Facilities Project Number: 689 Dear Ms. Haney: Enclosed for your review is a Nuclear Energy Institute white paper on the use of Integrated Safety Analysis (ISA) at U.S. Nuclear Regulatory Commission-licensed recycling facilities. This paper is intended as an information source for the NRC and should serve as a foundation for discussion with industry representatives on the issue.

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

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

162

Hazard Evaluation for Storage of Spent Nuclear Fuel (SNF) Sludge at the Solid Waste Treatment Facility  

SciTech Connect

As part of the Spent Nuclear Fuel (SNF) storage basin clean-up project, sludge that has accumulated in the K Basins due to corrosion of damaged irradiated N Reactor will be loaded into containers and placed in interim storage. The Hanford Site Treatment Complex (T Plant) has been identified as the location where the sludge will be stored until final disposition of the material occurs. Long term storage of sludge from the K Basin fuel storage facilities requires identification and analysis of potential accidents involving sludge storage in T Plant. This report is prepared as the initial step in the safety assurance process described in DOE Order 5480.23, Nuclear Safety Analysis Reports and HNF-PRO-704, Hazards and Accident Analysis Process. This report documents the evaluation of potential hazards and off-normal events associated with sludge storage activities. This information will be used in subsequent safety analyses, design, and operations procedure development to ensure safe storage. The hazards evaluation for the storage of SNF sludge in T-Plant used the Hazards and Operability Analysis (HazOp) method. The hazard evaluation identified 42 potential hazardous conditions. No hazardous conditions involving hazardous/toxic chemical concerns were identified. Of the 42 items identified in the HazOp study, eight were determined to have potential for onsite worker consequences. No items with potential offsite consequences were identified in the HazOp study. Hazardous conditions with potential onsite worker or offsite consequences are candidates for quantitative consequence analysis. The hazardous conditions with potential onsite worker consequences were grouped into two event categories, Container failure due to overpressure - internal to T Plant, and Spill of multiple containers. The two event categories will be developed into accident scenarios that will be quantitatively analyzed to determine release consequences. A third category, Container failure due to overpressure--external to T Plant, was included for completeness but is not within the scope of the hazards evaluation. Container failures external to T Plant will be addressed as part of the transportation analysis. This document describes the HazOp analysis performed for the activities associated with the storage of SNF sludge in the T Plant.

SCHULTZ, M.V.

2000-08-22T23:59:59.000Z

163

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

164

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

165

Procuring Fuel Cells for Stationary Power: A Guide for Federal Facility Decision Makers  

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

This step-by-step manual guides readers through the process of implementing a fuel cell stationary power project. The guide outlines the basics of fuel cell technology and describes how fuel cell projects can meet on-site energy service needs as well as support strategic agency objectives and sustainability requirements. This guide will help agencies decide whether a fuel cell project may be feasible and economically viable at their site. The guide then presents a four-part process for implementing a fuel cell project.

166

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

167

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

168

Alternative Fuels Data Center: Agriculturally-Derived Fuel Production  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Derived Derived Fuel Production Facility Loan Guarantees to someone by E-mail Share Alternative Fuels Data Center: Agriculturally-Derived Fuel Production Facility Loan Guarantees on Facebook Tweet about Alternative Fuels Data Center: Agriculturally-Derived Fuel Production Facility Loan Guarantees on Twitter Bookmark Alternative Fuels Data Center: Agriculturally-Derived Fuel Production Facility Loan Guarantees on Google Bookmark Alternative Fuels Data Center: Agriculturally-Derived Fuel Production Facility Loan Guarantees on Delicious Rank Alternative Fuels Data Center: Agriculturally-Derived Fuel Production Facility Loan Guarantees on Digg Find More places to share Alternative Fuels Data Center: Agriculturally-Derived Fuel Production Facility Loan Guarantees on AddThis.com...

169

Fresh and Spent Nuclear Fuel Repatriation from the IRT-2000 Research Reactor Facility, Sofia, Bulgaria  

SciTech Connect

The IRT 2000 research reactor, operated by the Bulgarian Institute for Nuclear Research and Nuclear Energy (INRNE), safely shipped all of their Russian-origin nuclear fuel from the Republic of Bulgaria to the Russian Federation beginning in 2003 and completing in 2008. These fresh and spent fuel shipments removed all highly enriched uranium (HEU) from Bulgaria. The fresh fuel was shipped by air in December 2003 using trucks and a commercial cargo aircraft. One combined spent fuel shipment of HEU and low enriched uranium (LEU) was completed in July 2008 using high capacity VPVR/M casks transported by truck, barge, and rail. The HEU shipments were assisted by the Russian Research Reactor Fuel Return Program (RRRFR) and the LEU spent fuel shipment was funded by Bulgaria. This report describes the work, approvals, organizations, equipment, and agreements required to complete these shipments and concludes with several major lessons learned.

K. J. Allen; T. G. Apostolov; I. S. Dimitrov

2009-03-01T23:59:59.000Z

170

Manufacturing Facility Opened Using EERE-Supported Low-Cost Fuel...  

Office of Environmental Management (EM)

and institutional barriers to the widespread commercialization of hydrogen and fuel cells. Addthis Related Articles Nebraska: Company More than Doubles Annual Sales and...

171

A computer code to estimate accidental fire and radioactive airborne releases in nuclear fuel cycle facilities: User's manual for FIRIN  

SciTech Connect

This manual describes the technical bases and use of the computer code FIRIN. This code was developed to estimate the source term release of smoke and radioactive particles from potential fires in nuclear fuel cycle facilities. FIRIN is a product of a broader study, Fuel Cycle Accident Analysis, which Pacific Northwest Laboratory conducted for the US Nuclear Regulatory Commission. The technical bases of FIRIN consist of a nonradioactive fire source term model, compartment effects modeling, and radioactive source term models. These three elements interact with each other in the code affecting the course of the fire. This report also serves as a complete FIRIN user's manual. Included are the FIRIN code description with methods/algorithms of calculation and subroutines, code operating instructions with input requirements, and output descriptions. 40 refs., 5 figs., 31 tabs.

Chan, M.K.; Ballinger, M.Y.; Owczarski, P.C.

1989-02-01T23:59:59.000Z

172

Advanced Safeguards Approaches for New Reprocessing Facilities  

SciTech Connect

U.S. efforts to promote the international expansion of nuclear energy through the Global Nuclear Energy Partnership (GNEP) will result in a dramatic expansion of nuclear fuel cycle facilities in the United States. New demonstration facilities, such as the Advanced Fuel Cycle Facility (AFCF), the Advanced Burner Reactor (ABR), and the Consolidated Fuel Treatment Center (CFTC) will use advanced nuclear and chemical process technologies that must incorporate increased proliferation resistance to enhance nuclear safeguards. The ASA-100 Project, “Advanced Safeguards Approaches for New Nuclear Fuel Cycle Facilities,” commissioned by the NA-243 Office of NNSA, has been tasked with reviewing and developing advanced safeguards approaches for these demonstration facilities. Because one goal of GNEP is developing and sharing proliferation-resistant nuclear technology and services with partner nations, the safeguards approaches considered are consistent with international safeguards as currently implemented by the International Atomic Energy Agency (IAEA). This first report reviews possible safeguards approaches for the new fuel reprocessing processes to be deployed at the AFCF and CFTC facilities. Similar analyses addressing the ABR and transuranic (TRU) fuel fabrication lines at AFCF and CFTC will be presented in subsequent reports.

Durst, Philip C.; Therios, Ike; Bean, Robert; Dougan, A.; Boyer, Brian; Wallace, Richard; Ehinger, Michael H.; Kovacic, Don N.; Tolk, K.

2007-06-24T23:59:59.000Z

173

Using mobile distributed pyrolysis facilities to deliver a forest residue resource for bio-fuel production.  

E-Print Network (OSTI)

??Distributed mobile conversion facilities using either fast pyrolysis or torrefaction processes can be used to convert forest residues to more energy dense substances (bio-oil, bio-slurry… (more)

Brown, Duncan

2013-01-01T23:59:59.000Z

174

Cleaning residual NaK in the fast flux test facility fuel storage cooling system  

SciTech Connect

The Fast Flux Test Facility (FFTF), located on the U.S. Department of Energy's Hanford Reservation, is a liquid metal-cooled test reactor. The FFTF was constructed to support the U.S. Liquid Metal Fast Breeder Reactor Program. The bulk of the alkali metal (sodium and NaK) has been drained and will be stored onsite prior to final disposition. Residual NaK needed to be removed from the pipes, pumps, heat exchangers, tanks, and vessels in the Fuel Storage Facility (FSF) cooling system. The cooling system was drained in 2004 leaving residual NaK in the pipes and equipment. The estimated residual NaK volume was 76 liters in the storage tank, 1.9 liters in the expansion tank, and 19-39 liters in the heat transfer loop. The residual NaK volume in the remainder of the system was expected to be very small, consisting of films, droplets, and very small pools. The NaK in the FSF Cooling System was not radiologically contaminated. The portions of the cooling system to be cleaned were divided into four groups: 1. The storage tank, filter, pump, and associated piping; 2. The heat exchanger, expansion tank, and associated piping; 3. Argon supply piping; 4. In-vessel heat transfer loop. The cleaning was contracted to Creative Engineers, Inc. (CEI) and they used their superheated steam process to clean the cooling system. It has been concluded that during the modification activities (prior to CEI coming onsite) to prepare the NaK Cooling System for cleaning, tank T-914 was pressurized relative to the In-Vessel NaK Cooler and NaK was pushed from the tank back into the Cooler and that on November 6, 2005, when the gas purge through the In-Vessel NaK Cooler was increased from 141.6 slm to 283.2 slm, NaK was forced from the In-Vessel NaK Cooler and it contacted water in the vent line and/or scrubber. The gases from the reaction then traveled back through the vent line coating the internal surface of the vent line with NaK and NaK reaction products. The hot gases also exited the scrubber through the stack and due to the temperature of the gas, the hydrogen auto ignited when it mixed with the oxygen in the air. There was no damage to equipment, no injuries, and no significant release of hazardous material. Even though the FSF Cooling System is the only system at FFTF that contains residual NaK, there are lessons to be learned from this event that can be applied to future residual sodium removal activities. The lessons learned are: - Before cleaning equipment containing residual alkali metal the volume of alkali metal in the equipment should be minimized to the extent practical. As much as possible, reconfirm the amount and location of the alkali metal immediately prior to cleaning, especially if additional evolutions have been performed or significant time has passed. This is especially true for small diameter pipe (<20.3 centimeters diameter) that is being cleaned in place since gas flow is more likely to move the alkali metal. Potential confirmation methods could include visual inspection (difficult in all-metal systems), nondestructive examination (e.g., ultrasonic measurements) and repeating previous evolutions used to drain the system. Also, expect to find alkali metal in places it would not reasonably be expected to be. - Staff with an intimate knowledge of the plant equipment and the bulk alkali metal draining activities is critical to being able to confirm the amount and locations of the alkali metal residuals and to safely clean the residuals. - Minimize the potential for movement of alkali metal during cleaning or limit the distance and locations into which alkali metal can move. - Recognize that when working with alkali metal reactions, occasional pops and bangs are to be anticipated. - Pre-plan emergency responses to unplanned events to assure responses planned for an operating reactor are appropriate for the deactivation phase.

Burke, T.M.; Church, W.R. [Fluor Hanford, PO Box 1000, Richland, Washington, 99352 (United States); Hodgson, K.M. [Fluor Government Group, PO Box 1050, Richland, Washington, 99352 (United States)

2008-01-15T23:59:59.000Z

175

The distribution of 129I around West Valley, an inactive nuclear fuel reprocessing facility in Western New York  

Science Journals Connector (OSTI)

A study of 129I levels in surface waters around an inactive nuclear fuel reprocessing facility at West Valley, Cattaraugus County, New York shows a strong presence of this long-lived radoiisotope (T12 = 15.7 Ma) of iodine around the facility. The signal is strong in creeks which drain the facility as well as those in the general vicinity over two decades after reprocessing activities at the site ceased in 1972. Highest 129I levels (1.36 × 1011 atoms/L) are observed at the site boundary in Buttermilk Creek which drains the site, and the resulting plume can be tracked into Lake Erie via Cattaraugus Creek. Other creeks in the West Valley area which do not receive drainage from the site have 129I concentrations on the order of 109–1010 atoms/L, indicating that atmospheric transport of the radionuclide is significant. 129I levels in surface waters around West Valley are 10–1000 times higher than background lelels in western New York, including 129I levels around active nuclear power plants (reported in Rao and Fehn, in preparation), and 100–10000 times higher than levels of 129I in areas outside western New York. However, 36ClCl and 3H measurements in Buttermilk Creek at the site boundary are consistent with present day rainwater values for the region.

Usha Rao; Udo Fehn

1997-01-01T23:59:59.000Z

176

A demonstration of variance and covariance calculations using MAVARIC (Materials Accounting VARIance Calculator) and PROFF (PROcessing and Fuel Facilities calculator)  

SciTech Connect

Good decision-making in materials accounting requires a valid calculation of control limits and detection sensitivity for facilities handling special nuclear materials (SNM). A difficult aspect of this calculation is determining the appropriate variance and covariance values for the terms in the materials balance (MB) equation. Computer software such as MAVARIC (Materials Accounting VARIance Calculator) and PROFF (PROcessing and Fuel Facilities calculator) can efficiently select and combine variance terms. These programs determine the variance and covariance of an MB equation by first obtaining relations for the variance and covariance of each term in the MB equation through propagating instrument errors and then substituting the measured quantities and their uncertainties into these relations. MAVARIC is a custom spreadsheet used with the second release of LOTUS 1-2-3.** PROFF is a stand-alone menu-driven program requiring no commercial software. Programs such as MAVARIC and PROFF facilitate the complex calculations required to determine the detection sensitivity of an SNM facility. These programs can also be used to analyze materials accounting systems.

Barlich, G.L.; Nasseri, S.S.

1990-01-01T23:59:59.000Z

177

Facility Effluent Monitoring Plan for the Spent Nuclear Fuel (SNF) Project  

SciTech Connect

A facility effluent monitoring plan is required by the US. Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document was prepared using the specific guidelines identified in Westinghouse Hanford Company (WHC)-EP-0438-1, ''A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans'', and assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the third revision to the original annual report. This document is reviewed annually even if there are no operational changes, and it is updated as necessary.

HUNACEK, G.S.

2000-08-01T23:59:59.000Z

178

Module 10: Maintenance and Fueling Guidelines  

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

This course covers safety guidelines for hydrogen, safe maintenance facilities, safety guidelines for hydrogen fueling facilities

179

Dose evaluation in criticality accident conditions using transient critical facilities fueled with a fissile solution  

Science Journals Connector (OSTI)

......first verify the reliability of the measurement...is a pulse-type reactor fueled with 10...conditions in the TRACY reactor room. The results...measurement and analysis are shown in Table...31. Table 1. Analysis of measured and...is also a pulsed reactor similar to the TRACY......

T. Nakamura; K. Tonoike; Y. Miyoshi

2004-08-01T23:59:59.000Z

180

Emission Reduction Using RTP Green Fuel in Industry Facilities: A Life Cycle Study  

Science Journals Connector (OSTI)

Scenario analyses were also conducted to determine responses to model assumptions including different biomass feedstocks, feedstock transport mode and distance, and geographical locations of the pyrolysis process. ... The savings of GHG emissions compared to fossil heavy fuel oil is greater than 80% for all of these biomass feedstocks. ...

Jiqing Fan; David Shonnard; Tom Kalnes; Monique Streff; Geoff Hopkins

2013-08-23T23:59:59.000Z

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


181

High-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

182

Development of a Safeguards Approach for a Small Graphite Moderated Reactor and Associated Fuel Cycle Facilities  

E-Print Network (OSTI)

in it and how nuclear material flows between facilities. The goals of the safeguards system were established next, using the normal IAEA standards for the non-detection and false alarm probabilities. The 5 MWe Reactor was modeled for both plutonium production...

Rauch, Eric B.

2010-07-14T23:59:59.000Z

183

DEVELOPMENT AND DEMONSTRATION OF A PILOT SCALE FACILITY FOR FABRICATION AND MARKETING OF LIGHTWEIGHT-COAL COMBUSTION BYPRODUCTS-BASED SUPPORTS AND MINE VENTILATION BLOCKS FOR UNDERGROUND MINES  

SciTech Connect

The overall goal of this program was to develop a pilot scale facility, and design, fabricate, and market CCBs-based lightweight blocks for mine ventilation control devices, and engineered crib elements and posts for use as artificial supports in underground mines to replace similar wooden elements. This specific project was undertaken to (1) design a pilot scale facility to develop and demonstrate commercial production techniques, and (2) provide technical and marketing support to Fly Lite, Inc to operate the pilot scale facility. Fly Lite, Inc is a joint venture company of the three industrial cooperators who were involved in research into the development of CCBs-based structural materials. The Fly-Lite pilot scale facility is located in McLeansboro, Illinois. Lightweight blocks for use in ventilation stoppings in underground mines have been successfully produced and marketed by the pilot-scale facility. To date, over 16,000 lightweight blocks (30-40 pcf) have been sold to the mining industry. Additionally, a smaller width (6-inch) full-density block was developed in August-September 2002 at the request of a mining company. An application has been submitted to Mine Safety and Health Administration for the developed block approval for use in mines. Commercialization of cribs and posts has also been accomplished. Two generations of cribs have been developed and demonstrated in the field. MSHA designated them suitable for use in mines. To date, over 2,000 crib elements have been sold to mines in Illinois. Two generations of posts were also demonstrated in the field and designated as suitable for use in mines by MSHA. Negotiations are currently underway with a mine in Illinois to market about 1,000 posts per year based on a field demonstration in their mine. It is estimated that 4-5 million tons CCBs (F-fly ash or FBC fly ash) may be utilized if the developed products can be commercially implemented in U.S. coal and non-coal mines.

Yoginder P. Chugh

2002-10-01T23:59:59.000Z

184

Fuel cycle facility control system for the Integral Fast Reactor Program  

SciTech Connect

As part of the Integral Fast Reactor (IFR) Fuel Demonstration, a new distributed control system designed, implemented and installed. The Fuel processes are a combination of chemical and machining processes operated remotely. To meet this special requirement, the new control system provides complete sequential logic control motion and positioning control and continuous PID loop control. Also, a centralized computer system provides near-real time nuclear material tracking, product quality control data archiving and a centralized reporting function. The control system was configured to use programmable logic controllers, small logic controllers, personal computers with touch screens, engineering work stations and interconnecting networks. By following a structured software development method the operator interface was standardized. The system has been installed and is presently being tested for operations.

Benedict, R.W.; Tate, D.A.

1993-09-01T23:59:59.000Z

185

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)

186

New Prototype Safeguards Technology Offers Improved Confidence and Automation for Uranium Enrichment Facilities  

SciTech Connect

An important requirement for the international safeguards community is the ability to determine the enrichment level of uranium in gas centrifuge enrichment plants and nuclear fuel fabrication facilities. This is essential to ensure that countries with nuclear nonproliferation commitments, such as States Party to the Nuclear Nonproliferation Treaty, are adhering to their obligations. However, current technologies to verify the uranium enrichment level in gas centrifuge enrichment plants or nuclear fuel fabrication facilities are technically challenging and resource-intensive. NNSA’s Office of Nonproliferation and International Security (NIS) supports the development, testing, and evaluation of future systems that will strengthen and sustain U.S. safeguards and security capabilities—in this case, by automating the monitoring of uranium enrichment in the entire inventory of a fuel fabrication facility. One such system is HEVA—hybrid enrichment verification array. This prototype was developed to provide an automated, nondestructive assay verification technology for uranium hexafluoride (UF6) cylinders at enrichment plants.

Brim, Cornelia P.

2013-03-04T23:59:59.000Z

187

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

188

Spatial correction factors for YALINA Booster facility loaded with medium and low enriched fuels  

SciTech Connect

The Bell and Glasstone spatial correction factor is used in analyses of subcritical assemblies to correct the experimental reactivity as function of the detector position. Besides the detector position, several other parameters affect the correction factor: the energy weighting function of the detector, the detector size, the energy-angle distribution of source neutrons, and the reactivity of the subcritical assembly. This work focuses on the dependency of the correction factor on the detector material and it investigates the YALINA Booster subcritical assembly loaded with medium (36%) and low (10%) enriched fuels. (authors)

Talamo, A.; Gohar, Y. [Argonne National Laboratory, 9700 S. Cass Ave, Argonne, IL 60439 (United States); Bournos, V.; Fokov, Y.; Kiyavitskaya, H.; Routkovskaya, C. [Joint Inst. for Power and Nuclear Research-Sosny, 99 Academician A.K.Krasin Str, Minsk 220109 (Belarus)

2012-07-01T23:59:59.000Z

189

Spent nuclear fuel project cold vacuum drying facility safety equipment list  

SciTech Connect

This document provides the safety equipment list (SEL) for the Cold Vacuum Drying Facility (CVDF). The SEL was prepared in accordance with the procedure for safety structures, systems, and components (SSCs) in HNF-PRO-516, ''Safety Structures, Systems, and Components,'' Revision 0 and HNF-PRO-097, Engineering Design and Evaluation, Revision 0. The SEL was developed in conjunction with HNF-SO-SNF-SAR-O02, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998). The SEL identifies the SSCs and their safety functions, the design basis accidents for which they are required to perform, the design criteria, codes and standards, and quality assurance requirements that are required for establishing the safety design basis of the SSCs. This SEL has been developed for the CVDF Phase 2 Safety Analysis Report (SAR) and shall be updated, expanded, and revised in accordance with future phases of the CVDF SAR until the CVDF final SAR is approved.

IRWIN, J.J.

1999-02-24T23:59:59.000Z

190

U.S. Army Energy and Environmental Requirements and Goals: Opportunities for Fuel Cells and Hydrogen - Facility Locations and Hydrogen Storage/Delivery Logistics  

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

US Army Corps US Army Corps of Engineers ® Engineer Research and Development Center U.S. Army Energy and Environmental Requirements and Goals: Opportunities for Fuel Cells and Hydrogen Facility Locations and Hydrogen Storage/Delivery Logistics Nicholas M. Josefik 217-373-4436 N-josefik@cecer.army.mil www.dodfuelcell.com Franklin H. Holcomb Project Leader, Fuel Cell Team 27 OCT 08 Distributed Generation H 2 Generation & Storage Material Handling H2 Vehicles 2 US Army Corps of Engineers ® Engineer Research and Development Center Presentation Outline * DoD Energy Use * Federal Facilities Goals and Requirements * Federal Vehicles and Fuel Goals * Opportunities & Conclusions 3 US Army Corps of Engineers ® Engineer Research and Development Center Where Does the Energy Go? * Tactical and Combat Vehicles (Jets,

191

Environmentally based siting assessment for synthetic-liquid-fuels facilities. Final report  

SciTech Connect

A detailed assessment of the major environmental constraints to siting a synthetic fuels industry and the results of that assessment are used to determine on a regional basis the potential for development of such an industry with minimal environmental conflicts. Secondly, the ability to mitigate some of the constraining impacts through alternative institutional arrangements, especially in areas that are judged to have a low development potential is also assessed. Limitations of the study are delineated, but specifically, the study is limited geographically to well-defined boundaries that include the prime coal and oil shale resource areas. The critical factors used in developing the framework are air quality, water availability, socioeconomic capacity, ecological sensitivity, environmental health, and the management of Federally owned lands. (MCW)

None

1980-01-01T23:59:59.000Z

192

Manganite nanorods supported palladium - a facile electrocatalyst for direct glycerol fuel cells  

Science Journals Connector (OSTI)

Manganite (MnOOH) nanorods were synthesised by a hydrothermal method and then used as a supportive material for Palladium towards glycerol electrooxidation in alkaline medium. The smaller quantities (5 and 15 weight %) of palladium are coated on the manganite nanorods by in situ reduction method. The electrooxidation of glycerol at Pd/Manganite electrode exhibits peak current vertexes at ?0.2 V, which is lower than Pd/C. By varying the alkali (KOH) and glycerol concentrations the electrocatalytic behaviour has been changed considerably and was discussed. The present study reveals that the manganite nanorods act as active support material for Pd. The support material will help to oxidise the intermediates formed during electrooxidation of fuel. The possibilities for the removal of poisonous intermediates were also discussed. The effect of support material on the electrooxidation reaction was explained by proper mechanism.

Ramanujam Kannan; Palanisamy Ravichandiran; Kulandaivelu Karunakaran

2014-01-01T23:59:59.000Z

193

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

194

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

195

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

196

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

197

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

198

Radiological transportation risk assessment of the shipment of sodium-bonded fuel from the Fast Flux Test Facility to the Idaho National Engineering Laboratory  

SciTech Connect

This document was written in support of Environmental Assessment: Shutdown of the Fast Flux Test Facility (FFTF), Hanford Site, Richland, Washington. It analyzes the potential radiological risks associated with the transportation of sodium-bonded metal alloy and mixed carbide fuel from the FFTF on the Hanford Site in Washington State to the Idaho Engineering Laboratory in Idaho in the T-3 Cask. RADTRAN 4 is used for the analysis which addresses potential risk from normal transportation and hypothetical accident scenarios.

Green, J.R.

1995-01-31T23:59:59.000Z

199

Fire hazard analysis for the fuel supply shutdown storage buildings  

SciTech Connect

The purpose of a fire hazards analysis (FHA) is to comprehensively assess the risk from fire and other perils within individual fire areas in a DOE facility in relation to proposed fire protection so as to ascertain whether the objectives of DOE 5480.7A, Fire Protection, are met. This Fire Hazards Analysis was prepared as required by HNF-PRO-350, Fire Hazards Analysis Requirements, (Reference 7) for a portion of the 300 Area N Reactor Fuel Fabrication and Storage Facility.

REMAIZE, J.A.

2000-09-27T23:59:59.000Z

200

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Tax Incentive Alternative fuel production facilities, including biodiesel, biomass, biogas, and ethanol production facilities, may qualify for a reduced property tax rate of 3%...

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

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

or individual that owns, controls, operates, or manages a facility that generates electricity exclusively for use in AFV charging or fueling facilities is not subject to...

202

Nuclear-fuel-cycle risk assessment: descriptions of representative non-reactor facilities, Sections 15-19  

SciTech Connect

Information is presented under the following section headings: fuel reprocessing; spent fuel and high-level and transuranic waste storage; spent fuel and high-level and transuranic waste disposal; low-level and intermediate-level waste disposal; and, transportation of radioactive materials in the nuclear fuel cycle. In each of the first three sections a description is given on the mainline process, effluent processing and waste management systems, plant layout, and alternative process schemes. Safety information and a summary are also included in each. The section on transport of radioactive materials includes information on the transportation of uranium ore, uranium ore concentrate, UF/sub 6/, PuO/sub 2/ powder, unirradiated uranium and mixed-oxide fuel assemblies, spent fuel, solidified high-level waste, contact-handled transuranic waste, remote-handled transuranic waste, and low and intermediate level nontransuranic waste. A glossary is included. (JGB)

Schneider, K.J.

1982-09-01T23:59:59.000Z

203

NREL Develops Test Facility and Test Protocols for Hydrogen Sensor Performance (Fact Sheet), Hydrogen and Fuel Cell Technical Highlights (HFCTH)  

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

8 * November 2010 8 * November 2010 The NREL hydrogen safety sensor test facility (Robert Burgess/NREL) PIX 18240 NREL Develops Test Facility and Test Protocols for Hydrogen Sensor Performance Team: Safety Codes & Standards Group, Hydrogen Technologies & Systems Center Accomplishment: The NREL Hydrogen Sensor Test Facility was recently commissioned for the quantitative assessment of hydrogen safety sensors (first reported in April 2010). Testing of sensors has started and is ongoing. Test Apparatus: The Test Facility was designed to test hydrogen sensors under precisely controlled conditions. The apparatus can simultaneously test multiple sensors and can handle all common electronic interfaces, including voltage, current, resistance,

204

MPA-11 Facilities  

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

Our Cleanroom Facility is available for use by LANL researchers MPA-11 Facilities Fuel cell testing, acoustics laboratories, and a wide spectrum of characterization equipment are essential to the research conducted in our group. Fuel Cell Testing. ........Acoustics. ........Characterization . ........ Many other multi-disciplinary staff and experimental/computational capabilities throughout Los Alamos National Laboratory are available to support our research. Access to enabling capabilities for the Fuel Cell Program is facilitated by the Laboratory's Institute for Hydrogen and Fuel Cell Research. Fuel Cell Testing Experimental equipment that is essential to our fuel cell efforts is housed in 24 laboratories at the Los Alamos National Laboratory. A partial list of

205

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

206

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

207

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

208

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

209

UK FT PDU Facility Draft EA  

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

Process Development Unit Facility February 2014 The facility is sized as a small-scale pilot CBTL plant that would produce research quantities of FT liquid fuels at...

210

Carbon Fiber Technology Facility | Department of Energy  

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

Carbon Fiber Technology Facility Carbon Fiber Technology Facility 2013 DOE Hydrogen and Fuel Cells Program and Vehicle Technologies Program Annual Merit Review and Peer Evaluation...

211

Carbon Fiber Technology Facility | Department of Energy  

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

Carbon Fiber Technology Facility Carbon Fiber Technology Facility 2011 DOE Hydrogen and Fuel Cells Program, and Vehicle Technologies Program Annual Merit Review and Peer Evaluation...

212

Carbon Fiber Technology Facility | Department of Energy  

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

Carbon Fiber Technology Facility Carbon Fiber Technology Facility 2012 DOE Hydrogen and Fuel Cells Program and Vehicle Technologies Program Annual Merit Review and Peer Evaluation...

213

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

214

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

215

NREL: Vehicles and Fuels Research - Fuels Performance  

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

about related NREL biomass research projects that focus on converting renewable biomass feedstocks into transportation fuels, chemicals, and products. Facilities NREL conducts...

216

Reliability Engineering Approach to Probabilistic Proliferation Resistance Analysis of the Example Sodium Fast Reactor Fuel Cycle Facility  

E-Print Network (OSTI)

-cooled fast reactor and pyroprocessing facility were designed by Argonne National Laboratory (ANL) for the purpose of facilitating discussion on the subject of fast reactor and pyroprocessing safeguards in the absence of a safeguards confidential design... proliferators due to the presence of bulk nuclear material and the ability to acquire plutonium in a form easier to convert to a weapon. The ESFR design includes four 800 MWth (300 MWe) reactors (Argonne National Laboratory 2006) and an on...

Cronholm, Lillian Marie

2012-10-19T23:59:59.000Z

217

Nanotechnology User Facility for  

E-Print Network (OSTI)

A National Nanotechnology User Facility for Industry Academia Government #12;The National Institute of Commerce's nanotechnology user facility. The CNST enables innovation by providing rapid access to the tools new measurement and fabrication methods in response to national nanotechnology needs. www

218

Energy, environmental, health and cost benefits of cogeneration from fossil fuels and nuclear energy using the electrical utility facilities of a province  

Science Journals Connector (OSTI)

A method is investigated for increasing the utilization efficiency of energy resources and reducing environmental emissions, focusing on utility-scale cogeneration and the contributions of nuclear energy. A case study is presented for Ontario using the nuclear and fossil facilities of the main provincial electrical utility. Implementation of utility-based cogeneration in Ontario or a region with a similar energy system and attributes is seen to be able to reduce significantly annual and cumulative uranium and fossil fuel use and related emissions, provide economic benefits for the province and its electrical utility, and substitute nuclear energy for fossil fuels. The reduced emissions of greenhouse gases are significant, and indicate that utility-based cogeneration can contribute notably to efforts to combat climate change. Ontario and other regions with similar energy systems and characteristics would benefit from working with the regional electrical utilities and other relevant parties to implementing cogeneration in a careful and optimal manner. Implementation decisions need to balance the interests of the stakeholders when determining which cogeneration options to adopt and barriers to regional utility-based cogeneration need to be overcome.

Marc A. Rosen

2009-01-01T23:59:59.000Z

219

Procuring Fuel Cells for Stationary Power: A Guide for Federal...  

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

1 Procuring Fuel Cells for Stationary Power: A Guide for Federal Facility Decision Makers Federal Facilities Guide to Fuel Cells May 8, 2012 - Outline * Distributed Generation and...

220

Procuring Fuel Cells for Stationary Power: A Guide for Federal...  

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

Procuring Fuel Cells for Stationary Power: A Guide for Federal Facility Decision Makers Procuring Fuel Cells for Stationary Power: A Guide for Federal Facility Decision Makers This...

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

Type A Accident Investigation Board report on the January 17, 1996, electrical accident with injury in Technical Area 21 Tritium Science and Fabrication Facility Los Alamos National Laboratory. Final report  

SciTech Connect

An electrical accident was investigated in which a crafts person received serious injuries as a result of coming into contact with a 13.2 kilovolt (kV) electrical cable in the basement of Building 209 in Technical Area 21 (TA-21-209) in the Tritium Science and Fabrication Facility (TSFF) at Los Alamos National Laboratory (LANL). In conducting its investigation, the Accident Investigation Board used various analytical techniques, including events and causal factor analysis, barrier analysis, change analysis, fault tree analysis, materials analysis, and root cause analysis. The board inspected the accident site, reviewed events surrounding the accident, conducted extensive interviews and document reviews, and performed causation analyses to determine the factors that contributed to the accident, including any management system deficiencies. Relevant management systems and factors that could have contributed to the accident were evaluated in accordance with the guiding principles of safety management identified by the Secretary of Energy in an October 1994 letter to the Defense Nuclear Facilities Safety Board and subsequently to Congress.

NONE

1996-04-01T23:59:59.000Z

222

Cryogenic Dark Matter Search Detector Fabrication Process and Recent Improvements  

E-Print Network (OSTI)

A dedicated facility has been commissioned for Cryogenic Dark Matter Search (CDMS) detector fabrication at Texas A&M University (TAMU). The fabrication process has been carefully tuned using this facility and its equipment. Production of successfully tested detectors has been demonstrated. Significant improvements in detector performance have been made using new fabrication methods/equipment and tuning of process parameters.

Andrew Jastram; Rusty Harris; Rupak Mahapatra; James Phillips; Mark Platt; Kunj Prasad; Joel Sander; Sriteja Upadhyayula

2014-08-01T23:59:59.000Z

223

Cryogenic Dark Matter Search Detector Fabrication Process and Recent Improvements  

E-Print Network (OSTI)

A dedicated facility has been commissioned for Cryogenic Dark Matter Search (CDMS) detector fabrication at Texas A&M University (TAMU). The fabrication process has been carefully tuned using this facility and its equipment. Production of successfully tested detectors has been demonstrated. Significant improvements in detector performance have been made using new fabrication methods/equipment and tuning of process parameters.

Jastram, Andrew; Mahapatra, Rupak; Phillips, James; Platt, Mark; Prasad, Kunj; Sander, Joel; Upadhyayula, Sriteja

2014-01-01T23:59:59.000Z

224

Waste minimization at a plutonium processing facility  

SciTech Connect

As part of Los Alamos National Laboratory`s (LANL) mission to reduce the nuclear danger throughout the world, the plutonium processing facility at LANL maintains expertise and skills in nuclear weapons technologies as well as leadership in all peaceful applications of plutonium technologies, including fuel fabrication for terrestrial and space reactors and heat sources and thermoelectric generators for space missions. Another near-term challenge resulted from two safety assessments performed by the Defense Nuclear Facilities Safety Board and the U.S. Department of Energy during the past two years. These assessments have necessitated the processing and stabilization of plutonium contained in tons of residues so that they can be stored safely for an indefinite period. This report describes waste streams and approaches to waste reduction of plutonium management.

Pillay, K.K.S. [Los Alamos National Laboratory, NM (United States)

1995-12-31T23:59:59.000Z

225

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Mandate All state-owned diesel fueling facilities must provide fuel containing at least 5% biodiesel (B5) at all diesel pumps. (Reference South Carolina Code of Laws 12-63-3...

226

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Department of Transportation and Public Facilities (Department) must evaluate the cost, efficiency, and commercial availability of alternative fuels for automotive purposes...

227

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

100 million for an alternative fuel or gasification facility that uses coal, oil shale, or tar sands as the primary feedstock; 25 million for an energy-efficient...

228

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Dakota offers loan guarantees for eligible entities constructing facilities using biomass for agriculturally-derived fuel production. Through July 31, 2015, a single loan...

229

Resource book: Decommissioning of contaminated facilities at Hanford  

SciTech Connect

In 1942 Hanford was commissioned as a site for the production of weapons-grade plutonium. The years since have seen the construction and operation of several generations of plutonium-producing reactors, plants for the chemical processing of irradiated fuel elements, plutonium and uranium processing and fabrication plants, and other facilities. There has also been a diversification of the Hanford site with the building of new laboratories, a fission product encapsulation plant, improved high-level waste management facilities, the Fast Flux test facility, commercial power reactors and commercial solid waste disposal facilities. Obsolescence and changing requirements will result in the deactivation or retirement of buildings, waste storage tanks, waste burial grounds and liquid waste disposal sites which have become contaminated with varying levels of radionuclides. This manual was established as a written repository of information pertinent to decommissioning planning and operations at Hanford. The Resource Book contains, in several volumes, descriptive information of the Hanford Site and general discussions of several classes of contaminated facilities found at Hanford. Supplementing these discussions are appendices containing data sheets on individual contaminated facilities and sites at Hanford. Twelve appendices are provided, corresponding to the twelve classes into which the contaminated facilities at Hanford have been organized. Within each appendix are individual data sheets containing administrative, geographical, physical, radiological, functional and decommissioning information on each facility within the class. 68 refs., 54 figs., 18 tabs.

Not Available

1991-09-01T23:59:59.000Z

230

Large-scale Demonstration and Deployment Project for D&D of Fuel Storage Canals and Associated Facilities at INEEL  

SciTech Connect

The Department of Energy (DOE) Office of Science and Technology (OST), Deactivation and Decommissioning Focus Area (DDFA), sponsored a Large Scale Demonstration and Deployment Project (LSDDP) at the Idaho National Engineering and Environmental Laboratory (INEEL) under management of the DOE National Energy Technology Laboratory (NETL). The INEEL LSDDP is one of several LSDDPs sponsored by DOE. The LSDDP process integrates field demonstrations into actual decontamination and decommissioning (D&D) operations by comparing new or improved technologies against existing baseline technologies using a side-by-side comparison. The goals are (a) to identify technologies that are cheaper, safer, faster, and cleaner (produce less waste), and (b) to incorporate those technologies into D&D baseline operations. The INEEL LSDDP reviewed more than 300 technologies, screened 141, and demonstrated 17. These 17 technologies have been deployed a total of 70 times at facilities other than those where the technology was demonstrated, and 10 have become baseline at the INEEL. Fifteen INEEL D&D needs have been modified or removed from the Needs Management System as a direct result of using these new technologies. Conservatively, the ten-year projected cost savings at the INEEL resulting from use of the technologies demonstrated in this INEEL LSDDP exceeds $39 million dollars.

Whitmill, Larry Joseph

2001-12-01T23:59:59.000Z

231

Atmospheric deposition, resuspension and root uptake of plutonium in corn and other grain-producing agroecosystems near a nuclear fuel facility  

SciTech Connect

Plutonium released to the environment may contribute to dose to humans through inhalation or ingestion of contaminated foodstuffs. Plutonium contamination of agricultural plants may result from interception and retention of atmospheric deposition, resuspension of Pu-bearing soil particles to plant surfaces, and root uptake and translocation to grain. Plutonium on vegetation surfaces may be transferred to grain surfaces during mechanical harvesting. Data obtained from corn grown near the US Department of Energy`s H-Area nuclear fuel chemical separations facility on the Savannah River Site was used to estimated parameters of a simple model of Pu transport in agroecosystems. The parameter estimates for corn were compared to those previously obtained for wheat and soybeans. Despite some differences in parameter estimates among crops, the relative importances of atmospheric deposition, resuspension and root uptake were similar among crops. For even small deposition rates, the relative importances of processes for Pu contamination of corn grain should be: transfer of atmospheric deposition from vegetation surfaces to grain surfaces during combining > resuspension of soil to grain surfaces > root uptake. Approximately 3.9 {times} 10{sup {minus}5} of a year`s atmospheric deposition is transferred to grain. Approximately 6.2 {times} 10{sup {minus}9} of the Pu inventory in the soil is resuspended to corn grain, and a further 7.3 {times} 10{sup {minus}10} of the soil inventory is absorbed by roots and translocated to grains.

Pinder, J.E. III; McLeod, K.W.; Adriano, D.C. [Savannah River Ecology Lab., Aiken, SC (United States); Corey, J.C.; Boni, A.L. [Savannah River Lab., Aiken, SC (United States)

1989-12-31T23:59:59.000Z

232

Atmospheric deposition, resuspension, and root uptake of Pu in corn and other grain-producing agroecosystems near a nuclear fuel facility  

SciTech Connect

Plutonium released to the environment may contribute to dose to humans through inhalation or ingestion of contaminated foodstuffs. Plutonium contamination of agricultural plants may result from interception and retention of atmospheric deposition, resuspension of Pu-bearing soil particles to plant surfaces, and root uptake. Plutonium on vegetation surfaces may be transferred to grain surfaces during mechanical harvesting. Data obtained from corn grown near the U.S. Department of Energy's H-Area nuclear fuel chemical separations facility on the Savannah River Site were used to estimate parameters of a simple model of Pu transport in agroecosystems. The parameter estimates for corn were compared to those previously obtained for wheat and soybeans. Despite some differences in parameter estimates among crops, the relative importances of atmospheric deposition, resuspension, and root uptake were similar among crops. For even small deposition rates, the relative importances of processes for Pu contamination of corn grain should be: transfer of atmospheric deposition from vegetation surfaces to grain surfaces during combining greater than resuspension of soil to grain surfaces greater than root uptake. Approximately 3.9 X 10(-5) of a year's atmospheric deposition is transferred to grain. Approximately 6.2 X 10(-9) of the Pu inventory in the soil is resuspended to corn grain, and a further 7.3 X 10(-10) of the soil Pu inventory is absorbed and translocated to grains.

Pinder, J.E. III; McLeod, K.W.; Adriano, D.C.; Corey, J.C.; Boni, A.L. (Savannah River Ecology Laboratory, Aiken, SC (USA))

1990-12-01T23:59:59.000Z

233

Atmospheric deposition, resuspension and root uptake of plutonium in corn and other grain-producing agroecosystems near a nuclear fuel facility  

SciTech Connect

Plutonium released to the environment may contribute to dose to humans through inhalation or ingestion of contaminated foodstuffs. Plutonium contamination of agricultural plants may result from interception and retention of atmospheric deposition, resuspension of Pu-bearing soil particles to plant surfaces, and root uptake and translocation to grain. Plutonium on vegetation surfaces may be transferred to grain surfaces during mechanical harvesting. Data obtained from corn grown near the US Department of Energy's H-Area nuclear fuel chemical separations facility on the Savannah River Site was used to estimated parameters of a simple model of Pu transport in agroecosystems. The parameter estimates for corn were compared to those previously obtained for wheat and soybeans. Despite some differences in parameter estimates among crops, the relative importances of atmospheric deposition, resuspension and root uptake were similar among crops. For even small deposition rates, the relative importances of processes for Pu contamination of corn grain should be: transfer of atmospheric deposition from vegetation surfaces to grain surfaces during combining > resuspension of soil to grain surfaces > root uptake. Approximately 3.9 {times} 10{sup {minus}5} of a year's atmospheric deposition is transferred to grain. Approximately 6.2 {times} 10{sup {minus}9} of the Pu inventory in the soil is resuspended to corn grain, and a further 7.3 {times} 10{sup {minus}10} of the soil inventory is absorbed by roots and translocated to grains.

Pinder, J.E. III; McLeod, K.W.; Adriano, D.C. (Savannah River Ecology Lab., Aiken, SC (United States)); Corey, J.C.; Boni, A.L. (Savannah River Lab., Aiken, SC (United States))

1989-01-01T23:59:59.000Z

234

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...

235

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

236

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

237

Enforcement Letter, Parsons Technology Development & Fabrication Complex -  

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

Parsons Technology Development & Fabrication Parsons Technology Development & Fabrication Complex - April 13, 2010 Enforcement Letter, Parsons Technology Development & Fabrication Complex - April 13, 2010 April 13, 2010 Enforcement Letter issued to Parsons Technology Development & Fabrication Complex related to Deficiencies in the Fabrication of Safety Significant Embed Plates at the Salt Waste Processing Facility at the Savannah River Site This letter refers to the Office of Health, Safety and Security's Office of Enforcement's investigation into the facts and circumstances associated with quality assurance deficiencies in the fabrication of safety significant embed plates. These embed plates were fabricated by Parsons Technology Development and Fabrication Complex (PTDFC) a supplier to

238

A Proposal to the Department of Energy for The Fabrication of a Very High Energy Polarized Gama Ray Beam Facility and A Program of Medium Energy Physics Research at The National Synchrotron Light Source  

SciTech Connect

This proposal requests support for the fabrication and operation of a modest facility that would provide relatively intense beams of monochromatic and polarized photons with energies in the range of several hundreds of MeV. These {gamma} rays would be produced by Compton backscattering laser light from the electrons circulating in the 2.5-3.0 GeV 'X-RAY' storage ring of the National Synchrotron Light Source (NSLS) at Brookhaven National Laboratory. The excellent emittance, phase space, and high current of this state-of-the-art storage ring will allow the production of 2 x 10{sup 7} {gamma} rays per second. These photons would be tagged by detecting the scattered electrons, thereby determining the energy to 2.7 MeV for all {gamma}-ray energies. The efficiency of this tagging procedure is 100% and the {gamma}-ray beam would be essentially background free. Tagging will also allow the flexibility of operating with a dynamic range as large as 200 MeV in photon energy while still preserving high resolution and polarization. These beams will permit a fruitful study of important questions in medium-energy nuclear physics. The initial goals of this program are to reach reliable operation with photon energies up to 300 MeV and to develop {gamma}-ray beams with energies up to about 500 MeV. To demonstrate reliable operation, a modest physics program is planned that, for the most part, utilizes existing magnets and detector systems but nonetheless addresses several important outstanding problems. Gamma ray beams of the versatility, intensity, energy, and resolution that can be achieved at this facility are not currently available at any other world facility either existing or under construction. Furthermore, the proposed program would produce the first intense source of medium-energy {gamma} rays that are polarized. Because of the difficulties in producing such polarized beams, it is very unlikely that viable alternate sources can be developed in the near future; at present, no others are planned.

Sandorfi, A.M.; LeVine, M.J.; Thorn, C.E.; Giordano, G.; Matone, G.

1982-09-01T23:59:59.000Z

239

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

240

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

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

Central Fabrication Services | Brookhaven National Laboratory  

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

Central Fabrication Services Central Fabrication Services Home Management Staff Facilities Heavy Machine Shop Welding Shop Sheet Metal Shop Central Cleaning Facility CR X-Ray Facility Inspection Area Services Fabrication Services Group is committed to providing exceptional service to all of its customers. Safety is an integral part of our program and is in the foundation of everything we do. Fabrication Services is a full service proto type shop with production capabilities. Our facilities include machining, wire EDM, water jet cutting, orbital welding, welding, sheet metal, precision measurement, 3D printing, maintenance metal working, cleaning for UHV applications, and our newest addition Computed Radiography. Our capabilities include working on ultra-miniature parts to 20 ton assemblies. Our capability and range of services we provide is largely due

242

Rsum -Les mthodologies de Design for Assembly et de Design for Manufacturing visent rendre les produits plus faciles fabriquer et assembler en se basant sur les caractristiques des procds actuels de fabrication, toutefois ces  

E-Print Network (OSTI)

the new capabilities of Additive Manufacturing. This article describes a design methodology for Additive - Fabrication additive, conception, fabrication rapide, prototypage rapide. Keywords ­ Additive manufacturing, design, rapid manufacturing, rapid prototyping. 1 INTRODUCTION La Fabrication Additive (FA) est définie

Boyer, Edmond

243

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

244

New INL High Energy Battery Test Facility | Department of Energy  

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

INL High Energy Battery Test Facility New INL High Energy Battery Test Facility 2011 DOE Hydrogen and Fuel Cells Program, and Vehicle Technologies Program Annual Merit Review and...

245

NREL Battery Thermal and Life Test Facility | Department of Energy  

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

NREL Battery Thermal and Life Test Facility NREL Battery Thermal and Life Test Facility 2011 DOE Hydrogen and Fuel Cells Program, and Vehicle Technologies Program Annual Merit...

246

Post-test Cell Characterization Facility | Department of Energy  

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

test Cell Characterization Facility Post-test Cell Characterization Facility 2012 DOE Hydrogen and Fuel Cells Program and Vehicle Technologies Program Annual Merit Review and Peer...

247

The used nuclear fuel problem - can reprocessing and consolidated storage be complementary?  

SciTech Connect

This paper describes our CISF (Consolidated Interim Storage Facilities) and Reprocessing Facility concepts and show how they can be combined with a geologic repository to provide a comprehensive system for dealing with spent fuels in the USA. The performance of the CISF was logistically analyzed under six operational scenarios. A 3-stage plan has been developed to establish the CISF. Stage 1: the construction at the CISF site of only a rail receipt interface and storage pad large enough for the number of casks that will be received. The construction of the CISF Canister Handling Facility, the Storage Cask Fabrication Facility, the Cask Maintenance Facility and supporting infrastructure are performed during stage 2. The construction and placement into operation of a water-filled pool repackaging facility is completed for Stage 3. By using this staged approach, the capital cost of the CISF is spread over a number of years. It also allows more time for a final decision on the geologic repository to be made. A recycling facility will be built, this facility will used the NUEX recycling process that is based on the aqueous-based PUREX solvent extraction process, using a solvent of tri-N-butyl phosphate in a kerosene diluent. It is capable of processing spent fuels at a rate of 5 MT per day, at burn-ups up to 50 GWD per ton of spent fuels and a minimum of 5 years out-of-reactor cooling.

Phillips, C.; Thomas, I. [EnergySolutions Federal EPC., 2345 Stevens Drive, Richland, WA 99354 (United States)

2013-07-01T23:59:59.000Z

248

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

249

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

250

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

251

Sodium removal process development for LMFBR fuel subassemblies  

SciTech Connect

Two 37-pin scale models of Clinch River Breeder Reactor Plant fuel subassemblies were designed, fabricated and used at Westinghouse Advanced Reactors Division in the development and proof-testing of a rapid water-based sodium removal process for the ORNL Hot Experimental Facility, Liquid Metal Fast Breeder Reactor Fuel Reprocessing Cycle. Through a series of development tests on one of the models, including five (5) sodium wettings and three (3) high temperature sodium removal operations, optimum process parameters for a rapid water vapor-argon-water rinse process were identified and successfully proof-tested on a second model containing argon-pressurized, sodium-corroded model fuel pins simulating the gas plenum and cladding conditions expected for spent fuel pins in full scale subassemblies. Based on extrapolations of model proof test data, preliminary process parameters for a water vapor-nitrogen-water rinse process were calculated and recommended for use in processing full scale fuel subassemblies in the Sodium Removal Facility of the Fuel Receiving Cell, ORNL HEF.

Simmons, C.R.; Taylor, G.R.

1981-10-01T23:59:59.000Z

252

Fuel Cell Technologies Office: Procuring Fuel Cells for Stationary Power: A  

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

Procuring Fuel Cells Procuring Fuel Cells for Stationary Power: A Guide for Federal Facility Decision Makers (Text Version) to someone by E-mail Share Fuel Cell Technologies Office: Procuring Fuel Cells for Stationary Power: A Guide for Federal Facility Decision Makers (Text Version) on Facebook Tweet about Fuel Cell Technologies Office: Procuring Fuel Cells for Stationary Power: A Guide for Federal Facility Decision Makers (Text Version) on Twitter Bookmark Fuel Cell Technologies Office: Procuring Fuel Cells for Stationary Power: A Guide for Federal Facility Decision Makers (Text Version) on Google Bookmark Fuel Cell Technologies Office: Procuring Fuel Cells for Stationary Power: A Guide for Federal Facility Decision Makers (Text Version) on Delicious Rank Fuel Cell Technologies Office: Procuring Fuel Cells for

253

Fuel Cycle Options for Optimized Recycling of Nuclear Fuel  

E-Print Network (OSTI)

The reduction of transuranic inventories of spent nuclear fuel depends upon the deployment of advanced fuels that can be loaded with recycled transuranics (TRU), and the availability of facilities to separate and reprocess ...

Aquien, A.

254

Diversion scenarios in an aqueous reprocessing facility  

E-Print Network (OSTI)

The International Atomic Energy Agency requires nuclear facilities around the world to abide by heavily enforced safeguards to prevent proliferation. Nuclear fuel reprocessing facilities are designed to be proliferation-resistant ...

Calderón, Lindsay Lorraine

2009-01-01T23:59:59.000Z

255

Services | Central Fabrication Services | Brookhaven National Laboratory  

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

Services & Capabilities Services & Capabilities The Central Fabrication Services Division's capabilities range from an Electric Discharge Machining (EDM) capability, to a state of the art cleaning facility, to a large fabricating facility which includes CNC Machining, Automatic Tube Welding, CNC Punch Press capability, and 3-D printing. CNC Auto Feed Saw High Bay Area 3-D Printer Main Shop, Building 479 Maintenance Sheet Metal Area Water Jet Machine X-ray Generating Tube CR X-ray Processor with High Resolution Monitor Low Bay Area in Machine Shop Wire EDM Machine Wire EDM Machine Oil Recycling Facility, Building 495 UHV Cleaning Facility, Building 498 Material Storage and Stock Central Fabrication Services is proud of it's highly proficient technical staff all of which are available, at no cost to the customer, for

256

Development of a nuclear fuel cycle transparency framework.  

SciTech Connect

Nuclear fuel cycle transparency can be defined as a confidence building approach among political entities to ensure civilian nuclear facilities are not being used for the development of nuclear weapons. Transparency concepts facilitate the transfer of nuclear technology, as the current international political climate indicates a need for increased methods of assuring non-proliferation. This research develops a system which will augment current non-proliferation assessment activities undertaken by U.S. and international regulatory agencies. It will support the export of nuclear technologies, as well as the design and construction of Gen. IV energy systems. Additionally, the framework developed by this research will provide feedback to cooperating parties, thus ensuring full transparency of a nuclear fuel cycle. As fuel handling activities become increasingly automated, proliferation or diversion potential of nuclear material still needs to be assessed. However, with increased automation, there exists a vast amount of process data to be monitored. By designing a system that monitors process data continuously, and compares this data to declared process information and plant designs, a faster and more efficient assessment of proliferation risk can be made. Figure 1 provides an illustration of the transparency framework that has been developed. As shown in the figure, real-time process data is collected at the fuel cycle facility; a reactor, a fabrication plant, or a recycle facility, etc. Data is sent to the monitoring organization and is assessed for proliferation risk. Analysis and recommendations are made to cooperating parties, and feedback is provided to the facility. The analysis of proliferation risk is based on the following factors: (1) Material attractiveness: the quantification of factors relevant to the proliferation risk of a certain material (e.g., highly enriched Pu-239 is more attractive than that of lower enrichment) (2) The static (baseline) risk: the quantification of risk factors regarding the expected value of proliferation risk under normal (not proliferating) operations. (3) The dynamic (changing) risk: the quantification of risk factors regarding the observed value of proliferation risk, based on monitor signals from facility operations. This framework could be implemented at facilities which have been exported (for instance, to third world countries), or facilities located in sensitive countries. Sandia National Laboratories is currently working with the Japan Nuclear Cycle Development Institute (JNC) to implement a demonstration of nuclear fuel cycle transparency technology at the Fuel Handling Training Model designed for the Monju Fast Reactor at the International Cooperation and Development Training Center in Japan. This technology has broad applications, both in the U.S. and abroad. Following the demonstration, we expect to begin further testing of the technology at an Enrichment Facility, a Fast Reactor, and at a Recycle Facility.

Love, Tracia L.

2005-04-01T23:59:59.000Z

257

Coupling fuel cycles with repositories: how repository institutional choices may impact fuel cycle design  

SciTech Connect

The historical repository siting strategy in the United States has been a top-down approach driven by federal government decision making but it has been a failure. This policy has led to dispatching fuel cycle facilities in different states. The U.S. government is now considering an alternative repository siting strategy based on voluntary agreements with state governments. If that occurs, state governments become key decision makers. They have different priorities. Those priorities may change the characteristics of the repository and the fuel cycle. State government priorities, when considering hosting a repository, are safety, financial incentives and jobs. It follows that states will demand that a repository be the center of the back end of the fuel cycle as a condition of hosting it. For example, states will push for collocation of transportation services, safeguards training, and navy/private SNF (Spent Nuclear Fuel) inspection at the repository site. Such activities would more than double local employment relative to what was planned for the Yucca Mountain-type repository. States may demand (1) the right to take future title of the SNF so if recycle became economic the reprocessing plant would be built at the repository site and (2) the right of a certain fraction of the repository capacity for foreign SNF. That would open the future option of leasing of fuel to foreign utilities with disposal of the SNF in the repository but with the state-government condition that the front-end fuel-cycle enrichment and fuel fabrication facilities be located in that state.

Forsberg, C. [Massachusetts Institute of Technology, 77 Massachusetts Ave., Room 24-207A Cambridge, MA 02139 (United States); Miller, W.F. [Texas A.M. University System, MS 3133 College Station, TX 77843-3133 (United States)

2013-07-01T23:59:59.000Z

258

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

259

Subject: Integrated Safety Analysis: Why It Is Appropriate for Fuel Recycling Facilities Project Number: 689Nuclear Energy Institute (NEI) Letter, 9/10/10  

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

Enclosed for your review is a Nuclear Energy Institute white paper on the use of Integrated Safety Analysis (ISA) at U.S. Nuclear Regulatory Commission-licensed recycling facilities. This paper is...

260

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

Note: This page contains sample records for the topic "fuel fabrication facility" 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 and Advanced Vehicles Data Center (EERE)

to a facility so that it may sell diesel fuel containing at least 2% biodiesel or green diesel. A retailer may only claim the credit for up to five years and is limited to...

262

Hydrogen Fuel Cell Engines and Related Technologies Course Manual...  

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

Module 10: Maintenance and Fueling Facility Guidelines Module 11: Glossary and Conversions Home About the Fuel Cell Technologies Office Hydrogen Production Hydrogen Delivery...

263

Analysis of a Nuclear Accident: Fission and Activation Product Releases from the Fukushima Daiichi Nuclear Facility as Remote Indicators of Source Identification, Extent of Release, and State of Damaged Spent Nuclear Fuel  

SciTech Connect

Measurements of several radionuclides within environmental samples taken from the Fukushima Daiichi nuclear facility and reported on the Tokyo Electric Power Company website following the recent tsunami-initiated catastrophe were evaluated for the purpose of identifying the source term, reconstructing the release mechanisms, and estimating the extent of the release. 136Cs/137Cs and 134Cs/137Cs ratios identified Units 1-3 as the major source of radioactive contamination to the surface soil close to the facility. A trend was observed between the fraction of the total core inventory released for a number of fission product isotopes and their corresponding Gibbs Free Energy of formation for the primary oxide form of the isotope, suggesting that release was dictated primarily by chemical volatility driven by temperature and reduction potential within the primary containment vessels of the vented reactors. The absence of any major fractionation beyond volatilization suggested all coolant had evaporated by the time of venting. High estimates for the fraction of the total inventory released of more volatile species (Te, Cs, I) indicated the damage to fuel bundles was likely extensive, minimizing any potential containment due to physical migration of these species through the fuel matrix and across the cladding wall. 238Pu/239,240Pu ratios close-in and at 30 km from the facility indicated that the damaged reactors were the major contributor of Pu to surface soil at the source but that this contribution likely decreased rapidly with distance from the facility. The fraction of the total Pu inventory released to the environment from venting units 1 and 3 was estimated to be ~0.003% based upon Pu/Cs isotope ratios relative to the within-reactor modeled inventory prior to venting and was consistent with an independent model evaluation that considered chemical volatility based upon measured fission product release trends. Significant volatile radionuclides within the spent fuel at the time of venting but not as yet observed and reported within environmental samples are suggested as potential analytes of concern for future environmental surveys around the site.

Schwantes, Jon M.; Orton, Christopher R.; Clark, Richard A.

2012-09-10T23:59:59.000Z

264

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

265

NETL's Hybrid Performance, or Hyper, facility  

ScienceCinema (OSTI)

NETL's Hybrid Performance, or Hyper, facility is a one-of-a-kind laboratory built to develop control strategies for the reliable operation of fuel cell/turbine hybrids and enable the simulation, design, and implementation of commercial equipment. The Hyper facility provides a unique opportunity for researchers to explore issues related to coupling fuel cell and gas turbine technologies.

None

2014-06-26T23:59:59.000Z

266

LANSCE | Facilities  

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

Isotope Production Facility (IPF) Lujan Neutron Scattering Center Materials Test Station (MTS) Proton Radiography (pRad) Ultracold Neutrons (UCN) Weapons Neutron Research Facility...

267

Underground Facilities Information (Iowa) | Department of Energy  

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

Facilities Information (Iowa) Facilities Information (Iowa) Underground Facilities Information (Iowa) < Back Eligibility Agricultural Commercial Construction Fuel Distributor Industrial Installer/Contractor Institutional Investor-Owned Utility Low-Income Residential Multi-Family Residential Municipal/Public Utility Residential Transportation Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Solar Wind Program Info State Iowa Program Type Environmental Regulations Provider Iowa Utilities Board This section applies to any excavation which may impact underground facilities, including those used for the conveyance of electricity or the transportation of hazardous liquids or natural gas. Excavation is prohibited unless notification takes place, as described in this chapter

268

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

269

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

270

ARM - Facility News Article  

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

December 3, 2004 [Facility News] December 3, 2004 [Facility News] First Deployment of ARM Mobile Facility to Occur on California Coast Bookmark and Share Image - Point Reyes Beach Image - Point Reyes Beach Point Reyes National Seashore, on the California coast north of San Francisco, has been identified as the official location for the first deployment of the DOE's Atmospheric Radiation Measurement (ARM) Mobile Facility (AMF). As part of a 6-month field campaign beginning in March 2005 to study the microphysical characteristics of marine stratus and, in particular, marine stratus drizzle processes, the AMF will provide a mature instrument system to help fill information gaps in the existing limited surveys of marine stratus microphysical structure. Marine stratus clouds are known to be susceptible to the byproducts of fossil fuel consumption, a

271

Argonne Transportation Technology R&D Center - Research Facilities - APRF,  

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

Transportation Research Facilities Transportation Research Facilities Argonne provides a wide range of facilities and laboratories for conducting cutting-edge transportation research and testing. The facilities offer state-of-the-art equipment and capabilities. APRF Advanced Powertrain Research Facility Battery Post-Test Facility Battery Post-Test Facility Battery testing at the EADL Electrochemical Analysis and Diagnostics Laboratory Engine Research Facility Engine Research Facility Fuel cell research Fuel Cell Test Facility Materials Engineering Research Facility Materials Engineering Research Facility Transportation APS Beamline Transportation Beamline at Argonne's Advanced Photon Source tribology lab Tribology Laboratory TRACC Transportation Research and Analysis Computing Center

272

NEPA REVIE\ry LASO-10-001 CATEGORICAL EXCLUSION FUELS RESEARCH LAB AT TA-35.455  

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

REVIE\ry REVIE\ry LASO-10-001 CATEGORICAL EXCLUSION FUELS RESEARCH LAB AT TA-35.455 I. DESCRIPTION OF PROPOSED ACTION: Los Alamos National Laboratory proposes to modify an existing laboratory for a Fuels Research Lab (455-FRL). The laboratory would be used to fabricate and characterize fuel pellets. The proposed activities would take place at the former location of the Polymers & Coating Lab (PCL) located at TA-35, Building 455, in room 104. Authorization would need to be obtained for the processing of radioactive materials in this location. The current laboratory configuration of chilled water supply and return, gas, compressed air, and vacuum supply, electrical supply, HEPA filtration, and ventilation would be assessed and modified to suit 455- TPCL facility needs. Analytical and process equipment would be required for this facility. Glovebox

273

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

274

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

275

A framework for nuclear facility safeguard evaluation using probabilistic methods and expert elicitation .  

E-Print Network (OSTI)

??With the advancement of the next generation of nuclear fuel cycle facilities, concerns of the effectiveness of nuclear facility safeguards have been increasing due to… (more)

Iamsumang, Chonlagarn

2010-01-01T23:59:59.000Z

276

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...

277

Energy Conversion and Transmission Facilities (South Dakota) | Department  

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

Energy Conversion and Transmission Facilities (South Dakota) Energy Conversion and Transmission Facilities (South Dakota) Energy Conversion and Transmission Facilities (South Dakota) < Back Eligibility Utility Commercial Investor-Owned Utility Industrial Construction Municipal/Public Utility Installer/Contractor Rural Electric Cooperative Retail Supplier Institutional Systems Integrator Fuel Distributor Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State South Dakota Program Type Siting and Permitting Provider South Dakota Public Utilities Commission This legislation applies to energy conversion facilities designed for or capable of generating 100 MW or more of electricity, wind energy facilities with a combined capacity of 100 MW, certain transmission facilities, and

278

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.

279

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...

280

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

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

VISION User Guide - VISION (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; 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 for U.S. nuclear power. 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 of 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. Note that recovered uranium is itself often partitioned: some RU flows with recycled transuranic elements, some flows with wastes, and the rest is designated RU. RU comes out of storage if needed to correct the U/TRU ratio in new recycled fuel. Neither RU nor DU are designated as wastes. 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. We use Microsoft Excel 2003 and have not tested VISION with Microsoft Excel 2007. The VISION team uses both Powersim Studio 2005 and 2009 and it should work with either.

Jacob J. Jacobson; Robert F. Jeffers; Gretchen E. Matthern; Steven J. Piet; Benjamin A. Baker; Joseph Grimm

2009-08-01T23:59:59.000Z

282

MDF | Manufacturing Demonstration Facility | ORNL  

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

BTRIC CNMS CSMB CFTF HFIR MDF Working with MDF NTRC OLCF SNS Titanium robotic hand holding sphere fabricated using additive manufacturing Home | User Facilities | MDF MDF | Manufacturing Demonstration Facility SHARE As the nation's premier research laboratory, ORNL is one of the world's most capable resources for transforming the next generation of scientific discovery into solutions for rebuilding and revitalizing America's manufacturing industries. Manufacturing industries engage ORNL's expertise in materials synthesis, characterization, and process technology to reduce technical risk and validate investment for innovations targeting products of the future. DOE's Manufacturing Demonstration Facility, established at ORNL, helps industry adopt new manufacturing technologies to reduce life-cycle energy

283

MDF | Manufacturing Demonstration Facility | ORNL  

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

Working with MDF Working with MDF Titanium robotic hand holding sphere fabricated using additive manufacturing Home | User Facilities | MDF MDF | Manufacturing Demonstration Facility SHARE As the nation's premier research laboratory, ORNL is one of the world's most capable resources for transforming the next generation of scientific discovery into solutions for rebuilding and revitalizing America's manufacturing industries. Manufacturing industries engage ORNL's expertise in materials synthesis, characterization, and process technology to reduce technical risk and validate investment for innovations targeting products of the future. DOE's Manufacturing Demonstration Facility, established at ORNL, helps industry adopt new manufacturing technologies to reduce life-cycle energy

284

Facility Safety  

Directives, Delegations, and Requirements

Establishes facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation.

1996-10-24T23:59:59.000Z

285

Facility Safety  

Directives, Delegations, and Requirements

Establishes facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation.

1995-11-16T23:59:59.000Z

286

Certified Facilities  

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

Industrial Leaders: The industrial facilities shown below are among the first to earn certification for Superior Energy Performance® (SEP™).

287

The Results From the First High-Pressure Melt Ejection Test Completed in the Molten Fuel Moderator Interaction Facility at Chalk River Laboratories  

SciTech Connect

A high-pressure melt ejection test using prototypical corium was conducted at Atomic Energy of Canada Limited Chalk River Laboratories. This test was planned by the CANDU Owners Group to study the potential for an energetic interaction between molten fuel and water under postulated single-channel flow-blockage events. The experiments were designed to address regulator concerns surrounding this very low probability postulated accident events in CANDU Pressurized Heavy Water Reactors. The objective of the experimental program is to determine whether a highly energetic 'steam explosion' and associated high-pressure pulse, is possible when molten material is finely fragmented as it is ejected from a fuel channel into the heavy-water moderator. The finely fragmented melt particles would transfer energy to the moderator as it is dispersed, creating a modest pressure pulse in the calandria vessel. The high-pressure melt ejection test consisted of heating up a {approx} 5 kg thermite mixture of U, U{sub 3}O{sub 8}, Zr, and CrO{sub 3} inside a 1.14-m length of insulated pressure tube. When the molten material reached the desired temperature of {approx} 2400 deg C, the pressure inside the tube was raised to 11.6 MPa, failing the pressure tube at a pre-machined flaw, and releasing the molten material into the surrounding tank of 68 deg C water. The experiment investigated the dynamic pressure history, debris size, and the effects of the material interacting with tubes representing neighbouring fuel channels. The measured mean particle size was 0.686 mm and the peak dynamic pressures were between 2.54 and 4.36 MPa, indicating that an energetic interaction between the melt and the water did not occur in the test. (authors)

Nitheanandan, T.; Kyle, G.; O'Connor, R.; Sanderson, DB. [Chalk River Laboratories, Atomic Energy of Canada Limited, Chalk River, Ontario, Canada, K0J 1J0 (Canada)

2006-07-01T23:59:59.000Z

288

18 years experience on UF{sub 6} handling at Japanese nuclear fuel manufacturer  

SciTech Connect

In the spring of 1991, a leading nuclear fuel manufacturing company in Japan, celebrated its 18th anniversary. Since 1973, the company has produced over 5000 metric ton of ceramic grade UO{sub 2} powder to supply to Japanese fabricators, without major accident/incident and especially with a successful safety record on UF{sub 6} handling. The company`s 18 years experience on nuclear fuel manufacturing reveals that key factors for the safe handling of UF{sub 6} are (1) installing adequate facilities, equipped with safety devices, (2) providing UF{sub 6} handling manuals and executing them strictly, and (3) repeating on and off the job training for operators. In this paper, equipment and the operation mode for UF{sub 6} processing at their facility are discussed.

Fujinaga, H.; Yamazaki, N.; Takebe, N. [Japan Nucelar Fuel Conversion Co., Ltd., Ibaraki (Japan)

1991-12-31T23:59:59.000Z

289

Use of CAP88 PC to infer differences in the chemical form of I-129 emitted from a fuel reprocessing facility  

SciTech Connect

Emissions of 129I from nuclear fuel separations conducted at the Hanford Site in Washington State have been occurring since the 1940’s. Fuel separation on the Hanford Site stopped in 1988, but emissions of 129I have continued as venting of the building occurred. In this study, atmospheric measurements of 129I concentrations were coupled with an EPA approved plume dispersion model (CAP-88PC) to evaluate the effectiveness of the dispersion model for estimating ambient concentrations at the Hanford Site. This evaluation led to the hypothesis of different chemical forms of iodine being emitted over the years; this hypothesis was developed as an explanation for the model agreeing with measurements over some time periods, but not over all time periods. The model was then run with modified emissions to simulate the short atmospheric half-life of the suspected reactive chemical form of iodine being emitted. This modification resulted in good agreement between the modeled and measured concentrations over the entire 20 year study period, and provided evidence that the hypothesis of a reactive form of iodine being emitted was correct.

Fritz, Brad G.; Phillips, Nathan RJ

2013-06-17T23:59:59.000Z

290

Independent Oversight Review, Hanford K Basin and Cold Vacuum Drying Facility- August 2012  

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

Review of Hanford K Basin and Cold Vacuum Drying Facility Found Fuel Multi-Canister Overpack Operations

291

NREL: Hydrogen and Fuel Cells Research - Webmaster  

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

Your name: Your email address: Your message: Send Message Printable Version Hydrogen & Fuel Cells Research Home Projects Success Stories Research Staff Facilities Working with Us...

292

NREL: Electricity Integration Research - Facilities  

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

Facilities Facilities NREL's electricity integration research is conducted in state-of-the-art facilities. These facilities assist industry in the development of power systems and address the operational challenges of full system integration. The Energy Systems Integration Facility can be used to design, test, and analyze components and systems to enable economic, reliable integration of renewable electricity, fuel production, storage, and building efficiency technologies with the U.S. electricity delivery infrastructure. New grid integration capabilities at the National Wind Technology Center will allow testing of many grid integration aspects of multi-megawatt, utility-scale variable renewable generation and storage technologies. The Distributed Energy Resources Test Facility can be used to characterize,

293

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

294

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

295

Occupational dose reduction at Department of Energy contractor facilities: Bibliography of selected readings in radiation protection and ALARA  

SciTech Connect

This bibliography contains abstracts relating to various aspects of ALARA program implementation and dose reduction activities, with a focus on DOE facilities. Abstracts included in this bibliography were selected from proceedings of technical meetings, journals, research reports, searches of the DOE Energy, Science and Technology Database (in general, the citation and abstract information is presented as obtained from this database), and reprints of published articles provided by the authors. Facility types and activities covered in the scope of this report include: radioactive waste, uranium enrichment, fuel fabrication, spent fuel storage and reprocessing, facility decommissioning, hot laboratories, tritium production, research, test and production reactors, weapons fabrication and testing, fusion, uranium and plutonium processing, radiography, and aocelerators. Information on improved shielding design, decontamination, containments, robotics, source prevention and control, job planning, improved operational and design techniques, as well as on other topics, has been included. In addition, DOE/EH reports not included in previous volumes of the bibliography are in this volume (abstracts 611 to 684). This volume (Volume 5 of the series) contains 217 abstracts. An author index and a subject index are provided to facilitate use. Both indices contain the abstract numbers from previous volumes, as well as the current volume. Information that the reader feels might be included in the next volume of this bibliography should be submitted to the BNL ALARA Center.

Dionne, B.J.; Sullivan, S.G.; Baum, J.W.

1993-12-01T23:59:59.000Z

296

Facility Interface Capability Assessment (FICA) summary report  

SciTech Connect

The Office of Civilian Radioactive Waste Management (OCRWM) is responsible for developing the Civilian Radioactive Waste Management System (CRWMS) to accept spent nuclear fuel from the commercial facilities. In support of the development of the CRWMS, OCRWM sponsored the Facility Interface Capability Assessment (FICA) project. The objective of this project was to assess the capability of each commercial facility to handle various spent nuclear fuel shipping casks. The purpose of this report is to summarize the results of the facility assessments completed within the FICA project. The project was conducted in two phases. During Phase I, the data items required to complete the facility assessments were identified and the data base for the project was created. During Phase II, visits were made to 122 facilities on 76 sites to collect data and information, the data base was updated, and assessments of the cask-handling capabilities at each facility were performed.

Viebrock, J.M.; Mote, N. [Nuclear Assurance Corp., Norcross, GA (United States); Pope, R.B. [ed.] [Oak Ridge National Lab., TN (United States)

1992-05-01T23:59:59.000Z

297

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)

298

Science Facilities  

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

Electron Microscopy Lab Ion Beam Materials Lab Matter-Radiation Interactions in Extremes (MaRIE) Proton Radiography Trident Laser Facility LOOK INTO LANL - highlights...

299

Alternative Fuels Data Center: Ryder Opens Natural Gas Vehicle Maintenance  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Ryder Opens Natural Ryder Opens Natural Gas Vehicle Maintenance Facility to someone by E-mail Share Alternative Fuels Data Center: Ryder Opens Natural Gas Vehicle Maintenance Facility on Facebook Tweet about Alternative Fuels Data Center: Ryder Opens Natural Gas Vehicle Maintenance Facility on Twitter Bookmark Alternative Fuels Data Center: Ryder Opens Natural Gas Vehicle Maintenance Facility on Google Bookmark Alternative Fuels Data Center: Ryder Opens Natural Gas Vehicle Maintenance Facility on Delicious Rank Alternative Fuels Data Center: Ryder Opens Natural Gas Vehicle Maintenance Facility on Digg Find More places to share Alternative Fuels Data Center: Ryder Opens Natural Gas Vehicle Maintenance Facility on AddThis.com... June 28, 2011 Ryder Opens Natural Gas Vehicle Maintenance Facility

300

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

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

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

302

December 5, 2005 Facilities Management Department  

E-Print Network (OSTI)

in areas adjacent to smoker's stations and will deposit all cigarette butts in smoker's stations. Grounds within 50 feet of gas pumps and other fueling areas. Philip Jones Associate Vice Chancellor Facilities

Howitt, Ivan

303

Applying x-ray digital imaging to the verification of cadmium in fuel-storage components  

SciTech Connect

The High Flux Isotope Reactor utilizes large underwater fuel-storage arrays to stage irradiated fuel before it is shipped from the facility. Cadmium is required as a thermal neutron absorber in these fuel-storage arrays to produce an acceptable margin of nuclear subcriticality during both normal and off-normal operating conditions. Due to incomplete documentation from the time of their fabrication, the presence of cadmium within two stainless-steel parts of fuel-storage arrays must be experimentally verified before they are reused in new fuel-storage arrays. A cadmium-verification program has been developed in association with the Waste Examination and Assay Facility located at the Oak Ridge national Laboratory to nondestructively examine these older shroud assemblies. The program includes the following elements (1) x-ray analog imaging, (2) x-ray digital imaging, (3) prompt-gamma-ray spectroscopy measurements, and (4) neutron-transmission measurements. X-ray digital imaging utilizes an analog-to-digital convertor to record attenuated x-ray intensities observed on a fluorescent detector by a video camera. These x-ray intensities are utilized in expressions for cadmium thickness based upon x-ray attenuation theory.

Dabbs, R.D.; Cook, D.H.

1997-03-01T23:59:59.000Z

304

Fuel cycle options for optimized recycling of nuclear fuel  

E-Print Network (OSTI)

The accumulation of transuranic inventories in spent nuclear fuel depends on both deployment of advanced reactors that can be loaded with recycled transuranics (TRU), and on availability of the facilities that separate and ...

Aquien, Alexandre

2006-01-01T23:59:59.000Z

305

Facility Safety  

Directives, Delegations, and Requirements

This Order establishes facility and programmatic safety requirements for Department of Energy facilities, which includes nuclear and explosives safety design criteria, fire protection, criticality safety, natural phenomena hazards mitigation, and the System Engineer Program. Cancels DOE O 420.1A. DOE O 420.1B Chg 1 issued 4-19-10.

2005-12-22T23:59:59.000Z

306

Mobile Facility  

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

Facility Facility AMF Information Science Architecture Baseline Instruments AMF1 AMF2 AMF3 Data Operations AMF Fact Sheet Images Contacts AMF Deployments Hyytiälä, Finland, 2014 Manacapuru, Brazil, 2014 Oliktok Point, Alaska, 2013 Los Angeles, California, to Honolulu, Hawaii, 2012 Cape Cod, Massachusetts, 2012 Gan Island, Maldives, 2011 Ganges Valley, India, 2011 Steamboat Springs, Colorado, 2010 Graciosa Island, Azores, 2009-2010 Shouxian, China, 2008 Black Forest, Germany, 2007 Niamey, Niger, 2006 Point Reyes, California, 2005 Mobile Facilities Pictured here in Gan, the second mobile facility is configured in a standard layout. Pictured here in Gan, the second mobile facility is configured in a standard layout. To explore science questions beyond those addressed by ARM's fixed sites at

307

Procuring Fuel Cells for Stationary Power: A Guide for Federal Decision Makers  

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

Presentation slides from the May 8, 2012, Fuel Cell Technologies Program webinar, Procuring Fuel Cells for Stationary Power: A Guide for Federal Facility Decision Makers.

308

The Business Case for Fuel Cells 2010: Why Top Companies are Purchasing Fuel Cells Today  

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

This report profiles companies and corporations that are deploying or demonstrating fuel cells for power in warehouses, stores, manufacturing facilities, hotels, and telecommunications sites.

309

Lignite Fuel Enhancement  

SciTech Connect

This 11th quarterly Technical Progress Report for the Lignite Fuel Enhancement Project summarizes activities from January 1st through March 31st of 2007. It summarizes the completion of the Prototype testing activity and initial full-scale dryer design, Budget Period 2 activity during that time period. The Design Team completed process design and layouts of air, water, and coal systems. Heyl-Patterson completed dryer drawings and has sent RFPs to several fabricators for build and assembly. Several meetings were held with Barr engineers to finalize arrangement of the drying, air jig, and coal handling systems. Honeywell held meetings do discuss the control system logic and hardware location. By the end of March we had processed nearly 300,000 tons of lignite through the dryer. Outage preparation maintenance activities on a coal transfer hopper restricted operation of the dryer in February and March. The Outage began March 17th. We will not dry coal again until early May when the Outage on Unit No.2 completes. The Budget Period 1 (Phase 1) final report was submitted this quarter. Comments were received from NETL and are being reviewed. The Phase 2 Project Management Plan was submitted to NETL in January 2007. This deliverable also included the Financing Plan. An application for R&D 100 award was submitted in February. The project received an award from the Minnesota Professional Engineering Society's Seven Wonders of Engineering Award and Minnesota ACEC Grand Award in January. To further summarize, the focus this quarter has been on finalizing commercial design and the layout of four dryers behind each Unit. The modification to the coal handling facilities at Coal Creek and incorporation of air jigs to further beneficiate the segregated material the dryers will reject 20 to 30 % of the mercury and sulfur is segregated however this modification will recover the carbon in that stream.

Charles Bullinger

2007-03-31T23:59:59.000Z

310

Remote Facilities | Department of Energy  

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

Remote Facilities Remote Facilities Remote Facilities October 16, 2013 - 4:55pm Addthis Renewable Energy Options for Renovations in Remote Areas Photovoltaics (PV) Small Wind Daylighting Solar Water Heating Passive Solar Design Biomass Heating When a Federal building or facility is located away from existing power lines, many renewable energy technologies including photovoltaics and wind become cost-effective options when compared to extending utilities or transporting fuel for onsite generators. Photovoltaics Photovoltaics (PV) are often cost-effective in remote power applications. In these circumstances, the system is coupled with batteries and can provide complete facility power. Proper system design is critical and must account for the building electrical loads and be sized to meet that load

311

Virginia Regional Industrial Facilities Act (Virginia) | Department of  

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

Regional Industrial Facilities Act (Virginia) Regional Industrial Facilities Act (Virginia) Virginia Regional Industrial Facilities Act (Virginia) < Back Eligibility Commercial Construction Developer Industrial Investor-Owned Utility Local Government Municipal/Public Utility Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State Virginia Program Type Industry Recruitment/Support Provider Regional Industrial Facility Authorities The Virginia Regional Industrial Facilities Act is meant to aid the economic development of localities within the Commonwealth. The Act provides a mechanism for localities to establish regional industrial facility authorities, enabling them to pool financial resources to stimulate economic development. The purpose of a regional industrial

312

Development of a Low NOx Medium sized Industrial Gas Turbine Operating on Hydrogen-Rich Renewable and Opportunity Fuels  

SciTech Connect

This report presents the accomplishments at the completion of the DOE sponsored project (Contract # DE-FC26-09NT05873) undertaken by Solar Turbines Incorporated. The objective of this 54-month project was to develop a low NOx combustion system for a medium sized industrial gas turbine engine operating on Hydrogen-rich renewable and opportunity Fuels. The work in this project was focused on development of a combustion system sized for 15MW Titan 130 gas turbine engine based on design analysis and rig test results. Although detailed engine evaluation of the complete system is required prior to commercial application, those tasks were beyond the scope of this DOE sponsored project. The project tasks were organized in three stages, Stages 2 through 4. In Stage 2 of this project, Solar Turbines Incorporated characterized the low emission capability of current Titan 130 SoLoNOx fuel injector while operating on a matrix of fuel blends with varying Hydrogen concentration. The mapping in this phase was performed on a fuel injector designed for natural gas operation. Favorable test results were obtained in this phase on emissions and operability. However, the resulting fuel supply pressure needed to operate the engine with the lower Wobbe Index opportunity fuels would require additional gas compression, resulting in parasitic load and reduced thermal efficiency. In Stage 3, Solar characterized the pressure loss in the fuel injector and developed modifications to the fuel injection system through detailed network analysis. In this modification, only the fuel delivery flowpath was modified and the air-side of the injector and the premixing passages were not altered. The modified injector was fabricated and tested and verified to produce similar operability and emissions as the Stage 2 results. In parallel, Solar also fabricated a dual fuel capable injector with the same air-side flowpath to improve commercialization potential. This injector was also test verified to produce 15-ppm NOx capability on high Hydrogen fuels. In Stage 4, Solar fabricated a complete set of injectors and a combustor liner to test the system capability in a full-scale atmospheric rig. Extensive high-pressure single injector rig test results show that 15-ppm NOx guarantee is achievable from 50% to 100% Load with fuel blends containing up to 65% Hydrogen. Because of safety limitations in Solar Test Facility, the atmospheric rig tests were limited to methane-based fuel blends. Further work to validate the durability and installed engine capability would require long-term engine field test.

Srinivasan, Ram

2013-07-31T23:59:59.000Z

313

Consolidated Fuel-Reprocessing Program. Progress report, April 1 to June 30, 1983  

SciTech Connect

All research and development on fuel reprocessing in the United States is managed under the Consolidated Fuel Reprocessing Program. Technical progress is reported in overview fashion. Conceptual studies for the proposed Breeder Reprocessing Engineering Test (BRET) have continued. Studies to date have confirmed the feasibility of modifying an existing DOE facility at Hanford, Washington. A study to measure the extent of plutonium polymerization during steam-jet transfers of nitric acid solutions indicated polymer would appear only after several successive transfers at temperatures of 75/sup 0/C or higher. Fast-Flux Test Facility fuel was processed for the first time in the Solvent Extraction Test Facility. Studies of krypton release from pulverized sputter-deposited Ni-Y-Kr matrices have shown that the release rate is inversely proportional to the particle radius at 200/sup 0/C. Preparation of the initial 500-g batch of mixed oxide gel-spheres was completed. Fabrication processing at HEDL of mixed oxide gel-spheres (DIPRES process) was initiated. Operational testing of both 8 packs of the centrifugal contactor has been completed. Fabrication of both the prototypical disassembly system and the prototypical shear system has been initiated. Planning for FY 1984 installation and modification work in the integrated equipment list facility was completed. Acceptance tests of the original Integrated Process Demonstration system have been completed. Instrumentation and controls work with the prototype multiwavelength uranium photometer was successful and has been expanded to continuously and simultaneously monitor three process streams (raffinate, aqueous feed, and organic strip) in the secondary extraction cycle. Major efforts of the environmental, safeguards, and waste management areas were directed toward providing data for BRET.

Not Available

1983-08-01T23:59:59.000Z

314

NETL- Severe Environment Corrosion Erosion Facility  

SciTech Connect

NETL's Severe Environment Corrosion Erosion Facility in Albany studies how new and old materials will stand up to new operating conditions. Work done in the lab supports NETL's oxy-fuel combustion oxidation work, refractory materials stability work, and the fuels program, in particular the hydrogen membrane materials stability work, to determine how best to upgrade existing power plants.

None

2013-09-12T23:59:59.000Z

315

NETL- Severe Environment Corrosion Erosion Facility  

ScienceCinema (OSTI)

NETL's Severe Environment Corrosion Erosion Facility in Albany studies how new and old materials will stand up to new operating conditions. Work done in the lab supports NETL's oxy-fuel combustion oxidation work, refractory materials stability work, and the fuels program, in particular the hydrogen membrane materials stability work, to determine how best to upgrade existing power plants.

None

2014-06-16T23:59:59.000Z

316

Occupational dose reduction at Department of Energy contractor facilities: Bibliography of selected readings in radiation protection and ALARA; Volume 5  

SciTech Connect

Promoting the exchange of information related to implementation of the As Low as Reasonably Achievable (ALARA) philosophy is a continuing objective for the Department of Energy (DOE). This report was prepared by the Brookhaven National Laboratory (BNL) ALARA Center for the DOE Office of Health. It contains the fifth in a series of bibliographies on dose reduction at DOE facilities. The BNL ALARA Center was originally established in 1983 under the sponsorship of the Nuclear Regulatory Commission to monitor dose-reduction research and ALARA activities at nuclear power plants. This effort was expanded in 1988 by the DOE`s Office of Environment, Safety and Health, to include DOE nuclear facilities. This bibliography contains abstracts relating to various aspects of ALARA program implementation and dose-reduction activities, with a specific focus on DOE facilities. Abstracts included in this bibliography were selected from proceedings of technical meetings, journals, research reports, searches of the DOE Energy, Science and Technology Database (in general, the citation and abstract information is presented as obtained from this database), and reprints of published articles provided by the authors. Facility types and activities covered in the scope of this report include: radioactive waste, uranium enrichment, fuel fabrication, spent fuel storage and reprocessing, facility decommissioning, hot laboratories, tritium production, research, test and production reactors, weapons fabrication and testing, fusion, uranium and plutonium processing, radiography, and accelerators. Information on improved shielding design, decontamination, containments, robotics, source prevention and control, job planning, improved operational and design techniques, as well as on other topics, has been included. In addition, DOE/EH reports not included in previous volumes of the bibliography are in this volume (abstracts 611 to 684). This volume (Volume 5 of the series) contains 217 abstracts.

Dionne, B.J.; Sullivan, S.G.; Baum, J.W. [Brookhaven National Lab., Upton, NY (United States)

1994-01-01T23:59:59.000Z

317

Interim Storage Facility decommissioning. Final report  

SciTech Connect

Decontamination and decommissioning of the Interim Storage Facility were completed. Activities included performing a detailed radiation survey of the facility, removing surface and imbedded contamination, excavating and removing the fuel storage cells, restoring the site to natural conditions, and shipping waste to Hanford, Washington, for burial. The project was accomplished on schedule and 30% under budget with no measurable exposure to decommissioning personnel.

Johnson, R.P.; Speed, D.L.

1985-03-15T23:59:59.000Z

318

Advanced Powertrain Research Facility  

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

95F 95F Vehicle Setup Information Vehicle architecture PHEV Test cell location Front Advanced Powertrain Research Facility Document date 10/18/2013 Vehicle dynamometer Input Revision Number 1 Test weight [lb] 3518 Notes: Target A [lb] 21.47 Target B [lb/mph] 0.21588 Target C [lb/mph^2] 0.012508 Test Fuel Information Revision Number 1 Test weight [lb] 3518 Test Fuel Information Fuel type EPA Tier II EEE HF0437 Fuel density [g/ml] 0.742 Fuel Net HV [BTU/lbm] 18475 Fuel type EPA Tier II EEE HF0437 T e s t I D [ # ] C y c l e C o l d s t a r t ( C S t ) H o t s t a r t [ H S t ] D a t e T e s t C e l l T e m p [ C ] T e s t C e l l R H [ % ] T e s t C e l l B a r o [ i n / H g ] V e h i c l e c o o l i n g f a n s p e e d : S p e e d M a t c h [ S M ] o r c o n s t a n t s p e e d [ C S ] S o l a r L a m p s [ W / m 2 ] V e i c l e C l i m a t e C o n t r o l s e t t i n g s H o o d P o s i t i o n [ U p ] o r [ C l o s e d ] W i n d o w P o s i t i o n [ C l o s e d ] o r [ D o w n ] C y

319

Renewable Fuels and Lubricants (ReFUEL) Laboratory (Fact Sheet)  

SciTech Connect

This fact sheet describes the Renewable Fuels and Lubricants (ReFUEL) Laboratory at the U.S. Department of Energy National Renewable Energy Laboratory (NREL) is a state-of-the-art research and testing facility for advanced fuels and vehicles. Research and development aims to improve vehicle efficiency and overcome barriers to the increased use of renewable diesel and other nonpetroleum-based fuels, such as biodiesel and synthetic diesel derived from biomass. The ReFUEL Laboratory features a chassis dynamometer for vehicle performance and emissions research, two engine dynamometer test cells for advanced fuels research, and precise emissions analysis equipment. As a complement to these capabilities, detailed studies of fuel properties, with a focus on ignition quality, are performed at NREL's Fuel Chemistry Laboratory.

Not Available

2012-03-01T23:59:59.000Z

320

Facility Safety  

Directives, Delegations, and Requirements

To establish facility safety requirements for the Department of Energy, including National Nuclear Security Administration. Cancels DOE O 420.1. Canceled by DOE O 420.1B.

2002-05-20T23:59:59.000Z

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

Facility Safety  

Directives, Delegations, and Requirements

The objective of this Order is to establish facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation. The Order has Change 1 dated 11-16-95, Change 2 dated 10-24-96, and the latest Change 3 dated 11-22-00 incorporated. The latest change satisfies a commitment made to the Defense Nuclear Facilities Safety Board (DNFSB) in response to DNFSB recommendation 97-2, Criticality Safety.

2000-11-20T23:59:59.000Z

322

Facility Safety  

Directives, Delegations, and Requirements

The order establishes facility and programmatic safety requirements for nuclear and explosives safety design criteria, fire protection, criticality safety, natural phenomena hazards (NPH) mitigation, and the System Engineer Program.Chg 1 incorporates the use of DOE-STD-1189-2008, Integration of Safety into the Design Process, mandatory for Hazard Category 1, 2 and 3 nuclear facilities. Cancels DOE O 420.1A.

2005-12-22T23:59:59.000Z

323

Facility Safety  

Directives, Delegations, and Requirements

DOE-STD-1104 contains the Department's method and criteria for reviewing and approving nuclear facility's documented safety analysis (DSA). This review and approval formally document the basis for DOE, concluding that a facility can be operated safely in a manner that adequately protects workers, the public, and the environment. Therefore, it is appropriate to formally require implementation of the review methodology and criteria contained in DOE-STD-1104.

2013-06-21T23:59:59.000Z

324

Hydrogen Fuel Quality  

SciTech Connect

For the past 6 years, open discussions and/or meetings have been held and are still on-going with OEM, Hydrogen Suppliers, other test facilities from the North America Team and International collaborators regarding experimental results, fuel clean-up cost, modeling, and analytical techniques to help determine levels of constituents for the development of an international standard for hydrogen fuel quality (ISO TC197 WG-12). Significant progress has been made. The process for the fuel standard is entering final stages as a result of the technical accomplishments. The objectives are to: (1) Determine the allowable levels of hydrogen fuel contaminants in support of the development of science-based international standards for hydrogen fuel quality (ISO TC197 WG-12); and (2) Validate the ASTM test method for determining low levels of non-hydrogen constituents.

Rockward, Tommy [Los Alamos National Laboratory

2012-07-16T23:59:59.000Z

325

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

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

326

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

327

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

328

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

329

Renewable Energy Co-Location of Distribution Facilities (Virginia) |  

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

Co-Location of Distribution Facilities (Virginia) Co-Location of Distribution Facilities (Virginia) Renewable Energy Co-Location of Distribution Facilities (Virginia) < Back Eligibility Commercial Construction Developer Fuel Distributor Industrial Installer/Contractor Investor-Owned Utility Local Government Municipal/Public Utility Rural Electric Cooperative Systems Integrator Tribal Government Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State Virginia Program Type Siting and Permitting Provider Virginia State Corporation Commission This legislation applies to distribution facilities, which include poles and wires, cables, pipelines, or other underground conduits by which a renewable generator is able to (i) supply electricity generated at its

330

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

331

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

332

METHODOLOGIES FOR REVIEW OF THE HEALTH AND SAFETY ASPECTS OF PROPOSED NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL SITES AND FACILITIES. VOLUME 9 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

of the health and safety impact of fossil fuel emissions.to public health and safety, of any fossil fuel plant areHEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL

Nero, A.V.

2010-01-01T23:59:59.000Z

333

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

334

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...

335

A conceptual redesign of an Inter-Building Fuel Transfer Cask  

SciTech Connect

The Inter-Building Fuel Transfer Cask, referred to as the IBC, is a lead shielded cask for transporting subassemblies between buildings on the Argonne National Laboratory-West site near Idaho Falls, Idaho. The cask transports both newly fabricated and spent reactor subassemblies between the Experimental Breeder Reactor-II (EBR-II), the Fuel Cycle Facility (FCF) and the Hot Fuel Examination Facility (HFEF). The IBC will play a key role in the Integral Fast Reactor (IFR) fuel recycling demonstration project. This report discusses a conceptual redesign of the IBC which has been performed. The objective of the conceptual design was to increase the passive heat removal capabilities, reduce the personnel radiation exposure and incorporate enhanced safety features into the design. The heat transfer, radiation and thermal-hydraulic properties of the IBC were analytically modelled to determine the principal factors controlling the desip. The scoping studies that were performed determined the vital physical characteristics (i.e., size, shielding, pumps, etc.) of the MC conceptual design.

Klann, R.T.; Picker, B.A. Jr.

1993-01-01T23:59:59.000Z

336

A conceptual redesign of an Inter-Building Fuel Transfer Cask  

SciTech Connect

The Inter-Building Fuel Transfer Cask, referred to as the IBC, is a lead shielded cask for transporting subassemblies between buildings on the Argonne National Laboratory-West site near Idaho Falls, Idaho. The cask transports both newly fabricated and spent reactor subassemblies between the Experimental Breeder Reactor-II (EBR-II), the Fuel Cycle Facility (FCF) and the Hot Fuel Examination Facility (HFEF). The IBC will play a key role in the Integral Fast Reactor (IFR) fuel recycling demonstration project. This report discusses a conceptual redesign of the IBC which has been performed. The objective of the conceptual design was to increase the passive heat removal capabilities, reduce the personnel radiation exposure and incorporate enhanced safety features into the design. The heat transfer, radiation and thermal-hydraulic properties of the IBC were analytically modelled to determine the principal factors controlling the desip. The scoping studies that were performed determined the vital physical characteristics (i.e., size, shielding, pumps, etc.) of the MC conceptual design.

Klann, R.T.; Picker, B.A. Jr.

1993-03-01T23:59:59.000Z

337

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Arkansas Incentives and Laws Arkansas Incentives and Laws The following is a list of expired, repealed, and archived incentives, laws, regulations, funding opportunities, or other initiatives related to alternative fuels and vehicles, advanced technologies, or air quality. Electric Vehicle (EV) Equipment and Fuel Cell Income Tax Credit Repealed: 03/06/2009 The following was repealed by House Bill 2081, 2009: An income tax credit is available to Arkansas taxpayers to offset the costs of an Arkansas-based facility that designs, develops, or produces advanced technologies, including EV equipment and fuel cells. The credit is equal to 50% of the amount spent during the taxable year to purchase or construct the facility, including land acquisition, infrastructure improvements, renovation,

338

NETL: Research Capabilities and Facilities  

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

Research Capabilities and Facilities Research Capabilities and Facilities Onsite Research Research Capabilities and Facilities Lab Worker As the lead field center for the DOE Office of Fossil Energy's research and development program, NETL has established a strong onsite research program conducted by Federal scientists and engineers. Onsite R&D – managed by NETL's Office of Research and Development – makes important contributions to NETL's mission of implementing a research, development, and demonstration program to resolve the environmental, supply, and reliability constraints of producing and using fossil resources. With its expert research staff and state-of-the-art facilities, NETL has extensive experience in working with the technical issues related to fossil resources. Onsite researchers also participate with NETL's industrial partners to solve problems that become barriers to commercialization of power systems, fuels, and environmental and waste management. Onsite research capabilities are strengthened by collaborations with well-known research universities.

339

METHODOLOGIES FOR REVIEW OF THE HEALTH AND SAFETY ASPECTS OF PROPOSED NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL SITES AND FACILITIES. VOLUME 9 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

for Fossil-Fuel and Geothermal Power Plants", Lawrenceof fossil-fuel and geothermal power plants. Choosing whatfor solid waste in geothermal power plants is the same as

Nero, A.V.

2010-01-01T23:59:59.000Z

340

DOE Hydrogen & Fuel Cell Overview  

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

Program Program Market Readiness Workshop DOE Hydrogen & Fuel Cell Overview Dr. Sunita Satyapal Program Manager U.S. Department of Energy Fuel Cell Technologies Program February 16, 2011 2 | Fuel Cell Technologies Program eere.energy.gov Fuel Cells - Where are we today? Fuel Cells for Transportation In the U.S., there are currently: > 200 fuel cell vehicles ~ 20 active fuel cell buses ~ 60 fueling stations In the U.S., there are currently: ~9 million metric tons of H 2 produced annually > 1200 miles of H 2 pipelines Fuel Cells for Stationary Power, Auxiliary Power, and Specialty Vehicles Fuel cells can be a cost-competitive option for critical-load facilities, backup power, and forklifts. The largest markets for fuel cells today are in

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

Facility Interface Capability Assessment (FICA) project report  

SciTech Connect

The US Department of Energy`s (DOE) Office of Civilian Radioactive Waste Management (OCRWM) is responsible for developing the Civilian Radioactive Waste Management System (CRWMS) to accept spent nuclear fuel from commercial facilities. The objective of the Facility Interface Capability Assessment (FICA) project was to assess the capability of each commercial spent nuclear fuel (SNF) storage facility, at which SNF is stored, to handle various SNF shipping casks. The purpose of this report is to present and analyze the results of the facility assessments completed within the FICA project. During Phase 1, the data items required to complete the facility assessments were identified and the database for the project was created. During Phase 2, visits were made to 122 facilities on 76 sites to collect data and information, the database was updated, and assessments of the cask-handling capabilities at each facility were performed. Each assessment of cask-handling capability contains three parts: the current capability of the facility (planning base); the potential enhanced capability if revisions were made to the facility licensing and/or administrative controls; and the potential enhanced capability if limited physical modifications were made to the facility. The main conclusion derived from the planning base assessments is that the current facility capabilities will not allow handling of any of the FICA Casks at 49 of the 122 facilities evaluated. However, consideration of potential revisions and/or modifications showed that all but one of the 49 facilities could be adapted to handle at least one of the FICA Casks. For this to be possible, facility licensing, administrative controls, and/or physical aspects of the facility would need to be modified.

Pope, R.B. [ed.] [Oak Ridge National Lab., TN (United States); MacDonald, R.R. [ed.] [Civilian Radioactive Waste Management System, Vienna, VA (United States); Viebrock, J.M.; Mote, N. [Nuclear Assurance Corp., Norcross, GA (United States)

1995-09-01T23:59:59.000Z

342

CRAD, Nuclear Facility Construction - Structural Steel, May 29, 2009 |  

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

Steel, May 29, Steel, May 29, 2009 CRAD, Nuclear Facility Construction - Structural Steel, May 29, 2009 May 29, 2009 Nuclear Facility Construction - Structural Steel (HSS CRAD 64-16, Rev. 0) Nuclear Facility Construction - Structural Steel criteria, review, and approach document, observes construction activities and review records and design documentation to assess the quality of structural steel fabrication and erection and to determine if requirements specified by design basis documents, contracts, and applicable codes and standards have been met. CRAD, Nuclear Facility Construction - Structural Steel, May 29, 2009 More Documents & Publications CRAD, Nuclear Facility Construction - Structural Concrete, May 29, 2009 CRAD, Nuclear Facility Construction - Mechanical Equipment - June 26, 2012

343

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

344

Small Power Production Facilities (Montana) | Department of Energy  

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

Facilities (Montana) Facilities (Montana) Small Power Production Facilities (Montana) < Back Eligibility Commercial Industrial Institutional Investor-Owned Utility Municipal/Public Utility Rural Electric Cooperative Systems Integrator Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State Montana Program Type Interconnection Provider Montana Public Service Commission For the purpose of these regulations, a small power production facility is defined as a facility that: : (a) produces electricity by the use, as a primary energy source, of biomass, waste, water, wind, or other renewable resource, or any combination of those sources; or : (b) produces electricity and useful forms of thermal energy, such as heat

345

Property Tax Abatement for Production and Manufacturing Facilities |  

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

Abatement for Production and Manufacturing Facilities Abatement for Production and Manufacturing Facilities Property Tax Abatement for Production and Manufacturing Facilities < Back Eligibility Commercial Industrial Savings Category Bioenergy Commercial Heating & Cooling Manufacturing Buying & Making Electricity Alternative Fuel Vehicles Hydrogen & Fuel Cells Solar Heating & Cooling Swimming Pool Heaters Water Heating Heating Wind Program Info Start Date 5/25/2007 State Montana Program Type Industry Recruitment/Support Rebate Amount 50% tax abatement Provider Montana Department of Revenue In May 2007, Montana enacted legislation (H.B. 3) that allows a property tax abatement for new renewable energy production facilities, new renewable energy manufacturing facilities, and renewable energy research and

346

Facility Safety  

Directives, Delegations, and Requirements

Establishes facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation. Cancels DOE 5480.7A, DOE 5480.24, DOE 5480.28 and Division 13 of DOE 6430.1A. Canceled by DOE O 420.1A.

1995-10-13T23:59:59.000Z

347

Facility Safety  

Directives, Delegations, and Requirements

The Order establishes facility and programmatic safety requirements for DOE and NNSA for nuclear safety design criteria, fire protection, criticality safety, natural phenomena hazards (NPH) mitigation, and System Engineer Program. Cancels DOE O 420.1B, DOE G 420.1-2 and DOE G 420.1-3.

2012-12-04T23:59:59.000Z

348

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

349

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

350

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

351

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

352

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

353

Oak Ridge partners: Global security and fuel development | Y-12 National  

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

Oak Ridge partners: Global ... Oak Ridge partners: Global ... Oak Ridge partners: Global security and fuel development Posted: July 18, 2012 - 10:00am | Y-12 Report | Volume 9, Issue 1 | 2012 Additive manufacturing builds metal parts, layer by layer, such as this titanium piece ORNL fabricated for Y-12. Y-12 is evaluating the technology for tooling and manufacturing applications. In 2011 the two DOE facilities shared 178 projects worth $12.5 million. In the 1940s Bear Creek and Bethel valleys cradled newly constructed facilities filled with people on a common mission that ended World War II. Today, the Y-12 National Security Complex and Oak Ridge National Laboratory thrive in those transformed valleys and collaborate daily. In 2011 they shared 178 projects worth $12.5 million. "With just a few miles separating our nationally renowned institutions,

354

Global Nuclear Energy Partnership Fact Sheet - Establish Reliable Fuel  

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

Global Nuclear Energy Partnership Fact Sheet - Establish Reliable Global Nuclear Energy Partnership Fact Sheet - Establish Reliable Fuel Services Global Nuclear Energy Partnership Fact Sheet - Establish Reliable Fuel Services GNEP would build and strengthen a reliable international fuel services consortium under which "fuel supplier nations" would choose to operate both nuclear power plants and fuel production and handling facilities, providing reliable fuel services to "user nations" that choose to only operate nuclear power plants. This international consortium is a critical component of the GNEP initiative to build an improved, more proliferation-resistant nuclear fuel cycle that recycles used fuel, while Global Nuclear Energy Partnership Fact Sheet - Establish Reliable Fuel Services More Documents & Publications

355

Used Fuel Testing Transportation Model  

SciTech Connect

This report identifies shipping packages/casks that might be used by the Used Nuclear Fuel Disposition Campaign Program (UFDC) to ship fuel rods and pieces of fuel rods taken from high-burnup used nuclear fuel (UNF) assemblies to and between research facilities for purposes of evaluation and testing. Also identified are the actions that would need to be taken, if any, to obtain U.S. Nuclear Regulatory (NRC) or other regulatory authority approval to use each of the packages and/or shipping casks for this purpose.

Ross, Steven B.; Best, Ralph E.; Maheras, Steven J.; Jensen, Philip J.; England, Jeffery L.; LeDuc, Dan

2014-09-24T23:59:59.000Z

356

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

357

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

358

Fuel Cell Technologies Office Newsletter: February 2013 | Department...  

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

is currently posted on the Energy Department's blog. The facility uses fuel cells and biogas from the Orange County Sanitation District's wastewater treatment plant to produce...

359

Fuel Cell Technologies Office: Past Events EventsDetail  

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

Facility located at NREL in Golden, Colorado. February 11, 2014 Online Webinar: Additive Manufacturing for Fuel Cells This webinar will focus on additive manufacturing to...

360

Energy Department Invests $7 Million to Commercialize Fuel Cells...  

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

per fueling and test 20 of these trucks at FedEx facilities in Tennessee and California. Air Products and Chemicals, Inc., of Allentown, Pennsylvania, and Structural Composites...

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

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

362

No Fossil Fuel - Kingston | Open Energy Information  

Open Energy Info (EERE)

No Fossil Fuel - Kingston No Fossil Fuel - Kingston Jump to: navigation, search Name No Fossil Fuel - Kingston Facility No Fossil Fuel - Kingston Sector Wind energy Facility Type Commercial Scale Wind Facility Status In Service Owner No Fossil Fuel LLC Developer No Fossil Fuel LLC Energy Purchaser Net-metered Location Kingston MA Coordinates 41.97388106°, -70.72577477° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":41.97388106,"lon":-70.72577477,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

363

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

364

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

365

Farm Fuel Safety Accidents in the handling, use and storage of gasoline, gasohol, diesel fuel, LP-gas and  

E-Print Network (OSTI)

112 Farm Fuel Safety Accidents in the handling, use and storage of gasoline, gasohol, diesel fuel and by keeping fuel storage facilities in top condition. Flammable Liquids and Gases Gasoline, diesel fuel, LP flammability and safety precautions. Do not keep gasoline inside the home or transport it in the trunks

366

Spent Fuel Background Report Volume I  

SciTech Connect

This report is an overview of current spent nuclear fuel management in the DOE complex. Sources of information include published literature, internal DOE documents, interviews with site personnel, and information provided by individual sites. Much of the specific information on facilities and fuels was provided by the DOE sites in response to the questionnaire for data for spent fuels and facilities data bases. This information is as accurate as is currently available, but is subject to revision pending results of further data calls. Spent fuel is broadly classified into three categories: (a) production fuels, (b) special fuels, and (c) naval fuels. Production fuels, comprising about 80% of the total inventory, are those used at Hanford and Savannah River to produce nuclear materials for defense. Special fuels are those used in a wide variety of research, development, and testing activities. Special fuels include fuel from DOE and commercial reactors used in research activities at DOE sites. Naval fuels are those developed and used for nuclear-powered naval vessels and for related research and development. Given the recent DOE decision to curtail reprocessing, the topic of main concern in the management of spent fuel is its storage. Of the DOE sites that have spent nuclear fuel, the vast majority is located at three sites-Hanford, INEL, and Savannah River. Other sites with spent fuel include Oak Ridge, West Valley, Brookhaven, Argonne, Los Alamos, and Sandia. B&W NESI Lynchburg Technology Center and General Atomics are commercial facilities with DOE fuel. DOE may also receive fuel from foreign research reactors, university reactors, and other commercial and government research reactors. Most DOE spent fuel is stored in water-filled pools at the reactor facilities. Currently an engineering study is being performed to determine the feasibility of using dry storage for DOE-owned spent fuel currently stored at various facilities. Delays in opening the deep geologic repository and the decision to phase out reprocessing of production fuels are extending the need for interim storage. The report describes the basic storage conditions and the general SNF inventory at individual DOE facilities.

Abbott, D.

1994-03-01T23:59:59.000Z

367

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

368

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

369

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

370

Facility effluent monitoring plan for the 324 Facility  

SciTech Connect

The 324 Facility [Waste Technology Engineering Laboratory] in the 300 Area primarily supports the research and development of radioactive and nonradioactive waste vitrification technologies, biological waste remediation technologies, spent nuclear fuel studies, waste mixing and transport studies, and tritium development programs. All of the above-mentioned programs deal with, and have the potential to, release hazardous and/or radioactive material. The potential for discharge would primarily result from (1) conducting research activities using the hazardous materials, (2) storing radionuclides and hazardous chemicals, and (3) waste accumulation and storage. This report summarizes the airborne and liquid effluents, and the results of the Facility Effluent Monitoring Plan (FEMP) determination for the facility. The complete monitoring plan includes characterizing effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements.

NONE

1994-11-01T23:59:59.000Z

371

SGP Central Facility  

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

Central Facility Central Facility SGP Related Links Facilities and Instruments Central Facility Boundary Facility Extended Facility Intermediate Facility Radiometric Calibration Facility Geographic Information ES&H Guidance Statement Operations Science Field Campaigns Visiting the Site Fact Sheet Images Information for Guest Scientists Contacts SGP Central Facility The ARM Climate Research Facility deploys specialized remote sensing instruments in a fixed location at the site to gather atmospheric data of unprecedented quality, consistency, and completeness. More than 30 instrument clusters have been placed around the site; the central facility; and the boundary, intermediate, and extended facilities. The locations for the instruments were chosen so that the measurements reflect conditions

372

ARM - SGP Central Facility  

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

Central Facility Central Facility SGP Related Links Facilities and Instruments Central Facility Boundary Facility Extended Facility Intermediate Facility Radiometric Calibration Facility Geographic Information ES&H Guidance Statement Operations Science Field Campaigns Visiting the Site Fact Sheet Images Information for Guest Scientists Contacts SGP Central Facility The ARM Climate Research Facility deploys specialized remote sensing instruments in a fixed location at the site to gather atmospheric data of unprecedented quality, consistency, and completeness. More than 30 instrument clusters have been placed around the site; the central facility; and the boundary, intermediate, and extended facilities. The locations for the instruments were chosen so that the measurements reflect conditions

373

Hydrogen Production and Dispensing Facility Opens at W. Va. Airport |  

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

Hydrogen Production and Dispensing Facility Opens at W. Va. Airport Hydrogen Production and Dispensing Facility Opens at W. Va. Airport Hydrogen Production and Dispensing Facility Opens at W. Va. Airport August 19, 2009 - 1:00pm Addthis Major General Allen Tackett of the National Guard's 130th Airlift Wing dispenses the first fill-up of hydrogen fuel from the Yeager facility. Major General Allen Tackett of the National Guard's 130th Airlift Wing dispenses the first fill-up of hydrogen fuel from the Yeager facility. Washington, D.C. -- A hydrogen production and dispensing station constructed and operated with support from the Office of Fossil Energy's National Energy Technology Laboratory (NETL) was officially opened Monday at the Yeager Airport in Charleston, W.Va. The facility is an example of how domestically produced fuels may be used to power a variety of vehicles

374

Independent Oversight Inspection, Savannah River Site- December 2009  

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

Inspection of Reinforced Concrete Construction at the Savannah River Site Mixed Oxide Fuel Fabrication Facility

375

NREL: Hydrogen and Fuel Cells Research - National Fuel Cell Technology  

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

National Fuel Cell Technology Evaluation Center National Fuel Cell Technology Evaluation Center The National Fuel Cell Technology Evaluation Center (NFCTEC) at NREL's Energy Systems Integration Facility (ESIF) plays a crucial role in NREL's independent, third-party analysis of hydrogen fuel cell technologies in real-world operation. The NFCTEC is designed for secure management, storage, and processing of proprietary data from industry. Access to the off-network NFCTEC is limited to NREL's Technology Validation Team, which analyzes detailed data and reports on fuel cell technology status, progress, and technical challenges. Graphic representing NREL's Hydrogen Secure Data Center and the variety of applications from which it gathers data, including fuel cell (FC) stacks, FC backup power, FC forklifts, FC cars, FC buses, and FC prime power, and hydrogen infrastructure.

376

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.

377

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

378

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

379

NREL: Energy Systems Integration Facility - Facility Design  

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

Facility Design Throughout the Energy Systems Integration Facility design process, the National Renewable Energy Laboratory hosted workshops in which stakeholders from across the...

380

Energy Facility Evaluation, Siting, Construction and Operation (New  

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

Energy Facility Evaluation, Siting, Construction and Operation (New Energy Facility Evaluation, Siting, Construction and Operation (New Hampshire) Energy Facility Evaluation, Siting, Construction and Operation (New Hampshire) < Back Eligibility Agricultural Commercial Construction Fed. Government Fuel Distributor Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Multi-Family Residential Municipal/Public Utility Retail Supplier Rural Electric Cooperative Tribal Government Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Solar Wind Program Info State New Hampshire Program Type Siting and Permitting Provider NH Department of Environmental Services, Public Information and Permitting Unit The statute establishes a procedure for the review, approval, monitoring,

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

North Dakota Energy Conversion and Transmission Facility Siting Act (North  

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

Dakota Energy Conversion and Transmission Facility Siting Act Dakota Energy Conversion and Transmission Facility Siting Act (North Dakota) North Dakota Energy Conversion and Transmission Facility Siting Act (North Dakota) < Back Eligibility Utility Fed. Government Commercial Agricultural Investor-Owned Utility State/Provincial Govt Industrial Construction Municipal/Public Utility Local Government Residential Installer/Contractor Rural Electric Cooperative Tribal Government Low-Income Residential Schools Retail Supplier Institutional Multi-Family Residential Systems Integrator Fuel Distributor Nonprofit General Public/Consumer Transportation Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State North Dakota Program Type Line Extension Analysis

382

NREL: Sustainable NREL - Integrated Biorefinery Research Facility  

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

Integrated Biorefinery Research Facility Integrated Biorefinery Research Facility A photo of a grey, three-story research facility on a large campus. The Integrated Biorefinery Research Facility The Integrated Biorefinery Research Facility (IBRF) incorporates a large number of energy efficiency and sustainability practices into its cutting-edge design. This facility received a Leadership in Energy and Environmental Design (LEED®) Gold-level certification from the U.S. Green Building Council and supports a variety of advanced biofuels projects and enables researchers and industry partners to develop, test, evaluate, and demonstrate processes for the production of bio-based products and fuels. Fast Facts Cost: $33.5M Square feet: 27,000 Occupants: 32 Labs/Equipment: high-bay biochemical conversion pilot plant that

383

Massachusetts Hazardous Waste Facility Siting Act (Massachusetts) |  

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

Massachusetts Hazardous Waste Facility Siting Act (Massachusetts) Massachusetts Hazardous Waste Facility Siting Act (Massachusetts) Massachusetts Hazardous Waste Facility Siting Act (Massachusetts) < Back Eligibility Commercial Fed. Government Fuel Distributor Industrial Institutional Investor-Owned Utility Local Government Municipal/Public Utility Rural Electric Cooperative Tribal Government Utility Program Info State Massachusetts Program Type Siting and Permitting Provider Department of Environmental Protection This Act establishes the means by which developers of proposed hazardous waste facilities will work with the community in which they wish to construct a facility. When the intent to construct, maintain, and/or operate a hazardous waste facility in a city or town is demonstrated, a local assessment committee will be established by that community. The

384

NREL: Photovoltaics Research - Solar Energy Research Facility  

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

Solar Energy Research Facility Solar Energy Research Facility Photo of the Solar Energy Research Facility. The exterior stepped clerestory of the Solar Energy Research Facility. Photovoltaics (PV) and basic energy sciences are two major research areas conducted in the Solar Energy Research Facility (SERF). The building incorporates a multitude of energy saving features that make it one of the government's most energy efficient buildings with 40 percent lower energy costs than similar buildings designed to meet federal energy standards. The SERF houses three adjoining modules each containing a laboratory pod and an office pod. Laboratories in the west module are used to develop semiconductor material for high-efficiency crystalline solar cells. Laboratories in the center module are used to fabricate prototype solar

385

1990 Washington State directory of biomass energy facilities  

SciTech Connect

This second edition is an update of biomass energy production and use in Washington State for 1989. The purpose of this directory is to provide a listing of known biomass users within the state and some basic information about their facilities. The data can be helpful to persons or organizations considering the use of biomass fuels. The directory is divided into three sections of biomass facilities with each section containing a map of locations and a data summary table. In addition, a conversion table, a glossary and an index are provided in the back of the directory. The first section deals with biogas production from wastewater treatment plants. The second section provides information on the wood combustion facilities in the state. This section is subdivided into two categories. The first is for facilities connected with the forest products industries. The second category include other facilities using wood for energy. The third section is composed of three different types of biomass facilities -- ethanol, municipal solid waste, and solid fuel processing. Biomass facilities included in this directory produce over 64 trillion Btu (British thermal units) per year. Wood combustion facilities account for 91 percent of the total. Biogas and ethanol facilities each produce close to 800 billion Btu per year, MSW facilities produce 1845 billion BTU, and solid fuel processing facilities produce 2321 billion Btu per year. To put these numbers in perspective, Washington's industrial section uses 200 trillion Btu of fuels per year. Therefore, biomass fuels used and/or produced by facilities listed in this directory account for nearly 32 percent of the state's total industrial fuel demand. This is a sizable contribution to the state's energy needs.

Deshaye, J.A.; Kerstetter, J.D.

1990-01-01T23:59:59.000Z

386

ANL: Prototype Cell Fabrication Facility | Department of Energy  

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

and Vehicle Technologies Program Annual Merit Review and Peer Evaluation arravt075esjansen2011p.pdf More Documents & Publications FY 2011 Annual Progress Report for Energy...

387

Cell Fabrication Facility Team Production and Research Activities...  

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

and Vehicle Technologies Program Annual Merit Review and Peer Evaluation Meeting es030jansen2013o.pdf More Documents & Publications Current Research Activities in Electrode and...

388

Cell Fabrication Facility Team Production and Research Activities  

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

25% Complete Need a high energy density battery for PHEVEV use that is safe, cost-effective, and has long cycle life. - Independent validation analysis of newly...

389

A framework for nuclear facility safeguard evaluation using probabilistic methods and expert elicitation  

E-Print Network (OSTI)

With the advancement of the next generation of nuclear fuel cycle facilities, concerns of the effectiveness of nuclear facility safeguards have been increasing due to the inclusion of highly enriched material and reprocessing ...

Iamsumang, Chonlagarn

2010-01-01T23:59:59.000Z

390

Fuel Cell Development and Test Laboratory (Fact Sheet)  

SciTech Connect

This fact sheet describes the purpose, lab specifications, applications scenarios, and information on how to partner with NREL's Fuel Cell Development and Test Laboratory at the Energy Systems Integration Facility. NREL's state-of-the-art Fuel Cell Development and Test Laboratory in the Energy Systems Integration Facility (ESIF) supports NREL's fuel cell research and development projects through in-situ fuel cell testing. Current projects include various catalyst development projects, a system contaminant project, and the manufacturing project. Testing capabilities include but are not limited to single cell fuel cells and fuel cell stacks.

Not Available

2011-10-01T23:59:59.000Z

391

4858 recreation facility [n  

Science Journals Connector (OSTI)

plan. recr. (Installation and equipment provided for recreation; ? simply-provided recreation facility , ? well-provided recreation facility ...

2010-01-01T23:59:59.000Z

392

Facilities | Argonne National Laboratory  

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

Engineering Research Facility Distributed Energy Research Center Engine Research Facility Heat Transfer Laboratory Tribology Laboratory Transportation Beamline at the Advanced...

393

San Diego County - Design Standards for County Facilities | Department of  

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

Design Standards for County Facilities Design Standards for County Facilities San Diego County - Design Standards for County Facilities < Back Eligibility Local Government Savings Category Heating & Cooling Home Weatherization Construction Commercial Weatherization Commercial Heating & Cooling Design & Remodeling Bioenergy Manufacturing Buying & Making Electricity Alternative Fuel Vehicles Hydrogen & Fuel Cells Energy Sources Solar Wind Other Program Info State California Program Type Energy Standards for Public Buildings Provider San Diego County The San Diego County Board of Supervisors established design standards for county facilities and property. Among other requirements, the policy requires that all new county buildings or major building renovations obtain U.S. Green Building Council (USGBC) LEED Building Certification.

394

Utility Facility Siting and Environmental Protection Act (South Carolina) |  

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

Utility Facility Siting and Environmental Protection Act (South Utility Facility Siting and Environmental Protection Act (South Carolina) Utility Facility Siting and Environmental Protection Act (South Carolina) < Back Eligibility Utility Commercial Investor-Owned Utility Industrial Construction Municipal/Public Utility Installer/Contractor Rural Electric Cooperative Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State South Carolina Program Type Siting and Permitting Provider South Carolina Public Service Commission This legislation applies to electric generating plants and associated facilities designed for or capable of operation at a capacity of more than 75 MW. A certificate from the Public Service Commission is required prior

395

Georgia Utility Facility Protection Act (Georgia) | Department of Energy  

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

Georgia Utility Facility Protection Act (Georgia) Georgia Utility Facility Protection Act (Georgia) Georgia Utility Facility Protection Act (Georgia) < Back Eligibility Agricultural Commercial Construction General Public/Consumer Industrial Installer/Contractor Investor-Owned Utility Municipal/Public Utility Rural Electric Cooperative Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State Georgia Program Type Safety and Operational Guidelines Siting and Permitting Provider Utilities Protection Center of Georgia The Georgia Utility Facility Protection Act (GUFPA) was established to protect the underground utility infrastructure of Georgia. GUFPA mandates that, before starting any mechanized digging or excavation work, you must

396

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

397

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

398

Alternative Fuels Data Center: Case Studies  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Case Studies to Case Studies to someone by E-mail Share Alternative Fuels Data Center: Case Studies on Facebook Tweet about Alternative Fuels Data Center: Case Studies on Twitter Bookmark Alternative Fuels Data Center: Case Studies on Google Bookmark Alternative Fuels Data Center: Case Studies on Delicious Rank Alternative Fuels Data Center: Case Studies on Digg Find More places to share Alternative Fuels Data Center: Case Studies on AddThis.com... Case Studies Find case studies and success stories about alternative transportation technologies and alternative fuels. A Chevy Volt sedan is plugged into a charging station in a parking area outside the City of Fort Collins fleet facility. Fort Collins: A Multi-Fuel Approach to Sustainable Fleet Operations A diversity of fuels and technologies offers flexibility in reaching energy

399

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

400

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

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

Measures of the environmental footprint of the front end of the nuclear fuel cycle  

SciTech Connect

Previous estimates of environmental impacts associated with the front end of the nuclear fuel cycle (FEFC) have focused primarily on energy consumption and CO2 emissions. Results have varied widely. This work builds upon reports from operating facilities and other primary data sources to build a database of front end environmental impacts. This work also addresses land transformation and water withdrawals associated with the processes of the FEFC. These processes include uranium extraction, conversion, enrichment, fuel fabrication, depleted uranium disposition, and transportation. To allow summing the impacts across processes, all impacts were normalized per tonne of natural uranium mined as well as per MWh(e) of electricity produced, a more conventional unit for measuring environmental impacts that facilitates comparison with other studies. This conversion was based on mass balances and process efficiencies associated with the current once-through LWR fuel cycle. Total energy input is calculated at 8.7 x 10- 3 GJ(e)/MWh(e) of electricity and 5.9 x 10- 3 GJ(t)/MWh(e) of thermal energy. It is dominated by the energy required for uranium extraction, conversion to fluoride compound for subsequent enrichment, and enrichment. An estimate of the carbon footprint is made from the direct energy consumption at 1.7 kg CO2/MWh(e). Water use is likewise dominated by requirements of uranium extraction, totaling 154 L/MWh(e). Land use is calculated at 8 x 10- 3 m2/MWh(e), over 90% of which is due to uranium extraction. Quantified impacts are limited to those resulting from activities performed within the FEFC process facilities (i.e. within the plant gates). Energy embodied in material inputs such as process chemicals and fuel cladding is identified but not explicitly quantified in this study. Inclusion of indirect energy associated with embodied energy as well as construction and decommissioning of facilities could increase the FEFC energy intensity estimate by a factor of up to 2.

E. Schneider; B. Carlsen; E. Tavrides; C. van der Hoeven; U. Phathanapirom

2013-11-01T23:59:59.000Z

402

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

403

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.

404

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

405

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

406

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.

407

Rates for Alternate Energy Production Facilities (Iowa) | Department of  

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

Rates for Alternate Energy Production Facilities (Iowa) Rates for Alternate Energy Production Facilities (Iowa) Rates for Alternate Energy Production Facilities (Iowa) < Back Eligibility Municipal/Public Utility Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State Iowa Program Type Generating Facility Rate-Making Provider Iowa Utilities Board The Utilities Board may require public utilities furnishing gas, electricity, communications, or water to public consumers, to own alternate energy production facilities, enter into long-term contracts to purchase power from such facilities, and/or provide supplemental or backup power to alternate energy production facilities. Uniform rates for these transactions will be set by the board. Some exemptions apply

408

Facility Representatives  

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

063-2011 063-2011 February 2011 Superseding DOE-STD-1063-2006 April 2006 DOE STANDARD FACILITY REPRESENTATIVES U.S. Department of Energy AREA MGMT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE DOE-STD-1063-2011 ii Available on the Department of Energy Technical Standards Program Web site at http://www.hss.doe.gov/nuclearsafety/ns/techstds/ DOE-STD-1063-2011 iii FOREWORD 1. This Department of Energy (DOE) standard is approved for use by all DOE/National Nuclear Security Administration (NNSA) Components. 2. The revision to this DOE standard was developed by a working group consisting of headquarters and field participants. Beneficial comments (recommendations,

409

Facility Representatives  

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

DOE-STD-1063-2006 April 2006 Superseding DOE-STD-1063-2000 March 2000 DOE STANDARD FACILITY REPRESENTATIVES U.S. Department of Energy AREA MGMT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE DOE-STD-1063-2006 ii Available on the Department of Energy Technical Standards Program web site at http://www.eh.doe.gov/techstds/ DOE-STD-1063-2006 iii FOREWORD 1. This Department of Energy standard is approved for use by all DOE Components. 2. The revision to this DOE standard was developed by a working group consisting of headquarters and field participants. Beneficial comments (recommendations, additions, deletions) and any pertinent data that may improve this document should

410

Facility Type!  

Office of Legacy Management (LM)

ITY: ITY: --&L~ ----------- srct-r~ -----------~------~------- if yee, date contacted ------------- cl Facility Type! i I 0 Theoretical Studies Cl Sample 84 Analysis ] Production 1 Diepasal/Storage 'YPE OF CONTRACT .--------------- 1 Prime J Subcontract&- 1 Purchase Order rl i '1 ! Other information (i.e., ---------~---~--~-------- :ontrait/Pirchaee Order # , I C -qXlJ- --~-------~~-------~~~~~~ I I ~~~---~~~~~~~T~~~ FONTRACTING PERIODi IWNERSHIP: ,I 1 AECIMED AECMED GOVT GOUT &NTtiAC+OR GUN-I OWNED ----- LEEE!? M!s LE!Ps2 -LdJG?- ---L .ANDS ILJILDINGS X2UIPilENT IRE OR RAW HA-I-L :INAL PRODUCT IASTE Z. RESIDUE I I kility l pt I ,-- 7- ,+- &!d,, ' IN&"E~:EW AT SITE -' ---------------- , . Control 0 AEC/tlED managed operations

411

Research Facility,  

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

Collecting and Delivering the Data Collecting and Delivering the Data As a general condition for use of the ARM Climate Research Facility, users are required to include their data in the ARM Data Archive. All data acquired must be of sufficient quality to be useful and must be documented such that users will be able to clearly understand the meaning and organization of the data. Final, quality-assured data sets are stored in the Data Archive and are freely accessible to the general scientific community. Preliminary data may be shared among field campaign participants during and shortly following the campaign. To facilitate sharing of preliminary data, the ARM Data Archive establishes restricted access capability, limited to participants and data managers.

412

Facility Operations 1993 fiscal year work plan: WBS 1.3.1  

SciTech Connect

The Facility Operations program is responsible for the safe, secure, and environmentally sound management of several former defense nuclear production facilities, and for the nuclear materials in those facilities. As the mission for Facility Operations plants has shifted from production to support of environmental restoration, each plant is making a transition to support the new mission. The facilities include: K Basins (N Reactor fuel storage); N Reactor; Plutonium-Uranium Reduction Extraction (PUREX) Plant; Uranium Oxide (UO{sub 3}) Plant; 300 Area Fuels Supply (N Reactor fuel supply); Plutonium Finishing Plant (PFP).

Not Available

1992-11-01T23:59:59.000Z

413

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

414

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

415

Methods for developing seismic and extreme wind-hazard models for evaluating critical structures and equipment at US Department of Energy facilities and commercial plutonium facilities in the United States  

SciTech Connect

Lawrence Livermore National Laboratory (LLNL) is developing seismic and wind hazard models for the US Department of Energy (DOE). The work is part of a three-phase effort to establish building design criteria developed with a uniform methodology for seismic and wind hazards at the various DOE sites throughout the United States. In Phase 1, LLNL gathered information on the sites and their critical facilities, including nuclear reactors, fuel-reprocessing plants, high-level waste storage and treatment facilities, and special nuclear material facilities. Phase 2 - development of seismic and wind hazard models - is discussed in this paper, which summarizes the methodologies used by seismic and extreme-wind experts and gives sample hazard curves for the first sites to be modeled. These hazard models express the annual probability that the site will experience an earthquake (or windspeed) greater than some specified magnitude. In the final phase, the DOE will use the hazards models and LLNL-recommended uniform design criteria to evaluate critical facilities. The methodology presented in this paper also was used for a related LLNL study - involving the seismic assessment of six commercial plutonium fabrication plants licensed by the US Nuclear Regulatory Commission (NRC). Details and results of this reassessment are documented in reference.

Coats, D.W.; Murray, R.C.; Bernreuter, D.L.

1981-02-04T23:59:59.000Z

416

Spent fuel pyroprocessing demonstration  

SciTech Connect

A major element of the shutdown of the US liquid metal reactor development program is managing the sodium-bonded spent metallic fuel from the Experimental Breeder Reactor-II to meet US environmental laws. Argonne National Laboratory has refurbished and equipped an existing hot cell facility for treating the spent fuel by a high-temperature electrochemical process commonly called pyroprocessing. Four products will be produced for storage and disposal. Two high-level waste forms will be produced and qualified for disposal of the fission and activation products. Uranium and transuranium alloys will be produced for storage pending a decision by the US Department of Energy on the fate of its plutonium and enriched uranium. Together these activities will demonstrate a unique electrochemical treatment technology for spent nuclear fuel. This technology potentially has significant economic and technical advantages over either conventional reprocessing or direct disposal as a high-level waste option.

McFarlane, L.F.; Lineberry, M.J.

1995-05-01T23:59:59.000Z

417

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Delaware Incentives and Laws Delaware Incentives and Laws The following is a list of expired, repealed, and archived incentives, laws, regulations, funding opportunities, or other initiatives related to alternative fuels and vehicles, advanced technologies, or air quality. Compressed Natural Gas (CNG) Fuel Rate Reduction Archived: 01/01/2009 Chesapeake Utilities has one publicly accessible quick-fill CNG fueling station in Dover. CNG is offered at a 20% discount as compared to the American Automobile Association (AAA) list price. Biodiesel Production Facility Grants Expired: 09/01/2007 The State Energy Office will administer moneys in the Green Energy Fund through a program of environmental incentive grants and loans for the development, promotion and support of energy efficiency programs and

418

Alternative Fuels Data Center  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Kansas Incentives and Laws Kansas Incentives and Laws The following is a list of expired, repealed, and archived incentives, laws, regulations, funding opportunities, or other initiatives related to alternative fuels and vehicles, advanced technologies, or air quality. Biofuel Blending Equipment Tax Incentives Expired: 01/01/2012 A Storage and Blending Equipment Credit is available for the purchase, construction, or installation of qualified equipment used for storing and blending petroleum-based fuel with biodiesel, ethanol, or other biofuel. The equipment must be installed at a fuel terminal, refinery, or biofuel production facility. The tax credit is equal to 10% of the qualified investment for the first $10,000,000 invested, and 5% of the investment in excess of $10,000,000. The credit may be taken in 10 equal annual

419

Integrated Waste Treatment Facility Fact Sheet | Department of...  

Office of Environmental Management (EM)

is designed to treat 900,000 gallons of radioactive liquid waste stored in underground tanks at a former Cold War spent nuclear fuel reprocessing facility located at DOE's Idaho...

420

NETL: News Release - Hydrogen Production and Dispensing Facility Opens at  

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

Hydrogen Production and Dispensing Facility Opens at West Virginia Airport Hydrogen Production and Dispensing Facility Opens at West Virginia Airport Station Provides Transportation Fuel from Domestic Resources for Hydrogen-Fueled Vehicles Washington, D.C. - A hydrogen production and dispensing station constructed and operated with support from the Office of Fossil Energy's National Energy Technology Laboratory (NETL) was officially opened Monday at the Yeager Airport in Charleston, W.Va. The facility is an example of how domestically produced fuels may be used to power a variety of vehicles and equipment, lessening U.S. dependence on foreign oil. The facility will produce, compress, store and dispense hydrogen as a fuel source for vehicles that have been converted to run on hydrogen, as well as other types of ground equipment at the airport.

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

422

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...

423

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...

424

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...

425

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...

426

Sandia National Laboratories: Research: Facilities: Sandia Pulsed Reactor  

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

Sandia Pulsed Reactor Facility - Critical Experiments Sandia Pulsed Reactor Facility - Critical Experiments Sandia scientist John Ford places fuel rods in the Seven Percent Critical Experiment (7uPCX) at the Sandia Pulsed Reactor Facility Critical Experiments (SPRF/CX) test reactor - a reactor stripped down to its simplest form. The Sandia Pulsed Reactor Facility - Critical Experiments (SPRF/CX) provides a flexible, shielded location for performing critical experiments that employ different reactor core configurations and fuel types. The facility is also available for hands-on nuclear criticality safety training. Research and other activities The 7% series, an evaluation of various core characteristics for higher commercial-fuel enrichment, is currently under way at the SPRF/CX. Past critical experiments at the SPRF/CX have included the Burnup Credit

427

Harrisburg Facility Biomass Facility | Open Energy Information  

Open Energy Info (EERE)

Harrisburg Facility Biomass Facility Harrisburg Facility Biomass Facility Jump to: navigation, search Name Harrisburg Facility Biomass Facility Facility Harrisburg Facility Sector Biomass Facility Type Landfill Gas Location Dauphin County, Pennsylvania Coordinates 40.2734277°, -76.7336521° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":40.2734277,"lon":-76.7336521,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

428

Brookhaven Facility Biomass Facility | Open Energy Information  

Open Energy Info (EERE)

Brookhaven Facility Biomass Facility Brookhaven Facility Biomass Facility Jump to: navigation, search Name Brookhaven Facility Biomass Facility Facility Brookhaven Facility Sector Biomass Facility Type Landfill Gas Location Suffolk County, New York Coordinates 40.9848784°, -72.6151169° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":40.9848784,"lon":-72.6151169,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

429

NREL: Vehicles and Fuels Research - ReFUEL Laboratory  

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

Research Research Search More Search Options Site Map NREL's Renewable Fuels and Lubricants (ReFUEL) Laboratory is a state-of-the-art research and testing facility for advanced fuels and vehicles. Research and development focuses on overcoming barriers to the increased use of renewable diesel and other nonpetroleum-based fuels, such as biodiesel and synthetic diesel derived from biomass, and improving vehicle efficiency. Using biofuels and improving vehicle efficiency reduces our dependence on imported petroleum and enhances our national energy security. The ReFUEL Laboratory houses the following specialized equipment: Heavy-duty chassis dynamometer with a simulation capability of 8,000 to 80,000 lbs for vehicle performance and emissions research Heavy-duty (up to 600 hp) and light-duty (up to 75 hp) engine

430

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

431

Uncertainty Analyses of Advanced Fuel Cycles  

SciTech Connect

The Department of Energy is developing technology, experimental protocols, computational methods, systems analysis software, and many other capabilities in order to advance the nuclear power infrastructure through the Advanced Fuel Cycle Initiative (AFDI). Our project, is intended to facilitate will-informed decision making for the selection of fuel cycle options and facilities for development.

Laurence F. Miller; J. Preston; G. Sweder; T. Anderson; S. Janson; M. Humberstone; J. MConn; J. Clark

2008-12-12T23:59:59.000Z

432

Spent Nuclear Fuel (SNF) Project Execution Plan  

SciTech Connect

The Spent Nuclear Fuel (SNF) Project supports the Hanford Site Mission to cleanup the Site by providing safe, economic, environmentally sound management of Site spent nuclear fuel in a manner that reduces hazards by staging it to interim onsite storage and deactivates the 100 K Area facilities.

LEROY, P.G.

2000-11-03T23:59:59.000Z

433

Fuel Cell Opportunities in Marine Corps Garrison  

E-Print Network (OSTI)

% 315,343, 4% 1,585,200, 19% 5,937,358, 73% E85 CNG B100 Diesel Gasoline #12;1 3 0 5 10 15 20 25 30 FY01 fuel cell vehicle operations & maintenance · Partner with Naval Facilities Engineering Service Center, TARDEC, General Motors (GMT800 pickup) · Temporary fueling capability Current Phase... Demonstrate

434

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...

435

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

SciTech Connect

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

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

2006-02-09T23:59:59.000Z

436

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

437

Development of molten carbonate fuel cell power plant technology. Quarterly technical progress report No. 2, January 1-March 31, 1980  

SciTech Connect

The overall objective of this 29-month program is to develop and verify the design of a prototype molten carbonate fuel cell stack which meets the requirements of 1990's competitive coal-fired electrical utility central station or industrial cogeneration power plants. During this quarter, effort was continued in all four major task areas: Task 1 - system studies to define the reference power plant design; Task 2 - cell and stack design, development and verification; Task 3 - preparation for fabrication and testing of the full-scale prototype stack; and Task 4 - developing the capability for operation of stacks on coal-derived gas. In the system study activity of Task 1, preliminary module and cell stack design requirements were completed. Fuel processor characterization has been completed by Bechtel National, Inc. Work under Task 2 defined design approaches for full-scale stack busbars and electrical isolation of reactant manifolds and reactant piping. Preliminary design requirements were completed for the anode. Conductive nickel oxide for cathode fabrication has been made by oxidation and lithiation of porous nickel sheet stock. A method of mechanizing the tape casting process for increased production rates was successfully demonstrated under Task 3. In Task 4, theoretical calculations indicated that hydrogen cyanide and ammonia, when present as impurities in the stack fuel gas, will have no harmful effects. Laboratory experiments using higher than anticipated levels of ethylene showed no harmful effects. Components for the mobile test facility are being ordered.

Not Available

1980-08-01T23:59:59.000Z

438

Cold vacuum drying facility 90% design review  

SciTech Connect

This document contains review comment records for the CVDF 90% design review. Spent fuels retrieved from the K Basins will be dried at the CVDF. It has also been recommended that the Multi-Conister Overpacks be welded, inspected, and repaired at the CVD Facility before transport to dry storage.

O`Neill, C.T.

1997-05-02T23:59:59.000Z

439

In situ PEM fuel cell water measurements  

SciTech Connect

Efficient PEM fuel cell performance requires effective water management. The materials used, their durability, and the operating conditions under which fuel cells run, make efficient water management within a practical fuel cell system a primary challenge in developing commercially viable systems. We present experimental measurements of water content within operating fuel cells. in response to operational conditions, including transients and freezing conditions. To help understand the effect of components and operations, we examine water transport in operating fuel cells, measure the fuel cell water in situ and model the water transport within the fuel cell. High Frequency Resistance (HFR), AC Impedance and Neutron imaging (using NIST's facilities) were used to measure water content in operating fuel cells with various conditions, including current density, relative humidity, inlet flows, flow orientation and variable GDL properties. Ice formation in freezing cells was also monitored both during operation and shut-down conditions.

Borup, Rodney L [Los Alamos National Laboratory; Mukundan, Rangachary [Los Alamos National Laboratory; Davey, John R [Los Alamos National Laboratory; Spendalow, Jacob S [Los Alamos National Laboratory

2008-01-01T23:59:59.000Z

440

Renewable Fuels and Lubricants Laboratory (Fact Sheet)  

SciTech Connect

This fact sheet describes the Renewable Fuels and Lubricants (ReFUEL) Laboratory at the U.S. Department of Energy National Renewable Energy Laboratory (NREL) is a state-of-the-art research and testing facility for advanced fuels and vehicles. Research and development aims to improve vehicle efficiency and overcome barriers to the increased use of renewable diesel and other nonpetroleum-based fuels, such as biodiesel and synthetic diesel derived from biomass. The ReFUEL Laboratory features a chassis dynamometer for vehicle performance and emissions research, two engine dynamometer test cells for advanced fuels research, and precise emissions analysis equipment. As a complement to these capabilities, detailed studies of fuel properties, with a focus on ignition quality, are performed at NREL's Fuel Chemistry Laboratory.

Not Available

2014-08-01T23:59:59.000Z

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


441

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

442

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

443

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

444

METHODOLOGIES FOR REVIEW OF THE HEALTH AND SAFETY ASPECTS OF PROPOSED NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL SITES AND FACILITIES. VOLUME 9 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

emergencies, Le. , accidents at nuclear facilities, there isas a result of nuclear accidents; these are the Protectiveassociated with a nuclear accident is of greater importance

Nero, A.V.

2010-01-01T23:59:59.000Z

445

Statement of work for sytem design and engineering of the spent nuclear fuel multi-cansiter overpack  

SciTech Connect

This Statement of Work (SOW) describes the work scope for the preparation of the Phase 2 (final) design for the Multiple Canister Overpack (MCO) equipment. The MCO is to be used as the radiological containment device for the Spent Nuclear Fuel (SNF) assemblies, currently in wet storage in K East and West Basins, to be transported and stored in the Canister Storage Building (CSB) until final disposal facilities are made available. The engineering services contractor will be requested to provide reports, studies, analyses, engineering, drawings, specifications, estimates and schedules. The overall goal of this task order is to do the following: 1. Prepare a fabrication specification, ASME Code exception report, a packaging, shipping and warehouse plan, and detailed fabrication drawings of the MCO in accordance with the MCO Performance Specification (HNF-S-0426, Rev. 3) for procurement activities by the SNF MCO Subproject. 2. Establish and maintain a comment data base on the comments, resolutions, changes to the design of the MCO. 3. Support fabrication activities through the review of vendor fabrication drawings and shop test reports.

Smith, K.E., Fluor Daniel Hanford

1997-03-03T23:59:59.000Z

446

International Facility Management Association Strategic Facility  

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

Facility Management Association Facility Management Association Strategic Facility Planning: A WhIte PAPer Strategic Facility Planning: A White Paper on Strategic Facility Planning © 2009 | International Facility Management Association For additional information, contact: 1 e. Greenway Plaza, Suite 1100 houston, tX 77046-0104 USA P: + 1-713-623-4362 F: + 1-713-623-6124 www.ifma.org taBle OF cOntentS PreFace ......................................................... 2 executive Summary .................................... 3 Overview ....................................................... 4 DeFinitiOn OF Strategic Facility Planning within the Overall cOntext OF Facility Planning ................. 5 SPecializeD analySeS ................................ 9 OrganizatiOnal aPPrOacheS tO SFP ... 10 the SFP PrOceSS .......................................

447

Nuclear Power Generating Facilities (Maine) | Department of Energy  

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

Nuclear Power Generating Facilities (Maine) Nuclear Power Generating Facilities (Maine) Nuclear Power Generating Facilities (Maine) < Back Eligibility Agricultural Commercial Construction Fed. Government Fuel Distributor General Public/Consumer Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Low-Income Residential Multi-Family Residential Municipal/Public Utility Nonprofit Residential Retail Supplier Rural Electric Cooperative Schools State/Provincial Govt Systems Integrator Transportation Tribal Government Utility Program Info State Maine Program Type Siting and Permitting Provider Radiation Control Program The first subchapter of the statute concerning Nuclear Power Generating Facilities provides for direct citizen participation in the decision to construct any nuclear power generating facility in Maine. The Legislature

448

Sales and Use Tax Exemption for Electrical Generating Facilities |  

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

Sales and Use Tax Exemption for Electrical Generating Facilities Sales and Use Tax Exemption for Electrical Generating Facilities Sales and Use Tax Exemption for Electrical Generating Facilities < Back Eligibility Commercial Industrial Savings Category Bioenergy Commercial Heating & Cooling Manufacturing Buying & Making Electricity Alternative Fuel Vehicles Hydrogen & Fuel Cells Water Solar Wind Program Info State North Dakota Program Type Sales Tax Incentive Rebate Amount 100% Provider Office of the State Tax Commissioner Electrical generating facilities are exempt from sales and use taxes in North Dakota. The exemption is granted for the purchase of building materials, production equipment, and any other tangible personal property that is used for constructing or expanding the facility. In order to qualify, the facility must have at least one electrical generation unity

449

Biofuels Company Builds New Facility in Nebraska | Department of Energy  

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

Biofuels Company Builds New Facility in Nebraska Biofuels Company Builds New Facility in Nebraska Biofuels Company Builds New Facility in Nebraska March 24, 2010 - 2:54pm Addthis Novozymes was awarded a $28.4 million tax credit to build an enzyme facility in Blair, N