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1

High-voltage-compatible, fully depleted CCDs  

SciTech Connect

We describe charge-coupled device (CCD) developmentactivities at the Lawrence Berkeley National Laboratory (LBNL).Back-illuminated CCDs fabricated on 200-300 mu m thick, fully depleted,high-resistivity silicon substrates are produced in partnership with acommercial CCD foundry.The CCDs are fully depleted by the application ofa substrate bias voltage. Spatial resolution considerations requireoperation of thick, fully depleted CCDs at high substrate bias voltages.We have developed CCDs that are compatible with substrate bias voltagesof at least 200V. This improves spatial resolution for a given thickness,and allows for full depletion of thicker CCDs than previously considered.We have demonstrated full depletion of 650-675 mu m thick CCDs, withpotential applications in direct x-ray detection. In this work we discussthe issues related to high-voltage operation of fully depleted CCDs, aswell as experimental results on high-voltage-compatible CCDs.

Holland, Stephen E.; Bebek, Chris J.; Dawson, Kyle S.; Emes, JohnE.; Fabricius, Max H.; Fairfield, Jessaym A.; Groom, Don E.; Karcher, A.; Kolbe, William F.; Palaio, Nick P.; Roe, Natalie A.; Wang, Guobin

2006-05-15T23:59:59.000Z

2

Effects of Ionizing Radiation on Digital Single Event Transients in a 180-nm Fully Depleted SOI Process  

E-Print Network (OSTI)

Effects of ionizing radiation on single event transients are reported for Fully Depleted SOI (FDSOI) technology using experiments and simulations. Logic circuits, i.e. CMOS inverter chains, were irradiated with cobalt-60 ...

Keast, Craig L.

3

Carrier transport and collection in fully depleted semiconductors by a combined action of the space charge field and the field due to electrode voltages  

DOE Patents (OSTI)

A semiconductor charge transport device and method for making same, characterized by providing a thin semiconductor wafer having rectifying junctions on its opposing major surfaces and including a small capacitance ohmic contact, in combination with bias voltage means and associated circuit means for applying a predetermined voltage to effectively deplete the wafer in regions thereof between the rectifying junctions and the ohmic contact. A charge transport device of the invention is usable as a drift chamber, a low capacitance detector, or a charge coupled device each constructed according to the methods of the invention for making such devices. Detectors constructed according to the principles of the invention are characterized by having significantly higher particle position indicating resolution than is attainable with prior art detectors, while at the same time requiring substantially fewer readout channels to realize such high resolution.

Rehak, Pavel (Patchogue, NY); Gatti, Emilio (Lesmo, IT)

1987-01-01T23:59:59.000Z

4

High-voltage-compatible, fully depleted CCDs  

E-Print Network (OSTI)

result of this high-voltage requirement, we have taken a di?voltage is necessary in order to meet the PSF requirementsrequirements for SNAP have resulted in a need to operate at substrate bias voltages

2006-01-01T23:59:59.000Z

5

Depleted Uranium  

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

Depleted Uranium Depleted Uranium Depleted Uranium line line Uranium Enrichment Depleted Uranium Health Effects Depleted Uranium Depleted uranium is uranium that has had some of its U-235 content removed. Over the last four decades, large quantities of uranium were processed by gaseous diffusion to produce uranium having a higher concentration of uranium-235 than the 0.72% that occurs naturally (called "enriched" uranium) for use in U.S. national defense and civilian applications. "Depleted" uranium is also a product of the enrichment process. However, depleted uranium has been stripped of some of its natural uranium-235 content. Most of the Department of Energy's (DOE) depleted uranium inventory contains between 0.2 to 0.4 weight-percent uranium-235, well

6

Prior Knowledge  

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

What do you know about Relativistic Lifetimes? What do you know about Relativistic Lifetimes?       Project Home - Prior Knowledge - Project Context - Resources Brainstorm In a small group write down everythingyou know about the applications of energy and momentum in HEP on butcher paper. At the same time write down questions or ideas that you are not sure about on another sheet of paper. After you have 10-20 good items, or just feel it is time to stop, go back and discuss each one. Look for connections between the items. Reorganize them into a diagram . . . this will serve as your first-order conceptual framework for discussing the energy-momentum relationship. These questions build a foundation for investigating this topic: What do we mean by the "lifetime" of a particle? Is it the time for

7

Charge Depleting:  

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

0.5 seconds 0.5 seconds Acceleration 1/4 Mile Time: 18.6 seconds Maximum Speed: 83.2 MPH Acceleration 1 Mile Maximum Speed: 100.6 MPH Charge Sustaining: Acceleration 0-60 MPH Time: 10.6 seconds Acceleration 1/4 Mile Time: 18.6 seconds Maximum Speed: 82.8 MPH Acceleration 1 Mile Maximum Speed: 101.9 MPH Brake Test @ 60 MPH Distance Required: 145.1 ft UDDS Fuel Economy 6 HWFET Fuel Economy 6,10 Distance (miles) Fuel Economy (mpg) AC Energy Consumed (kWh) 7 Distance (miles) Fuel Economy (mpg) AC Energy Consumed (kWh) 7 10 118.5 2.85 10 53.0 1.80 20 116.8 5.49 20 56.6 3.37 40 116.0 10.50 40 58.0 6.38 60 90.7 11.34 60 55.3 9.48 80 76.6 11.34 80 51.4 11.11 100 68.0 11.34 100 47.2 11.13 200 50.9 11.34 200 38.7 11.13 Fuel Economy with A/C Off 1 Cold Start Charge Depleting 2 : Fuel Economy: 119.7 MPG AC kWh Consumed 7 : 0.282 kWh/mi Charge Depleting

8

Fully depleted, back-illuminated charge-coupled devices ...  

silicon layer capped by indium tin oxide and silicon dioxide. ... supported by the Department of Energy under Contract DE ... silicon for solar cell applications ...

9

Depleted Uranium Hexafluoride Management  

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

OFFICE OF DEPLETED URANIUM HEXAFLUORIDE MANAGEMENT Issuance Of Final Report On Preconceptual Designs For Depleted Uranium Hexafluoride Conversion Plants The Department of Energy...

10

Depleted Uranium Health Effects  

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

Depleted Uranium Health Effects Depleted Uranium Health Effects Depleted Uranium line line Uranium Enrichment Depleted Uranium Health Effects Depleted Uranium Health Effects Discussion of health effects of external exposure, ingestion, and inhalation of depleted uranium. Depleted uranium is not a significant health hazard unless it is taken into the body. External exposure to radiation from depleted uranium is generally not a major concern because the alpha particles emitted by its isotopes travel only a few centimeters in air or can be stopped by a sheet of paper. Also, the uranium-235 that remains in depleted uranium emits only a small amount of low-energy gamma radiation. However, if allowed to enter the body, depleted uranium, like natural uranium, has the potential for both chemical and radiological toxicity with the two important target organs

11

FAQ 23-How much depleted uranium -- including depleted uranium...  

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

is stored in the United States? How much depleted uranium -- including depleted uranium hexafluoride -- is stored in the United States? In addition to the depleted uranium stored...

12

Battery depletion monitor  

SciTech Connect

A cmos inverter is used to compare pacemaker battery voltage to a referenced voltage. When the reference voltage exceeds the measured battery voltage, the inverter changes state to indicate battery depletion.

Lee, Y.S.

1982-01-26T23:59:59.000Z

13

Depleted uranium valuation  

SciTech Connect

The following uses for depleted uranium were examined to determine its value: a substitute for lead in shielding applications, feed material in gaseous diffusion enrichment facilities, feed material for an advanced enrichment concept, Mixed Oxide (MOx) diluent and blanket material in LMFBRs, and fertile material in LMFBR systems. A range of depleted uranium values was calculated for each of these applications. The sensitivity of these values to analysis assumptions is discussed. 9 tables.

Lewallen, M.A.; White, M.K.; Jenquin, U.P.

1979-04-01T23:59:59.000Z

14

Video: The Depleted Uranium Hexafluoride Story  

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

Depleted UF6 Story The Depleted Uranium Hexafluoride Story An overview of Uranium, its isotopes, the need and history of diffusive separation, the handling of the Depleted Uranium...

15

Depleted uranium management alternatives  

SciTech Connect

This report evaluates two management alternatives for Department of Energy depleted uranium: continued storage as uranium hexafluoride, and conversion to uranium metal and fabrication to shielding for spent nuclear fuel containers. The results will be used to compare the costs with other alternatives, such as disposal. Cost estimates for the continued storage alternative are based on a life-cycle of 27 years through the year 2020. Cost estimates for the recycle alternative are based on existing conversion process costs and Capital costs for fabricating the containers. Additionally, the recycle alternative accounts for costs associated with intermediate product resale and secondary waste disposal for materials generated during the conversion process.

Hertzler, T.J.; Nishimoto, D.D.

1994-08-01T23:59:59.000Z

16

Polyethylene Encapsulated Depleted Uranium  

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

Poly DU Poly DU Polyethylene Encapsulated Depleted Uranium Technology Description: Brookhaven National Laboratory (BNL) has completed preliminary work to investigate the feasibility of encapsulating DU in low density polyethylene to form a stable, dense product. DU loadings as high as 90 wt% were achieved. A maximum product density of 4.2 g/cm3 was achieved using UO3, but increased product density using UO2 is estimated at 6.1 g/cm3. Additional product density improvements up to about 7.2 g/cm3 were projected using DU aggregate in a hybrid technique known as micro/macroencapsulation.[1] A U.S. patent for this process has been received.[2] Figure 1 Figure 1: DU Encapsulated in polyethylene samples produced at BNL containing 80 wt % depleted UO3 A recent DU market study by Kapline Enterprises, Inc. for DOE thoroughly identified and rated potential applications and markets for DU metal and oxide materials.[3] Because of its workability and high DU loading capability, the polyethylene encapsulated DU could readily be fabricated as counterweights/ballast (for use in airplanes, helicopters, ships and missiles), flywheels, armor, and projectiles. Also, polyethylene encapsulated DU is an effective shielding material for both gamma and neutron radiation, with potential application for shielding high activity waste (e.g., ion exchange resins, glass gems), spent fuel dry storage casks, and high energy experimental facilities (e.g., accelerator targets) to reduce radiation exposures to workers and the public.

17

Depleted Uranium Hexafluoride Management  

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

for for DUF 6 Conversion Project Environmental Impact Statement Scoping Meetings November/December 2001 Overview Depleted Uranium Hexafluoride (DUF 6 ) Management Program DUF 6 EIS Scoping Briefing 2 DUF 6 Management Program Organizational Chart DUF 6 Management Program Organizational Chart EM-10 Policy EM-40 Project Completion EM-20 Integration EM-50 Science and Technology EM-31 Ohio DUF6 Management Program EM-32 Oak Ridge EM-33 Rocky Flats EM-34 Small Sites EM-30 Office of Site Closure Office of Environmental Management EM-1 DUF 6 EIS Scoping Briefing 3 DUF 6 Management Program DUF 6 Management Program * Mission: Safely and efficiently manage the DOE inventory of DUF 6 in a way that protects the health and safety of workers and the public, and protects the environment DUF 6 EIS Scoping Briefing 4 DUF 6 Inventory Distribution

18

The ultimate disposition of depleted uranium  

SciTech Connect

Significant amounts of the depleted uranium (DU) created by past uranium enrichment activities have been sold, disposed of commercially, or utilized by defense programs. In recent years, however, the demand for DU has become quite small compared to quantities available, and within the US Department of Energy (DOE) there is concern for any risks and/or cost liabilities that might be associated with the ever-growing inventory of this material. As a result, Martin Marietta Energy Systems, Inc. (Energy Systems), was asked to review options and to develop a comprehensive plan for inventory management and the ultimate disposition of DU accumulated at the gaseous diffusion plants (GDPs). An Energy Systems task team, under the chairmanship of T. R. Lemons, was formed in late 1989 to provide advice and guidance for this task. This report reviews options and recommends actions and objectives in the management of working inventories of partially depleted feed (PDF) materials and for the ultimate disposition of fully depleted uranium (FDU). Actions that should be considered are as follows. (1) Inspect UF{sub 6} cylinders on a semiannual basis. (2) Upgrade cylinder maintenance and storage yards. (3) Convert FDU to U{sub 3}O{sub 8} for long-term storage or disposal. This will include provisions for partial recovery of costs to offset those associated with DU inventory management and the ultimate disposal of FDU. Another recommendation is to drop the term tails'' in favor of depleted uranium'' or DU'' because the tails'' label implies that it is waste.'' 13 refs.

Not Available

1990-12-01T23:59:59.000Z

19

Depleted UF6 Overview Presentation  

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

Information network Web Site. The presentation covers the following topics: The uranium mining and enrichment processes - how depleted UF6 is created, How and where...

20

Fully Integrating the Design Process  

SciTech Connect

The basic approach to designing nuclear facilities in the United States does not currently reflect the routine consideration of proliferation resistance and international safeguards. The fully integrated design process is an approach for bringing consideration of international safeguards and proliferation resistance, together with state safeguards and security, fully into the design process from the very beginning, while integrating them sensibly and synergistically with the other project functions. In view of the recently established GNEP principles agreed to by the United States and at least eighteen other countries, this paper explores such an integrated approach, and its potential to help fulfill the new internationally driven design requirements with improved efficiencies and reduced costs.

T.A. Bjornard; R.S. Bean

2008-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "fully depleted prior" 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

Fully-automated white matter hyperintensity detection with anatomical prior knowledge and without FLAIR.  

E-Print Network (OSTI)

Table 1: Intraclass correlation coe?cients (ICCs) between ground-truthTable 2: Intraclass correlation coe?cients (ICCs) between ground-truth

Schwarz, Christopher; Fletcher, Evan; DeCarli, Charles; Carmichael, Owen

2009-01-01T23:59:59.000Z

22

Priors in quantum Bayesian inference  

E-Print Network (OSTI)

In quantum Bayesian inference problems, any conclusions drawn from a finite number of measurements depend not only on the outcomes of the measurements but also on a prior. Here we show that, in general, the prior remains important even in the limit of an infinite number of measurements. We illustrate this point with several examples where two priors lead to very different conclusions given the same measurement data.

Christopher A. Fuchs; Ruediger Schack

2009-06-09T23:59:59.000Z

23

News Media Exits for Depleted Uranium and Depleted UF6 Articles  

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

line line Archived News and Events News Media Links News Media Exits for Depleted Uranium and Depleted UF6 Articles Online editions of newspapers that cover Depleted Uranium...

24

Fully synthetic taped insulation cables  

DOE Patents (OSTI)

A high voltage oil-impregnated electrical cable with fully polymer taped insulation operable to 765 kV. Biaxially oriented, specially processed, polyethylene, polybutene or polypropylene tape with an embossed pattern is wound in multiple layers over a conductive core with a permeable screen around the insulation. Conventional oil which closely matches the dielectric constant of the tape is used, and the cable can be impregnated after field installation because of its excellent impregnation characteristics.

Forsyth, Eric B. (Brookhaven, NY); Muller, Albert C. (Center Moriches, NY)

1984-01-01T23:59:59.000Z

25

A modern depleted uranium manufacturing facility  

SciTech Connect

The Specific Manufacturing Capabilities (SMC) Project located at the Idaho National Engineering Laboratory (INEL) and operated by Lockheed Martin Idaho Technologies Co. (LMIT) for the Department of Energy (DOE) manufactures depleted uranium for use in the U.S. Army MIA2 Abrams Heavy Tank Armor Program. Since 1986, SMC has fabricated more than 12 million pounds of depleted uranium (DU) products in a multitude of shapes and sizes with varying metallurgical properties while maintaining security, environmental, health and safety requirements. During initial facility design in the early 1980`s, emphasis on employee safety, radiation control and environmental consciousness was gaining momentum throughout the DOE complex. This fact coupled with security and production requirements forced design efforts to focus on incorporating automation, local containment and computerized material accountability at all work stations. The result was a fully automated production facility engineered to manufacture DU armor packages with virtually no human contact while maintaining security, traceability and quality requirements. This hands off approach to handling depleted uranium resulted in minimal radiation exposures and employee injuries. Construction of the manufacturing facility was complete in early 1986 with the first armor package certified in October 1986. Rolling facility construction was completed in 1987 with the first certified plate produced in the fall of 1988. Since 1988 the rolling and manufacturing facilities have delivered more than 2600 armor packages on schedule with 100% final product quality acceptance. During this period there was an annual average of only 2.2 lost time incidents and a single individual maximum radiation exposure of 150 mrem. SMC is an example of designing and operating a facility that meets regulatory requirements with respect to national security, radiation control and personnel safety while achieving production schedules and product quality.

Zagula, T.A.

1995-07-01T23:59:59.000Z

26

Improved Spatial Resolution in Thick, Fully-Depleted CCDs with Enhanced Red Sensitivity  

E-Print Network (OSTI)

the fiber is fed into a brass tube on the x-y-z translationis collimated by a 25 mm long brass tube. Scattered light isthread on the inside of the brass tube and absorbed by the

Fairfield, Jessamyn A.

2005-01-01T23:59:59.000Z

27

Fully Depleted 4H-SiC SOI MESFET with Graded Channel Doping ...  

Science Conference Proceedings (OSTI)

... as Shielding Materials for Electromagnetic Interference and Radiation Shielding ... for Nuclear Power Plant Steam Generators during Cold-Working Process.

28

Fully-depleted, back-illuminated charge-coupled devices fabricated on high-resistivity silicon  

E-Print Network (OSTI)

layer capped by indium tin oxide and silicon dioxide. Thisand ? 600 ? of indium tin oxide (ITO) A is deposited [27].

Holland, Stephen E.; Groom, Donald E.; Palaio, Nick P.; Stover, Richard J.; Wei, Mingzhi

2002-01-01T23:59:59.000Z

29

Heavy-ion-induced digital single event transients in a 180 nm fully depleted SOI process  

E-Print Network (OSTI)

Heavy-ion-induced single events transients (SETs) in advanced digital circuits are a significant reliability issue for space-based systems. SET pulse widths in silicon-on-insulator (SOI) technologies are often significantly ...

Gouker, Pascale M.

30

Depleted Uranium (DU) Dioxide Fill  

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

Fill Depleted Uranium (DU) Dioxide Fill DU dioxide in the form of sand may be used to fill the void spaces in the waste package after the package is loaded with SNF. This...

31

Depleted UF6 Health Risks  

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

(depleted UF6) is released to the atmosphere, the uranium compounds and hydrogen fluoride (HF) gas that are formed by reaction with moisture in the air can be chemically...

32

Depleted UF6 Internet Resources  

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

DUF6 Guide DU Uses DUF6 Management and Uses DUF6 Conversion EIS Documents News FAQs Internet Resources Glossary Home Internet Resources Depleted UF6 Internet Resources Links...

33

FAQ 6-What is depleted uranium?  

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

depleted uranium? What is depleted uranium? Depleted uranium is created during the processing that is done to make natural uranium suitable for use as fuel in nuclear power plants...

34

Effect of Shim Arm Depletion in the NBSR  

SciTech Connect

The cadmium shim arms in the NBSR undergo burnup during reactor operation and hence, require periodic replacement. Presently, the shim arms are replaced after every 25 cycles to guarantee they can maintain sufficient shutdown margin. Two prior reports document the expected change in the 113Cd distribution because of the shim arm depletion. One set of calculations was for the present high-enriched uranium fuel and the other for the low-enriched uranium fuel when it was in the COMP7 configuration (7 inch fuel length vs. the present 11 inch length). The depleted 113Cd distributions calculated for these cores were applied to the current design for an equilibrium low-enriched uranium core. This report details the predicted effects, if any, of shim arm depletion on the shim arm worth, the shutdown margin, power distributions and kinetics parameters.

Hanson A. H.; Brown N.; Diamond, D.J.

2013-02-22T23:59:59.000Z

35

Environmental Risks of Depleted UF6 Disposal  

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

Depleted UF6 Environmental Risks line line Storage Conversion Manufacturing Disposal Environmental Risks of Depleted UF6 Disposal A discussion of the environmental impacts...

36

Pennsylvania Natural Gas Underground Storage Depleted Fields...  

U.S. Energy Information Administration (EIA) Indexed Site

Underground Storage Depleted Fields Capacity (Million Cubic Feet) Pennsylvania Natural Gas Underground Storage Depleted Fields Capacity (Million Cubic Feet) Decade Year-0 Year-1...

37

FAQ 26-Are there any uses for depleted uranium?  

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

uses for depleted uranium? Are there any uses for depleted uranium? Several current and potential uses exist for depleted uranium. Depleted uranium could be mixed with highly...

38

Depleted UF6 Management Program Overview Presentation  

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

Depleted UF6 Management Program Overview Presentation Cylinders Photo Next Screen A Legacy of Uranium Enrichment...

39

PRETREATMENT OF BIOMASS PRIOR TO LIQUEFACTION  

E-Print Network (OSTI)

UC-61 PRETREATMENT OF BIOMASS PRIOR TO LIQUEFACTION Larry L.10093 PRETREATMENT OF BIOMASS PRIOR TO LIQUEFACTION Larry L.hydrolytic pretreatment to biomass feedstocks, higher acid

Schaleger, Larry L.

2012-01-01T23:59:59.000Z

40

Potential Uses of Depleted Uranium  

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

POTENTIAL USES OF DEPLETED URANIUM POTENTIAL USES OF DEPLETED URANIUM Robert R. Price U.S. Department of Energy Germantown, Maryland 20874 M. Jonathan Haire and Allen G. Croff Chemical Technology Division Oak Ridge National Laboratory * Oak Ridge, Tennessee 37831-6180 June 2000 For American Nuclear Society 2000 International Winter and Embedded Topical Meetings Washington, D.C. November 12B16, 2000 The submitted manuscript has been authored by a contractor of the U.S. Government under contract DE-AC05-00OR22725. Accordingly, the U.S. Government retains a nonexclusive, royalty-free license to publish or reproduce the published form of this contribution, or allow others to do so, for U.S. Government purposes. _________________________

Note: This page contains sample records for the topic "fully depleted prior" 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

Depleted Uranium Uses Research and Development  

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

DU Uses DU Uses Depleted Uranium Uses Research & Development A Depleted Uranium Uses Research and Development Program was initiated to explore beneficial uses of depleted uranium (DU) and other materials resulting from conversion of depleted UF6. A Depleted Uranium Uses Research and Development Program was initiated to explore the safe, beneficial use of depleted uranium and other materials resulting from conversion of depleted UF6 (e.g., fluorine and empty carbon steel cylinders) for the purposes of resource conservation and cost savings compared with disposal. This program explored the risks and benefits of several depleted uranium uses, including uses as a radiation shielding material, a catalyst, and a semi-conductor material in electronic devices.

42

Fully localized two-dimensional embedded solitons  

Science Conference Proceedings (OSTI)

We report the prediction of fully localized two-dimensional embedded solitons. These solitons are obtained in a quasi-one-dimensional waveguide array which is periodic along one spatial direction and localized along the orthogonal direction. Under appropriate nonlinearity, these solitons are found to exist inside the Bloch bands (continuous spectrum) of the waveguide and thus are embedded solitons. These embedded solitons are fully localized along both spatial directions. In addition, they are fully stable under perturbations.

Yang Jianke [Department of Mathematics and Statistics, University of Vermont, Burlington, Vermont 05401 (United States)

2010-11-15T23:59:59.000Z

43

A geometric view of conjugate priors  

Science Conference Proceedings (OSTI)

In Bayesian machine learning, conjugate priors are popular, mostly due to mathematical convenience. In this paper, we show that there are deeper reasons for choosing a conjugate prior. Specifically, we formulate the conjugate prior in the form of Bregman ... Keywords: Bregman divergence, Conjugate prior, Exponential families, Generative models

Arvind Agarwal; Hal Daumé, III

2010-10-01T23:59:59.000Z

44

Depleted uranium disposal options evaluation  

SciTech Connect

The Department of Energy (DOE), Office of Environmental Restoration and Waste Management, has chartered a study to evaluate alternative management strategies for depleted uranium (DU) currently stored throughout the DOE complex. Historically, DU has been maintained as a strategic resource because of uses for DU metal and potential uses for further enrichment or for uranium oxide as breeder reactor blanket fuel. This study has focused on evaluating the disposal options for DU if it were considered a waste. This report is in no way declaring these DU reserves a ``waste,`` but is intended to provide baseline data for comparison with other management options for use of DU. To PICS considered in this report include: Retrievable disposal; permanent disposal; health hazards; radiation toxicity and chemical toxicity.

Hertzler, T.J.; Nishimoto, D.D.; Otis, M.D. [Science Applications International Corp., Idaho Falls, ID (United States). Waste Management Technology Div.

1994-05-01T23:59:59.000Z

45

Depleted Argon from Underground Sources  

Science Conference Proceedings (OSTI)

Argon is a strong scintillator and an ideal target for Dark Matter detection; however {sup 39}Ar contamination in atmospheric argon from cosmic ray interactions limits the size of liquid argon dark matter detectors due to pile-up. Argon from deep underground is depleted in {sup 39}Ar due to the cosmic ray shielding of the earth. In Cortez, Colorado, a CO{sub 2} well has been discovered to contain approximately 600 ppm of argon as a contamination in the CO{sub 2}. We first concentrate the argon locally to 3% in an Ar, N{sub 2}, and He mixture, from the CO{sub 2} through chromatographic gas separation, and then the N{sub 2} and He will be removed by continuous distillation to purify the argon. We have collected 26 kg of argon from the CO{sub 2} facility and a cryogenic distillation column is under construction at Fermilab to further purify the argon.

Back, H. O.; Galbiati, C.; Goretti, A.; Loer, B.; Montanari, D.; Mosteiro, P. [Department of Physics, Princeton University, Jadwin Hall, Princeton, NJ 08544 (United States); Alexander, T.; Alton, A.; Rogers, H. [Augustana College, Physics Department, 2001 South Summit Ave., Sioux Fall, SD 57197 (United States); Kendziora, C.; Pordes, S. [Fermi National Accelerator Laboratory, P.O. Box 500, Batavia, IL 60510 (United States)

2011-04-27T23:59:59.000Z

46

Prior NIST Work in Public Safety Communications  

Science Conference Proceedings (OSTI)

... Prior NIST Work in Public Safety Communications. ... Distributed Testbed for First Responders; Guide to Public Safety Communication Technologies.

2013-05-26T23:59:59.000Z

47

Time-Dependent Fully Nonlinear Geostrophic Adjustment  

Science Conference Proceedings (OSTI)

Shock-capturing numerical methods are employed to integrate the fully nonlinear, rotating 1D shallow-water equations starting from steplike nongeostrophic initial conditions (a Rossby adjustment problem). Such numerical methods allow one to ...

Allen C. Kuo; Lorenzo M. Polvani

1997-08-01T23:59:59.000Z

48

,"Natural Gas Depleted Fields Storage Capacity "  

U.S. Energy Information Administration (EIA) Indexed Site

Depleted Fields Storage Capacity " ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","Natural...

49

Depleted Uranium De-conversion  

E-Print Network (OSTI)

This Environmental Report (ER) constitutes one portion of an application being submitted by International Isotopes Fluorine Products (IIFP) to construct and operate a facility that will utilize depleted DUF6 to produce high purity inorganic fluorides, uranium oxides, and anhydrous hydrofluoric acid. The proposed IIFP facility will be located near Hobbs, New Mexico. IIFP has prepared the ER to meet the requirements specified in 10 CFR 51, Subpart A, particularly those requirements set forth in 10 CFR 51.45(b)-(e). The organization of this ER is generally consistent with NUREG-1748, “Environmental Review Guidance for Licensing Actions Associated with NMSS Programs, Final Report.” The Environmental Report for this proposed facility provides information that is specifically required by the NRC to assist it in meeting its obligations under the National Environmental Policy Act (NEPA) of 1969 and the agency’s NEPA-implementing regulations. This ER demonstrates that the environmental protection measures proposed by IIFP are adequate to protect both the environment and the health and safety of the public. This Environmental Report evaluates the potential environmental impacts of the Proposed Action and its reasonable alternatives. This ER also describes the environment potentially affected by IIEF’s proposal,

Fluorine Extraction Process

2009-01-01T23:59:59.000Z

50

Depleted argon from underground sources  

Science Conference Proceedings (OSTI)

Argon is a powerful scintillator and an excellent medium for detection of ionization. Its high discrimination power against minimum ionization tracks, in favor of selection of nuclear recoils, makes it an attractive medium for direct detection of WIMP dark matter. However, cosmogenic {sup 39}Ar contamination in atmospheric argon limits the size of liquid argon dark matter detectors due to pile-up. The cosmic ray shielding by the earth means that Argon from deep underground is depleted in {sup 39}Ar. In Cortez Colorado a CO{sub 2} well has been discovered to contain approximately 500ppm of argon as a contamination in the CO{sub 2}. In order to produce argon for dark matter detectors we first concentrate the argon locally to 3-5% in an Ar, N{sub 2}, and He mixture, from the CO{sub 2} through chromatographic gas separation. The N{sub 2} and He will be removed by continuous cryogenic distillation in the Cryogenic Distillation Column recently built at Fermilab. In this talk we will discuss the entire extraction and purification process; with emphasis on the recent commissioning and initial performance of the cryogenic distillation column purification.

Back, H.O.; /Princeton U.; Alton, A.; /Augustana U. Coll.; Calaprice, F.; Galbiati, C.; Goretti, A.; /Princeton U.; Kendziora, C.; /Fermilab; Loer, B.; /Princeton U.; Montanari, D.; /Fermilab; Mosteiro, P.; /Princeton U.; Pordes, S.; /Fermilab

2011-09-01T23:59:59.000Z

51

FAQ 7-How is depleted uranium produced?  

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

How is depleted uranium produced? How is depleted uranium produced? How is depleted uranium produced? Depleted uranium is produced during the uranium enrichment process. In the United States, uranium is enriched through the gaseous diffusion process in which the compound uranium hexafluoride (UF6) is heated and converted from a solid to a gas. The gas is then forced through a series of compressors and converters that contain porous barriers. Because uranium-235 has a slightly lighter isotopic mass than uranium-238, UF6 molecules made with uranium-235 diffuse through the barriers at a slightly higher rate than the molecules containing uranium-238. At the end of the process, there are two UF6 streams, with one stream having a higher concentration of uranium-235 than the other. The stream having the greater uranium-235 concentration is referred to as enriched UF6, while the stream that is reduced in its concentration of uranium-235 is referred to as depleted UF6. The depleted UF6 can be converted to other chemical forms, such as depleted uranium oxide or depleted uranium metal.

52

THE RIMINI PROTOCOL Oil Depletion Protocol  

E-Print Network (OSTI)

Soaring oil prices have drawn attention to the issue of the relative supply and demand for crude oil. This fact alone tells us that oil is a finite resource, which in turn means that it is subject to depletion1 THE RIMINI PROTOCOL an Oil Depletion Protocol ~ Heading Off Economic Chaos and Political Conflict

Keeling, Stephen L.

53

Bayesian Generic Priors for Causal Learning  

E-Print Network (OSTI)

informal argumenta- tion: A Bayesian approach to reasoningcausal learning using Bayesian generic priors on generativeHolyoak, K. J. (2007). Bayesian models of judgments of

Lu, Hongjing; Yuille, Alan L.; Liljeholm, Mimi; Cheng, Patricia W.; Holyoak, Keith J.

2008-01-01T23:59:59.000Z

54

Bayesian Generic Priors for Causal Learning  

E-Print Network (OSTI)

informal argumenta- tion: A Bayesian approach to reasoningcausal learning using Bayesian generic priors on generativeHolyoak, K. J. (2007). Bayesian models of judgments of

Hongjing Lu; Alan L. Yuille; Mimi Liljeholm; Patricia W. Cheng; Keith J. Holyoak

2011-01-01T23:59:59.000Z

55

Towards a scalable fully-implicit fully-coupled resistive MHD formulation with stabilized FE methods  

Science Conference Proceedings (OSTI)

This paper explores the development of a scalable, nonlinear, fully-implicit stabilized unstructured finite element (FE) capability for 2D incompressible (reduced) resistive MHD. The discussion considers the implementation of a stabilized FE formulation ... Keywords: Direct-to-steady-state, Fully-implicit, Large-scale parallel, Multilevel preconditioner, Newton-Krylov, Resistive MHD, Stabilized finite element

J. N. Shadid; R. P. Pawlowski; J. W. Banks; L. Chacón; P. T. Lin; R. S. Tuminaro

2010-10-01T23:59:59.000Z

56

Depleted uranium: A DOE management guide  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy (DOE) has a management challenge and financial liability in the form of 50,000 cylinders containing 555,000 metric tons of depleted uranium hexafluoride (UF{sub 6}) that are stored at the gaseous diffusion plants. The annual storage and maintenance cost is approximately $10 million. This report summarizes several studies undertaken by the DOE Office of Technology Development (OTD) to evaluate options for long-term depleted uranium management. Based on studies conducted to date, the most likely use of the depleted uranium is for shielding of spent nuclear fuel (SNF) or vitrified high-level waste (HLW) containers. The alternative to finding a use for the depleted uranium is disposal as a radioactive waste. Estimated disposal costs, utilizing existing technologies, range between $3.8 and $11.3 billion, depending on factors such as applicability of the Resource Conservation and Recovery Act (RCRA) and the location of the disposal site. The cost of recycling the depleted uranium in a concrete based shielding in SNF/HLW containers, although substantial, is comparable to or less than the cost of disposal. Consequently, the case can be made that if DOE invests in developing depleted uranium shielded containers instead of disposal, a long-term solution to the UF{sub 6} problem is attained at comparable or lower cost than disposal as a waste. Two concepts for depleted uranium storage casks were considered in these studies. The first is based on standard fabrication concepts previously developed for depleted uranium metal. The second converts the UF{sub 6} to an oxide aggregate that is used in concrete to make dry storage casks.

NONE

1995-10-01T23:59:59.000Z

57

Audit Report on "Depleted Uranium Hexafluoride Conversion," DOE...  

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

Marketing Administration Other Agencies You are here Home Audit Report on "Depleted Uranium Hexafluoride Conversion," DOEIG-0642 Audit Report on "Depleted Uranium Hexafluoride...

58

Follow-up of Depleted Uranium Hexafluoride Conversion, IG-0751...  

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

Marketing Administration Other Agencies You are here Home Follow-up of Depleted Uranium Hexafluoride Conversion, IG-0751 Follow-up of Depleted Uranium Hexafluoride...

59

Depleted Uranium Operations at the Y-12 National Security Complex...  

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

Sites Power Marketing Administration Other Agencies You are here Home Depleted Uranium Operations at the Y-12 National Security Complex, G-0570 Depleted Uranium Operations...

60

Depleted UF6 Production and Handling Slide Presentation  

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

Production and Handling Depleted UF6 Production and Handling Slide Presentation An online slide presentation about production and handling of depleted UF6, from mining of uranium...

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61

FAQ 14-What does a depleted uranium hexafluoride cylinder look...  

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

depleted uranium hexafluoride cylinder look like? What does a depleted uranium hexafluoride cylinder look like? A picture is worth a thousand words The pictures below show typical...

62

California Working Natural Gas Underground Storage Depleted Fields...  

U.S. Energy Information Administration (EIA) Indexed Site

Natural Gas Underground Storage Depleted Fields Capacity (Million Cubic Feet) California Working Natural Gas Underground Storage Depleted Fields Capacity (Million Cubic...

63

EIA - Natural Gas Pipeline Network - Depleted Reservoir Storage...  

Annual Energy Outlook 2012 (EIA)

Depleted Reservoir Storage Configuration About U.S. Natural Gas Pipelines - Transporting Natural Gas based on data through 20072008 with selected updates Depleted Production...

64

Production and Handling Slide 42: Typical Depleted Cylinder Storage...  

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

Typical Depleted Cylinder Storage Yard Skip Presentation Navigation First Slide Previous Slide Next Slide Last Presentation Table of Contents Typical Depleted Cylinder Storage Yard...

65

Maryland Natural Gas Underground Storage Depleted Fields Capacity...  

U.S. Energy Information Administration (EIA) Indexed Site

Underground Storage Depleted Fields Capacity (Million Cubic Feet) Maryland Natural Gas Underground Storage Depleted Fields Capacity (Million Cubic Feet) Decade Year-0 Year-1 Year-2...

66

Tennessee Natural Gas Underground Storage Depleted Fields Capacity...  

U.S. Energy Information Administration (EIA) Indexed Site

Underground Storage Depleted Fields Capacity (Million Cubic Feet) Tennessee Natural Gas Underground Storage Depleted Fields Capacity (Million Cubic Feet) Decade Year-0 Year-1...

67

Nebraska Natural Gas Underground Storage Depleted Fields Capacity...  

U.S. Energy Information Administration (EIA) Indexed Site

Underground Storage Depleted Fields Capacity (Million Cubic Feet) Nebraska Natural Gas Underground Storage Depleted Fields Capacity (Million Cubic Feet) Decade Year-0 Year-1 Year-2...

68

Arkansas Natural Gas Underground Storage Depleted Fields Capacity...  

U.S. Energy Information Administration (EIA) Indexed Site

Underground Storage Depleted Fields Capacity (Million Cubic Feet) Arkansas Natural Gas Underground Storage Depleted Fields Capacity (Million Cubic Feet) Decade Year-0 Year-1 Year-2...

69

Colorado Natural Gas Underground Storage Depleted Fields Capacity...  

U.S. Energy Information Administration (EIA) Indexed Site

Underground Storage Depleted Fields Capacity (Million Cubic Feet) Colorado Natural Gas Underground Storage Depleted Fields Capacity (Million Cubic Feet) Decade Year-0 Year-1 Year-2...

70

Oklahoma Natural Gas Underground Storage Depleted Fields Capacity...  

U.S. Energy Information Administration (EIA) Indexed Site

Underground Storage Depleted Fields Capacity (Million Cubic Feet) Oklahoma Natural Gas Underground Storage Depleted Fields Capacity (Million Cubic Feet) Decade Year-0 Year-1 Year-2...

71

Oregon Natural Gas Underground Storage Depleted Fields Capacity...  

U.S. Energy Information Administration (EIA) Indexed Site

Underground Storage Depleted Fields Capacity (Million Cubic Feet) Oregon Natural Gas Underground Storage Depleted Fields Capacity (Million Cubic Feet) Decade Year-0 Year-1 Year-2...

72

Ohio Natural Gas Underground Storage Depleted Fields Capacity...  

U.S. Energy Information Administration (EIA) Indexed Site

Underground Storage Depleted Fields Capacity (Million Cubic Feet) Ohio Natural Gas Underground Storage Depleted Fields Capacity (Million Cubic Feet) Decade Year-0 Year-1 Year-2...

73

Montana Natural Gas Underground Storage Depleted Fields Capacity...  

U.S. Energy Information Administration (EIA) Indexed Site

Underground Storage Depleted Fields Capacity (Million Cubic Feet) Montana Natural Gas Underground Storage Depleted Fields Capacity (Million Cubic Feet) Decade Year-0 Year-1 Year-2...

74

New Mexico Working Natural Gas Underground Storage Depleted Fields...  

U.S. Energy Information Administration (EIA) Indexed Site

Natural Gas Underground Storage Depleted Fields Capacity (Million Cubic Feet) New Mexico Working Natural Gas Underground Storage Depleted Fields Capacity (Million Cubic Feet)...

75

Findings from the 2004 Fully Automated Demand Response Tests...  

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

the 2004 Fully Automated Demand Response Tests in Large Facilities Title Findings from the 2004 Fully Automated Demand Response Tests in Large Facilities Publication Type Report...

76

Hierarchical 3D diffusion wavelet shape priors  

E-Print Network (OSTI)

In this paper, we propose a novel representation of prior knowledge for image segmentation, using diffusion wavelets that can reflect arbitrary continuous interdependencies in shape data. The application of diffusion ...

Langs, Georg

77

The New MCNP6 Depletion Capability  

SciTech Connect

The first MCNP based inline Monte Carlo depletion capability was officially released from the Radiation Safety Information and Computational Center as MCNPX 2.6.0. Both the MCNP5 and MCNPX codes have historically provided a successful combinatorial geometry based, continuous energy, Monte Carlo radiation transport solution for advanced reactor modeling and simulation. However, due to separate development pathways, useful simulation capabilities were dispersed between both codes and not unified in a single technology. MCNP6, the next evolution in the MCNP suite of codes, now combines the capability of both simulation tools, as well as providing new advanced technology, in a single radiation transport code. We describe here the new capabilities of the MCNP6 depletion code dating from the official RSICC release MCNPX 2.6.0, reported previously, to the now current state of MCNP6. NEA/OECD benchmark results are also reported. The MCNP6 depletion capability enhancements beyond MCNPX 2.6.0 reported here include: (1) new performance enhancing parallel architecture that implements both shared and distributed memory constructs; (2) enhanced memory management that maximizes calculation fidelity; and (3) improved burnup physics for better nuclide prediction. MCNP6 depletion enables complete, relatively easy-to-use depletion calculations in a single Monte Carlo code. The enhancements described here help provide a powerful capability as well as dictate a path forward for future development to improve the usefulness of the technology.

Fensin, Michael Lorne [Los Alamos National Laboratory; James, Michael R. [Los Alamos National Laboratory; Hendricks, John S. [Los Alamos National Laboratory; Goorley, John T. [Los Alamos National Laboratory

2012-06-19T23:59:59.000Z

78

Depleted Uranium (DU) Cermet Waste Package  

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

Package Package Depleted Uranium (DU) Cermet Waste Package The steel components of the waste package could be replaced with a uranium cermet. The cermet contains uranium dioxide particulates, which are embedded in steel. Cermets are made with outer layers of clean steel; thus, there is no radiation-contamination hazard in handling the waste packages. Because cermets are made of the same materials that would normally be found in the YM repository (uranium dioxide and steel), there are no chemical compatibility issues. From half to all of the DU inventory in the United States could be used for this application. Depleted Uranium Dioxide Steel Cermet Cross Section of a Depleted Uranium Dioxide Steel Cermet Follow the link below for more information on Cermets:

79

Microsoft Word - LibraryofPriorRulemakings.doc  

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

Library of Prior Rulemakings Library of Prior Rulemakings List of prior final rules amending the DEAR You may view any of these by accessing http://www.gpoaccess.gov/fr/retrieve.html and entering the Federal Register document year and page number. Either print this page or write down the year and page number before accessing the GPO page as you will need to insert the year and page number on the Federal Register page. Title Date Page Technical Amendments Security - Drug Testing Defense Priorities and Allocations Technical Revisions Cooperative Audit Strategy Make-or-Buy Elimination Research Misconduct Work for Others Conditional Payment of Fee Motor Vehicle Fuel Efficiency Affirmative Procurement Program National Industrial Security Program Patent Regulations, M&Os

80

Nuclear conflict and ozone depletion Quick summary  

E-Print Network (OSTI)

Nuclear conflict and ozone depletion Quick summary o Regional nuclear war could cause global which traps pollutants o Nuclear weapons cause explosions, which then causes things around the vicinity to start burning, which in turn releases black carbon; it is not the nuclear material or fallout causing

Toohey, Darin W.

Note: This page contains sample records for the topic "fully depleted prior" from the National Library of EnergyBeta (NLEBeta).
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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

A fully quantum model of Big Bang  

E-Print Network (OSTI)

In the paper the closed Friedmann-Robertson-Walker model with quantization in the presence of the positive cosmological constant and radiation is studied. For analysis of tunneling probability for birth of an asymptotically deSitter, inflationary Universe as a function of the radiation energy a new definition of a "free" wave propagating inside strong fields is proposed. On such a basis, tunneling boundary condition is corrected, penetrability and reflection concerning to the barrier are calculated in fully quantum stationary approach. For the first time non-zero interference between the incident and reflected waves has been taken into account which turns out to play important role inside cosmological potentials and could be explained by non-locality of barriers in quantum mechanics. Inside whole region of energy of radiation the tunneling probability for the birth of the inflationary Universe is found to be close to its value obtained in semiclassical approach. The reflection from the barrier is determined for the first time (which is essentially differs on 1 at the energy of radiation close to the barrier height). The proposed method could be easily generalized on the cosmological models with the barriers of arbitrary shape, that has been demonstrated for the FRW-model with included Chaplygin gas. Result is stable for variations of the studied barriers, accuracy are found to be 11--18 digits for all coefficients and energies below the barrier height.

Sergei P. Maydanyuk; Antonino Del Popolo; Vladislav S. Olkhovsky

2013-01-19T23:59:59.000Z

82

Depleted Uranium Uses: Regulatory Requirements and Issues  

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

1 Depleted Uranium Uses Depleted Uranium Uses Regulatory Requirements Regulatory Requirements and Issues and Issues Nancy L. Ranek Nancy L. Ranek Argonne National Laboratory Argonne National Laboratory August 5, 1998 August 5, 1998 Beneficial Reuse '98 Beneficial Reuse '98 Knoxville, TN Knoxville, TN NOTES Work Performed for: Office of Facilities (NE-40) Office of Nuclear Energy, Science and Technology U.S. Department of Energy Work Performed by: Environmental Assessment Division Argonne National Laboratory 955 L'Enfant Plaza North, S.W. Washington, D.C. 20024 Phone: 202/488-2417 E-mail: ranekn@smtplink.dis.anl.gov 2 2 2 Programmatic Environmental Programmatic Environmental Impact Statement (PEIS) Impact Statement (PEIS) Draft PEIS Published 12/97 * Preferred Alternative = 100% Use

83

Depleted UF6 Conversion facility EIS Topics  

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

Topics Topics Depleted UF6 Conversion Facility EIS Topics A listing of topics included in the Depleted UF6 Conversion Facility EISs. DOE addressed the following environmental issues when assessing the potential environmental impacts of the alternatives in the two site-specific EISs. DOE solicited comment from the Federal agencies, Native American tribes, state and local governments, and the general public on these and any other issues as part of the public scoping process: Potential impacts on health from DUF6 conversion activities, including potential impacts to workers and the public from exposure to radiation and chemicals during routine and accident conditions for the construction, operation, maintenance, and decontamination and decommissioning of DUF6 conversion facilities.

84

Assessment of Preferred Depleted Uranium Disposal Forms  

SciTech Connect

The Department of Energy (DOE) is in the process of converting about 700,000 metric tons (MT) of depleted uranium hexafluoride (DUF6) containing 475,000 MT of depleted uranium (DU) to a stable form more suitable for long-term storage or disposal. Potential conversion forms include the tetrafluoride (DUF4), oxide (DUO2 or DU3O8), or metal. If worthwhile beneficial uses cannot be found for the DU product form, it will be sent to an appropriate site for disposal. The DU products are considered to be low-level waste (LLW) under both DOE orders and Nuclear Regulatory Commission (NRC) regulations. The objective of this study was to assess the acceptability of the potential DU conversion products at potential LLW disposal sites to provide a basis for DOE decisions on the preferred DU product form and a path forward that will ensure reliable and efficient disposal.

Croff, A.G.; Hightower, J.R.; Lee, D.W.; Michaels, G.E.; Ranek, N.L.; Trabalka, J.R.

2000-06-01T23:59:59.000Z

85

Depleted uranium plasma reduction system study  

Science Conference Proceedings (OSTI)

A system life-cycle cost study was conducted of a preliminary design concept for a plasma reduction process for converting depleted uranium to uranium metal and anhydrous HF. The plasma-based process is expected to offer significant economic and environmental advantages over present technology. Depleted Uranium is currently stored in the form of solid UF{sub 6}, of which approximately 575,000 metric tons is stored at three locations in the U.S. The proposed system is preconceptual in nature, but includes all necessary processing equipment and facilities to perform the process. The study has identified total processing cost of approximately $3.00/kg of UF{sub 6} processed. Based on the results of this study, the development of a laboratory-scale system (1 kg/h throughput of UF6) is warranted. Further scaling of the process to pilot scale will be determined after laboratory testing is complete.

Rekemeyer, P.; Feizollahi, F.; Quapp, W.J.; Brown, B.W.

1994-12-01T23:59:59.000Z

86

Uranio impoverito: perché? (Depleted uranium: why?)  

E-Print Network (OSTI)

In this paper we develop a simple model of the penetration process of a long rod through an uniform target. Applying the momentum and energy conservation laws, we derive an analytical relation which shows how the penetration depth depends upon the density of the rod, given a fixed kinetic energy. This work was sparked off by the necessity of understanding the effectiveness of high density penetrators (e.g. depleted uranium penetrators) as anti-tank weapons.

Germano D'Abramo

2003-05-28T23:59:59.000Z

87

Depletion modeling of liquid dominated geothermal reservoirs  

DOE Green Energy (OSTI)

Depletion models for liquid-dominated geothermal reservoirs are derived and presented. The depletion models are divided into two categories: confined and unconfined. For both cases depletion models with no recharge (or influx), and depletion models including recharge, are used to match field data from the Svartsengi high temperature geothermal field in Iceland. The influx models included with the mass and energy balances are adopted from the petroleum engineering literature. The match to production data from Svartsengi is improved when influx was included. The Schilthuis steady-state influx gives a satisfactory match. The finite aquifer method of Fetkovitch, and the unsteady state method of Hurst gave reasonable answers, but not as good. The best match is obtained using Hurst simplified solution when lambda = 1.3 x 10{sup -4} m{sup -1}. From the match the cross-sectional area of the aquifer was calculated as 3.6 km{sup 2}. The drawdown was predicted using the Hurst simplified method, and compared with predicted drawdown from a boiling model and an empirical log-log model. A large difference between the models was obtained. The predicted drawdown using the Hurst simplified method falls between the other two. Injection has been considered by defining the net rate as being the production rate minus the injection rate. No thermal of transient effects were taken into account. Prediction using three different net rates shows that the pressure can be maintained using the Hurst simplified method if there is significant fluid reinjection. 32 refs., 44 figs., 2 tabs.

Olsen, G.

1984-06-01T23:59:59.000Z

88

Transpassive electrodissolution of depleted uranium in alkaline electrolytes  

SciTech Connect

To aid in removal of oralloy from the nuclear weapons stockpile, scientists at the Los Alamos National Laboratory Plutonium Facility are decontaminating oralloy parts by electrodissolution in neutral to alkaline electrolytes composed of sodium nitrate and sodium sulfate. To improve the process, electrodissolution experiments were performed with depleted uranium to understand the effects of various operating parameters. Sufficient precipitate was also produced to evaluate the feasibility of using ultrafiltration to separate the uranium oxide precipitates from the electrolyte before it enters the decontamination fixture. In preparation for the experiments, a potential-pH diagram for uranium was constructed from thermodynamic data for fully hydrated species. Electrodissolution in unstirred solutions showed that uranium dissolution forms two layers, an acidic bottom layer rich in uranium and an alkaline upper layer. Under stirred conditions results are consistent with the formation of a yellow precipitate of composition UO{sub 3}{center_dot}2H{sub 2}O, a six electron process. Amperometric experiments showed that current efficiency remained near 100% over a wide range of electrolytes, electrolyte concentrations, pH, and stirring conditions.

Weisbrod, K.R.; Schake, A.R.; Morgan, A.N.; Purdy, G.M.; Martinez, H.E.; Nelson, T.O.

1998-03-01T23:59:59.000Z

89

FAQ 24-Who is responsible for managing depleted uranium?  

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

Who is responsible for managing depleted uranium? Who is responsible for managing depleted uranium? In the United States, the U.S. Department of Energy is responsible for managing...

90

Unsubscribe from the Depleted UF6 E-mail List  

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

Services Unsubscribe Unsubscribe from the Depleted UF6 E-mail List This form allows you to remove yourself from the Depleted UF6 e-mail list. Type your e-mail address here:...

91

U.S. Working Natural Gas Underground Storage Depleted Fields...  

Annual Energy Outlook 2012 (EIA)

Depleted Fields Capacity (Million Cubic Feet) U.S. Working Natural Gas Underground Storage Depleted Fields Capacity (Million Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4...

92

New Mexico Natural Gas Number of Underground Storage Depleted...  

U.S. Energy Information Administration (EIA) Indexed Site

Depleted Fields Capacity (Number of Elements) New Mexico Natural Gas Number of Underground Storage Depleted Fields Capacity (Number of Elements) Decade Year-0 Year-1 Year-2 Year-3...

93

New Mexico Natural Gas Underground Storage Depleted Fields Capacity...  

U.S. Energy Information Administration (EIA) Indexed Site

Depleted Fields Capacity (Million Cubic Feet) New Mexico Natural Gas Underground Storage Depleted Fields Capacity (Million Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4...

94

Free, Prior, and Informed Consent in REDD+: Principles and Approaches...  

Open Energy Info (EERE)

Free, Prior, and Informed Consent in REDD+: Principles and Approaches for Policy and Project Development Jump to: navigation, search Tool Summary Name: Free, Prior, and Informed...

95

IMPROVED PHOTOMETRIC REDSHIFTS WITH SURFACE LUMINOSITY PRIORS  

SciTech Connect

We apply Bayesian statistics with prior probabilities of galaxy surface luminosity (SL) to improve photometric redshifts. We apply the method to a sample of 1266 galaxies with spectroscopic redshifts in the GOODS North and South fields at 0.1 {approx}< z {approx}< 2.0. We start with spectrophotometric redshifts (SPZs) based on Probing Evolution and Reionization Spectroscopically grism spectra, which cover a wavelength range of 6000-9000 A, combined with (U)BViz(JHK) broadband photometry in the GOODS fields. The accuracy of SPZ redshifts is estimated to be {sigma}({delta}(z)) = 0.035 with an systematic offset of -0.026, where {delta}(z) = {delta}z/(1 + z), for galaxies in redshift range of 0.5 {approx}< z {approx}< 1.25. The addition of the SL prior probability helps break the degeneracy of SPZ redshifts between low redshift 4000 A break galaxies and high-redshift Lyman break galaxies which are mostly catastrophic outliers. For the 1138 galaxies at z {approx}< 1.6, the fraction of galaxies with redshift deviation {delta}(z)>0.2 is reduced from 15.0% to 10.4%, while the rms scatter of the fractional redshift error does not change much.

Xia Lifang; Cohen, Seth; Malhotra, Sangeeta; Rhoads, James; Grogin, Norman; Windhorst, Rogier A. [School of Earth and Space Exploration, Arizona State University, Tempe, AZ 85287-1404 (United States); Hathi, Nimish P. [Department of Physics and Astronomy, University of California, Riverside, CA 92521 (United States); Pirzkal, Nor; Xu Chun [Space Telescope Science Institute, Baltimore, MD 21218 (United States)], E-mail: lifang.xia@asu.edu

2009-07-15T23:59:59.000Z

96

FAQ 25-What are the options for managing depleted uranium in...  

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

options for managing depleted uranium in the future? What are the options for managing depleted uranium in the future? The options for managing depleted uranium were evaluated in...

97

Depletion effects of silicon deposition from methyltrichlorosilane  

DOE Green Energy (OSTI)

The deposition rate of SiC on carbon-coated Nicalon fibers from methyltrichlorosilane in hydrogen was measured as a function of temperature, pressure, total flow rate, and simulated reactant depletion. The results, which are included in this paper together with kinetic information on the stability of methyltrichlorosilane, led to two conclusions: two different mechanisms of deposition can occur depending on whether the methyltrichlorosilane has an opportunity to dissociate into separate silicon- and carbon-containing precursors, and the deposition rate is strongly reduced by the generation of byproduct HCl. The data were fitted to a simple etch model to obtain a kinetic expression that accounts for the significant effect of HCl.

Besmann, T.M.; Sheldon, B.W.; Moss, T.S. III; Kaster, M.D. (Oak Ridge National Lab., TN (United States))

1992-10-01T23:59:59.000Z

98

A Green Anode Plant Performance Analysis Tool Fully Embedded In ...  

Science Conference Proceedings (OSTI)

Presentation Title, A Green Anode Plant Performance Analysis Tool Fully Embedded In The Plant Control System. Author(s), Xavier Genin, Pasquale Calo,

99

Geothermal: Sponsored by OSTI -- Using fully coupled hydro-geomechanic...  

Office of Scientific and Technical Information (OSTI)

Using fully coupled hydro-geomechanical numerical test bed to study reservoir stimulation with low hydraulic pressure Geothermal Technologies Legacy Collection HelpFAQ | Site Map...

100

Overview of Depleted Uranium Hexafluoride Management Program  

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

DOE's DUF DOE's DUF 6 Cylinder Inventory a Location Number of Cylinders DUF 6 (MT) b Paducah, Kentucky 36,910 450,000 Portsmouth, Ohio 16,041 198,000 Oak Ridge (ETTP), Tennessee 4,683 56,000 Total 57,634 704,000 a The DOE inventory includes DUF 6 generated by the government, as well as DUF 6 transferred from U.S. Enrichment Corporation pursuant to two memoranda of agreement. b A metric ton (MT) is equal to 1,000 kilograms, or 2,200 pounds. Overview of Depleted Uranium Hexafluoride Management Program Over the last four decades, large quantities of uranium were processed by gaseous diffusion to produce enriched uranium for U.S. national defense and civilian purposes. The gaseous diffusion process uses uranium in the form of uranium hexafluoride (UF 6 ), primarily because UF 6 can conveniently be used in

Note: This page contains sample records for the topic "fully depleted prior" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
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to obtain the most current and comprehensive results.


101

Regulation of New Depleted Uranium Uses  

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

2-5 2-5 Regulation of New Depleted Uranium Uses Environmental Assessment Division Argonne National Laboratory Operated by The University of Chicago, under Contract W-31-109-Eng-38, for the United States Department of Energy DISCLAIMER 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 The University of Chicago, nor any of their employees or officers, 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,

102

Lithium Depletion of Nearby Young Stellar Associations  

E-Print Network (OSTI)

We estimate cluster ages from lithium depletion in five pre-main-sequence groups found within 100 pc of the Sun: TW Hydrae Association, Eta Chamaeleontis Cluster, Beta Pictoris Moving Group, Tucanae-Horologium Association and AB Doradus Moving Group. We determine surface gravities, effective temperatures and lithium abundances for over 900 spectra through least squares fitting to model-atmosphere spectra. For each group, we compare the dependence of lithium abundance on temperature with isochrones from pre-main-sequence evolutionary tracks to obtain model dependent ages. We find that the Eta Chamaelontis Cluster and the TW Hydrae Association are the youngest, with ages of 12+/-6 Myr and 12+/-8 Myr, respectively, followed by the Beta Pictoris Moving Group at 21+/-9 Myr, the Tucanae-Horologium Association at 27+/-11 Myr, and the AB Doradus Moving Group at an age of at least 45 Myr (where we can only set a lower limit since the models -- unlike real stars -- do not show much lithium depletion beyond this age). Here, the ordering is robust, but the precise ages depend on our choice of both atmospheric and evolutionary models. As a result, while our ages are consistent with estimates based on Hertzsprung-Russell isochrone fitting and dynamical expansion, they are not yet more precise. Our observations do show that with improved models, much stronger constraints should be feasible: the intrinsic uncertainties, as measured from the scatter between measurements from different spectra of the same star, are very low: around 10 K in effective temperature, 0.05 dex in surface gravity, and 0.03 dex in lithium abundance.

Erin Mentuch; Alexis Brandeker; Marten H. van Kerkwijk; Ray Jayawardhana; Peter H. Hauschildt

2008-08-26T23:59:59.000Z

103

Press Release: DOE Seeks Public Input for Depleted Uranium Hexafluorid...  

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

Perry, (865) 576-0885 September 24, 2001 www.oakridge.doe.gov DOE SEEKS PUBLIC INPUT FOR DEPLETED URANIUM HEXAFLUORIDE ENVIRONMENTAL IMPACT STATEMENT Public Meetings Planned in...

104

Numerical study of error propagation in Monte Carlo depletion simulations.  

E-Print Network (OSTI)

??Improving computer technology and the desire to more accurately model the heterogeneity of the nuclear reactor environment have made the use of Monte Carlo depletion… (more)

Wyant, Timothy Joseph

2012-01-01T23:59:59.000Z

105

DOE Selects Contractor for Depleted Hexafluoride Conversion Project...  

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

in Paducah, Kentucky and Portsmouth, Ohio. For several decades DOE was responsible for uranium enrichment, the uranium hexafluoride depleted in the 235U isotope (typically down...

106

Environmental Risks of Depleted UF6-related Manufacturing Activities  

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

and operation of a facility to fabricate representative products containing depleted uranium. Impacts Analyzed in the PEIS The PEIS evaluated the general environmental impacts...

107

Health Risks Associated with Disposal of Depleted Uranium  

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

Disposal DUF6 Health Risks line line Accidents Storage Conversion Manufacturing Disposal Transportation Disposal of Depleted Uranium A discussion of risks associated with disposal...

108

Environmental Impacts of Options for Disposal of Depleted Uranium...  

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

study by Oak Ridge National Laboratory evaluated the acceptability of several depleted uranium conversion products at potential LLW disposal sites to provide a basis for DOE...

109

Application of thermal depletion model to geothermal reservoirs...  

Open Energy Info (EERE)

of thermal depletion model to geothermal reservoirs with fracture and pore permeability Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Conference Proceedings:...

110

Depleted UF6 Management Information Network - A resource for...  

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

is an online repository of information about the U.S. Department of Energy's (DOE's) inventory of depleted uranium hexafluoride (DUF6), a product of the uranium enrichment...

111

Fully deuterated microorganisms: Tools in magnetic resonance and neutron scattering  

SciTech Connect

Current work at Argonne emphasizes the use of fully deuterated algae and cyanobacteria as tools in the study of photosynthesis and as a source of complex substrates for the culture of engineered overproducing bacteria. 17 refs., 1 fig., 1 tab.

Crespi, H.L.

1988-01-01T23:59:59.000Z

112

Analysis of Hydrogen Depletion Using a Scaled Passive Autocatalytic Recombiner  

DOE Green Energy (OSTI)

Hydrogen depletion tests of a scaled passive autocatalytic recombine (pAR) were performed in the Surtsey test vessel at Sandia National Laboratories (SNL). The experiments were used to determine the hydrogen depletion rate of a PAR in the presence of steam and also to evaluate the effect of scale (number of cartridges) on the PAR performance at both low and high hydrogen concentrations.

Blanchat, T.K.; Malliakos, A.

1998-10-28T23:59:59.000Z

113

Disposition of DOE Excess Depleted Uranium, Natural Uranium, and  

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

Disposition of DOE Excess Depleted Uranium, Natural Uranium, and Disposition of DOE Excess Depleted Uranium, Natural Uranium, and Low-Enriched Uranium Disposition of DOE Excess Depleted Uranium, Natural Uranium, and Low-Enriched Uranium The U.S. Department of Energy (DOE) owns and manages an inventory of depleted uranium (DU), natural uranium (NU), and low-enriched uranium (LEU) that is currently stored in large cylinders as depleted uranium hexafluoride (DUF6), natural uranium hexafluoride (NUF6), and low-enriched uranium hexafluoride (LEUF6) at the DOE Paducah site in western Kentucky (DOE Paducah) and the DOE Portsmouth site near Piketon in south-central Ohio (DOE Portsmouth)1. This inventory exceeds DOE's current and projected energy and defense program needs. On March 11, 2008, the Secretary of Energy issued a policy statement (the

114

Regulation of new depleted uranium uses.  

DOE Green Energy (OSTI)

This report evaluates how the existing U.S. Nuclear Regulatory Commission (NRC) regulatory structure and pending modifications would affect full deployment into radiologically uncontrolled areas of certain new depleted uranium (DU) uses being studied as part of the U.S. Department of Energy's DU uses research and development program. Such new DU uses include as catalysts (for destroying volatile organic compounds in off-gases from industrial processes and for hydrodesulfurization [HDS] of petroleum fuels), semiconductors (for fabricating integrated circuits, solar cells, or thermoelectric devices, especially if such articles are expected to have service in hostile environments), and electrodes (for service in solid oxide fuel cells, in photoelectrochemical cells used to produce hydrogen, and in batteries). The report describes each new DU use and provides a detailed analysis of whether any existing NRC licensing exemption or general license would be available to users of products and devices manufactured to deploy the new use. Although one existing licensing exemption was found to be possibly available for catalysts used for HDS of petroleum fuels and one general license was found to be possibly available for catalysts, semiconductors, and electrodes used in hydrogen production or batteries, existing regulations would require most users of products and devices deploying new DU uses to obtain specific source material licenses from the NRC or an Agreement State. This situation would not be improved by pending regulatory modifications. Thus, deployment of new DU uses may be limited because persons having no previous experience with NRC or Agreement State regulations may be hesitant to incur the costs and inconvenience of regulatory compliance, unless using a DU-containing product or device offers a substantial economic benefit over nonradioactive alternatives. Accordingly, estimating the risk of deploying new DU-containing products and devices in certain radiologically uncontrolled areas is recommended. If the estimated risks of such deployment are found to be acceptable, then it may be possible to justify adding new exemptions or general licenses to the NRC regulations.

Ranek, N. L.

2003-01-22T23:59:59.000Z

115

A Bayesian Approach for Image Segmentation with Shape Priors  

E-Print Network (OSTI)

Gibbs distribution and the Bayesian restoration of images.A Bayesian Approach for Image Segmentation with Shapeshape prior models within a Bayesian framework. Interactive

Chang, Hang

2009-01-01T23:59:59.000Z

116

Microsoft Word - LibraryofPriorRulemakings.doc | Department of...  

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

ofPriorRulemakings.doc More Documents & Publications Solar Background Document 1 Natural Gas Imports and Exports - Second Quarter Report 2013 Searchable Electronic Department of...

117

Virtual Reading Room prior to 2000 | National Nuclear Security...  

National Nuclear Security Administration (NNSA)

prior to 2000 | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our...

118

Challenges dealing with depleted uranium in Germany - Reuse or disposal  

SciTech Connect

During enrichment large amounts of depleted Uranium are produced. In Germany every year 2.800 tons of depleted uranium are generated. In Germany depleted uranium is not classified as radioactive waste but a resource for further enrichment. Therefore since 1996 depleted Uranium is sent to ROSATOM in Russia. However it still has to be dealt with the second generation of depleted Uranium. To evaluate the alternative actions in case a solution has to be found in Germany, several studies have been initiated by the Federal Ministry of the Environment. The work that has been carried out evaluated various possibilities to deal with depleted uranium. The international studies on this field and the situation in Germany have been analyzed. In case no further enrichment is planned the depleted uranium has to be stored. In the enrichment process UF{sub 6} is generated. It is an international consensus that for storage it should be converted to U{sub 3}O{sub 8}. The necessary technique is well established. If the depleted Uranium would have to be characterized as radioactive waste, a final disposal would become necessary. For the planned Konrad repository - a repository for non heat generating radioactive waste - the amount of Uranium is limited by the licensing authority. The existing license would not allow the final disposal of large amounts of depleted Uranium in the Konrad repository. The potential effect on the safety case has not been roughly analyzed. As a result it may be necessary to think about alternatives. Several possibilities for the use of depleted uranium in the industry have been identified. Studies indicate that the properties of Uranium would make it useful in some industrial fields. Nevertheless many practical and legal questions are open. One further option may be the use as shielding e.g. in casks for transport or disposal. Possible techniques for using depleted Uranium as shielding are the use of the metallic Uranium as well as the inclusion in concrete. Another possibility could be the use of depleted uranium for the blending of High enriched Uranium (HEU) or with Plutonium to MOX-elements. (authors)

Moeller, Kai D. [Federal Office for Radiation Protection, Bundesamt fuer Strahlenschutz - BFS, Postfach 10 01 49, D-38201 Salzgitter (Germany)

2007-07-01T23:59:59.000Z

119

Weak Interaction Neutron Production Rates in Fully Ionized Plasmas  

E-Print Network (OSTI)

Employing the weak interaction reaction wherein a heavy electron is captured by a proton to produce a neutron and a neutrino, the neutron production rate for neutral hydrogen gases and for fully ionized plasmas is computed. Using the Coulomb atomic bound state wave functions of a neutral hydrogen gas, our production rate results are in agreement with recent estimates by Maiani {\\it et al}. Using Coulomb scattering state wave functions for the fully ionized plasma, we find a substantially enhanced neutron production rate. The scattering wave function should replace the bound state wave function for estimates of the enhanced neutron production rate on water plasma drenched cathodes of chemical cells.

A. Widom; J. Swain; Y. N. Srivastava

2013-05-19T23:59:59.000Z

120

Depleted Uranium Dioxide as SNF Waste Package Fill: A Disposal...  

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

DEPLETED URANIUM DIOXIDE AS SNF WASTE PACKAGE FILL: A DISPOSAL OPTION Charles W. Forsberg Oak Ridge National Laboratory * P.O. Box 2008 Oak Ridge, Tennessee 37831-6179 Tel: (865)...

Note: This page contains sample records for the topic "fully depleted prior" 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

Health Risks Associated with Conversion of Depleted UF6  

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

Conversion Conversion DUF6 Health Risks line line Accidents Storage Conversion Manufacturing Disposal Transportation Conversion A discussion of health risks associated with conversion of depleted UF6 to another chemical form. General Health Risks of Conversion The potential environmental impacts, including potential health risks, associated with conversion activities will be evaluated in detail as part of the Depleted Uranium Hexafluoride management program after a contract is awarded for conversion services. This section discusses in general the types of health risks associated with the conversion process. The conversion of depleted UF6 to another chemical form will be done in an industrial facility dedicated to the conversion process. Conversion will involve the handling of depleted UF6 cylinders. Hazardous chemicals, such

122

DOE Selects Contractor for Depleted Hexafluoride Conversion Project Support  

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

DOE Selects Contractor for Depleted Hexafluoride Conversion Project DOE Selects Contractor for Depleted Hexafluoride Conversion Project Support DOE Selects Contractor for Depleted Hexafluoride Conversion Project Support March 25, 2013 - 12:00pm Addthis Media Contact Bill Taylor, 803-952-8564 Bill.Taylor@srs.gov Cincinnati - The U.S. Department of Energy (DOE) today awarded a competitive small business task order to Navarro Research and Engineering Inc. of Oak Ridge, Tennessee. The award is a $22 million, time and materials task order with a three-year performance period and two one-year extension options. Navarro Research and Engineering Inc. will provide engineering and operations technical support services to the DOE Portsmouth Paducah Project Office (PPPO) in Lexington, Kentucky and the Depleted Uranium Hexafluoride (DUF6) Conversion Project in Paducah, Kentucky and Portsmouth, Ohio.

123

DOE Issues Request for Quotations for Depleted Uranium Hexafluoride  

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

Issues Request for Quotations for Depleted Uranium Hexafluoride Issues Request for Quotations for Depleted Uranium Hexafluoride Conversion Technical Services DOE Issues Request for Quotations for Depleted Uranium Hexafluoride Conversion Technical Services December 12, 2012 - 12:00pm Addthis Media Contact Bill Taylor, 803-952-8564 bill.taylor@srs.gov Cincinnati - The U.S. Department of Energy (DOE) today issued a Request for Quotation (RFQ) for engineering and operations technical services to support the Portsmouth Paducah Project Office and the oversight of operations of the Depleted Uranium Hexafluoride (DUF6) Conversion Project located in Paducah KY, and Portsmouth OH. The RFQ is for a Time-and-Materials Task Order for three years with two one-year option periods. The estimated contract value is approximately $15 - 20 million.

124

DOE Issues Request for Quotations for Depleted Uranium Hexafluoride  

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

Issues Request for Quotations for Depleted Uranium Hexafluoride Issues Request for Quotations for Depleted Uranium Hexafluoride Conversion Technical Services DOE Issues Request for Quotations for Depleted Uranium Hexafluoride Conversion Technical Services December 12, 2012 - 12:00pm Addthis Media Contact Bill Taylor, 803-952-8564 bill.taylor@srs.gov Cincinnati - The U.S. Department of Energy (DOE) today issued a Request for Quotation (RFQ) for engineering and operations technical services to support the Portsmouth Paducah Project Office and the oversight of operations of the Depleted Uranium Hexafluoride (DUF6) Conversion Project located in Paducah KY, and Portsmouth OH. The RFQ is for a Time-and-Materials Task Order for three years with two one-year option periods. The estimated contract value is approximately $15 - 20 million.

125

DOE Selects Contractor for Depleted Hexafluoride Conversion Project Support  

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

Contractor for Depleted Hexafluoride Conversion Project Contractor for Depleted Hexafluoride Conversion Project Support DOE Selects Contractor for Depleted Hexafluoride Conversion Project Support March 25, 2013 - 12:00pm Addthis Media Contact Bill Taylor, 803-952-8564 Bill.Taylor@srs.gov Cincinnati - The U.S. Department of Energy (DOE) today awarded a competitive small business task order to Navarro Research and Engineering Inc. of Oak Ridge, Tennessee. The award is a $22 million, time and materials task order with a three-year performance period and two one-year extension options. Navarro Research and Engineering Inc. will provide engineering and operations technical support services to the DOE Portsmouth Paducah Project Office (PPPO) in Lexington, Kentucky and the Depleted Uranium Hexafluoride (DUF6) Conversion Project in Paducah, Kentucky and Portsmouth, Ohio.

126

Virtual Reading Room prior to 2000 | National Nuclear Security  

National Nuclear Security Administration (NNSA)

prior to 2000 | National Nuclear Security prior to 2000 | 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 Virtual Reading Room prior to 2000 Home > About Us > Our Operations > NNSA Office of General Counsel > Freedom of Information Act (FOIA) > Virtual Reading Room prior to 2000 Virtual Reading Room prior to 2000 Printer-friendly version Printer-friendly version

127

DISPERSION AND DISSIPATION ERRORS OF TWO FULLY DISCRETE DISCONTINUOUS GALERKIN  

E-Print Network (OSTI)

-dimensional Euler equations in gas dynamics. There has been abundant study on the dispersion analysis of many nuDISPERSION AND DISSIPATION ERRORS OF TWO FULLY DISCRETE DISCONTINUOUS GALERKIN METHODS HE YANG, FENGYAN LI, AND JIANXIAN QIU Abstract. The dispersion and dissipation properties of numerical meth- ods

Li, Fengyan

128

FULLY FUNDED DEPARTMENT OF ENERGY BIOFUELS RESEARCH INTERNSHIP  

E-Print Network (OSTI)

FULLY FUNDED DEPARTMENT OF ENERGY BIOFUELS RESEARCH INTERNSHIP AT PACIFIC NORTHWEST NATIONAL LABORATORY Position Description The overall project objective is to utilize marine microalgae for biofuels production (i.e., lipids for biodiesel or jet biofuel). The student will set up a series of photobioreactors

129

FULLY FUNDED DEPARTMENT OF ENERGY BIOFUELS RESEARCH INTERNSHIP  

E-Print Network (OSTI)

FULLY FUNDED DEPARTMENT OF ENERGY BIOFUELS RESEARCH INTERNSHIP AT PACIFIC NORTHWEST NATIONAL LABORATORY Position Description The overall project objective is to utilize marine microalgae for biofuels (i.e., lipids for biodiesel or jet biofuel) production. The student will set up a series

Wildermuth, Mary C

130

Production and Handling Slide 38: 48G Depleted UF6 Storage Cylinder  

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

48G Depleted UF6 Storage Cylinder Refer to caption below for image description After enrichment, depleted uranium hexafluoride is placed in large steel cylinders for storage....

131

Magnetohydrodynamics in stationary and axisymmetric spacetimes: A fully covariant approach  

Science Conference Proceedings (OSTI)

A fully geometrical treatment of general relativistic magnetohydrodynamics is developed under the hypotheses of perfect conductivity, stationarity, and axisymmetry. The spacetime is not assumed to be circular, which allows for greater generality than the Kerr-type spacetimes usually considered in general relativistic magnetohydrodynamics. Expressing the electromagnetic field tensor solely in terms of three scalar fields related to the spacetime symmetries, we generalize previously obtained results in various directions. In particular, we present the first relativistic version of the Soloviev transfield equation, subcases of which lead to fully covariant versions of the Grad-Shafranov equation and of the Stokes equation in the hydrodynamical limit. We have also derived, as another subcase of the relativistic Soloviev equation, the equation governing magnetohydrodynamical equilibria with purely toroidal magnetic fields in stationary and axisymmetric spacetimes.

Gourgoulhon, Eric [Laboratoire Univers et Theories, UMR 8102 du CNRS, Observatoire de Paris, Universite Paris Diderot, F-92190 Meudon (France); Markakis, Charalampos [Department of Physics, University of Wisconsin-Milwaukee, P.O. Box 413, Milwaukee, Wisconsin 53201 (United States); Uryu, Koji [Department of Physics, University of the Ryukyus, Senbaru, Nishihara, Okinawa 903-0213 (Japan); Eriguchi, Yoshiharu [Department of Earth Science and Astronomy, Graduate School of Arts and Sciences, University of Tokyo, Komaba, Meguro-ku, 3-8-1, 153-8902 Tokyo (Japan)

2011-05-15T23:59:59.000Z

132

Fully Ceramic Microencapsulated Fuel Development for LWR Applications  

SciTech Connect

The concept, fabrication, and key feasibility issues of a new fuel form based on the microencapsulated (TRISO-type) fuel which has been specifically engineered for LWR application and compacted within a SiC matrix will be presented. This fuel, the so-called fully ceramic microencapsulated fuel is currently undergoing development as an accident tolerant fuel for potential UO2 replacement in commercial LWRs. While the ability of this fuel to facilitate normal LWR cycle performance is an ongoing effort within the program, this will not be a focus of this paper. Rather, key feasibility and performance aspects of the fuel will be presented including the ability to fabricate a LWR-specific TRISO, the need for and route to a high thermal conductivity and fully dense matrix that contains neutron poisons, and the performance of that matrix under irradiation and the interaction of the fuel with commercial zircaloy clad.

Snead, Lance Lewis [ORNL; Besmann, Theodore M [ORNL; Terrani, Kurt A [ORNL; Voit, Stewart L [ORNL

2012-01-01T23:59:59.000Z

133

Fully hadronic ttbar cross section measurement with ATLAS detector  

E-Print Network (OSTI)

The top quark pair production cross section in the fully hadronic final state is characterized by a six jet topology, two of which could be identified as originating from a b-quark using ATLAS b-tagging algorithms. Compared to other decay channels, this final state presents an advantageous larger branching ratio; on the other hand it suffers from a very large QCD multi-jet background, generally difficult to estimate from Monte Carlo simulation and therefore evaluated using data-driven techniques. The analysis is performed using 36pb-1 of pp collisions produced at the LHC with a center-of-mass energy of 7 TeV. The observed upper limit is set at 261 pb at 95% confidence level, where the expected Standard Model cross-section for the ttbar process is 165+11-16 pb. In the future, when the LHC luminosity increases, it is essential, to efficiently trigger on these fully hadronic ttbar events, to use dedicated triggers. An overview of the analysis for ttbar production cross section measurement in the fully hadronic final state and the state-of-the-art of the b-jet trigger performance estimation are presented in this contribution.

Claudia Bertella

2011-11-16T23:59:59.000Z

134

Process to upgrade coal liquids by extraction prior to hydrodenitrogenation  

DOE Patents (OSTI)

Oxygen compounds are removed, e.g., by extraction, from a coal liquid prior to its hydrogenation. As a result, compared to hydrogenation of such a non-treated coal liquid, the rate of nitrogen removal is increased.

Schneider, Abraham (Overbrook Hills, PA); Hollstein, Elmer J. (Wilmington, DE); Janoski, Edward J. (Havertown, PA); Scheibel, Edward G. (Media, PA)

1982-01-01T23:59:59.000Z

135

Using prior shape and intensity profile in medical image segmentation  

Science Conference Proceedings (OSTI)

In this note we present a coupled optimization model forboundary determination. One part of the model incorporatesa prior shape into a geometric active contour modelwith a fixed parameter. The second part determines the'best' parameter used in the first ...

Yunmei Chen; Feng Huang; Hemant D. Tagare; Murali Rao; David Wilson; Edward A. Geiser

2003-10-01T23:59:59.000Z

136

A Bayesian Approach for Image Segmentation with Shape Priors  

SciTech Connect

Color and texture have been widely used in image segmentation; however, their performance is often hindered by scene ambiguities, overlapping objects, or missingparts. In this paper, we propose an interactive image segmentation approach with shape prior models within a Bayesian framework. Interactive features, through mouse strokes, reduce ambiguities, and the incorporation of shape priors enhances quality of the segmentation where color and/or texture are not solely adequate. The novelties of our approach are in (i) formulating the segmentation problem in a well-de?ned Bayesian framework with multiple shape priors, (ii) ef?ciently estimating parameters of the Bayesian model, and (iii) multi-object segmentation through user-speci?ed priors. We demonstrate the effectiveness of our method on a set of natural and synthetic images.

Chang, Hang; Yang, Qing; Parvin, Bahram

2008-06-20T23:59:59.000Z

137

Ozone depletion, greenhouse gases, and climate change: Proceedings  

SciTech Connect

This symposium was primarily concerned with the linkages between ozone depletion and increasing greenhouse gases and with their combined effect in causing climate change to occur on a global scale. The presentations in these proceedings review the current state of knowledge about stratospheric ozone depletion, discuss the probable effect of predicted greenhouse gas increase on future ozone trends, summarize observational data on changing atmospheric chemistry and associated atmospheric temperatures, and describe the continuing effort to model and predict future scenarios of climatic change relative to ozone and greenhouse gases in both the stratosphere and the troposphere. Some of the questions and answers that followed the presentations have been included when they highlight noteworthy points that were not covered in the presentation itself. The request by the National Climate Program Office for a symposium on the above related issues is included. The symposium agenda and participants are given. As well as a glossary of special terms and abbreviations. In summary, the Joint Symposium on Ozone Depletion, Greenhouse Gases, and Climate Change reviewed the magnitude and causes of stratospheric ozone depletion and examined the connections that exist between this problem and the impending climate warming to increasing greenhouse gases. The presentations of these proceedings indicate that the connections are real and important, and that the stratospheric ozone depletion and tropospheric greenhouse warming problems must be studied as parts of an interactive global system rather than as more or less unconnected events.

1989-01-01T23:59:59.000Z

138

Status Report and Proposal Concerning the Supply of Depleted Uranium Metal Bands for a Particle Detector  

E-Print Network (OSTI)

Status Report and Proposal Concerning the Supply of Depleted Uranium Metal Bands for a Particle Detector

1980-01-01T23:59:59.000Z

139

Depleted uranium as a backfill for nuclear fuel waste package  

DOE Patents (OSTI)

A method is described for packaging spent nuclear fuel for long-term disposal in a geological repository. At least one spent nuclear fuel assembly is first placed in an unsealed waste package and a depleted uranium fill material is added to the waste package. The depleted uranium fill material comprises flowable particles having a size sufficient to substantially fill any voids in and around the assembly and contains isotopically-depleted uranium in the +4 valence state in an amount sufficient to inhibit dissolution of the spent nuclear fuel from the assembly into a surrounding medium and to lessen the potential for nuclear criticality inside the repository in the event of failure of the waste package. Last, the waste package is sealed, thereby substantially reducing the release of radionuclides into the surrounding medium, while simultaneously providing radiation shielding and increased structural integrity of the waste package. 6 figs.

Forsberg, C.W.

1998-11-03T23:59:59.000Z

140

Application of thermal depletion model to geothermal reservoirs with  

Open Energy Info (EERE)

thermal depletion model to geothermal reservoirs with thermal depletion model to geothermal reservoirs with fracture and pore permeability Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Conference Proceedings: Application of thermal depletion model to geothermal reservoirs with fracture and pore permeability Details Activities (2) Areas (2) Regions (0) Abstract: If reinjection and production wells intersect connected fractures, it is expected that reinjected fluid would cool the production well much sooner than would be predicted from calculations of flow in a porous medium. A method for calculating how much sooner that cooling will occur was developed. Basic assumptions of the method are presented, and possible application to the Salton Sea Geothermal Field, the Raft River System, and to reinjection of supersaturated fluids is discussed.

Note: This page contains sample records for the topic "fully depleted prior" 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

Environmental Risks Associated with Conversion of Depleted UF6  

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

Conversion Conversion Depleted UF6 Environmental Risks line line Storage Conversion Manufacturing Disposal Conversion A general discussion of the potential environmental impacts associated with depleted UF6 conversion activities. Impacts Analyzed in the PEIS The potential environmental impacts associated with conversion activities will be evaluated in detail as part of the Depleted Uranium Hexafluoride management program after a contract is awarded for conversion services. This page discusses in general the types of impacts that might be associated with the conversion process based on the PEIS analysis. The PEIS evaluated the potential environmental impacts for representative conversion facilities. Conversion to uranium oxide and uranium metal were considered. Potential impacts were evaluated for a representative site, and

142

Depleted uranium as a backfill for nuclear fuel waste package  

DOE Patents (OSTI)

A method is described for packaging spent nuclear fuel for long-term disposal in a geological repository. At least one spent nuclear fuel assembly is first placed in an unsealed waste package and a depleted uranium fill material is added to the waste package. The depleted uranium fill material comprises flowable particles having a size sufficient to substantially fill any voids in and around the assembly and contains isotonically-depleted uranium in the +4 valence state in an amount sufficient to inhibit dissolution of the spent nuclear fuel from the assembly into a surrounding medium and to lessen the potential for nuclear criticality inside the repository in the event of failure of the waste package. Last, the waste package is sealed, thereby substantially reducing the release of radionuclides into the surrounding medium, while simultaneously providing radiation shielding and increased structural integrity of the waste package.

Forsberg, Charles W.

1997-12-01T23:59:59.000Z

143

Depleted uranium as a backfill for nuclear fuel waste package  

DOE Patents (OSTI)

A method for packaging spent nuclear fuel for long-term disposal in a geological repository. At least one spent nuclear fuel assembly is first placed in an unsealed waste package and a depleted uranium fill material is added to the waste package. The depleted uranium fill material comprises flowable particles having a size sufficient to substantially fill any voids in and around the assembly and contains isotopically-depleted uranium in the +4 valence state in an amount sufficient to inhibit dissolution of the spent nuclear fuel from the assembly into a surrounding medium and to lessen the potential for nuclear criticality inside the repository in the event of failure of the waste package. Last, the waste package is sealed, thereby substantially reducing the release of radionuclides into the surrounding medium, while simultaneously providing radiation shielding and increased structural integrity of the waste package.

Forsberg, Charles W. (Oak Ridge, TN)

1998-01-01T23:59:59.000Z

144

A fully dynamical simulation of central nuclear collisions  

E-Print Network (OSTI)

We present a fully dynamical simulation of central nuclear collisions around mid-rapidity at LHC energies. Unlike previous treatments, we simulate all phases of the collision, including the equilibration of the system. For the simulation, we use numerical relativity solutions to AdS/CFT for the pre-equilibrium stage, viscous hydrodynamics for the plasma equilibrium stage and kinetic theory for the low density hadronic stage. Our pre-equilibrium stage provides initial conditions for hydrodynamics and our results are insensitive to the AdS/hydro switching time. The resulting light particle spectra reproduce the measurements from the ALICE experiment at all transverse momenta.

van der Schee, Wilke; Pratt, Scott

2013-01-01T23:59:59.000Z

145

Non-Facility Contractor Prior Performance, IG-0857  

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

Non-Facility Contractor Prior Non-Facility Contractor Prior Performance DOE/IG-0857 October 2011 Department of Energy Washington, DC 20585 October 28, 2011 MEMORANDUM FOR THE SECRETARY FROM: Gregory H. Friedman Inspector General SUBJECT: INFORMATION: Audit Report on "Non-Facility Contractor Prior Performance" INTRODUCTION AND OBJECTIVE The Department of Energy obligated approximately $89 billion during Fiscal Years 2009 and 2010, through various contracts and financial assistance awards, including contracts funded by the American Recovery and Reinvestment Act of 2009. Holding contractors accountable for past performance is an important tool for making sure that the Federal government and the taxpayers that it represents, receive good value from its contracts. To determine whether a prospective

146

Prior BG/P Driver Information | Argonne Leadership Computing Facility  

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

Intrepid/Challenger/Surveyor Intrepid/Challenger/Surveyor Introducing Challenger Quick Reference Guide System Overview BG/P Driver Information Prior BG/P Driver Information Internal Networks Machine Environment FAQs Block and Job State Documentation Machine Partitions Data Transfer Data Storage & File Systems Compiling and Linking Queueing and Running Jobs Debugging and Profiling Performance Tools and APIs IBM References Software and Libraries Tukey Eureka / Gadzooks Policies Documentation Feedback Please provide feedback to help guide us as we continue to build documentation for our new computing resource. [Feedback Form] Prior BG/P Driver Information Prior BGP Driver Information This page contains information about the drivers and efixes currently installed on the ALCF resources Intrepid and Surveyor, as well as

147

Bayesian Inference with Adaptive Fuzzy Priors and Likelihoods  

E-Print Network (OSTI)

Abstract—Fuzzy rule-based systems can approximate prior and likelihood probabilities in Bayesian inference and thereby approximate posterior probabilities. This fuzzy approximation technique allows users to apply a much wider and more flexible range of prior and likelihood probability density functions than found in most Bayesian inference schemes. The technique does not restrict the user to the few known closed-form conjugacy relations between the prior and likelihood. It allows the user in many cases to describe the densities with words. And just two rules can absorb any bounded closed-form probability density directly into the rulebase. Learning algorithms can tune the expert rules as well as grow them from sample data. The learning laws and fuzzy approximators have a tractable form because of the convex-sum structure of additive fuzzy systems. This convex-sum structure carries over to the fuzzy posterior

Osonde Osoba; Sanya Mitaim; Bart Kosko

2011-01-01T23:59:59.000Z

148

Archaeopteryx Feathers and Bone Chemistry Fully Revealed via Synchrotron  

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

Archaeopteryx Feathers and Bone Chemistry Fully Revealed via Archaeopteryx Feathers and Bone Chemistry Fully Revealed via Synchrotron Imaging Archaeopteryx specimens are important but extremely rare fossils. Due to their possession of both reptilian (jaws with teeth, long bony tail) and avian (feathered wings) characters, Archaeopteryx has been crucial in the development of Darwinian evolution. Despite their importance, no Archaeopteryx specimen has ever been chemically analyzed. This in large part may be explained by the analytical obstacles which preclude applying standard methods to such valuable specimens; destructive sampling is not an option and most non-destructive methods cannot handle large specimens. Furthermore, mapping using conventional methods is far too slow to enable chemical zonation to be reasonably determined. Mapping of trace element chemistry is of tremendous interest, however, because it opens a window into understanding several critical questions about Archaeopteryx in particular, and about fossil specimens in general. Preserved trace chemistry in bones and soft tissue may be remnants of the living organism, and therefore may give insight into life processes of extinct organisms. When mapping includes the embedding rock matrix, mass transfer between the fossil and the matrix can be constrained, hence giving information about mode of preservation. Chemical analysis can also resolve artefacts of the curation process. Finally, accurate chemical maps can also be useful for directing future work by highlighting regions that may be promising for other types of analysis including structural methods (CT, diffraction) or techniques that use other parts of the electromagnetic spectrum (infra-red).

149

Design and Control of a Fully Automated Vehicle door  

E-Print Network (OSTI)

The objective of the research was to develop a fully automated vehicle car door that can detect any object obstructing its path during operation. A fully automated door concept has not yet been implemented in the car industry. The door, operated via a pull of the door handle, utilizes an IR sensor to detect objects in its path. The vehicle door utilizes a linear direct current (DC) actuator with a built in potentiometer to power and control the vehicle door. The built in potentiometer provides feedback to the system. Proportional integral (PI) control was implemented to the system in order to provide a smoother and safer operation. The rise time of the system is 0.77 seconds and settling time is 1.07 seconds. The operation time is 3 seconds for the door to either open or close. The automated door has greater benefits compared to a manually operated door, such as ensuring greater safety in door operation and enhancing the lifetime as the door will not be slammed during its cycle. In addition, the door will provide more convenience to physically challenged people, as they will be able to open and close the door with the push of a button.

Hong, Kyung-Min

2010-05-01T23:59:59.000Z

150

Lithium depletion and the rotational history of exoplanet host stars  

E-Print Network (OSTI)

Israelian et al. (2004) reported that exoplanet host stars are lithium depleted compared to solar-type stars without detected massive planets, a result recently confirmed by Gonzalez (2008). We investigate whether enhanced lithium depletion in exoplanet host stars may result from their rotational history. We have developed rotational evolution models for slow and fast solar-type rotators from the pre-main sequence (PMS) to the age of the Sun and compare them to the distribution of rotational periods observed for solar-type stars between 1 Myr and 5 Gyr. We show that slow rotators develop a high degree of differential rotation between the radiative core and the convective envelope, while fast rotators evolve with little core-envelope decoupling. We suggest that strong differential rotation at the base of the convective envelope is responsible for enhanced lithium depletion in slow rotators. We conclude that lithium-depleted exoplanet host stars were slow rotators on the zero-age main sequence (ZAMS) and argue that slow rotation results from a long lasting star-disk interaction during the PMS. Altogether, this suggests that long-lived disks (> 5 Myr) may be a necessary condition for massive planet formation/migration.

Jerome Bouvier

2008-08-28T23:59:59.000Z

151

The depleted hydrogen atoms in chemical graph theory  

Science Conference Proceedings (OSTI)

A new algorithm which explicitly describes the depleted hydrogen atoms is proposed for chemical graph computations, and especially for molecular connectivity model studies. The new algorithm continues to be centred on the concepts of complete graphs ... Keywords: General chemical graphs, complete graphs, hydrogen perturbation, molecular connectivity computations

Lionello Pogliani

2008-12-01T23:59:59.000Z

152

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

SciTech Connect

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

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

2012-01-01T23:59:59.000Z

153

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

SciTech Connect

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

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

2013-01-01T23:59:59.000Z

154

Fully Coupled Well Models for Fluid Injection and Production  

SciTech Connect

Wells are the primary engineered component of geologic sequestration systems with deep subsurface reservoirs. Wells provide a conduit for injecting greenhouse gases and producing reservoirs fluids, such as brines, natural gas, and crude oil, depending on the target reservoir. Well trajectories, well pressures, and fluid flow rates are parameters over which well engineers and operators have control during the geologic sequestration process. Current drilling practices provided well engineers flexibility in designing well trajectories and controlling screened intervals. Injection pressures and fluids can be used to purposely fracture the reservoir formation or to purposely prevent fracturing. Numerical simulation of geologic sequestration processes involves the solution of multifluid transport equations within heterogeneous geologic media. These equations that mathematically describe the flow of fluid through the reservoir formation are nonlinear in form, requiring linearization techniques to resolve. In actual geologic settings fluid exchange between a well and reservoir is a function of local pressure gradients, fluid saturations, and formation characteristics. In numerical simulators fluid exchange between a well and reservoir can be specified using a spectrum of approaches that vary from totally ignoring the reservoir conditions to fully considering reservoir conditions and well processes. Well models are a numerical simulation approach that account for local conditions and gradients in the exchange of fluids between the well and reservoir. As with the mathematical equations that describe fluid flow in the reservoir, variation in fluid properties with temperature and pressure yield nonlinearities in the mathematical equations that describe fluid flow within the well. To numerically simulate the fluid exchange between a well and reservoir the two systems of nonlinear multifluid flow equations must be resolved. The spectrum of numerical approaches for resolving these equations varies from zero coupling to full coupling. In this paper we describe a fully coupled solution approach for well model that allows for a flexible well trajectory and screened interval within a structured hexahedral computational grid. In this scheme the nonlinear well equations have been fully integrated into the Jacobian matrix for the reservoir conservation equations, minimizing the matrix bandwidth.

White, Mark D.; Bacon, Diana H.; White, Signe K.; Zhang, Z. F.

2013-08-05T23:59:59.000Z

155

Passive Fully Polarimetric W-Band Millimeter-Wave Imaging  

Science Conference Proceedings (OSTI)

We present the theory, design, and experimental results obtained from a scanning passive W-band fully polarimetric imager. Passive millimeter-wave imaging offers persistent day/nighttime imaging and the ability to penetrate dust, clouds and other obscurants, including clothing and dry soil. The single-pixel scanning imager includes both far-field and near-field fore-optics for investigation of polarization phenomena. Using both fore-optics, a variety of scenes including natural and man-made objects was imaged and these results are presented showing the utility of polarimetric imaging for anomaly detection. Analysis includes conventional Stokes-parameter based approaches as well as multivariate image analysis methods.

Bernacki, Bruce E.; Kelly, James F.; Sheen, David M.; McMakin, Douglas L.; Tedeschi, Jonathan R.; Harris, Robert V.; Mendoza, Albert; Hall, Thomas E.; Hatchell, Brian K.; Valdez, Patrick LJ

2012-04-01T23:59:59.000Z

156

Fully nonlinear excitations of non-Abelian plasma  

E-Print Network (OSTI)

We investigate fully nonlinear, non-Abelian excitations of quark-antiquark plasma, using relativistic fluid theory in cold plasma approximation. There are mainly three important nonlinearities, coming from various sources such as non-Abelian interactions of Yang-Mills (YM) fields, Wong's color dynamics and plasma nonlinearity, in our model. By neglecting nonlinearities due to plasma and color dynamics we get back the earlier results of Blaizot {\\it et. al.}, Phys. Rev. Lett. 72, 3317 (1994). Similarly, by neglecting YM fields nonlinearity and plasma nonlinearity, it reduces to the model of Gupta {\\it et. al.}, Phys. Lett. B498, 223 (2005). Thus we have the most general non-Abelian mode of quark-gluon plasma (QGP). Further, our model resembles the problem of propagation of laser beam through relativistic plasma, Physica 9D, 96 (1983). in the absence of all non-Abelian interactions.

Vishnu M. Bannur

2007-06-06T23:59:59.000Z

157

CRDIAC: Coupled Reactor Depletion Instrument with Automated Control  

SciTech Connect

When modeling the behavior of a nuclear reactor over time, it is important to understand how the isotopes in the reactor will change, or transmute, over that time. This is especially important in the reactor fuel itself. Many nuclear physics modeling codes model how particles interact in the system, but do not model this over time. Thus, another code is used in conjunction with the nuclear physics code to accomplish this. In our code, Monte Carlo N-Particle (MCNP) codes and the Multi Reactor Transmutation Analysis Utility (MRTAU) were chosen as the codes to use. In this way, MCNP would produce the reaction rates in the different isotopes present and MRTAU would use cross sections generated from these reaction rates to determine how the mass of each isotope is lost or gained. Between these two codes, the information must be altered and edited for use. For this, a Python 2.7 script was developed to aid the user in getting the information in the correct forms. This newly developed methodology was called the Coupled Reactor Depletion Instrument with Automated Controls (CRDIAC). As is the case in any newly developed methodology for modeling of physical phenomena, CRDIAC needed to be verified against similar methodology and validated against data taken from an experiment, in our case AFIP-3. AFIP-3 was a reduced enrichment plate type fuel tested in the ATR. We verified our methodology against the MCNP Coupled with ORIGEN2 (MCWO) method and validated our work against the Post Irradiation Examination (PIE) data. When compared to MCWO, the difference in concentration of U-235 throughout Cycle 144A was about 1%. When compared to the PIE data, the average bias for end of life U-235 concentration was about 2%. These results from CRDIAC therefore agree with the MCWO and PIE data, validating and verifying CRDIAC. CRDIAC provides an alternative to using ORIGEN-based methodology, which is useful because CRDIAC's depletion code, MRTAU, uses every available isotope in its depletion, unlike ORIGEN, which only depletes the isotopes specified by the user. This means that depletions done by MRTAU more accurately reflect reality. MRTAU also allows the user to build new isotope data sets, which means any isotope with nuclear data could be depleted, something that would help predict the outcomes of nuclear reaction testing in materials other than fuel, like beryllium or gold.

Steven K. Logan

2012-08-01T23:59:59.000Z

158

Shock induced multi-mode damage in depleted uranium  

SciTech Connect

Recent dynamic damage studies on depleted uranium samples have revealed mixed mode failure mechanisms leading to incipient cracking as well as ductile failure processes. Results show that delamination of inclusions upon compression may provide nucleation sites for damage initiation in the form of crack tip production. However, under tension the material propagates cracks in a mixed shear localization and mode-I ductile tearing and cracking. Cracks tips appear to link up through regions of severe, shear dominated plastic flow. Shock recovery experiments were conducted on a 50 mm single stage light gas gun. Serial metallographic sectioning was conducted on the recovered samples to characterize the bulk response of the sample. Experiments show delaminated inclusions due to uniaxial compression without damage propagation. Further results show the propagation of the damage through tensile loading to the incipient state, illustrating ductile processes coupled with mixed mode-I tensile ductile tearing, shear localization, and mode-I cracking in depleted uranium.

Koller, Darcie D [Los Alamos National Laboratory; Cerreta, Ellen K [Los Alamos National Laboratory; Gray, Ill, George T [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

159

depleted underground oil shale for the permanent storage of carbon  

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

depleted underground oil shale for the permanent storage of carbon depleted underground oil shale for the permanent storage of carbon dioxide (CO 2 ) generated during the oil shale extraction process. AMSO, which holds a research, development, and demonstration (RD&D) lease from the U.S. Bureau of Land Management for a 160-acre parcel of Federal land in northwest Colorado's oil-shale rich Piceance Basin, will provide technical assistance and oil shale core samples. If AMSO can demonstrate an economically viable and environmentally acceptable extraction process, it retains the right to acquire a 5,120-acre commercial lease. When subject to high temperatures and high pressures, oil shale (a sedimentary rock that is rich in hydrocarbons) can be converted into oil. Through mineralization, the CO 2 could be stored in the shale

160

Cermet Waste Packages Using Depleted Uranium Dioxide and Steel  

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

CERMET WASTE PACKAGES USING DEPLETED URANIUM DIOXIDE AND STEEL CERMET WASTE PACKAGES USING DEPLETED URANIUM DIOXIDE AND STEEL Charles W. Forsberg Oak Ridge National Laboratory * P.O. Box 2008 Oak Ridge, Tennessee 37831-6180 Tel: (865) 574-6783 Fax: (865) 574-9512 Email: forsbergcw@ornl.gov Manuscript Number: 078 File Name: DuCermet.HLWcon01.article.final Article Prepared for 2001 International High-Level Radioactive Waste Management Conference American Nuclear Society Las Vegas, Nevada April 29-May 3, 2001 Limits: 1500 words; 3 figures Actual: 1450 words; 3 figures Session: 3.6 Disposal Container Materials and Designs The submitted manuscript has been authored by a contractor of the U.S. Government under contract DE-AC05-00OR22725. Accordingly, the U.S. Government retains a nonexclusive, royalty-free license to publish or reproduce the published form of this contribution,

Note: This page contains sample records for the topic "fully depleted prior" from the National Library of EnergyBeta (NLEBeta).
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161

Uranio impoverito: perch'e? (Depleted uranium: why?)  

E-Print Network (OSTI)

In this paper we develop a simple model of the penetration process of a long rod through an uniform target. Applying the momentum and energy conservation laws, we derive an analytical relation which shows how the penetration depth depends upon the density of the rod, given a fixed kinetic energy. This work was sparked off by the necessity of the author of understanding the reasons of the effectiveness of high density penetrators (e.g. depleted uranium penetrators) as anti-tank weapons.

D'Abramo, G

2003-01-01T23:59:59.000Z

162

Depletion-induced structure and dynamics in bimodal colloidal suspensions.  

Science Conference Proceedings (OSTI)

Combined small angle x-ray scattering and x-ray photon correlation spectroscopy studies of moderately concentrated bimodal hard-sphere colloidal suspensions in the fluid phase show that depletion-induced demixing introduces spatially heterogeneous dynamics with two distinct time scales. The adhesive nature, as well as the mobility, of the large particles is determined by the level of interaction within the monomodal domains. This interaction is driven by osmotic forces, which are governed by the relative concentration of the constituents.

Sikorski, M.; Sandy, A. R.; Narayanan, S. (X-Ray Science Division)

2011-05-03T23:59:59.000Z

163

Prior Lake, Minnesota: Energy Resources | Open Energy Information  

Open Energy Info (EERE)

Prior Lake, Minnesota: Energy Resources Prior Lake, Minnesota: Energy Resources Jump to: navigation, search Equivalent URI DBpedia Coordinates 44.7132969°, -93.4227274° 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":44.7132969,"lon":-93.4227274,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

164

Accounting for Depletion of Oil and Gas Resources in Malaysia  

Science Conference Proceedings (OSTI)

Since oil and gas are non-renewable resources, it is important to identify the extent to which they have been depleted. Such information will contribute to the formulation and evaluation of appropriate sustainable development policies. This paper provides an assessment of the changes in the availability of oil and gas resources in Malaysia by first compiling the physical balance sheet for the period 2000-2007, and then assessing the monetary balance sheets for the said resource by using the Net Present Value method. Our findings show serious reduction in the value of oil reserves from 2001 to 2005, due to changes in crude oil prices, and thereafter the depletion rates decreased. In the context of sustainable development planning, albeit in the weak sustainability sense, it will be important to ascertain if sufficient reinvestments of the estimated resource rents in related or alternative capitals are being attempted by Malaysia. For the study period, the cumulative resource rents were to the tune of RM61 billion. Through a depletion or resource rents policy, the estimated quantum may guide the identification of a reinvestment threshold (after considering needed capital investment for future development of the industry) in light of ensuring the future productive capacity of the economy at the time when the resource is exhausted.

Othman, Jamal, E-mail: jortman@ukm.my; Jafari, Yaghoob, E-mail: yaghoob.jafari@gmail.com [Universiti Kebangsaan Malaysia, Faculty of Economics and Management (Malaysia)

2012-12-15T23:59:59.000Z

165

CO depletion --- An evolutionary tracer for molecular clouds  

E-Print Network (OSTI)

Planck cold clumps are among the most promising objects to investigate the initial conditions of the evolution of molecular clouds. In this work, by combing the dust emission data from the survey of Planck satellite with the molecular data of $^{12}$CO/$^{13}$CO (1-0) lines from observations with the Purple Mountain Observatory (PMO) 14 m telescope, we investigate the CO abundance, CO depletion and CO-to-H$_{2}$ conversion factor of 674 clumps in the early cold cores (ECC) sample. The median and mean values of the CO abundance are 6.2$\\times10^{-5}$ and 9.1$\\times10^{-5}$, respectively. The mean and median of CO depletion factor are 2.8 and 1.4, respectively. The median value of $X_{CO-to-H_{2}}$ for the whole sample is $3.3\\times10^{20}$ cm$^{-2}$K$^{-1}$km$^{-1}$ s. The CO abundance, CO depletion factor and CO-to-H$_{2}$ conversion factor seems to be strongly correlated to other physical parameters (e.g. dust temperature, dust emissivity spectra index and column density). CO gas severely freeze out in colde...

Liu, Tie; Zhang, Huawei

2013-01-01T23:59:59.000Z

166

Analysis of an interwell tracer test in a depleted heavy-oil reservoir  

SciTech Connect

This paper presents field data and analyses of an interwell tracer test conducted in the Niitsu oil field, which is a fully depleted heavy-oil reservoir of unconsolidated sand formation. Water containing a chemical tracer was injected at a constant rate into an injector surrounded by three production wells. Effluent analyses showed very early breakthrough of injected water at two of the producing wells. The test results suggest a strong areal heterogeneity of the tested formation. An appropriate analytic model was used to obtain a preliminary interpretation of the results. A modified three-dimensional (3D) black-oil model developed to simulate th polymer flood process was then used for analyzing the data in more detail. The model treats tracer solution as a fourth component and can also account for adsorption of tracer. Simulation efforts were concentrated on matching the breakthrough times and tracer profiles after breakthrough. Through both the analytic and the simulation work, the reservoir is characterized by a highly heterogeneous distribution of horizontal permeability, a thin layer of high permeability, and a natural waterdrive that cause a preferential flow trend in a direction toward one producer. The authors conclude that the interwell tracer test is an effective tool for evaluating reservoir heterogeneities and a quantitative analysis of test data is done with the polymer option of a black-oil simulator.

Ohno, K.; Nanba, T.; Horne, R.N.

1987-12-01T23:59:59.000Z

167

Analysis of an interwell tracer test in a depleted heavy oilreservoir  

SciTech Connect

This paper presents field data and analyses of an interwell tracer test conducted in the Niitsu oil field which is a fully depleted heavy oil reservoir of unconsolidated sand formation. The purpose of the tracer test is to diagnose reservoir heterogeneity at a location where a micellar/ polymer field test is planned. Water containing a chemical tracer was injected at a constant rate into an injector surrounded by three production wells. Effluent analyses showed very early breakthrough of injected water at two of the producing wells, no tracer, however, was detected at the third producer thoughout the test period. In addition, tracer production profiles at two wells after breakthrough differed much from each other. These test results suggest a strong areal heterogeneity of the tested formation. An appropriate analytical model was used to obtain a preliminary interpretation of the results. A modified three-dimensional black oil model developed to simulate polymer flood process was then utilized for analyzing the data in more detail. The model treats tracer solution as a fourth component, and can also account for adsorption of tracer.

Ohno, K.; Horne, R.N.; Nanba, T.

1985-03-01T23:59:59.000Z

168

A fully microfabricated two-dimensional electrospray array with applications to space propulsion; Fully microfabricated 2D electrospray array with applications to space propulsion.  

E-Print Network (OSTI)

??This thesis presents the design, fabrication and testing of a fully-integrated planar electrospray thruster array, which could lead to more efficient and precise thrusters for… (more)

Gassend, Blaise L. P. (Blaise Laurent Patrick), 1978-

2007-01-01T23:59:59.000Z

169

Antibiotic Consumption in Children Prior to Diagnosis of Asthma  

E-Print Network (OSTI)

the most frequent diag- noses preceding the antibiotic dispensations in the 6 months prior to the index date (Table 4). Lower RTI and bronchitis were more frequently associated with antibiotic dispensing in the one month before the index date compared... to the 5 months before. Upper RTI, acute otitis media, lower urinary tract infection, and skin/soft tissue infection were less frequently associated with antibiotic dispensing in the one month before the index date compared to the 5 months before that...

Marra, Fawziah; Marra, Carlo A; Richardson, Kathryn J; Lynd, Larry D; Fitzgerald, J Mark

2011-05-31T23:59:59.000Z

170

Characterization of in situ oil shale retorts prior to ignition  

DOE Patents (OSTI)

Method and system for characterizing a vertical modified in situ oil shale retort prior to ignition of the retort. The retort is formed by mining a void at the bottom of a proposed retort in an oil shale deposit. The deposit is then sequentially blasted into the void to form a plurality of layers of rubble. A plurality of units each including a tracer gas cannister are installed at the upper level of each rubble layer prior to blasting to form the next layer. Each of the units includes a receiver that is responsive to a coded electromagnetic (EM) signal to release gas from the associated cannister into the rubble. Coded EM signals are transmitted to the receivers to selectively release gas from the cannisters. The released gas flows through the retort to an outlet line connected to the floor of the retort. The time of arrival of the gas at a detector unit in the outlet line relative to the time of release of gas from the cannisters is monitored. This information enables the retort to be characterized prior to ignition.

Turner, Thomas F. (Laramie, WY); Moore, Dennis F. (Laramie, WY)

1984-01-01T23:59:59.000Z

171

FAQ 16-How much depleted uranium hexafluoride is stored in the United  

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

How much depleted uranium hexafluoride is stored in the United States? How much depleted uranium hexafluoride is stored in the United States? How much depleted uranium hexafluoride is stored in the United States? U.S. DOE's inventory of depleted UF6 consists of approximately 700,000 metric tons of depleted UF6, containing about 470,000 metric tons of uranium, currently stored at the Paducah Site in Kentucky, the Portsmouth Site in Ohio, and the East Tennessee Technology Park (ETTP) in Tennessee (formerly known as the K-25 Site). This inventory of depleted UF6 is stored in about 57,000 steel cylinders. The inventory is listed in the table below. DOE Inventory of Depleted UF6 Location Total Cylinders Total Depleted UF6 (metric tons) Paducah, Kentucky 36,191 436,400 Portsmouth, Ohio 16,109 195,800 Oak Ridge, Tennessee 4,822 54,300

172

FAQ 35-What are the potential health risks from disposal of depleted...  

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

health risks from disposal of depleted uranium as an oxide? Once depleted uranium has been converted from UF6 to the oxide form, the risk associated with handling at a disposal...

173

FAQ 33-What are the potential health risks from storage of depleted...  

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

health risks from storage of depleted uranium as an oxide? Once depleted uranium has been converted from UF6 to the oxide form, the risk associated with storage and handling is...

174

On equilibrium tides in fully convective planets and stars  

E-Print Network (OSTI)

We consider the tidal interaction of a fully convective primary star and a point mass. Using a normal mode decomposition we calculate the evolution of the primary angular velocity and orbit for arbitrary eccentricity e. The dissipation acting on the tidal perturbation is associated with convective turbulence. A novel feature of the Paper is that, to take into account of the fact that there is a relaxation time t_{c}, being the turn-over time of convective eddies, associated with the process, this is allowed to act non locally in time, producing a dependence of the dissipation on tidal forcing frequency. Results are expressed in terms of the Fourier coefficients of the tidal potential. We find analytical approximations for these valid for $e>0.2$. When the tidal response is frequency independent, our results are equivalent to those obtained in the standard constant time lag approximation. When there is the frequency dependence of the dissipative response, the evolution can differ drastically. In that case the system can evolve through a sequence of spin-orbit corotation resonances with Omega_{r}/Omega_{orb}=n/2, where Omega_{r} and Omega_{orb} are the rotation and orbital frequencies and n is an integer. We study this case analytically and numerically.

P. B. Ivanov; J. C. B. Papaloizou

2003-12-22T23:59:59.000Z

175

Depletion Reactivity Benchmark for the International Handbook of Evaluated Reactor Physics Benchmark Experiments  

Science Conference Proceedings (OSTI)

The Electric Power Research Institute– (EPRI-) sponsored depletion reactivity benchmarks documented in reports 1022909, Benchmarks for Quantifying Fuel Reactivity Depletion Uncertainty, and 1025203, Utilization of the EPRI Depletion Benchmarks for Burnup Credit Validation, have been translated to an evaluated benchmark for incorporation in the International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhE), published by the Organisation for Economic ...

2013-04-10T23:59:59.000Z

176

Gas Emission Rate Prediction in Fully-Mechanized Excavated Faces Based on Support Vector Machine  

Science Conference Proceedings (OSTI)

In order to ensure safety in coal production, full assurance is given for fully-mechanized excavated faces. Based on the vector supporting machine for regression (SVR), a model is established for predicting the gas emission in fully-mechanized excavated ... Keywords: SVM, Tracking, emission rate, fully-mechanized excavated faces, gas prediction

Wang Changlong; Fu Weihua

2009-11-01T23:59:59.000Z

177

Conditioning of carbonaceous material prior to physical beneficiation  

DOE Patents (OSTI)

A carbonaceous material such as coal is conditioned by contact with a supercritical fluid prior to physical beneficiation. The solid feed material is contacted with an organic supercritical fluid such as cyclohexane or methanol at temperatures slightly above the critical temperature and pressures of 1 to 4 times the critical pressure. A minor solute fraction is extracted into critical phase and separated from the solid residuum. The residuum is then processed by physical separation such as by froth flotation or specific gravity separation to recover a substantial fraction thereof with reduced ash content. The solute in supercritical phase can be released by pressure reduction and recombined with the low-ash, carbonaceous material.

Warzinski, Robert P. (Venetia, PA); Ruether, John A. (McMurray, PA)

1987-01-01T23:59:59.000Z

178

Selection of a management strategy for depleted uranium hexafluoride  

Science Conference Proceedings (OSTI)

A consequence of the uranium enrichment process used in the United States (US) is the accumulation of a significant amount of depleted uranium hexafluoride (UF{sub 6}). Currently, approximately 560,000 metric tons of the material are stored at three different sites. The US Department of Energy (DOE) has recently initiated a program to consider alternative strategies for the cost-effective and environmentally safe long-term management of this inventory of depleted UF{sub 6}. The program involves a technology and engineering assessment of proposed management options (use/reuse, conversion, storage, or disposal) and an analysis of the potential environmental impacts and life-cycle costs of alternative management strategies. The information obtained from the studies will be used by the DOE to select a preferred long-term management strategy. The selection and implementation of a management strategy will involve consideration of a number of important issues such as environmental, health, and safety effects; the balancing of risks versus costs in a context of reduced government spending; socioeconomic implications, including effects on the domestic and international uranium industry; the technical status of proposed uses or technologies; and public involvement in the decision making process. Because of its provisions for considering a wide range of relevant issues and involving the public, this program has become a model for future DOE materials disposition programs. This paper presents an overview of the Depleted Uranium Hexafluoride Management Program. Technical findings of the program to date are presented, and major issues involved in selecting and implementing a management strategy are discussed.

Patton, S.E.; Hanrahan, E.J.; Bradley, C.E.

1995-09-06T23:59:59.000Z

179

Background Fact Sheet Transfer of Depleted Uranium and Subsequent Transactions  

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

Background Fact Sheet Background Fact Sheet Transfer of Depleted Uranium and Subsequent Transactions At the direction of Energy Secretary Steven Chu, over many months, the Energy Department (DOE) has been working closely with Energy Northwest (ENW), the Tennessee Valley Authority (TVA), and USEC Inc. (USEC) to develop a plan to address the challenges at USEC's Paducah Gaseous Diffusion Plant (GDP) that advances America's national security interests, protects taxpayers, and provides benefits for TVA and the Bonneville Power Administration's (BPA's) electric ratepayers and business operations. BPA is ENW's sole customer, purchasing 100 percent of ENW's Columbia Generating Station's electric power as part of BPA's overall

180

Engineering Analysis for Disposal of Depleted Uranium Tetrafluoride (UF4)  

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

6 6 Engineering Analysis for Disposal of Depleted Uranium Tetrafluoride (UF 4 ) Environmental Assessment Division Argonne National Laboratory Operated by The University of Chicago, under Contract W-31-109-Eng-38, for the United States Department of Energy Argonne National Laboratory Argonne National Laboratory, with facilities in the states of Illinois and Idaho, is owned by the United States Government and operated by The University of Chicago under the provisions of a contract with the Department of Energy. This technical memorandum is a product of Argonne's Environmental Assessment Division (EAD). For information on the division's scientific and engineering activities, contact: Director, Environmental Assessment Division Argonne National Laboratory Argonne, Illinois 60439-4832

Note: This page contains sample records for the topic "fully depleted prior" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
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181

Depleted uranium storage and disposal trade study: Summary report  

SciTech Connect

The objectives of this study were to: identify the most desirable forms for conversion of depleted uranium hexafluoride (DUF6) for extended storage, identify the most desirable forms for conversion of DUF6 for disposal, evaluate the comparative costs for extended storage or disposal of the various forms, review benefits of the proposed plasma conversion process, estimate simplified life-cycle costs (LCCs) for five scenarios that entail either disposal or beneficial reuse, and determine whether an overall optimal form for conversion of DUF6 can be selected given current uncertainty about the endpoints (specific disposal site/technology or reuse options).

Hightower, J.R.; Trabalka, J.R.

2000-02-01T23:59:59.000Z

182

Record of Decision for Long-term Management and Use of Depleted Uranium Hexafluoride  

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

Record of Decision for Long-Term Management and Use of Depleted Uranium Hexafluoride AGENCY: Department of Energy ACTION: Record of Decision SUMMARY: The Department of Energy ("DOE" or "the Department") issued the Final Programmatic Environmental Impact Statement for Alternative Strategies for the Long-Term Management and Use of Depleted Uranium Hexafluoride (Final PEIS) on April 23, 1999. DOE has considered the environmental impacts, benefits, costs, and institutional and programmatic needs associated with the management and use of its approximately 700,000 metric tons of depleted uranium hexafluoride (DUF 6 ). DOE has decided to promptly convert the depleted UF 6 inventory to depleted uranium oxide, depleted uranium metal, or a combination of both. The depleted uranium oxide will be

183

Towards a fully printable battery : robocast deposition of separators.  

Science Conference Proceedings (OSTI)

The development of thin batteries has presented several interesting problems which are not seen in traditional battery sizes. As the size of a battery reaches a minimum, the usable capacity of the battery decreases due to the fact that the major constituent of the battery becomes the package and separator. As the size decreases, the volumetric contribution from the package and separator increases. This can result in a reduction of capacity from these types of batteries of nearly all of the available power. The development of a method for directly printing the battery layers, including the package, in place would help to alleviate this problem. The technology used in this paper to directly print battery components is known as robocasting and is capable of direct writing of slurries in complex geometries. This method is also capable of conformally printing on three dimensional surfaces, opening up the possibility of novel batteries based on tailoring battery footprints to conform to the available substrate geometry. Interfacial resistance can also be reduced by using the direct write method. Each layer is printed in place on the battery stack instead of being stacked one at a time. This ensures an intimate contact and seal at every interface within the cell. By limiting the resistance at these interfaces, we effectively help increase the useable capacity of our battery through increase transport capability. We have developed methodology for printing several different separator materials for use in a lithium cell. When combined with a printable cathode comprised of LiFePO{sub 4} (as seen in Figure 1) and a lithium anode, our battery is capable of delivering a theoretical capacity of 170 mAh g{sup -1}. This capacity is diminished by transport phenomena within the cell which limit the transport rate of the lithium ions during the discharge cycle. The material set chosen for the printable separator closely resemble those used in commercially available separators in order to keep the transport rates high within the cell during charge and discharge. In order to evaluate the effect of each layer being printed using the robocasting technique, coin cells using printed separator materials were assembled and cycled vs. Li/Li{sup +}. This allows for the standardization of a test procedure in order to evaluate each layer of a printed cell one layer at a time. A typical charge/discharge curve can be seen in Figure 2 using a printed LiFePO{sub 4} cathode and a printed separator with a commercial Celgard separator. This experiment was run to evaluate the loss in capacity and slowdown of transport within the cell due to the addition of the printed separator. This cell was cycled multiple times and showed a capacity of 75 mAh/g. The ability for this cell to cycle with good capacity indicates that a fully printable separator material is viable for use in a full lithium cell due to the retention of capacity. Most of the fully printed cathode and separator cells exhibit working capacities between 65 and 95 mAh/g up to this point. This capacity should increase as the efficiency of the printed separator increases. The ability to deposit each layer within the cell allows for intimate contact of each layer and ensures for a reduction of interfacial impedance of each layer within the cell. The overall effect of printing multiple layers within the cell will be an overall increase in the ionic conductivity during charge and discharge cycles. Several different polymer membranes have been investigated for use as a printed separator. The disadvantage of using polymer separators or solid electrolyte batteries is that they have relatively low conductivities at room temperature (10{sup -6} - 10{sup -8} S cm{sup -1}). This is orders of magnitude lower than the typically accepted 10{sup -3} S cm{sup -1} needed for proper ionic transport during battery discharge Because of their low conductivity, typical polymer separators such as polyethylene oxide (PEO) have a normal operational temperature well above ambient. At elevated temperature the conductivity of the

Atanassov, Plamen Borissov (University of New Mexico); Fenton, Kyle Ross (University of New Mexico); Apblett, Christopher Alan

2010-04-01T23:59:59.000Z

184

Performance of Transuranic-Loaded Fully Ceramic Micro-Encapsulated Fuel in LWRs Final Report, Including Void Reactivity Evaluation  

SciTech Connect

The current focus of the Deep Burn Project is on once-through burning of transuranics (TRU) in light-water reactors (LWRs). The fuel form is called Fully-Ceramic Micro-encapsulated (FCM) fuel, a concept that borrows the tri-isotropic (TRISO) fuel particle design from high-temperature reactor technology. In the Deep Burn LWR (DB-LWR) concept, these fuel particles are pressed into compacts using SiC matrix material and loaded into fuel pins for use in conventional LWRs. The TRU loading comes from the spent fuel of a conventional LWR after 5 years of cooling. Unit cell and assembly calculations have been performed using the DRAGON-4 code to assess the physics attributes of TRU-only FCM fuel in an LWR lattice. Depletion calculations assuming an infinite lattice condition were performed with calculations of various reactivity coefficients performed at each step. Unit cells and assemblies containing typical UO2 and mixed oxide (MOX) fuel were analyzed in the same way to provide a baseline against which to compare the TRU-only FCM fuel. Then, assembly calculations were performed evaluating the performance of heterogeneous arrangements of TRU-only FCM fuel pins along with UO2 pins.

Michael A. Pope; R. Sonat Sen; Brian Boer; Abderrafi M. Ougouag; Gilles Youinou

2011-09-01T23:59:59.000Z

185

Shape prior model for media-adventitia border segmentation in IVUS using graph cut  

Science Conference Proceedings (OSTI)

We present a shape prior based graph cut method which does not require user initialisation. The shape prior is generalised from multiple training shapes, rather than using singular templates as priors. Weighted directed graph construction is used to ... Keywords: IVUS, graph cut, image segmentation, shape prior

Ehab Essa; Xianghua Xie; Igor Sazonov; Perumal Nithiarasu; Dave Smith

2012-10-01T23:59:59.000Z

186

Attainable Burnup in a LIFE Engine Loaded with Depleted Uranium  

Science Conference Proceedings (OSTI)

The Laser Inertial Fusion-based Energy (LIFE) system uses a laser-based fusion source for electricity production. The (D,T) reaction, beside a pure fusion system, allows the option to drive a sub-critical fission blanket in order to increase the total energy gain. In a typical fusion-fission LIFE engine the fission blanket is a spherical shell around the fusion source, preceded by a beryllium shell for neutron multiplications by means of (n,2n) reactions. The fuel is in the form of TRISO particles dispersed in carbon pebbles, cooled by flibe. The optimal design features 80 cm thick blanket, 16 cm multiplier, and 20% TRISO packing factor. A blanket loaded with depleted uranium and depleted in a single batch with continuous mixing can achieve burnup as high as {approx}85% FIMA while generating 2,000 MW of total thermal power and producing enough tritium to be used for fusion. A multi-segment blanket with a central promotion shuffling scheme enhances burnup to {approx}90% FIMA, whereas a blanket that is operated with continuous refueling achieves only 82% FIMA under the same constraints of thermal power and tritium self-sufficiency. Both, multi-segment and continuous refueling eliminate the need for a fissile breeding phase.

Fratoni, M; Kramer, K J; Latkowski, J F

2009-11-30T23:59:59.000Z

187

Calculating Capstone Depleted Uranium Aerosol Concentrations from Beta Activity Measurements  

SciTech Connect

Beta activity measurements were used as surrogate measurements of uranium mass in aerosol samples collected during the field testing phase of the Capstone Depleted Uranium (DU) Aerosol Study. These aerosol samples generated by the perforation of armored combat vehicles were used to characterize the depleted uranium (DU) source term for the subsequent human health risk assessment (HHRA) of Capstone aerosols. Establishing a calibration curve between beta activity measurements and uranium mass measurements is straightforward if the uranium isotopes are in equilibrium with their immediate short-lived, beta-emitting progeny. For DU samples collected during the Capstone study, it was determined that the equilibrium between the uranium isotopes and their immediate short lived, beta-emitting progeny had been disrupted when penetrators had perforated target vehicles. Adjustments were made to account for the disrupted equilibrium and for wall losses in the aerosol samplers. Correction factors for the disrupted equilibrium ranged from 0.16 to 1, and the wall loss correction factors ranged from 1 to 1.92.

Szrom, Fran; Falo, Gerald A.; Parkhurst, MaryAnn; Whicker, Jeffrey J.; Alberth, David P.

2009-03-01T23:59:59.000Z

188

Ozone-depleting-substance control and phase-out plan  

SciTech Connect

Title VI of the Federal Clean Air Act Amendments of 1990 requires regulation of the use and disposal of ozone-depleting substances (ODSs) (e.g., Halon, Freon). Several important federal regulations have been promulgated that affect the use of such substances at the Hanford Site. On April 23, 1993, Executive Order (EO) 12843, Procurement Requirements and Policies for Federal Agencies for Ozone-Depleting Substances (EPA 1993) was issued for Federal facilities to conform to the new US Environmental Protection Agency (EPA) regulations implementing the Clean Air Act of 1963 (CAA), Section 613, as amended. To implement the requirements of Title VI the US Department of Energy, Richland Operations Office (RL), issued a directive to the Hanford Site contractors on May 25, 1994 (Wisness 1994). The directive assigns Westinghouse Hanford Company (WHC) the lead in coordinating the development of a sitewide comprehensive implementation plan to be drafted by July 29, 1994 and completed by September 30, 1994. The implementation plan will address several areas where immediate compliance action is required. It will identify all current uses of ODSs and inventories, document the remaining useful life of equipment that contains ODS chemicals, provide a phase-out schedule, and provide a strategy that will be implemented consistently by all the Hanford Site contractors. This plan also addresses the critical and required elements of Federal regulations, the EO, and US Department of Energy (DOE) guidance. This plan is intended to establish a sitewide management system to address the clean air requirements.

Nickels, J.M.; Brown, M.J.

1994-07-01T23:59:59.000Z

189

The scale analysis sequence for LWR fuel depletion  

Science Conference Proceedings (OSTI)

The SCALE (Standardized Computer Analyses for Licensing Evaluation) code system is used extensively to perform away-from-reactor safety analysis (particularly criticality safety, shielding, heat transfer analyses) for spent light water reactor (LWR) fuel. Spent fuel characteristics such as radiation sources, heat generation sources, and isotopic concentrations can be computed within SCALE using the SAS2 control module. A significantly enhanced version of the SAS2 control module, which is denoted as SAS2H, has been made available with the release of SCALE-4. For each time-dependent fuel composition, SAS2H performs one-dimensional (1-D) neutron transport analyses (via XSDRNPM-S) of the reactor fuel assembly using a two-part procedure with two separate unit-cell-lattice models. The cross sections derived from a transport analysis at each time step are used in a point-depletion computation (via ORIGEN-S) that produces the burnup-dependent fuel composition to be used in the next spectral calculation. A final ORIGEN-S case is used to perform the complete depletion/decay analysis using the burnup-dependent cross sections. The techniques used by SAS2H and two recent applications of the code are reviewed in this paper. 17 refs., 5 figs., 5 tabs.

Hermann, O.W.; Parks, C.V.

1991-01-01T23:59:59.000Z

190

Numerical study of error propagation in Monte Carlo depletion simulations  

Science Conference Proceedings (OSTI)

Improving computer technology and the desire to more accurately model the heterogeneity of the nuclear reactor environment have made the use of Monte Carlo depletion codes more attractive in recent years, and feasible (if not practical) even for 3-D depletion simulation. However, in this case statistical uncertainty is combined with error propagating through the calculation from previous steps. In an effort to understand this error propagation, a numerical study was undertaken to model and track individual fuel pins in four 17 x 17 PWR fuel assemblies. By changing the code's initial random number seed, the data produced by a series of 19 replica runs was used to investigate the true and apparent variance in k{sub eff}, pin powers, and number densities of several isotopes. While this study does not intend to develop a predictive model for error propagation, it is hoped that its results can help to identify some common regularities in the behavior of uncertainty in several key parameters. (authors)

Wyant, T.; Petrovic, B. [Nuclear and Radiological Engineering, Georgia Inst. of Technology, 770 State Street, Atlanta, GA 30332-0745 (United States)

2012-07-01T23:59:59.000Z

191

Sampling Plan for Assaying Plates Containing Depleted or Normal Uranium  

Science Conference Proceedings (OSTI)

This paper describes the rationale behind the proposed method for selecting a 'representative' sample of uranium metal plates, portions of which will be destructively assayed at the Y-12 Security Complex. The total inventory of plates is segregated into two populations, one for Material Type 10 (depleted uranium (DU)) and one for Material Type 81 (normal [or natural] uranium (NU)). The plates within each population are further stratified by common dimensions. A spreadsheet gives the collective mass of uranium element (and isotope for DU) and the piece count of all plates within each stratum. These data are summarized in Table 1. All plates are 100% uranium metal, and all but approximately 60% of the NU plates have Kel-F{reg_sign} coating. The book inventory gives an overall U-235 isotopic percentage of 0.22% for the DU plates, ranging from 0.19% to 0.22%. The U-235 ratio of the NU plates is assumed to be 0.71%. As shown in Table 1, the vast majority of the plates are comprised of depleted uranium, so most of the plates will be sampled from the DU population.

Ivan R. Thomas

2011-11-01T23:59:59.000Z

192

Including environmental concerns in management strategies for depleted uranium hexafluoride  

Science Conference Proceedings (OSTI)

One of the major programs within the Office of Nuclear Energy, Science, and Technology of the US Department of Energy (DOE) is the depleted uranium hexafluoride (DUF{sub 6}) management program. The program is intended to find a long-term management strategy for the DUF{sub 6} that is currently stored in approximately 46,400 cylinders at Paducah, KY; Portsmouth, OH; and Oak Ridge, TN, USA. The program has four major components: technology assessment, engineering analysis, cost analysis, and the environmental impact statement (EIS). From the beginning of the program, the DOE has incorporated the environmental considerations into the process of strategy selection. Currently, the DOE has no preferred alternative. The results of the environmental impacts assessment from the EIS, as well as the results from the other components of the program, will be factored into the strategy selection process. In addition to the DOE`s current management plan, other alternatives continued storage, reuse, or disposal of depleted uranium, will be considered in the EIS. The EIS is expected to be completed and issued in its final form in the fall of 1997.

Goldberg, M. [Argonne National Laboratory, Washington, DC (United States); Avci, H.I. [Argonne National Lab., IL (United States); Bradley, C.E. [USDOE, Washington, DC (United States)

1995-12-31T23:59:59.000Z

193

On the Presence of Depleted Zones in Platinum  

SciTech Connect

In the bombardment of materials with heavy particles a large amount of energy can be deposited in a very small region by a primary knock-on atom and the local atomic arrangement can be thereby drastically disrupted. Various measurements of physical properties of such irradiated materials indicate the presence of distributions of defects which are removed in a step-like manner by annealing. One of the more interesting physical property changes accompanying fast particle irradiation is the attendant change in mechanical properties of irradiated crystals. The defect which is responsible for the mechanical property changes of irradiated crystals is only removed at high temperatures, temperatures coresponding to self diffusion. This observation, as well as others, has led to the model of a depleted zone as being responsible for the changes of mechanical properties of irradiated crystals. A depleted zone is envisioned as a region of crystal where a high local concentration of point defects exists - a belt of interstitials surrounding a multiply connected complex of vacancy clusters. We would like to present here some evidence which lends support to the existence of such defects.

Attardo, M J; Galligan, J M

1966-08-05T23:59:59.000Z

194

Repository Applications: Potential Benefits of Using Depleted Uranium (DU)  

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

Repository Applications Repository Applications Repository Applications: Potential Benefits of Using Depleted Uranium (DU) in a Geological Repository The United States is investigating the Yucca Mountain (YM) site in Nevada for the disposal of radioactive spent nuclear fuel (SNF)—the primary waste from nuclear power plants. The SNF would be packaged and then emplaced 200 to 300 m underground in parallel disposal tunnels. The repository isolates the SNF from the biosphere until the radionuclides decay to safe levels. DU may improve the performance of geological repositories for disposal of SNF via three mechanisms: Radiation shielding for waste packages to protect workers Lowering the potential for long-term nuclear criticality in the repository Reducing the potential for releases of radionuclides from the SNF

195

Military use of depleted uranium assessment of prolonged population exposure  

E-Print Network (OSTI)

This work is an exposure assessment for a population living in an area contaminated by use of depleted uranium (DU) weapons. RESRAD 5.91 code is used to evaluate the average effective dose delivered from 1, 10, 20 cm depths of contaminated soil, in a residential farmer scenario. Critical pathway and group are identified in soil inhalation or ingestion and children playing with the soil, respectively. From available information on DU released on targeted sites, both critical and average exposure can leave to toxicological hazards; annual dose limit for population can be exceeded on short-term period (years) for soil inhalation. As a consequence, in targeted sites cleaning up must be planned on the basis of measured concentration, when available, while special cautions have to be adopted altogether to reduce unaware exposures, taking into account the amount of the avertable dose.

Giannardi, C

2001-01-01T23:59:59.000Z

196

Video: The Inside Story (of a Depleted Uranium Hexafluoride Cylinder)  

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

Inside Story Inside Story The Inside Story The Inside Story (of a Depleted Uranium Hexafluoride Cylinder) Probes are used to look at the inside of a Uranium Hexafluoride cylinder. The distribution and structure of the contents are discussed. View this Video in Real Player format Download free RealPlayer SP Highlights of the Video: Video 00:42 10 ton 48Xcylinder of UF6 Video 01:19 Liquid UF6 filling 95% of cylinder volume Video 02:15 Liquid UF6 Video 02:23 Beginning of UF6 phase change from liquid to solid Video 02:32 Solid UF6 Video 03:00 Probe and instrument to investigate inside cylinder Video 04:09 Workers preparing to insert TV camera probe into 48X cylinder containing 10 tons of solid UF6 Video 04:28 Inner surface of head of cylinder showing no corrosion

197

Investigation of breached depleted UF{sub 6} cylinders  

Science Conference Proceedings (OSTI)

In June 1990, during a three-site inspection of cylinders being used for long-term storage of solid depleted UF{sub 6}, two 14-ton steel cylinders at Portsmouth, Ohio, were discovered with holes in the barrel section of the cylinders. Both holes, concealed by UF{sub 4} reaction products identical in color to the cylinder coating, were similarly located near the front stiffening ring. The UF{sub 4} appeared to have self-sealed the holes, thus containing nearly all of the uranium contents. Martin Marietta Energy Systems, Inc., Vice President K.W. Sommerfeld immediately formed an investigation team to: (1) identify the most likely cause of failure for the two breached cylinders, (2) determine the impact of these incidents on the three-site inventory, and (3) provide recommendations and preventive measures. This document discusses the results of this investigation.

Barber, E.J.; Butler, T.R.; DeVan, J.H.; Googin, J.M.; Taylor, M.S.; Dyer, R.H.; Russell, J.R.

1991-09-01T23:59:59.000Z

198

Investigation of breached depleted UF sub 6 cylinders  

Science Conference Proceedings (OSTI)

In June 1990, during a three-site inspection of cylinders being used for long-term storage of solid depleted UF{sub 6}, two 14-ton steel cylinders at Portsmouth, Ohio, were discovered with holes in the barrel section of the cylinders. Both holes, concealed by UF{sub 4} reaction products identical in color to the cylinder coating, were similarly located near the front stiffening ring. The UF{sub 4} appeared to have self-sealed the holes, thus containing nearly all of the uranium contents. Martin Marietta Energy Systems, Inc., Vice President K.W. Sommerfeld immediately formed an investigation team to: (1) identify the most likely cause of failure for the two breached cylinders, (2) determine the impact of these incidents on the three-site inventory, and (3) provide recommendations and preventive measures. This document discusses the results of this investigation.

Barber, E.J.; Butler, T.R.; DeVan, J.H.; Googin, J.M.; Taylor, M.S.; Dyer, R.H.; Russell, J.R.

1991-09-01T23:59:59.000Z

199

Draft Supplement Analysis for Location(s) to Dispose of Depleted Uranium Oxide Conversion Product Generated from DOE'S Inventory of Depleted Uranium Hexafluoride  

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

DRAFT SUPPLEMENT ANALYSIS FOR LOCATION(S) TO DISPOSE OF DEPLETED DRAFT SUPPLEMENT ANALYSIS FOR LOCATION(S) TO DISPOSE OF DEPLETED URANIUM OXIDE CONVERSION PRODUCT GENERATED FROM DOE'S INVENTORY OF DEPLETED URANIUM HEXAFLUORIDE (DOE/EIS-0359-SA1 AND DOE/EIS-0360-SA1) March 2007 March 2007 i CONTENTS NOTATION........................................................................................................................... iv 1 INTRODUCTION AND BACKGROUND ................................................................. 1 1.1 Why DOE Has Prepared This Draft Supplement Analysis .............................. 1 1.2 Background ....................................................................................................... 3 1.3 Proposed Actions Considered in this Draft Supplement Analysis.................... 4

200

A fully 3D approach for metal artifact reduction in computed tomography  

SciTech Connect

Purpose: In computed tomography imaging metal objects in the region of interest introduce inconsistencies during data acquisition. Reconstructing these data leads to an image in spatial domain including star-shaped or stripe-like artifacts. In order to enhance the quality of the resulting image the influence of the metal objects can be reduced. Here, a metal artifact reduction (MAR) approach is proposed that is based on a recomputation of the inconsistent projection data using a fully three-dimensional Fourier-based interpolation. The success of the projection space restoration depends sensitively on a sensible continuation of neighboring structures into the recomputed area. Fortunately, structural information of the entire data is inherently included in the Fourier space of the data. This can be used for a reasonable recomputation of the inconsistent projection data. Methods: The key step of the proposed MAR strategy is the recomputation of the inconsistent projection data based on an interpolation using nonequispaced fast Fourier transforms (NFFT). The NFFT interpolation can be applied in arbitrary dimension. The approach overcomes the problem of adequate neighborhood definitions on irregular grids, since this is inherently given through the usage of higher dimensional Fourier transforms. Here, applications up to the third interpolation dimension are presented and validated. Furthermore, prior knowledge may be included by an appropriate damping of the transform during the interpolation step. This MAR method is applicable on each angular view of a detector row, on two-dimensional projection data as well as on three-dimensional projection data, e.g., a set of sequential acquisitions at different spatial positions, projection data of a spiral acquisition, or cone-beam projection data. Results: Results of the novel MAR scheme based on one-, two-, and three-dimensional NFFT interpolations are presented. All results are compared in projection data space and spatial domain with the well-known one-dimensional linear interpolation strategy. Conclusions: In conclusion, it is recommended to include as much spatial information into the recomputation step as possible. This is realized by increasing the dimension of the NFFT. The resulting image quality can be enhanced considerably.

Kratz, Baerbel; Weyers, Imke; Buzug, Thorsten M. [Institute of Medical Engineering, University of Luebeck, Luebeck 23562 (Germany); Institute of Anatomy, University of Luebeck, Luebeck 23562 (Germany); Institute of Medical Engineering, University of Luebeck, Luebeck 23562 (Germany)

2012-11-15T23:59:59.000Z

Note: This page contains sample records for the topic "fully depleted prior" 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

A Fully Two-Dimensional, Nonoscillatory Advection Scheme for Momentum and Scalar Transport Equations  

Science Conference Proceedings (OSTI)

The advection scheme developed in this study is a fully two-dimensional and nonoscillatory extension of the one-dimensional Crowley-type mass-conserving schemes. The fully two-dimensional scheme includes new cell-to-cell fluxes directed along the ...

Elías Valur Hólm

1995-02-01T23:59:59.000Z

202

Accuracy Analysis of a Spectral Element Atmospheric Model Using a Fully Implicit Solution Framework  

Science Conference Proceedings (OSTI)

A fully implicit (FI) time integration method has been implemented into a spectral finite-element shallow-water equation model on a sphere, and it is compared to existing fully explicit leapfrog and semi-implicit methods for a suite of test ...

Katherine J. Evans; Mark A. Taylor; John B. Drake

2010-08-01T23:59:59.000Z

203

An efficient preconditioned iterative solution of fully-coupled elastohydrodynamic lubrication problems  

Science Conference Proceedings (OSTI)

This paper presents the fast preconditioned iterative solution to large sparse linear systems arising from the application of Newton and quasi-Newton methods to fully coupled elastohydrodynamic lubrication line and point contact problems. The new blockwise ... Keywords: Elastohydrodynamic lubrication, Finite element method, Fully coupled approach, Linear elasticity, Multigrid, Preconditioned GMRES

Sarfraz Ahmed; Christopher E. Goodyer; Peter K. Jimack

2012-05-01T23:59:59.000Z

204

A study of variable selection using g-prior distribution with ridge parameter  

Science Conference Proceedings (OSTI)

In the Bayesian stochastic search variable selection framework, a common prior distribution for the regression coefficients is the g-prior of Zellner. However there are two standard cases where the associated covariance matrix does not exist and the ... Keywords: Bayesian Lasso, Generalized linear mixed model, Metropolis-within-Gibbs algorithm, Probit mixed regression model, Ridge parameter, Stochastic search variable selection, Zellner prior

M. Baragatti; D. Pommeret

2012-06-01T23:59:59.000Z

205

Depleted-Uranium Weapons the Whys and Wherefores  

E-Print Network (OSTI)

The only military application in which present-day depleted-uranium (DU) alloys out-perform tungsten alloys is long-rod penetration into a main battle-tank's armor. However, this advantage is only on the order of 10% and disappearing when the comparison is made in terms of actual lethality of complete anti-tank systems instead of laboratory-type steel penetration capability. Therefore, new micro- and nano-engineered tungsten alloys may soon out-perform existing DU alloys, enabling the production of tungsten munition which will be better than uranium munition, and whose overall life-cycle cost will be less due to the absence of the problems related to the radioactivity of uranium. The reasons why DU weapons have been introduced and used are analysed from the perspective that their radioactivity must have played an important role in the decision making process. It is found that DU weapons belong to the diffuse category of low-radiological-impact nuclear weapons to which emerging types of low-yield, i.e., fourth...

Gsponer, A

2003-01-01T23:59:59.000Z

206

Kr Ion Irradiation Study of the Depleted-Uranium Alloys  

SciTech Connect

Fuel development for the Reduced Enrichment Research and Test Reactor program is tasked with the development of new low-enriched uranium nuclear fuels that can be employed to replace existing highly enriched uranium fuels currently used in some research reactors throughout the world. For dispersion-type fuels, radiation stability of the fuel/cladding interaction product has a strong impact on fuel performance. Three depleted uranium alloys are cast for the radiation stability studies of the fuel/cladding interaction product using Kr ion irradiation to investigate radiation damage from fission products. SEM analysis indicates the presence of the phases of interest: U(Si, Al)3, (U, Mo)(Si, Al)3, UMo2Al20, U6Mo4Al43, and UAl4. Irradiations of TEM disc samples were conducted with 500 keV Kr ions at 200ºC to ion doses up to 2.5 × 1015 ions/cm2 (~ 10 dpa) with an Kr ion flux of 1012 ions/cm2-sec (~ 4.0 × 10-3 dpa/sec). Microstructural evolution of the phases relevant to fuel-cladding interaction products was investigated using transmission electron microscopy.

J. Gan; D. Keiser; B. Miller; M. Kirk; J. Rest; T. Allen; D. Wachs

2010-12-01T23:59:59.000Z

207

Kr ion irradiation study of the depleted-uranium alloys.  

Science Conference Proceedings (OSTI)

Fuel development for the reduced enrichment research and test reactor (RERTR) program is tasked with the development of new low enrichment uranium nuclear fuels that can be employed to replace existing high enrichment uranium fuels currently used in some research reactors throughout the world. For dispersion type fuels, radiation stability of the fuel-cladding interaction product has a strong impact on fuel performance. Three depleted-uranium alloys are cast for the radiation stability studies of the fuel-cladding interaction product using Kr ion irradiation to investigate radiation damage from fission products. SEM analysis indicates the presence of the phases of interest: U(Al, Si){sub 3}, (U, Mo)(Al, Si){sub 3}, UMo{sub 2}Al{sub 20}, U{sub 6}Mo{sub 4}Al{sub 43} and UAl{sub 4}. Irradiations of TEM disc samples were conducted with 500 keV Kr ions at 200 C to ion doses up to 2.5 x 10{sup 19} ions/m{sup 2} ({approx}10 dpa) with an Kr ion flux of 10{sup 16} ions/m{sup 2}/s ({approx}4.0 x 10{sup -3} dpa/s). Microstructural evolution of the phases relevant to fuel-cladding interaction products was investigated using transmission electron microscopy.

Gan, J.; Keiser, D. D.; Miller, B. D.; Kirk, M. A.; Rest, J.; Allen, T. R.; Wachs, D. M. (Materials Science Division); (INL); (Univ. of Wisconsin)

2010-12-01T23:59:59.000Z

208

Investigation of breached depleted UF sub 6 cylinders  

Science Conference Proceedings (OSTI)

In June 1990, during a three-site inspection of cylinders being used for long-term storage of solid depleted UF{sub 6}, two 14-ton cylinders at Portsmouth, Ohio, were discovered with holes in the barrel section of the cylinders. An investigation team was immediately formed to determine the cause of the failures and their impact on future storage procedures and to recommend corrective actions. Subsequent investigation showed that the failures most probably resulted from mechanical damage that occurred at the time that the cylinders had been placed in the storage yard. In both cylinders evidence pointed to the impact of a lifting lug of an adjacent cylinder near the front stiffening ring, where deflection of cylinder could occur only by tearing the cylinder. The impacts appear to have punctured the cylinders and thereby set up corrosion processes that greatly extended the openings in the wall and obliterated the original crack. Fortunately, the reaction products formed by this process were relatively protective and prevented any large-scale loss of uranium. The main factors that precipitated the failures were inadequate spacing between cylinders and deviations in the orientations of lifting lugs from their intended horizontal position. After reviewing the causes and effects of the failures, the team's principal recommendation for remedial action concerned improved cylinder handling and inspection procedures. Design modifications and supplementary mechanical tests were also recommended to improve the cylinder containment integrity during the stacking operation. 4 refs., 2 figs.

DeVan, J.H.

1991-01-01T23:59:59.000Z

209

EIS-0360: Depleted Uranium Oxide Conversion Product at the Portsmouth, Ohio  

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

60: Depleted Uranium Oxide Conversion Product at the 60: Depleted Uranium Oxide Conversion Product at the Portsmouth, Ohio Site EIS-0360: Depleted Uranium Oxide Conversion Product at the Portsmouth, Ohio Site Summary This site-specific EIS analyzes the construction, operation, maintenance, and decontamination and decommissioning of the proposed depleted uranium hexafluoride (DUF6) conversion facility at three alternative locations within the Portsmouth site; transportation of all cylinders (DUF6, enriched, and empty) currently stored at the East Tennessee Technology Park (ETTP) near Oak Ridge, Tennessee, to Portsmouth; construction of a new cylinder storage yard at Portsmouth (if required) for ETTP cylinders; transportation of depleted uranium conversion products and waste materials to a disposal facility; transportation and sale of the hydrogen fluoride

210

Benefits of the delta K of depletion benchmarks for burnup credit validation  

SciTech Connect

Pressurized Water Reactor (PWR) burnup credit validation is demonstrated using the benchmarks for quantifying fuel reactivity decrements, published as 'Benchmarks for Quantifying Fuel Reactivity Depletion Uncertainty,' EPRI Report 1022909 (August 2011). This demonstration uses the depletion module TRITON available in the SCALE 6.1 code system followed by criticality calculations using KENO-Va. The difference between the predicted depletion reactivity and the benchmark's depletion reactivity is a bias for the criticality calculations. The uncertainty in the benchmarks is the depletion reactivity uncertainty. This depletion bias and uncertainty is used with the bias and uncertainty from fresh UO{sub 2} critical experiments to determine the criticality safety limits on the neutron multiplication factor, k{sub eff}. The analysis shows that SCALE 6.1 with the ENDF/B-VII 238-group cross section library supports the use of a depletion bias of only 0.0015 in delta k if cooling is ignored and 0.0025 if cooling is credited. The uncertainty in the depletion bias is 0.0064. Reliance on the ENDF/B V cross section library produces much larger disagreement with the benchmarks. The analysis covers numerous combinations of depletion and criticality options. In all cases, the historical uncertainty of 5% of the delta k of depletion ('Kopp memo') was shown to be conservative for fuel with more than 30 GWD/MTU burnup. Since this historically assumed burnup uncertainty is not a function of burnup, the Kopp memo's recommended bias and uncertainty may be exceeded at low burnups, but its absolute magnitude is small. (authors)

Lancaster, D. [NuclearConsultants.com, 187 Faith Circle, Boalsburg, PA 16827 (United States); Machiels, A. [Electric Power Research Inst., Inc., 3420 Hillview Avenue, Palo Alto, CA 94304 (United States)

2012-07-01T23:59:59.000Z

211

Radiological Risk Assessment of Capstone Depleted Uranium Aerosols  

SciTech Connect

Assessment of the health risk from exposure to aerosols of depleted uranium (DU) is an important outcome of the Capstone aerosol studies that established exposure ranges to personnel in armored combat vehicles perforated by DU munitions. Although the radiation exposure from DU is low, there is concern that DU deposited in the body may increase cancer rates. Radiation doses to various organs of the body resulting from the inhalation of DU aerosols measured in the Capstone studies were calculated using International Commission on Radiological Protection (ICRP) models. Organs and tissues with the highest calculated committed equivalent 50-yr doses were lung and extrathoracic tissues (nose and nasal passages, pharynx, larynx, mouth and thoracic lymph nodes). Doses to the bone surface and kidney were about 5 to 10% of the doses to the extrathoracic tissues. The methodologies of the ICRP International Steering Committee on Radiation Standards (ISCORS) were used for determining the whole body cancer risk. Organ-specific risks were estimated using ICRP and U.S. Environmental Protection Agency (EPA) methodologies. Risks for crewmembers and first responders were determined for selected scenarios based on the time interval of exposure and for vehicle and armor type. The lung was the organ with the highest cancer mortality risk, accounting for about 97% of the risks summed from all organs. The highest mean lifetime risk for lung cancer for the scenario with the longest exposure time interval (2 h) was 0.42%. This risk is low compared with the natural or background risk of 7.35%. These risks can be significantly reduced by using an existing ventilation system (if operable) and by reducing personnel time in the vehicle immediately after perforation.

Hahn, Fletcher; Roszell, Laurie E.; Daxon, Eric G.; Guilmette, Ray A.; Parkhurst, MaryAnn

2009-02-26T23:59:59.000Z

212

Capstone Depleted Uranium Aerosol Biokinetics, Concentrations, and Doses  

SciTech Connect

One of the principal goals of the Capstone Depleted Uranium (DU) Aerosol Study was to quantify and characterize DU aerosols generated inside armored vehicles by perforation with a DU penetrator. This study consequently produced a database in which the DU aerosol source terms were specified both physically and chemically for a variety of penetrator-impact geometries and conditions. These source terms were used to calculate radiation doses and uranium concentrations for various scenarios as part of the Capstone DU Human Health Risk Assessment (HHRA). This paper describes the scenario-related biokinetics of uranium, and summarizes intakes, chemical concentrations to the organs, and E(50) and HT(50) for organs and tissues based on exposure scenarios for personnel in vehicles at the time of perforation as well as for first responders. For a given exposure scenario (duration time and breathing rates), the range of DU intakes among the target vehicles and shots was not large, about a factor of 10, with the lowest being from a ventilated operational Abrams tank and the highest being for an unventilated Abrams with DU penetrator perforating DU armor. The ranges of committed effective doses were more scenario-dependent than were intakes. For example, the largest range, a factor of 20, was shown for scenario A, a 1-min exposure, whereas, the range was only a factor of two for the first-responder scenario (E). In general, the committed effective doses were found to be in the tens of mSv. The risks ascribed to these doses are discussed separately.

Guilmette, Raymond A.; Miller, Guthrie; Parkhurst, MaryAnn

2009-02-26T23:59:59.000Z

213

Characterization of Thermal Properties of Depleted Uranium Metal Microspheres  

E-Print Network (OSTI)

Nuclear fuel comes in many forms; oxide fuel is the most commonly used in current reactor systems while metal fuel is a promising fuel type for future reactors due to neutronic performance and increased thermal conductivity. As a key heat transfer parameter, thermal conductivity describes the heat transport properties of a material based upon the density, specific heat, and thermal diffusivity. A material’s ability to transport thermal energy through its structure is a measurable property known as thermal diffusivity; the units for thermal diffusivity are given in area per unit time (e.g., m2/s). Current measurement methods for thermal diffusivity include LASER (or light) Flash Analysis and the hot-wire method. This study examines an approach that combines these previous two methods to characterize the diffusivity of a packed bed of microspheres of depleted uranium (DU) metal, which have a nominal diameter of 250 micrometers. The new apparatus is designated as the Crucible Heater Test Assembly (CHTA), and it induces a radial transient across a packed sample of microspheres then monitors the temperature profile using an array of thermocouples located at different distances from the source of the thermal transient. From the thermocouple data and an accurate time log, the thermal diffusivity of the sample may be calculated. Results indicate that DU microspheres have very low thermal conductivity, relative to solid uranium metal, and rapidly form an oxidation layer. At 500°C, the thermal conductivity of the DU microspheres was 0.431 ± 13% W/m-K compared to approximately 32 W/m-K for solid uranium metal. Characterization of the developed apparatus revealed a method that may be useful for measuring the thermal diffusivity of powders and liquids.

Humrickhouse, Carissa Joy

2012-05-01T23:59:59.000Z

214

Fully Lagrangian Floats in Labrador Sea Deep Convection: Comparison of Numerical and Experimental Results  

Science Conference Proceedings (OSTI)

Measurements of deep convection from fully Lagrangian floats deployed in the Labrador Sea during February and March 1997 are compared with results from model drifters embedded in a large eddy simulation (LES) of the rapidly deepening mixed layer. ...

Ramsey R. Harcourt; Elizabeth L. Steffen; Roland W. Garwood; Eric A. D'Asaro

2002-02-01T23:59:59.000Z

215

A Low Power, Low Voltage, Fully Differential CMOS Variable Gain Amplifier.  

E-Print Network (OSTI)

?? This research presents a low voltage (0.8 V) fully differential CMOS variable gain amplifier. SPECTRE simulations on the designed amplifier show a -17 dB… (more)

Siddiqui, Muhammad Yousuf

2011-01-01T23:59:59.000Z

216

Loads Analysis of a Floating Offshore Wind Turbine Using Fully Coupled Simulation: Preprint  

SciTech Connect

This paper presents the use of fully coupled aero-hydro-servo-elastic simulation tools to perform a loads analysis of a 5-MW offshore wind turbine supported by a barge with moorings, one of many promising floating platform concepts.

Jonkman, J. M.; Buhl, M. L., Jr.

2007-06-01T23:59:59.000Z

217

Package of Homojunction of Fully Conjugated Heterocyclic Aromatic Rigid-rod Polymer Light Emitting Diodes.  

E-Print Network (OSTI)

??The focus of this study is mono-layer polymer light emitting diode (PLED). The emitting layer is poly-p-phenylenebenzobisoxazole (PBO). PBO is a fully conjugated heterocyclic aromatic… (more)

Liao, Hung-chi

2004-01-01T23:59:59.000Z

218

A fully microfabricated two-dimensional electrospray array with applications to space propulsion  

E-Print Network (OSTI)

This thesis presents the design, fabrication and testing of a fully-integrated planar electrospray thruster array, which could lead to more efficient and precise thrusters for space propulsion applications. The same ...

Gassend, Blaise L. P. (Blaise Laurent Patrick), 1978-

2007-01-01T23:59:59.000Z

219

A Fully Conserved Minimal Adjustment Scheme with (T, S) Coherency for Stabilization of Hydrographic Profiles  

Science Conference Proceedings (OSTI)

A new, fully conserved minimal adjustment scheme with temperature and salinity (T, S) coherency is presented for eliminating false static instability generated from analyzing and assimilating stable ocean (T, S) profiles data, that is, from ...

Xidong Wang; Peter C. Chu; Guijun Han; Wei Li; Xuefeng Zhang; Dong Li

2012-12-01T23:59:59.000Z

220

Fully automatic calibration of LIDAR and video streams from a vehicle  

E-Print Network (OSTI)

This work describes a fully automatic technique to calibrate a geometric mapping between lidar and video feeds on a mobile ground-based platform. This data association is a crucial first step for any multi-modal scene ...

Bileschi, Stanley M.

Note: This page contains sample records for the topic "fully depleted prior" 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

,"U.S. Working Natural Gas Underground Storage Depleted Fields Capacity (MMcf)"  

U.S. Energy Information Administration (EIA) Indexed Site

Depleted Fields Capacity (MMcf)" Depleted Fields Capacity (MMcf)" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description","# Of Series","Frequency","Latest Data for" ,"Data 1","U.S. Working Natural Gas Underground Storage Depleted Fields Capacity (MMcf)",1,"Annual",2012 ,"Release Date:","12/12/2013" ,"Next Release Date:","1/7/2014" ,"Excel File Name:","nga_epg0_sacwd_nus_mmcfa.xls" ,"Available from Web Page:","http://tonto.eia.gov/dnav/ng/hist/nga_epg0_sacwd_nus_mmcfa.htm" ,"Source:","Energy Information Administration" ,"For Help, Contact:","infoctr@eia.doe.gov"

222

Dupoly process for treatment of depleted uranium and production of beneficial end products  

DOE Patents (OSTI)

The present invention provides a process of encapsulating depleted uranium by forming a homogenous mixture of depleted uranium and molten virgin or recycled thermoplastic polymer into desired shapes. Separate streams of depleted uranium and virgin or recycled thermoplastic polymer are simultaneously subjected to heating and mixing conditions. The heating and mixing conditions are provided by a thermokinetic mixer, continuous mixer or an extruder and preferably by a thermokinetic mixer or continuous mixer followed by an extruder. The resulting DUPoly shapes can be molded into radiation shielding material or can be used as counter weights for use in airplanes, helicopters, ships, missiles, armor or projectiles.

Kalb, Paul D. (Wading River, NY); Adams, Jay W. (Stony Brook, NY); Lageraaen, Paul R. (Seaford, NY); Cooley, Carl R. (Gaithersburg, MD)

2000-02-29T23:59:59.000Z

223

Proposal concerning the participation of CERN in the procurement of depleted-uranium sheets for the UA1 calorimeter upgrading  

E-Print Network (OSTI)

Proposal concerning the participation of CERN in the procurement of depleted-uranium sheets for the UA1 calorimeter upgrading

1985-01-01T23:59:59.000Z

224

Depleted Uraniuim Dioxide as a Spent-Nuclear-Fuel-Waste Package...  

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

15 DEPLETED URANIUM DIOXIDE AS A SPENT-NUCLEAR-FUEL WASTE-PACKAGE PARTICULATE FILL: FILL BEHAVIOR Charles W. Forsberg Oak Ridge National Laboratory * P.O. Box 2008 Oak Ridge,...

225

Separating the Dynamical Effects of Climate Change and Ozone Depletion. Part II: Southern Hemisphere Troposphere  

Science Conference Proceedings (OSTI)

The separate effects of ozone depleting substances (ODSs) and greenhouse gases (GHGs) on forcing circulation changes in the Southern Hemisphere extratropical troposphere are investigated using a version of the Canadian Middle Atmosphere Model (...

Charles McLandress; Theodore G. Shepherd; John F. Scinocca; David A. Plummer; Michael Sigmond; Andreas I. Jonsson; M. Catherine Reader

2011-03-01T23:59:59.000Z

226

Sequestration of CO2 in a Depleted Oil Reservoir: An Overview  

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

in a Depleted Oil Reservoir: An Overview H. Westrich (hrwestr@sandia.gov; 505-844-9092) J. Lorenz (jcloren@sandia.gov; 505-3695) S. Cooper (spcoope@sandia.gov; 505-844-3977) C....

227

FAQ 15-What are the dimensions of a depleted uranium hexafluoride cylinder?  

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

are the dimensions of a depleted uranium hexafluoride cylinder? are the dimensions of a depleted uranium hexafluoride cylinder? What are the dimensions of a depleted uranium hexafluoride cylinder? Several different cylinder types are in use, although the vast majority of cylinders are designed to contain 14-tons (12-metric tons) of depleted UF6. The 14-ton-capacity cylinders are 12 ft (3.7 m) long by 4 ft (1.2 m) in diameter, with most having an initial wall thickness of 5/16 in. (0.79 cm) of steel. The cylinders have external stiffening rings that provide support. Lifting lugs for handling are attached to the stiffening rings. A small percentage of the cylinders have skirted ends (extensions of the cylinder walls past the rounded ends of the cylinder). Each cylinder has a single valve for filling and emptying located on one end at the 12 o'clock position. Similar, but slightly smaller, cylinders designed to contain 10 tons (9 metric tons) of depleted UF6 are also in use. Cylinders are manufactured in accordance with an American National Standards Institute standard (ANSI N14.1, American National Standard for Nuclear Materials - Uranium Hexafluoride - Packaging for Transport) as specified in 49 CFR 173.420, the federal regulations governing transport of depleted UF6.

228

Effect of twinning on texture evolution of depleted uranium using a viscoplastic self-consistent model  

Science Conference Proceedings (OSTI)

Ductility and fracture toughness is a major stumbling block in using depleted uranium as a structural material. The ability to correctly model deformation of uranium can be used to create process path methods to improve its structural design ability. The textural evolution of depleted uranium was simulated using a visco-plastic self consistent model and analyzed by comparing pole figures of the simulations and experimental samples. Depleted uranium has the same structure as alpha uranium, which is an orthorhombic phase of uranium. Both deformation slip and twin systems were compared. The VPSC model was chosen to simulate this material because the model encompasses both low-symmetry materials as well as twinning in materials. This is of particular interest since depleted uranium has a high propensity for twinning, which dominates deformation and texture evolution. Simulated results were compared to experimental results to measure the validity of the model. One specific twin system, the {l_brace}176{r_brace}[512] twin, was of specific notice. The VPSC model was used to simulate the influence of this twin on depleted uranium and was compared with a mechanically shocked depleted uranium sample. Under high strain rate shock deformation conditions, the {l_brace}176{r_brace}[512] twin system appears to be a dominant deformation system. By simulating a compression process using the VPSC model with the {l_brace}176{r_brace}[512] twin as the dominant deformation mode, a favorable comparison could be made between the experimental and simulated textures. (authors)

Ho, J.; Garmestani, H. [Georgia Inst. of Technology, Atlanta, GA 30332-0245 (United States); Burrell, R.; Belvin, A. [Y-12 National Security Complex, Oak Ridge, TN (United States); Li, D. [Fundamental and Computational Sciences Directorate, Pacific Northwest National Laboratory, Richland, WA 99352 (United States); McDowell, D. [Woodruff School of Mechanical Engineering, Atlanta, GA 30332-0245 (United States); Rollett, A. [Dept. of Materials Science and Engineering, Carnegie Mellon Univ., Pittsburgh, PA 15213 (United States)

2012-07-01T23:59:59.000Z

229

Fully Covariant Van Dam-Veltman-Zakharov Discontinuity, and Absence Thereof  

E-Print Network (OSTI)

In both old and recent literature, it has been argued that the celebrated van Dam-Veltman-Zakharov (vDVZ) discontinuity of massive gravity is an artifact due to linearization of the true equations of motion. In this letter, we investigate that claim. First, we exhibit an explicit -albeit somewhat arbitrary- fully covariant set of equations of motion that, upon linearization, reduce to the standard Pauli-Fierz equations. We show that the vDVZ discontinuity still persists in that non-linear, covariant theory. Then, we restrict our attention to a particular system that consistently incorporates massive gravity: the Dvali-Gabadadze-Porrati (DGP) model. DGP is fully covariant and does not share the arbitrariness and imperfections of our previous covariantization, and its linearization exhibits a vDVZ discontinuity. Nevertheless, we explicitly show that the discontinuity does disappear in the fully covariant theory, and we explain the reason for this phenomenon.

M. Porrati

2002-03-01T23:59:59.000Z

230

Performance of Trasuranic-Loaded Fully Ceramic Micro-Encapsulated Fuel in LWRs Interim Report, Including Void Reactivity Evaluation  

Science Conference Proceedings (OSTI)

The current focus of the Deep Burn Project is on once-through burning of transuranice (TRU) in light water reactors (LWRs). The fuel form is called Fully-Ceramic Micro-encapsulated (FCM) fuel, a concept that borrows the tri-isotropic (TRISO) fuel particle design from high-temperature reactor technology. In the Deep Burn LWR (DB-LWR) concept, these fuel particles would be pressed into compacts using SiC matrix material and loaded into fuel pins for use in conventional LWRs. The TRU loading comes from the spent fuel of a conventional LWR after 5 years of cooling. Unit cell calculations have been performed using the DRAGON-4 code in order assess the physics attributes of TRU-only FCM fuel in an LWR lattice. Depletion calculations assuming an infinite lattice condition were performed with calculations of various reactivity coefficients performed at each step. Unit cells containing typical UO2 and MOX fuel were analyzed in the same way to provide a baseline against which to compare the TRU-only FCM fuel. Loading of TRU-only FCM fuel into a pin without significant quantities of uranium challenges the design from the standpoint of several key reactivity parameters, particularly void reactivity, and to some degree, the Doppler coefficient. These unit cells, while providing an indication of how a whole core of similar fuel would behave, also provide information of how individual pins of TRU-only FCM fuel would influence the reactivity behavior of a heterogeneous assembly. If these FCM fuel pins are included in a heterogeneous assembly with LEU fuel pins, the overall reactivity behavior would be dominated by the uranium pins while attractive TRU destruction performance of the TRU-only FCM fuel pins may be preserved. A configuration such as this would be similar to CONFU assemblies analyzed in previous studies. Analogous to the plutonium content limits imposed on MOX fuel, some amount of TRU-only FCM pins in an otherwise-uranium fuel assembly may give acceptable reactivity performance. Assembly calculations will be performed in future work to explore the design options for heterogeneous assemblies of this type and their impact on reactivity coefficients.

Michael A. Pope; Brian Boer; Gilles Youinou; Abderrafi M. Ougouag

2011-03-01T23:59:59.000Z

231

T-697: Google Chrome Prior to 13.0.782.107 Multiple Security  

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

97: Google Chrome Prior to 13.0.782.107 Multiple Security 97: Google Chrome Prior to 13.0.782.107 Multiple Security Vulnerabilities T-697: Google Chrome Prior to 13.0.782.107 Multiple Security Vulnerabilities August 19, 2011 - 3:02pm Addthis PROBLEM: Attackers can exploit these issues to execute arbitrary code in the context of the browser or cause denial-of-service conditions; other attacks may also be possible. PLATFORM: Cross Platform: Google Chrome Prior to 13.0.782.107: Versions and Vulnerabilities (Details) ABSTRACT: Attackers can exploit these issues to execute arbitrary code in the context of the browser or cause denial-of-service conditions; other attacks may also be possible. The Chromium Projects Security Overview. reference LINKS: SecurityFocus: Google Chrome Prior to 13.0.782.107 Multiple Security Vulnerabilities

232

Copyright 2008 No part of this presentation may be reproduced in any form without prior authorization.  

E-Print Network (OSTI)

demon- stration project for Xcel Energy, convert- ing a Ford Escape Hybrid PHEV vehicle to put power. Utilizing fully automated fast processing, the new technology will be capable of produc- ing one solar cell

Amin, S. Massoud

233

Prior-free Mechanisms The big challenge that separates mechanism design from (non-game-theoretic) optimization  

E-Print Network (OSTI)

Chapter 6 Prior-free Mechanisms The big challenge that separates mechanism design from (non and the designer suggests that there must be a completely prior-free theory of mechanism design. Intuitively, the class of good prior-free mechanisms should be smaller than the class of good prior

Fiat, Amos

234

Fully automated smart wireless frost prediction and protection system using a fuzzy logic controller  

Science Conference Proceedings (OSTI)

A smart fuzzy logic controller system is presented to protect the crops from frost damage that occurs every year. The system is a fully automated system to predict the frost and to protect the crops using wireless sensor network technology. The sensors ...

Shadi A. Alboon; Amin T. Alqudah; Hussein R. Al-Zoubi; Abedalgany A. Athamneh

2012-09-01T23:59:59.000Z

235

Fully complex-valued radial basis function networks: Orthogonal least squares regression and classification  

Science Conference Proceedings (OSTI)

We consider a fully complex-valued radial basis function (RBF) network for regression and classification applications. For regression problems, the locally regularised orthogonal least squares (LROLS) algorithm aided with the D-optimality experimental ... Keywords: Classification, Complex-valued radial basis function network, D-optimality experimental design, Fisher ratio of class separability measure, Orthogonal least squares algorithm, Regression

S. Chen; X. Hong; C. J. Harris; L. Hanzo

2008-10-01T23:59:59.000Z

236

NTU Carbon Management Statement 2010 Nottingham Trent University fully supports government and HEFCE climate  

E-Print Network (OSTI)

NTU Carbon Management Statement 2010 Nottingham Trent University fully supports government the following absolute carbon reduction target aligned to higher education sector target: · At least a 48% reduction in scope 1 and 2 carbon emissions from 2005/6 to 2020/21 NTU is currently completing actions from

Evans, Paul

237

Propagation of Wind Energy into the Deep Ocean through a Fully Turbulent Mesoscale Eddy Field  

Science Conference Proceedings (OSTI)

The authors analyze the 3D propagation of wind-forced near-inertial motions in a fully turbulent mesoscale eddy field with a primitive equation numerical model. Although the wind stress is uniform, the near-inertial motion field quickly becomes ...

Eric Danioux; Patrice Klein; Pascal Rivière

2008-10-01T23:59:59.000Z

238

Development of new Consolidity Theory for systems' analysis and design in fully fuzzy environment  

Science Conference Proceedings (OSTI)

This paper establishes the foundation of new systems' Consolidity Theory using the Arithmetic Fuzzy Logic-Based Representation approach for investigating the internal behavior of systems operating in fully fuzzy environment. Consolidated systems are ... Keywords: Advanced fuzzy control systems, Arithmetic Fuzzy Logic-Based Representation, Fuzzy dynamic systems, Fuzzy econometric models, Fuzzy smart grids, Fuzzy theory, Normalized fuzzy matrices, Systems' Consolidity Theory

Hassen Taher Dorrah; Walaa Ibrahim Gabr

2012-01-01T23:59:59.000Z

239

Fully monolithic cellular buck converter design for 3-D power delivery  

E-Print Network (OSTI)

A fully monolithic interleaved buck dc-dc point-of-load (PoL) converter has been designed and fabricated in a 0.18-mm SiGe BiCMOS process. Target application of the design is 3-D power delivery for future microprocessors, ...

Sun, Jian

240

Can Fully Accounting for Clouds in Data Assimilation Improve Short-Term Forecasts by Global Models?  

Science Conference Proceedings (OSTI)

This paper explores the degree to which short-term forecasts with global models might be improved if clouds were fully included in a data assimilation system, so that observations of clouds affected all parts of the model state and cloud ...

Robert Pincus; Robert J. Patrick Hofmann; Jeffrey L. Anderson; Kevin Raeder; Nancy Collins; Jeffrey S. Whitaker

2011-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "fully depleted prior" 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

A fully-integrated 5 Gbit/s CMOS clock and data recovery circuit  

Science Conference Proceedings (OSTI)

A fully-integrated 5 Gb/s PLL-based clock and data recovery circuit based on a linear half-rate phase detector (PD) architecture is presented. Data retiming performed by the linear PD provides practically no systematic offset for the operating frequency ... Keywords: CMOS analog integrated circuits, Clock data recovery, Half-rate CDR, Linear PD, PLL

Tan Kok-Siang; Mohd-Shahiman Sulaiman; Mamun Reaz; Chuah Hean-Teik; Manoj Sachdev

2007-05-01T23:59:59.000Z

242

Prior Knowledge  

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

working on other Web-based projects that one might use to develop this understanding. Project Contact: Tom Jordan Web Maintainer: qnet-webmaster@fnal.gov Last Update: 18 December...

243

FAQ 37-What are the potential health risks from transportation of depleted  

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

depleted uranium metal or oxide? depleted uranium metal or oxide? What are the potential health risks from transportation of depleted uranium metal or oxide? In the PEIS, risks associated with transportation of depleted uranium oxide and metal were estimated for transport by either rail or truck. Normal transport of oxide or metal would result in low-level external exposure to radiation for persons in the vicinity of a shipment. Based on estimates in the PEIS, the levels of exposure would result in negligible increased cancer risks. Risks from material released in an accident were also estimated. For a hypothetical railcar accident involving powder U3O8 that was assumed to occur in a highly-populated urban area under stable (nighttime) weather conditions, it was estimated that up to 20 people might experience irreversible adverse effects from chemical toxicity, with no fatalities expected. Approximately 2 potential latent cancer fatalities from radiological hazards are estimated for an accident under the same conditions. The probability of such an accident occurring is very low. The consequences from a truck accident would be lower, because trucks have a smaller shipment capacity. The consequences of transportation accidents involving depleted uranium metal would be much smaller than those involving uranium oxide because uranium metal would be in the form of solid blocks and would not be easily dispersed in an accident.

244

Disclosing Prior Art to the U.S. Patent and Trademark Office  

Science Conference Proceedings (OSTI)

... art in the patent application as filed, as this provides an initial opportunity to place the prior art in context in the evolutionary process that led to the invention.

245

On a euro basis, Brent crude oil spot price surpasses prior ...  

U.S. Energy Information Administration (EIA)

On a euro basis, the spot price for Brent crude oil, a global benchmark, has surpassed its prior record high and set a new record high of 96.53 euros per barrel on ...

246

Duty to Disclose Prior Art to the United States Patent and Trademark ...  

Science Conference Proceedings (OSTI)

Failure of a person who is involved in the preparation or prosecution of a United States patent application to disclose material prior art can result in the patent not  ...

247

Underwater acoustic signal separation based on prior estimation of the channel impulse response  

Science Conference Proceedings (OSTI)

An underwater acoustic signals separation method based on prior information about the channel impulse response (IR) is presented. Using a sound speed profile measured in a real world environment, the IR of the ocean is estimated with normal mode theory ...

S. Bonnifay; K. Yao; C. Jutten

2000-06-01T23:59:59.000Z

248

HIGH-DENSITY CONCRETE WITH CERAMIC AGGREGATE BASED ON DEPLETED URANIUM DIOXIDE  

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

DENSITY CONCRETE WITH CERAMIC AGGREGATE BASED ON DEPLETED URANIUM DENSITY CONCRETE WITH CERAMIC AGGREGATE BASED ON DEPLETED URANIUM DIOXIDE S.G. Ermichev, V.I. Shapovalov, N.V.Sviridov (RFNC-VNIIEF, Sarov, Russia) V.K. Orlov, V.M. Sergeev, A. G. Semyenov, A.M. Visik, A.A. Maslov, A. V. Demin, D.D. Petrov, V.V. Noskov, V. I. Sorokin, O. I. Uferov (VNIINM, Moscow, Russia) L. Dole (ORNL, Oak Ridge, USA) Abstract - Russia is researching the production and testing of concretes with ceramic aggregate based on depleted uranium dioxide (UO 2 ). These DU concretes are to be used as structural and radiation-shielded material for casks for A-plant spent nuclear fuel transportation and storage. This paper presents the results of studies aimed at selection of ceramics and concrete composition, justification of their production technology, investigation of mechanical properties, and chemical stability.

249

,"U.S. Natural Gas Number of Underground Storage Depleted Fields Capacity (Count)"  

U.S. Energy Information Administration (EIA) Indexed Site

Depleted Fields Capacity (Count)" Depleted Fields Capacity (Count)" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description","# Of Series","Frequency","Latest Data for" ,"Data 1","U.S. Natural Gas Number of Underground Storage Depleted Fields Capacity (Count)",1,"Annual",2012 ,"Release Date:","12/12/2013" ,"Next Release Date:","1/7/2014" ,"Excel File Name:","na1391_nus_8a.xls" ,"Available from Web Page:","http://tonto.eia.gov/dnav/ng/hist/na1391_nus_8a.htm" ,"Source:","Energy Information Administration" ,"For Help, Contact:","infoctr@eia.doe.gov" ,,"(202) 586-8800",,,"12/12/2013 5:43:06 PM"

250

,"U.S. Natural Gas Underground Storage Depleted Fields Capacity (MMcf)"  

U.S. Energy Information Administration (EIA) Indexed Site

Depleted Fields Capacity (MMcf)" Depleted Fields Capacity (MMcf)" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description","# Of Series","Frequency","Latest Data for" ,"Data 1","U.S. Natural Gas Underground Storage Depleted Fields Capacity (MMcf)",1,"Annual",2012 ,"Release Date:","12/12/2013" ,"Next Release Date:","1/7/2014" ,"Excel File Name:","na1391_nus_2a.xls" ,"Available from Web Page:","http://tonto.eia.gov/dnav/ng/hist/na1391_nus_2a.htm" ,"Source:","Energy Information Administration" ,"For Help, Contact:","infoctr@eia.doe.gov" ,,"(202) 586-8800",,,"12/12/2013 5:43:05 PM"

251

DANDE: a linked code system for core neutronics/depletion analysis  

SciTech Connect

This report describes DANDE - a modular neutronics, depletion code system for reactor analysis. It consists of nuclear data processing, core physics, and fuel depletion modules, and allows one to use diffusion and transport methods interchangeably in core neutronics calculations. This latter capability is especially important in the design of small modular cores. Additional unique features include the capability of updating the nuclear data file during a calculation; a detailed treatment of depletion, burnable poisons as well as fuel; and the ability to make geometric changes such as control rod repositioning and fuel relocation in the course of a calculation. The detailed treatment of reactor fuel burnup, fission-product creation and decay, as well as inventories of higher-order actinides is a necessity when predicting the behavior of reactor fuel under increased burn conditions. The operation of the code system is made clear in this report by following a sample problem.

LaBauve, R.J.; England, T.R.; George, D.C.; MacFarlane, R.E.; Wilson, W.B.

1985-06-01T23:59:59.000Z

252

Transient effects and pump depletion in stimulated Raman scattering. [Para-hydrogen  

DOE Green Energy (OSTI)

Stimulated rotational Raman scattering in a 300-K multipass cell filled with para-H/sub 2/ with a single-mode CO/sub 2/-pumped laser is studied using a frequency-narrowed optical parametric oscillator (OPO) as a probe laser at the Stokes frequency for the S/sub 0/(O) transition. Amplification and pump depletion are examined as a function of incident pump energy. The pump depletion shows clear evidence of transient behavior. A theoretical treatment of transient stimulated Raman scattering, including effects of both pump depletion and medium saturation is presented. In a first approximation, diffraction effects are neglected, and only plane-wave interactions are considered. The theoretical results are compared to the experimental pulse shapes.

Carlsten, J.L.; Wenzel, R.G.; Druehl, K.

1983-01-01T23:59:59.000Z

253

Summary of the engineering analysis report for the long-term management of depleted uranium hexafluoride  

SciTech Connect

The Department of Energy (DOE) is reviewing ideas for the long-term management and use of its depleted uranium hexafluoride. DOE owns about 560,000 metric tons (over a billion pounds) of depleted uranium hexafluoride. This material is contained in steel cylinders located in storage yards near Paducah, Kentucky; Portsmouth, Ohio; and at the East Tennessee Technology Park (formerly the K-25 Site) in Oak Ridge, Tennessee. On November 10, 1994, DOE announced its new Depleted Uranium Hexafluoride Management Program by issuing a Request for Recommendations and an Advance Notice of Intent in the Federal Register (59 FR 56324 and 56325). The first part of this program consists of engineering, costs and environmental impact studies. Part one will conclude with the selection of a long-term management plan or strategy. Part two will carry out the selected strategy.

Dubrin, J.W., Rahm-Crites, L.

1997-09-01T23:59:59.000Z

254

Structure and Depletion at Fluoro- and Hydro-carbon/Water Liquid/Liquid Interfaces  

E-Print Network (OSTI)

The results of x-ray reflectivity studies of two oil/water (liquid/liquid) interfaces are inconsistent with recent predictions of the presence of a vapor-like depletion region at hydrophobic/aqueous interfaces. One of the oils, perfluorohexane, is a fluorocarbon whose super-hydrophobic interface with water provides a stringent test for the presence of a depletion layer. The other oil, heptane, is a hydrocarbon and, therefore, is more relevant to the study of biomolecular hydrophobicity. These results are consistent with the sub-angstrom proximity of water to soft hydrophobic materials.

Kaoru Kashimoto; Jaesung Yoon; Binyang Hou; Chiu-hao Chen; Binhua Lin; Makoto Aratono; Takanori Takiue; Mark L. Schlossman

2008-07-18T23:59:59.000Z

255

Development of a Reliable Fuel Depletion Methodology for the HTR-10 Spent Fuel Analysis  

Science Conference Proceedings (OSTI)

A technical working group formed in 2007 between NNSA and CAEA to develop a reliable fuel depletion method for HTR-10 based on MCNPX and to analyze the isotopic inventory and radiation source terms of the HTR-10 spent fuel. Conclusions of this presentation are: (1) Established a fuel depletion methodology and demonstrated its safeguards application; (2) Proliferation resistant at high discharge burnup ({approx}80 GWD/MtHM) - Unfavorable isotopics, high number of pebbles needed, harder to reprocess pebbles; (3) SF should remain under safeguards comparable to that of LWR; and (4) Diversion scenarios not considered, but can be performed.

Chung, Kiwhan [Los Alamos National Laboratory; Beddingfield, David H. [Los Alamos National Laboratory; Geist, William H. [Los Alamos National Laboratory; Lee, Sang-Yoon [unaffiliated

2012-07-03T23:59:59.000Z

256

Stability of a fully magnetized ferromagnetic state in repulsively interacting ultracold Fermi gases  

SciTech Connect

We construct a variational wave function to study whether a fully polarized Fermi sea of ultracold atoms is energetically stable against a single spin flip. Our variational wave function contains short-range correlations at least to the same level as Gutzwiller's projected wave function. For the Hubbard lattice model and the continuum model with pure repulsive interaction, we show that a fully polarized Fermi sea is generally unstable even for infinite repulsive strength. By contrast, for a resonance model, the ferromagnetic state is possible if the s-wave scattering length is positive and sufficiently large and the system is prepared to be orthogonal to the molecular bound state. However, we cannot rule out the possibility that more exotic correlations can destabilize the ferromagnetic state.

Cui Xiaoling [Beijing National Laboratory for Condensed Matter Physics and Institute for Physics, Chinese Academy of Science, Beijing, 100190 (China); Zhai Hui [Institute for Advanced Study, Tsinghua University, Beijing, 100084 (China)

2010-04-15T23:59:59.000Z

257

A fully automated data reduction pipeline for the FRODOSpec integral field spectrograph  

E-Print Network (OSTI)

A fully autonomous data reduction pipeline has been developed for FRODOSpec, an optical fibre-fed integral field spectrograph currently in use at the Liverpool Telescope. This paper details the process required for the reduction of data taken using an integral field spectrograph and presents an overview of the computational methods implemented to create the pipeline. Analysis of errors and possible future enhancements are also discussed.

Barnsley, R M; Steele, I A

2011-01-01T23:59:59.000Z

258

Findings from the 2004 Fully Automated Demand Response Tests in Large  

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

the 2004 Fully Automated Demand Response Tests in Large the 2004 Fully Automated Demand Response Tests in Large Facilities Title Findings from the 2004 Fully Automated Demand Response Tests in Large Facilities Publication Type Report LBNL Report Number LBNL-58178 Year of Publication 2005 Authors Piette, Mary Ann, David S. Watson, Naoya Motegi, and Norman Bourassa Date Published 10/18/2005 Keywords market sectors, technologies Abstract This report describes the results of the second season of research to develop and evaluate the performance of new Automated Demand Response (Auto-DR) hardware and software technology in large facilities. Demand Response (DR) is a set of time dependant activities that reduce or shift electricity use to improve electric grid reliability, manage electricity costs, and provide systems that encourage load shifting or shedding during times when the electric grid is near its capacity or electric prices are high. Demand Response is a subset of demand side management, which also includes energy efficiency and conservation. The overall goal of this research project was to support increased penetration of DR in large facilities through the use of automation and better understanding of DR technologies and strategies in large facilities. To achieve this goal, a set of field tests were designed and conducted. These tests examined the performance of Auto-DR systems that covered a diverse set of building systems, ownership and management structures, climate zones, weather patterns, and control and communication configurations.

259

Batteries on the battlefield developing a methodology to estimate the fully burdened cost of batteries in the Department of Defense .  

E-Print Network (OSTI)

??L), have developed methodologies to calculate the fully burdened cost of fuel as delivered energy in defense systems. Whereas these previous studies did not consider… (more)

Hughley, Anthony E.

2010-01-01T23:59:59.000Z

260

Verification of a Depletion Method in SCALE for the Advanced High Temperature Reactor  

SciTech Connect

This study describes a new method utilizing the Dancoff factor to model a non-standard TRISO fuel form characteristic of the AHTR reactor design concept for depletion analysis using the TRITON sequence of SCALE and the validation of this method by code-to-code comparisons. The fuel used in AHTR has the TRISO particles concentrated along the edges of a slab fuel element. This particular geometry prevented the use of a standard DOUBLEHET treatment, previously developed in SCALE to handle NGNP-designed fuel. The new method permits fuel depletion on complicated geometries that traditionally can be handled only by continuous energy based depletion code systems. The method was initially tested on a fuel design typical of the NGNP, where the DOUBLEHET treatment is available. A more comprehensive study was performed using the VESTA code that uses the continuous energy MCNP5 code as a transport solver and ORIGEN2.2 code for depletion calculations. Comparisons of the results indicate good agreement of whole core characteristics, such as the multiplication factor, and the isotopics, including their spatial distribution. Key isotopes analyzed included 235U, 239Pu, 240Pu and 241Pu. The results from this study indicate that the Dancoff factor method can generate estimates of core characteristics with reasonable precision for scoping studies of configurations where the DOUBLEHET treatment is unavailable.

KELLY, RYAN [Texas A& M University; Ilas, Dan [ORNL

2012-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "fully depleted prior" 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

Peak production in an oil depletion model with triangular field profiles  

E-Print Network (OSTI)

Peak production in an oil depletion model with triangular field profiles Dudley Stark School;1 Introduction M. King Hubbert [5] used curve fitting to predict that the peak of oil produc- tion in the U.S.A. would occur between 1965 and 1970. Oil production in the U.S.A. actually peaked in 1970 and has been

Stark, Dudley

262

Decadal Changes of Wind Stress over the Southern Ocean Associated with Antarctic Ozone Depletion  

Science Conference Proceedings (OSTI)

Using 40-yr ECMWF Re-Analysis (ERA-40) data and in situ observations, the positive trend of Southern Ocean surface wind stress during two recent decades is detected, and its close linkage with spring Antarctic ozone depletion is established. The ...

Xiao-Yi Yang; Rui Xin Huang; Dong Xiao Wang

2007-07-01T23:59:59.000Z

263

Depleted uranium oxides as spent-nuclear-fuel waste-package fill materials  

SciTech Connect

Depleted uranium dioxide fill inside the waste package creates the potential for significant improvements in package performance based on uranium geochemistry, reduces the potential for criticality in a repository, and consumes DU inventory. As a new concept, significant uncertainties exist: fill properties, impacts on package design, post- closure performance.

Forsberg, C.W.

1997-07-07T23:59:59.000Z

264

The use of geometric prior information in Bayesian tomographic image reconstruction: A preliminary report  

Science Conference Proceedings (OSTI)

In this paper we examine the possibility of using pure geometrical information from a prior image to assist in the reconstruction of tomographic data sets with lower number of counts. The situation can arise in dynamic studies, for example, in which the sum image from a number of time frames is available, defining desired regions-of-interest (ROI`s) with good accuracy, and the time evolution of uptake in those ROI`s needs to be obtained from the low count individual data sets. `the prior information must be purely geometrical in such a case, so that the activity in the ROI`s of the prior does not influence the estimated uptake from the individual time frames. It is also desired that the prior does not impose any other conditions on the reconstructions, i.e., no smoothness or deviation from a known set of values is desired. We attack this problem in the framework of Vision Response Functions (VRFs), based on the work done by J.J. Koenderink in Utrecht. We show that there are assemblies of VRF`s that can be presented in a form that is invariant with respect to rotations and translations and that some functions of those invariants can convey the desired geometric prior information independent of the level of activity in the ROI`S, except at very low levels.

Lacer, J. [Lawrence Berkeley Lab., CA (United States); ter Haar Romeny, B.M.; Viergever, M.A. [University Hospital Urtecht, (Netherlands)

1992-06-01T23:59:59.000Z

265

Synthetic liquid fuels development: assessment of critical factors. Volume III. Coal resource depletion  

DOE Green Energy (OSTI)

While US coal resources are known to be vast, their rate of depletion in a future based predominantly on coal has not been examined analytically heretofore. The Coal Depletion Model inventories the coal resource on a regional basis and calculates the cost of coal extraction by three technologies - strip and underground mining and in-situ combustion. A plausible coal demand scenario extending from 1975 to the year 2050 is used as a basis in applying the model. In the year 2050, plants in operation include 285 syncrude plants, each producing 100,000 B/D; 312 SNG plants, each producing 250 million SCF/D and 722 coal-fired electric power plants, each of 1000 MW capacity. In addition, there is 890 million tons per year of industrial coal consumption. Such a high level of coal use would deplete US coal resources much more rapidly than most people appreciate. Of course, the actual amount of US coal is unknown, and if the coal in the hypothetical reliability category is included, depletion is delayed. Coal in this category, however, has not been mapped; it is only presumed to exist on the basis of geological theory. The coal resource depletion model shows that unilateral imposition of a severance tax by a state tends to shift production to other coal producing regions. Boom and bust cycles are both delayed and reduced in their magnitude. When several states simultaneously impose severance taxes, the effect of each is weakened.Key policy issues that emerge from this analysis concern the need to reduce the uncertainty of the magnitude and geographic distribution of the US coal resource and the need to stimulate interaction among the parties at interest to work out equitable and acceptable coal conversion plant location strategies capable of coping with the challenges of a high-coal future.

Dickson, E.M.; Yabroff, I.W.; Kroll, C.A.; White, R.K.; Walton, B.L.; Ivory, M.E.; Fullen, R.E.; Weisbecker, L.W.; Hays, R.L.

1977-01-01T23:59:59.000Z

266

Review of Status of Prior Export Control Recommendations at the Department  

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

Status of Prior Export Control Recommendations at the Status of Prior Export Control Recommendations at the Department of Energy, INS-O-07-01 Review of Status of Prior Export Control Recommendations at the Department of Energy, INS-O-07-01 The National Defense Authorization Act (NDAA) for Fiscal Year 2000 provided that beginning in the year 2000 and ending in the year 2007, the President shall annually submit to Congress a report by the Inspectors General of, at a minimum, the Departments of Energy (Energy), Commerce (Commerce), Defense (Defense), and State (State) of the policies and procedures of the United States Government with respect to the export of technologies and technical information with potential military application to countries and entities of concern. To date, the Energy Office of Inspector General (OIG) has issued 7 reports under this requirement and has

267

Free, Prior, and Informed Consent in REDD+: Principles and Approaches for  

Open Energy Info (EERE)

Free, Prior, and Informed Consent in REDD+: Principles and Approaches for Free, Prior, and Informed Consent in REDD+: Principles and Approaches for Policy and Project Development Jump to: navigation, search Tool Summary Name: Free, Prior, and Informed Consent in REDD+: Principles and Approaches for Policy and Project Development Agency/Company /Organization: German Agency for International Cooperation (GIZ) Sector: Land, Climate Focus Area: Forestry Topics: Implementation, Policies/deployment programs Resource Type: Guide/manual Website: www.forclime.org/images/stories/RECOFTC-GIZ_FPIC_in_REDD_2011.pdf UN Region: South-Eastern Asia, "Pacific" is not in the list of possible values (Eastern Africa, Middle Africa, Northern Africa, Southern Africa, Western Africa, Caribbean, Central America, South America, Northern America, Central Asia, Eastern Asia, Southern Asia, South-Eastern Asia, Western Asia, Eastern Europe, Northern Europe, Southern Europe, Western Europe, Australia and New Zealand, Melanesia, Micronesia, Polynesia, Latin America and the Caribbean) for this property.

268

Rates of contraction of posterior distributions based on Gaussian process priors  

E-Print Network (OSTI)

We derive rates of contraction of posterior distributions on nonparametric or semiparametric models based on Gaussian processes. The rate of contraction is shown to depend on the position of the true parameter relative to the reproducing kernel Hilbert space of the Gaussian process and the small ball probabilities of the Gaussian process. We determine these quantities for a range of examples of Gaussian priors and in several statistical settings. For instance, we consider the rate of contraction of the posterior distribution based on sampling from a smooth density model when the prior models the log density as a (fractionally integrated) Brownian motion. We also consider regression with Gaussian errors and smooth classification under a logistic or probit link function combined with various priors.

Van der Vaart, A W

2008-01-01T23:59:59.000Z

269

Label-to-region with continuity-biased bi-layer sparsity priors  

Science Conference Proceedings (OSTI)

In this work, we investigate how to reassign the fully annotated labels at image level to those contextually derived semantic regions, namely Label-to-Region (L2R), in a collective manner. Given a set of input images with label annotations, the basic ... Keywords: Label-to-Region, bag-of-hierarchical-patch, image annotation, sparse representation

Xiaobai Liu; Shuicheng Yan; Bin Cheng; Jinhui Tang; Tat-Sheng Chua; Hai Jin

2012-11-01T23:59:59.000Z

270

Long-term comparison of dissolution behavior between fully radioactive and simulated nuclear waste glasses  

SciTech Connect

The behavior of radioactive sludge-based and simulated nuclear waste glasses has been compared by long-term testing of radioactive and simulated compositions of Savannah River Laboratory 165, 131, and 200 glasses. Static tests at glass surface area-to-solution volume (SA/V) ratios of 340 and 2000 m[sup [minus]1] up to 720 days show little difference in reactivity between radioactive and simulated waste glasses. The same leach trends are observed for both glass types. The differences in reactivity at an SA/V of 2000 m[sup [minus]1] or below are not large enough to alter the order of glass durability for the different compositions nor to change the controlling glass dissolution processes. The small differences in reactivity between fully radioactive and simulated glasses can reasonably be explained if the controlling reaction process and leachate pH values are accounted for. However, at an SA/V of 20,000 m[sup [minus]1], the simulated nuclear waste glass, 200S, leaches faster than the corresponding radioactive glass by a factor of 40 within 1 yr. The accelerated reaction with the simulated glass 200S is associated with the formation of crystalline phases such as clinoptilolite (or K-feldspar), and a pH excursion. The radiation field generated by the fully radioactive glass reduces the solution pH, which, in turn, may retard the onset of the increased reaction rate. This result suggests that the fully radioactive nuclear waste glass 200R may be substantially more durable than the simulated 200S glass if the lower pH in the 200R leachate can be sustained. Meaningful comparison tests between radioactive and simulated nuclear waste glasses should include long-term and high SA/V tests.

Feng, Xiangdong; Bates, J.K.; Buck, E.C.; Bradley, C.R.; Gong, Meiling (Argonne National Lab., Argonne, IL (United States))

1993-11-01T23:59:59.000Z

271

Associated Higgs-W-Boson Production at Hadron Colliders: A Fully Exclusive QCD Calculation at NNLO  

SciTech Connect

We consider QCD radiative corrections to standard model Higgs-boson production in association with a W boson in hadron collisions. We present a fully exclusive calculation up to next-to-next-to-leading order (NNLO) in QCD perturbation theory. To perform this NNLO computation, we use a recently proposed version of the subtraction formalism. Our calculation includes finite-width effects, the leptonic decay of the W boson with its spin correlations, and the decay of the Higgs boson into a bb pair. We present selected numerical results at the Tevatron and the LHC.

Ferrera, Giancarlo [Dipartimento di Fisica e Astronomia, Universita di Firenze and INFN, Sezione di Firenze, I-50019 Sesto Fiorentino, Florence (Italy); Grazzini, Massimiliano [Institut fuer Theoretische Physik, Universitaet Zuerich, CH-8057 Zuerich (Switzerland); Tramontano, Francesco [Theory Group, Physics Department, CERN, CH-1211 Geneva 23 (Switzerland)

2011-10-07T23:59:59.000Z

272

MASS TRANSFER TO ROTATING DISKS AND ROTATING RINGS IN LAMINAR, TRANSITION, AND FULLY DEVELOPED TURBULENT FLOW  

SciTech Connect

Experimental data and theoretical calculations are presented for the mass-transfer rate to rotating disks and rotating rings when laminar, transition, and fully developed turbulent flow exist upon different portions of the surface. Good agreement of data and the model is obtained for rotating disks and relatively thick rotating rings. Results of the calculations for thin rings generally exceed the experimental data measured in transition and turbulent flow. A y{sup +{sup 3}} form for the eddy diffusivity is used to fit the data. No improvement is noticed with a form involving both y{sup +{sup 3}} and y{sup +{sup 3}}.

Law Jr., C.G.; Pierini, P.; Newman, J.

1980-07-01T23:59:59.000Z

273

Phenomenology Studies Using a Scanning Fully Polarimetric Passive W-Band Millimeter Wave Imager  

SciTech Connect

We present experimental results obtained from a scanning passive W-band fully polarimetric imager. In addition to a conventional approach to polarimetric image analysis in which the Stokes I, Q, U, and V images were formed and displayed, we present an alternative method for polarimetric image exploitation based upon multivariate image analysis (MIA). MIA uses principal component analysis (PCA) and 2D scatter or score plots to identify various pixel classes in the image compared with the more conventional scene-based image analysis approaches. Multivariate image decomposition provides a window into the complementary interplay between spatial and statistical correlations contained in the data.

Bernacki, Bruce E.; Kelly, James F.; Sheen, David M.; McMakin, Douglas L.; Tedeschi, Jonathan R.; Hall, Thomas E.; Hatchell, Brian K.; Valdez, Patrick LJ

2011-05-01T23:59:59.000Z

274

Optimal Portfolio-Consumption with Habit Formation and Partial Observations: The Fully Explicit Solutions Approach  

E-Print Network (OSTI)

We consider a model of optimal investment and consumption with both habit-formation and partial observations in incomplete Ito processes markets. The individual investor develops addictive consumption habits gradually while he can only observe the market stock prices but not the instantaneous rates of return, which follow Ornstein-Uhlenbeck processes. Applying the Kalman-Bucy filtering theorem and Dynamic Programming arguments, we solve the associated HJB equation fully explicitly for this path dependent stochastic control problem in the case of power utility preferences. We will provide the optimal investment and consumption policies in explicit feedback forms using rigorous verification arguments.

Yu, Xiang

2011-01-01T23:59:59.000Z

275

Spatially resolved measurements of fully ionized low-Z impurities in the PDX tokamak  

DOE Green Energy (OSTI)

Fully ionized oxygen and carbon in PDX plasmas are detected via charge-exchange recombination reactions between the impurities and hydrogen atoms from a low-power neutral beam. The C/sup 6 +/ and O/sup 8 +/ ions are observed out to radii beyond the limiter, which is in contrast to expectations based on coronal equilibrium but consistent with a simple diffusive transport model. Central values of Z/sub eff/ obtained with these measurements agree with values obtained from plasma resistivity and visible bremsstrahlung measurements.

Fonck, R.J.; Finkenthal, M.; Goldston, R.J.; Herndon, D.L.; Hulse, R.A.; Kaita, R.; Meyerhofer, D.D.

1982-09-06T23:59:59.000Z

276

Fully coherent follow-up of continuous gravitational-wave candidates  

E-Print Network (OSTI)

The search for continuous gravitational waves from unknown isolated sources is computationally limited due to the enormous parameter space that needs to be covered and the weakness of the expected signals. Therefore semi-coherent search strategies have been developed and applied in distributed computing environments such as Einstein@Home, in order to narrow down the parameter space and identify interesting candidates. However, in order to optimally confirm or dismiss a candidate as a possible gravitational-wave signal, a fully-coherent follow-up using all the available data is required. We present a general method and implementation of a direct (2-stage) transition to a fully-coherent follow-up on semi-coherent candidates. This method is based on a grid-less Mesh Adaptive Direct Search (MADS) algorithm using the F-statistic. We demonstrate the detection power and computing cost of this follow-up procedure using extensive Monte-Carlo simulations on (simulated) semi-coherent candidates from a directed as well a...

Shaltev, Miroslav

2013-01-01T23:59:59.000Z

277

Fully coherent follow-up of continuous gravitational-wave candidates  

E-Print Network (OSTI)

The search for continuous gravitational waves from unknown isolated sources is computationally limited due to the enormous parameter space that needs to be covered and the weakness of the expected signals. Therefore semi-coherent search strategies have been developed and applied in distributed computing environments such as Einstein@Home, in order to narrow down the parameter space and identify interesting candidates. However, in order to optimally confirm or dismiss a candidate as a possible gravitational-wave signal, a fully-coherent follow-up using all the available data is required. We present a general method and implementation of a direct (2-stage) transition to a fully-coherent follow-up on semi-coherent candidates. This method is based on a grid-less Mesh Adaptive Direct Search (MADS) algorithm using the F-statistic. We demonstrate the detection power and computing cost of this follow-up procedure using extensive Monte-Carlo simulations on (simulated) semi-coherent candidates from a directed as well as from an all-sky search setup.

Miroslav Shaltev; Reinhard Prix

2013-03-11T23:59:59.000Z

278

Technique for the experimental estimation of nonlinear energy transfer in fully developed turbulence  

Science Conference Proceedings (OSTI)

A new procedure for calculating the nonlinear energy transfer and linear growth/damping rate of fully developed turbulence is derived. It avoids the unphysically large damping rates typically obtained using the predecessor method of Ritz [Ch. P. Ritz, E. J. Powers, and R. D. Bengtson, Phys. Fluids B {bold 1}, 153 (1989)]. It enforces stationarity of the turbulence to reduce the effects of noise and fluctuations not described by the basic governing equation, and includes the fourth-order moment to avoid the closure approximation. The new procedure has been implemented and tested on simulated, fully developed two-dimensional (2-D) turbulence data from a 2-D trapped-particle fluid code, and has been shown to give excellent reconstructions of the input growth rate and nonlinear coupling coefficients with good noise rejection. However, in the experimentally important case where only a one-dimensional (1-D) averaged representation of the underlying 2-D turbulence is available, this technique does not, in general, give acceptable results. A new 1-D algorithm has thus been developed for analysis of 1-D measurements of intrinsically 2-D turbulence. This new 1-D algorithm includes the nonresonant wave numbers in calculating the bispectra, and generally gives useful results when the width of the radial wave number spectrum is comparable to or less than that of the poloidal spectrum. {copyright} {ital 1996 American Institute of Physics.}

Kim, J.S.; Durst, R.D.; Fonck, R.J. [Department of Nuclear Engineering and Engineering Physics, University of Wisconsin, Madison, Wisconsin 53706 (United States)] [Department of Nuclear Engineering and Engineering Physics, University of Wisconsin, Madison, Wisconsin 53706 (United States); Fernandez, E.; Ware, A.; Terry, P.W. [Department of Physics, University of Wisconsin, Madison, Wisconsin 53706 (United States)] [Department of Physics, University of Wisconsin, Madison, Wisconsin 53706 (United States)

1996-11-01T23:59:59.000Z

279

Charge Depleting:  

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

3 seconds 3 seconds Acceleration 1/4 Mile Time: 20.3 seconds Maximum Speed: 74.3 MPH Acceleration 1 Mile Maximum Speed: 103.4 MPH Charge Sustaining: Acceleration 0-60 MPH Time: 13.4 seconds Acceleration 1/4 Mile Time: 20.4 seconds Maximum Speed: 74.8 MPH Acceleration 1 Mile Maximum Speed: 104.0 MPH Brake Test @ 60 MPH Distance Required: 153.0 ft UDDS Fuel Economy 6 HWFET Fuel Economy 6 Distance (miles)

280

Charge Depleting:  

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

0 seconds 0 seconds Acceleration 1/4 Mile Time: 20.1 seconds Maximum Speed: 75.7 MPH Acceleration 1 Mile Maximum Speed: 104.9 MPH Charge Sustaining: Acceleration 0-60 MPH Time: 12.8 seconds Acceleration 1/4 Mile Time: 20.0 seconds Maximum Speed: 75.7 MPH Acceleration 1 Mile Maximum Speed: 105.0 MPH Brake Test @ 60 MPH Distance Required: 126.8 ft UDDS Fuel Economy 6 HWFET Fuel Economy 6 Distance (miles)

Note: This page contains sample records for the topic "fully depleted prior" 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

Charge Depleting:  

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

(mpg) Fuel Economy (mpg) Fuel Economy AC Energy Consumed AC Energy Consumed AC Energy (kWh) 7 Distance (miles) Fuel Economy (mpg) Fuel Economy (mpg) Fuel Economy AC Energy...

282

Neutronic Analysis of the Burning of Transuranics in Fully Ceramic Micro-Encapsulated Tri-Isotropic Particle-Fuel in a PWR  

SciTech Connect

Calculations have been performed to assess the neutronic behavior of pins of Fully-Ceramic Micro-encapsulated (FCM) fuel in otherwise-conventional Pressurized Water Reactor (PWR) fuel pins. The FCM fuel contains transuranic (TRU) – only oxide fuel in tri-isotropic (TRISO) particles with the TRU loading coming from the spent fuel of a conventional LWR after 5 years of cooling. Use of the TRISO particle fuel would provide an additional barrier to fission product release in the event of cladding failure. Depletion calculations were performed to evaluate reactivity-limited burnup of the TRU-only FCM fuel. These calculations showed that due to relatively little space available for fuel, the achievable burnup with these pins alone is quite small. Various reactivity parameters were also evaluated at each burnup step including moderator temperature coefficient (MTC), Doppler, and soluble boron worth. These were compared to reference UO2 and MOX unit cells. The TRU-only FCM fuel exhibits degraded MTC and Doppler coefficients relative to UO2 and MOX. Also, the reactivity effects of coolant voiding suggest that the behavior of this fuel would be similar to a MOX fuel of very high plutonium fraction, which are known to have positive void reactivity. In general, loading of TRU-only FCM fuel into an assembly without significant quantities of uranium presents challenges to the reactor design. However, if such FCM fuel pins are included in a heterogeneous assembly alongside LEU fuel pins, the overall reactivity behavior is dominated by the uranium pins while attractive TRU destruction performance levels in the TRU-only FCM fuel pins is. From this work, it is concluded that use of heterogeneous assemblies such as these appears feasible from a preliminary reactor physics standpoint.

Michael A. Pope; R. Sonat Sen; Abderrafi M. Ougouag; Gilles Youinou; Brian Boer

2012-11-01T23:59:59.000Z

283

Recruiting for Ideas: How Firms Exploit the Prior Inventions of New Hires  

Science Conference Proceedings (OSTI)

When firms recruit inventors, they acquire not only the use of their skills but also enhanced access to their stock of ideas. But do hiring firms actually increase their use of new recruits' prior inventions? Our estimates suggest they do, quite significantly ... Keywords: access to ideas, coarsened exact matching, collaborative networks, difference in differences, inventor mobility, knowledge spillovers, learning by hiring, patent citations

Jasjit Singh; Ajay Agrawal

2011-01-01T23:59:59.000Z

284

Copyright 2009 No part of this presentation may be reproduced in any form without prior authorization.  

E-Print Network (OSTI)

PV ideal for rural applications both in MN and elsewhere Orb Energy Working to make solar power Ethanol centric Limited solar opportunities Lack of cultural awareness Opportunities Increase public without prior authorization. Minnesota Energy Sources · Limited solar · Good location for wind, hydro

Amin, S. Massoud

285

Not to be cited without prior reference to the authors. ICES CM 2006 / H:12  

E-Print Network (OSTI)

Not to be cited without prior reference to the authors. ICES CM 2006 / H:12 Theme session H the male phase and reproduce as females already in their first reproductive season) responds is parameterized for Epinephelus fuscoguttatus (common names: brown #12;marbled grouper or flowery cod

Heino, Mikko

286

Heavy-Tailed Process Priors for Selective Shrinkage Fabian L. Wauthier  

E-Print Network (OSTI)

Heavy-Tailed Process Priors for Selective Shrinkage Fabian L. Wauthier University of California@cs.berkeley.edu Abstract Heavy-tailed distributions are often used to enhance the robustness of regression space, which are isolated observations in sparsely populated regions. We show that heavy

Jordan, Michael I.

287

The Statistics of the Number of Neutron Collisions Prior to Absorption  

E-Print Network (OSTI)

The Statistics of the Number of Neutron Collisions Prior to Absorption Sara A. Pozzi* Oak Ridge University of Technology, Department of Reactor Physics, SE - 41296 Göteborg, Sweden Received May 19, 2005 of the number of collisions undergone by fast neutrons during slowing down until they are absorbed. We assume

Pázsit, Imre

288

Design of Transport Casks with Depleted Uranium Gamma Shield and Advanced Safety  

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

Transport Casks with Depleted Uranium Gamma Shield and Advanced Safety Transport Casks with Depleted Uranium Gamma Shield and Advanced Safety Matveev V.Z., Morenko A.I., Shapovalov V.I. Russian Federal Nuclear Center - All-Russian Research Institute of Experimental Physics (RFNC-VNIIEF) 37 Mira Prospect, Sarov, Russia, 607190, matveev@vniief.ru Maslov A.A., Orlov V.K., Semenov A.G., Sergeev V.M., Yuferov O.I., Visik A.M. Bochvar Institute of Inorganic Materials (VNIINM) 5-A Rogova street, p.b. 369, Moscow, Russia, 123060, majul2000@mail.ru Abstract - The report is dedicated to a problem of creation of a new generation of dual-purpose transport packing complete sets (TPCS) 1 with advanced safety. These sets are intended for transportation and storage of spent nuclear fuel assemblies (SNFA) 2 of VVER reactors and spent spark elements (SSE)

289

Methods Used to Calculate Doses Resulting from Inhalation of Capstone Depleted Uranium Aerosols  

Science Conference Proceedings (OSTI)

The methods used to calculate radiological and toxicological doses to hypothetical persons inside either a United States Army Abrams tank or Bradley Fighting Vehicle that has been perforated by depleted uranium munitions is described. Data from time- and particle-size-resolved measurements of depleted uranium aerosol as well as particle-size resolved measurements of aerosol solubility in lung fluids for aerosol produced in the breathing zones of the hypothetical occupants were used. The aerosol was approximated as a mixture of nine monodisperse (single particle size) components corresponding to particle size increments measured by the eight stages plus backup filter of the cascade impactors used. A Markov Chain Monte Carlo Bayesian analysis technique was employed, which straightforwardly calculates the uncertainties in doses. Extensive quality control checking of the various computer codes used is described.

Miller, Guthrie; Cheng, Yung-Sung; Traub, Richard J.; Little, Thomas T.; Guilmette, Ray A.

2009-02-26T23:59:59.000Z

290

Summary of the Preliminary Analysis of Savannah River Depleted Uranium Trioxide  

SciTech Connect

This report summarizes a preliminary special analysis of the Savannah River Depleted Uranium Trioxide waste stream (SVRSURANIUM03, Revision 2). The analysis is considered preliminary because a final waste profile has not been submitted for review. The special analysis is performed to determine the acceptability of the waste stream for shallow land burial at the Area 5 Radioactive Waste Management Site (RWMS) at the Nevada National Security Site (NNSS). The Savannah River Depleted Uranium Trioxide waste stream requires a special analysis because the waste stream’s sum of fractions exceeds one. The 99Tc activity concentration is 98 percent of the NNSS Waste Acceptance Criteria and the largest single contributor to the sum of fractions.

NSTec Environmental Management

2010-10-13T23:59:59.000Z

291

Assessing the risk from the depleted uranium weapons used in Operation Allied Force.  

E-Print Network (OSTI)

The conflict in Yugoslavia has been a source of great concern for the neighboring countries, about the radiological and toxic hazard posed by the alleged presence of depleted uranium in NATO weapons. In the present study a worst-case scenario is assumed mainly to assess the risk for Greece and other neighboring countries of Yugoslavia at similar distances. The risk of the weapons currently in use is proved to be negligible at distances greater than 100 Km. For shorter distances classified data of weapons composition are needed to obtain a reliable assessment. Operation Allied Force (OAF) has been going on for weeks in Yugoslavia with grave environmental consequences in the neighboring countries. Unfortunately, the sophisticated weapons that are being used carry the spectrum of radiological contamination. Over the past decades there has been a tremendous effort in weapons laboratories to use depleted uranium

unknown authors

1999-01-01T23:59:59.000Z

292

Melted and Granulated Depleted Uranium Dioxide for Use in Containers for Spent Nuclear Fuel  

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

Melted and Granulated Depleted Uranium Dioxide for Use in Containers for Spent Nuclear Fuel Melted and Granulated Depleted Uranium Dioxide for Use in Containers for Spent Nuclear Fuel Vitaly T. Gotovchikov a , Victor A. Seredenko a , Valentin V. Shatalov a , Vladimir N. Kaplenkov a , Alexander S. Shulgin a , Vladimir K. Saranchin a , Michail A. Borik a∗ , Charles W. Forsberg b , All-Russian Research Institute of Chemical Technology (ARRICT) 33, Kashirskoe ave., Moscow, Russia, 115409, E-mail: chem.conv@ru.net Oak Ridge National Laboratory (ORNL) Bethel Wall Road, P.O. Box 2008, MS-6165, Oak Ridge, TN, USA, 37831 Abstract - Induction cold crucible melters (ICCM) have the potential to be a very-low-cost high-throughput method for the production of DUO 2 for SNF casks. The proposed work would develop these melters for this specific application. If a

293

Development of a Novel Depleted Uranium Treatment Process at Lawrence Livermore National Laboratory  

Science Conference Proceedings (OSTI)

A three-stage process was developed at Lawrence Livermore National Laboratory to treat potentially pyrophoric depleted uranium metal wastes. The three-stage process includes waste sorting/rinsing, acid dissolution of the waste metal with a hydrochloric and phosphoric acid solution, and solidification of the neutralized residuals from the second stage with clay. The final product is a solid waste form that can be transported to and disposed of at a permitted low-level radioactive waste disposal site.

Gates-Anderson, D; Bowers, J; Laue, C; Fitch, T

2007-01-22T23:59:59.000Z

294

Comparative study of femtosecond and nanosecond laser-induced breakdown spectroscopy of depleted uranium  

SciTech Connect

We present spectra of depleted uranium metal from laser plasmas generated by nanosecond Nd:YAG (1064 nm) and femtosecond Ti:sapphire (800 nm) laser pulses. The latter pulses produce short-lived and relatively cool plasmas in comparison to the longer pulses, and the spectra of neutral uranium atoms appear immediately after excitation. Evidence for nonequilibrium excitation with femtosecond pulses is found in the dependence of spectral line intensities on the pulse chirp.

Emmert, Luke A.; Chinni, Rosemarie C.; Cremers, David A.; Jones, C. Randy; Rudolph, Wolfgang

2011-01-20T23:59:59.000Z

295

Adjoint-Based Uncertainty Quantification and Sensitivity Analysis for Reactor Depletion Calculations  

E-Print Network (OSTI)

Depletion calculations for nuclear reactors model the dynamic coupling between the material composition and neutron flux and help predict reactor performance and safety characteristics. In order to be trusted as reliable predictive tools and inputs to licensing and operational decisions, the simulations must include an accurate and holistic quantification of errors and uncertainties in its outputs. Uncertainty quantification is a formidable challenge in large, realistic reactor models because of the large number of unknowns and myriad sources of uncertainty and error. We present a framework for performing efficient uncertainty quantification in depletion problems using an adjoint approach, with emphasis on high-fidelity calculations using advanced massively parallel computing architectures. This approach calls for a solution to two systems of equations: (a) the forward, engineering system that models the reactor, and (b) the adjoint system, which is mathematically related to but different from the forward system. We use the solutions of these systems to produce sensitivity and error estimates at a cost that does not grow rapidly with the number of uncertain inputs. We present the framework in a general fashion and apply it to both the source-driven and k-eigenvalue forms of the depletion equations. We describe the implementation and verification of solvers for the forward and ad- joint equations in the PDT code, and we test the algorithms on realistic reactor analysis problems. We demonstrate a new approach for reducing the memory and I/O demands on the host machine, which can be overwhelming for typical adjoint algorithms. Our conclusion is that adjoint depletion calculations using full transport solutions are not only computationally tractable, they are the most attractive option for performing uncertainty quantification on high-fidelity reactor analysis problems.

Stripling, Hayes Franklin

2013-08-01T23:59:59.000Z

296

Validation of a Monte Carlo Based Depletion Methodology Using HFIR Post-Irradiation Measurements  

Science Conference Proceedings (OSTI)

Post-irradiation uranium isotopic atomic densities within the core of the High Flux Isotope Reactor (HFIR) were calculated and compared to uranium mass spectrographic data measured in the late 1960s and early 70s [1]. This study was performed in order to validate a Monte Carlo based depletion methodology for calculating the burn-up dependent nuclide inventory, specifically the post-irradiation uranium

Chandler, David [ORNL; Maldonado, G Ivan [ORNL; Primm, Trent [ORNL

2009-11-01T23:59:59.000Z

297

Depleted uranium oxides as spent-nuclear-fuel waste-package invert and backfill materials  

SciTech Connect

A new technology has been proposed in which depleted uranium, in the form of oxides or silicates, is placed around the outside of the spent nuclear fuel waste packages in the geological repository. This concept may (1) reduce the potential for repository nuclear criticality events and (2) reduce long-term release of radionuclides from the repository. As a new concept, there are significant uncertainties.

Forsberg, C.W.; Haire, M.J.

1997-07-07T23:59:59.000Z

298

Power distributions in fresh and depleted LEU and HEU cores of the MITR reactor.  

Science Conference Proceedings (OSTI)

The Massachusetts Institute of Technology Reactor (MITR-II) is a research reactor in Cambridge, Massachusetts designed primarily for experiments using neutron beam and in-core irradiation facilities. It delivers a neutron flux comparable to current LWR power reactors in a compact 6 MW core using Highly Enriched Uranium (HEU) fuel. In the framework of its non-proliferation policies, the international community presently aims to minimize the amount of nuclear material available that could be used for nuclear weapons. In this geopolitical context, most research and test reactors both domestic and international have started a program of conversion to the use of Low Enriched Uranium (LEU) fuel. A new type of LEU fuel based on an alloy of uranium and molybdenum (UMo) is expected to allow the conversion of U.S. domestic high performance reactors like the MITR-II reactor. Toward this goal, core geometry and power distributions are presented. Distributions of power are calculated for LEU cores depleted with MCODE using an MCNP5 Monte Carlo model. The MCNP5 HEU and LEU MITR models were previously compared to experimental benchmark data for the MITR-II. This same model was used with a finer spatial depletion in order to generate power distributions for the LEU cores. The objective of this work is to generate and characterize a series of fresh and depleted core peak power distributions, and provide a thermal hydraulic evaluation of the geometry which should be considered for subsequent thermal hydraulic safety analyses.

Wilson, E.H.; Horelik, N.E.; Dunn, F.E.; Newton, T.H., Jr.; Hu, L.; Stevens, J.G. (Nuclear Engineering Division); (2MIT Nuclear Reactor Laboratory and Nuclear Science and Engineering Department)

2012-04-04T23:59:59.000Z

299

Potential hazards of compressed air energy storage in depleted natural gas reservoirs.  

DOE Green Energy (OSTI)

This report is a preliminary assessment of the ignition and explosion potential in a depleted hydrocarbon reservoir from air cycling associated with compressed air energy storage (CAES) in geologic media. The study identifies issues associated with this phenomenon as well as possible mitigating measures that should be considered. Compressed air energy storage (CAES) in geologic media has been proposed to help supplement renewable energy sources (e.g., wind and solar) by providing a means to store energy when excess energy is available, and to provide an energy source during non-productive or low productivity renewable energy time periods. Presently, salt caverns represent the only proven underground storage used for CAES. Depleted natural gas reservoirs represent another potential underground storage vessel for CAES because they have demonstrated their container function and may have the requisite porosity and permeability; however reservoirs have yet to be demonstrated as a functional/operational storage media for compressed air. Specifically, air introduced into a depleted natural gas reservoir presents a situation where an ignition and explosion potential may exist. This report presents the results of an initial study identifying issues associated with this phenomena as well as possible mitigating measures that should be considered.

Cooper, Paul W.; Grubelich, Mark Charles; Bauer, Stephen J.

2011-09-01T23:59:59.000Z

300

Vacancies in fully hydrogenated boron nitride layer: implications for functional nanodevices  

SciTech Connect

Using density functional theory, a series of calculations of structural and electronic properties of hydrogen vacancies in a fully hydrogenated boron nitride (fH-BN) layer were conducted. By dehydrogenating the fH-BN structure, B-terminated vacancies can be created which induce complete spin polarization around the Fermi level, irrespective of the vacancy size. On the contrary, the fH-BN structure with N-terminated vacancies can be a small-gap semiconductor, a typical spin gapless semiconductor, or a metal depending on the vacancy size. Utilizing such vacancy-induced band gap and magnetism changes, possible applications in spintronics are proposed, and a special fH-BN based quantum dot device is designed.

Zhou, Yungang; Wang, Zhiguo; Nie, JL; Yang, Ping; Sun, Xin; Khaleel, Mohammad A.; Zu, Xiaotao; Gao, Fei

2012-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "fully depleted prior" 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

cuInspiral: prototype gravitational waves detection pipeline fully coded on GPU using CUDA  

E-Print Network (OSTI)

In this paper we report the prototype of the first coalescing binary detection pipeline fully implemented on NVIDIA GPU hardware accelerators. The code has been embedded in a GPU library, called cuInspiral and has been developed under CUDA framework. The library contains for example a PN gravitational wave signal generator, matched filtering/FFT and detection algorithms that have been profiled and compared with the corresponding CPU code with dedicated benchmark in order to provide gain factor respect to the standard CPU implementation. In the paper we present performances and accuracy results about some of the main important elements of the pipeline, demonstrating the feasibility and the chance of obtain an impressive computing gain from these new many-core architectures in the perspective of the second and third generations of gravitational wave detectors.

Bosi, Leone B

2010-01-01T23:59:59.000Z

302

Fluid preconditioning for Newton-Krylov-based, fully implicit, electrostatic particle-in-cell simulations  

E-Print Network (OSTI)

A recent proof-of-principle study proposes an energy- and charge-conserving, nonlinearly implicit electrostatic particle-in-cell (PIC) algorithm in one dimension [Chen et al, J. Comput. Phys., 230 (2011) 7018]. The algorithm in the reference employs an unpreconditioned Jacobian-free Newton-Krylov method, which ensures nonlinear convergence at every timestep (resolving the dynamical timescale of interest). Kinetic enslavement, which is one key component of the algorithm, not only enables fully implicit PIC a practical approach, but also allows preconditioning the kinetic solver with a fluid approximation. This study proposes such a preconditioner, in which the linearized moment equations are closed with moments computed from particles. Effective acceleration of the linear GMRES solve is demonstrated, on both uniform and non-uniform meshes. The algorithm performance is largely insensitive to the electron-ion mass ratio. Numerical experiments are performed on a 1D multi-scale ion acoustic wave test problem.

Chen, Guangye; Leibs, Christopher A; Knoll, Dana A; Taitano, William

2013-01-01T23:59:59.000Z

303

Stress intensity magnification factors for fully circumferential cracks in valve bodies (thick cylinders)  

SciTech Connect

The stress intensity solutions presented herein were obtained using an energy method in conjunction with a two-dimensional finite element program in order to explicitly account for curvature effect for fully circumferential cracks. The magnification factors for a specific crack depth were calculated by successively loading the crack surface by a uniform, linear, quadratic, and a cubic loading distribution. The magnification factors can be used to calculate the stress intensity factors by superposition method. The functions for each load condition in terms of radius to thickness ratio (R/t) and a fractional distance in terms of crack depth to thickness ratio (a/t) were developed. The validity of these functions is R/t = 1.5 to 10.0 and for 0.0125 {le} a/t {le} 0.8125. The functions agree to within 1% of the finite elements solutions for most magnification factors.

Toor, P.M.

1998-11-01T23:59:59.000Z

304

Double ionization of helium by bare ions: Theoretical study of the fully differential cross sections  

SciTech Connect

This work presents a theoretical study of fully differential cross sections (FDCSs) for the double ionization of an He target by ion impact within a distorted wave model. The initial atomic system is described by two approximated wave functions of different accuracy proposed by Bonham and Kohl. For the final channel several models are considered based upon improvements and simplifications of the well-known three-body Coulomb (3C) model. The influence of the receding projectile on the resulting fragments is also studied by implementing a model with effective charges that depend on the momenta of the four particles. The FDCSs resulting for different electron energy sharing are discussed. The sensitivity of the FDCSs to the projectile charge sign and magnitude is explored over the energy range 700 keV/amu through 6 MeV/amu.

Lopez, S. D.; Garibotti, C. R. [Consejo Nacional de Investigaciones Cientificas y Tecnicas and Centro Atomico Bariloche, Avenida Bustillo 9400, 8400 San Carlos de Bariloche (Argentina); Otranto, S. [Instituto de Fisica del Sur and Departamento de Fisica, Universidad Nacional del Sur, 8000 Bahia Blanca (Argentina)

2011-06-15T23:59:59.000Z

305

An Efficient Method for Fully Relativistic Simulations of Coalescing Binary Neutron Stars  

E-Print Network (OSTI)

The merger of two neutron stars has been proposed as a source of gamma-ray bursts, r-process elements, and detectable gravitational waves. Extracting information from observations of these phenomena requires fully relativistic simulations. Unfortunately, the only demonstrated method for stably evolving neutron stars requires solving elliptic equations at each time step, adding substantially to the computational resources required. In this paper we present a simpler, more efficient method. The key insight is in how we apply numerical diffusion. We perform a number of tests to validate the method and our implementation. We also carry out a very rough simulation of coalescence and extraction of the gravitational waves to show that the method is viable if realistic initial data are provided.

Walter Landry; Saul A. Teukolsky

1999-12-01T23:59:59.000Z

306

Assessing the Vulnerability of Large Critical Infrastructure Using Fully-Coupled Blast Effects Modeling  

Science Conference Proceedings (OSTI)

Structural failures, such as the MacArthur Maze I-880 overpass in Oakland, California and the I-35 bridge in Minneapolis, Minnesota, are recent examples of our national infrastructure's fragility and serve as an important reminder of such infrastructure in our everyday lives. These two failures, as well as the World Trade Center's collapse and the levee failures in New Orleans, highlight the national importance of protecting our infrastructure as much as possible against acts of terrorism and natural hazards. This paper describes a process for evaluating the vulnerability of critical infrastructure to large blast loads using a fully-coupled finite element approach. A description of the finite element software and modeling technique is discussed along with the experimental validation of the numerical tools. We discuss how such an approach can be used for specific problems such as modeling the progressive collapse of a building.

McMichael, L D; Noble, C R; Margraf, J D; Glascoe, L G

2009-03-26T23:59:59.000Z

307

A fully implicit numerical method for single-fluid resistive magnetohydrodynamics  

SciTech Connect

We present a nonlinearly implicit, conservative numerical method for integration of the single-fluid resistive MHD equations. The method uses a high-order spatial discretization that preserves the solenoidal property of the magnetic field. The fully coupled PDE system is solved implicitly in time, providing for increased interaction between physical processes as well as additional stability over explicit-time methods. A high-order adaptive time integration is employed, which in many cases enables time steps ranging from one to two orders of magnitude larger than those constrained by the explicit CFL condition. We apply the solution method to illustrative examples relevant to stiff magnetic fusion processes which challenge the efficiency of explicit methods. We provide computational evidence showing that for such problems the method is comparably accurate with explicit-time simulations, while providing a significant runtime improvement due to its increased temporal stability.

Reynolds, Daniel R. [Department of Mathematics, University of California at San Diego, 9500 Gilman Drive, Dept 0112, La Jolla, San Diego, CA 92093-0112 (United States)]. E-mail: drreynolds@ucsd.edu; Samtaney, Ravi [Princeton Plasma Physics Lab, MS 26, P.O. Box 451, Princeton, NJ 08543 (United States)]. E-mail: samtaney@pppl.gov; Woodward, Carol S. [Lawrence Livermore National Lab, P.O. Box 808, L-551, Livermore, CA 94551 (United States)]. E-mail: cswoodward@llnl.gov

2006-11-20T23:59:59.000Z

308

Development of Fully Coupled Aeroelastic and Hydrodynamic Models for Offshore Wind Turbines: Preprint  

SciTech Connect

Aeroelastic simulation tools are routinely used to design and analyze onshore wind turbines, in order to obtain cost effective machines that achieve favorable performance while maintaining structural integrity. These tools employ sophisticated models of wind-inflow; aerodynamic, gravitational, and inertial loading of the rotor, nacelle, and tower; elastic effects within and between components; and mechanical actuation and electrical responses of the generator and of control and protection systems. For offshore wind turbines, additional models of the hydrodynamic loading in regular and irregular seas, the dynamic coupling between the support platform motions and wind turbine motions, and the dynamic characterization of mooring systems for compliant floating platforms are also important. Hydrodynamic loading includes contributions from hydrostatics, wave radiation, and wave scattering, including free surface memory effects. The integration of all of these models into comprehensive simulation tools, capable of modeling the fully coupled aeroelastic and hydrodynamic responses of floating offshore wind turbines, is presented.

Jonkman, J. M.; Sclavounos, P. D.

2006-01-01T23:59:59.000Z

309

cuInspiral: prototype gravitational waves detection pipeline fully coded on GPU using CUDA  

E-Print Network (OSTI)

In this paper we report the prototype of the first coalescing binary detection pipeline fully implemented on NVIDIA GPU hardware accelerators. The code has been embedded in a GPU library, called cuInspiral and has been developed under CUDA framework. The library contains for example a PN gravitational wave signal generator, matched filtering/FFT and detection algorithms that have been profiled and compared with the corresponding CPU code with dedicated benchmark in order to provide gain factor respect to the standard CPU implementation. In the paper we present performances and accuracy results about some of the main important elements of the pipeline, demonstrating the feasibility and the chance of obtain an impressive computing gain from these new many-core architectures in the perspective of the second and third generations of gravitational wave detectors.

Leone B. Bosi

2010-06-16T23:59:59.000Z

310

Identification of intermittent multi-fractal turbulence in fully kinetic simulations of magnetic reconnection  

E-Print Network (OSTI)

Recent fully nonlinear, kinetic three-dimensional simulations of magnetic reconnection [Daughton et al. 2011] evolve structures and exhibit dynamics on multiple scales, in a manner reminiscent of turbulence. These simulations of reconnection are among the first to be performed at sufficient spatio-temporal resolution to allow formal quantitative analysis of statistical scaling which we present here. We find that the magnetic field fluctuations generated by reconnection are anisotropic, have non-trivial spatial correlation and exhibit the hallmarks of finite range fluid turbulence; they have non-Gaussian distributions, exhibit Extended Self-Similarity in their scaling and are spatially multifractal. Furthermore, we find that the field J.E is also multifractal, so that magnetic energy is converted to plasma kinetic energy in a manner that is spatially intermittent. This suggests that dissipation in this sense in collisionless reconnection on kinetic scales has an analogue in fluid-like turbulent phenomenology, ...

Leonardis, E; Daughton, W; Roytershteyn, V; Karimabadi, H

2013-01-01T23:59:59.000Z

311

Double Barrier Resonant Tunneling Transistor with a Fully Two Dimensional Emitter  

SciTech Connect

A novel planar resonant tunneling transistor is demonstrated. The growth structure is similar to that of a double-barrier resonant tunneling diode (RTD), except for a fully two-dimensional (2D) emitter formed by a quantum well. Current is fed laterally into the emitter, and the 2D--2D resonant tunneling current is controlled by a surface gate. This unique device structure achieves figures-of-merit, i.e. peak current densities and peak voltages, approaching that of state-of-the-art RTDs. Most importantly, sensitive control of the peak current and voltage is achieved by gating of the emitter quantum well subband energy. This quantum tunneling transistor shows exceptional promise for ultra-high speed and multifunctional operation at room temperature.

MOON,J.S.; SIMMONS,JERRY A.; RENO,JOHN L.; BACA,WES E.; BLOUNT,MARK A.; HIETALA,VINCENT M.; JONES,ERIC D.

2000-07-13T23:59:59.000Z

312

REVIEW ARTICLE Ozone depletion and increased UV-B radiation: is there a real threat to photosynthesis?  

E-Print Network (OSTI)

on photosynthetic competence or light-interception. It is concluded that O depletion and the concurrent rise This critical review of recent literature questions earl-3 in UV-B irradiance is not a direct threat to photosynier predictions that photosynthetic productivity of thetic productivity of crops and natural vegetation. higher plants is vulnerable to increased ultraviolet-B (UV-B) radiation as a result of stratospheric ozone (O) 3 Key words: Biomass, development, ozone depletion, depletion. Direct UV-B-induced inhibition of photosyn- photosynthesis, ultraviolet-B. thetic competence is observed only at high UV-B irradiances and primarily involves the loss of soluble Calvin

Damian J. Allen; Salvador Nogués; Neil R. Baker

1998-01-01T23:59:59.000Z

313

Fully Nonlinear Statistics of Wave Crest Elevation Calculated Using a Spectral Response Surface Method: Applications to Unidirectional Sea States  

Science Conference Proceedings (OSTI)

This paper concerns the calculation of the probability of exceedance of wave crest elevation. The statistics have been calculated for broadbanded, unidirectional, deep-water sea states by incorporating a fully nonlinear wave model into a spectral ...

R. S. Gibson; C. Swan; P. S. Tromans

2007-01-01T23:59:59.000Z

314

Structure and Formation of an Annular Hurricane Simulated in a Fully Compressible, Nonhydrostatic Model—TCM4  

Science Conference Proceedings (OSTI)

The structure and formation of an annular hurricane simulated in a fully compressible, nonhydrostatic tropical cyclone model—TCM4—are analyzed. The model is initialized with an axisymmetric vortex on an f plane in a quiescent environment, and ...

Yuqing Wang

2008-05-01T23:59:59.000Z

315

Annual Energy Outlook Retrospective Review: Evaluation of 2011 and Prior Reference Case Projections  

Gasoline and Diesel Fuel Update (EIA)

Annual Energy Outlook Annual Energy Outlook Retrospective Review: Evaluation of 2011 and Prior Reference Case Projections March 2012 Independent Statistics & Analysis www.eia.gov U.S. Department of Energy Washington, DC 20585 U.S. Energy Information Administration | AEO Retrospective Review: Evaluation of 2011 and Prior Reference Case Projections i This report was prepared by the U.S. Energy Information Administration (EIA), the statistical and analytical agency within the U.S. Department of Energy. By law, EIA's data, analyses, and forecasts are independent of approval by any other officer or employee of the United States Government. The views in this report therefore should not be construed as representing those of the Department of Energy or

316

Microsoft PowerPoint - PNNL-Prior ODS work 1.pptx  

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

MA957 at PNNL for Fast MA957 at PNNL for Fast Reactor Application: Prior Work (to 2000) Presented by Curt Lavender K. S. Weil and G. J. Grant "Fe- Based ODS Alloys: Role and Future Applications" November 17-18, 2010 University of California, San Diego La Jolla, California Outline * Discussion of work performed prior 2000 * ODS MA957 for Liquid Metal Reactor Cladding tubes * Supplier development - to develop multiple sources for tubing * Security of supply for reactor operations * Characterization of ODS MA 957 * Production validation * NDE - not discussed * End closure joining - EM pulse joining was qualified - not discussed * Where ODS may be headed * What may be done to speed qualification Motivation/Objective * Motivation: US DOE sponsored work to develop improved fuel cladding materials for liquid fast metal

317

Generalized beta prior models on fraction defective in reliability test planning  

Science Conference Proceedings (OSTI)

In many reliability analyses, the probability of obtaining a defective unit in a production process should not be considered constant even though the process is stable and in control. Engineering experience or previous data of similar or related products ... Keywords: 62N03, 62N05, Average producer and consumer risks, Generalized beta distribution, Maximum entropy prior, Quantiles, Reliability demonstration sampling plan, Shifted exponential distribution

Arturo J. Fernández; Carlos J. Pérez-González

2012-07-01T23:59:59.000Z

318

Stratospheric Ozone Depletion: The Main Driver of Twentieth-Century Atmospheric Circulation Changes in the Southern Hemisphere  

Science Conference Proceedings (OSTI)

The importance of stratospheric ozone depletion on the atmospheric circulation of the troposphere is studied with an atmospheric general circulation model, the Community Atmospheric Model, version 3 (CAM3), for the second half of the twentieth ...

Lorenzo M. Polvani; Darryn W. Waugh; Gustavo J. P. Correa; Seok-Woo Son

2011-02-01T23:59:59.000Z

319

Assessment of the mechanical performance of the Westinghouse BWR control rod CR 99 at high depletion levels  

SciTech Connect

A long-term program assessing the mechanical performance of the Westinghouse BWR control rod CR 99 at high depletion levels has been performed. The scope of the program has mainly been based on the operation of four CR 99 Generation 2 control rods in demanding positions during 6 and 7 cycles in the Leibstadt Nuclear Power Plant (KKL) and on the detailed visual inspections and blade wing thickness measurements that were performed after the rods were discharged. By correlating statistically the blade wing thickness measurements to the appearance of irradiation-assisted stress corrosion cracking (IASCC), the probability of IASCC appearance as function of the blade wing swelling was estimated. In order to correlate the IASCC probability of a CR 99 to its depletion, the {sup 10}B depletion of the studied rods was calculated in detail on a local level with the stochastic Monte Carlo code MCNP in combination with the Westinghouse nodal code system PHOENIX4/POLCA7. Using this information coupled to the blade wing measurement data, a finite element model describing the blade wing swelling of an arbitrary CR 99 design as function of {sup 10}B depletion could then be generated. In the final step, these relationships were used to quantify the probability of IASCC appearance as function of the {sup 10}B depletion of the CR 99 Generations 2 and 3. Applying this detailed mapping of the CR 99 behavior at high depletion levels and using an on-line core monitoring system with explicit {sup 10}B depletion tracking capabilities will enable a reliable prediction of the probability for IASCC appearance, thus enhancing the optimized design and the sound operation of the CR 99 control rod. Another important outcome of the program was that it was clearly shown that no significant amount of boron leakage did occur through any of the detected IASCC cracks, despite the very high depletion levels achieved. (authors)

Seltborg, P.; Jinnestrand, M. [Westinghouse Electric Sweden AB, SE-721 63 Vaesteraas (Sweden)

2012-07-01T23:59:59.000Z

320

Aerosol Sampling System for Collection of Capstone Depleted Uranium Particles in a High-Energy Environment  

SciTech Connect

The Capstone Depleted Uranium Aerosol Study was undertaken to obtain aerosol samples resulting from a kinetic-energy cartridge with a large-caliber depleted uranium (DU) penetrator striking an Abrams or Bradley test vehicle. The sampling strategy was designed to (1) optimize the performance of the samplers and maintain their integrity in the extreme environment created during perforation of an armored vehicle by a DU penetrator, (2) collect aerosols as a function of time post-impact, and (3) obtain size-classified samples for analysis of chemical composition, particle morphology, and solubility in lung fluid. This paper describes the experimental setup and sampling methodologies used to achieve these objectives. Custom-designed arrays of sampling heads were secured to the inside of the target in locations approximating the breathing zones of the vehicle commander, loader, gunner, and driver. Each array was designed to support nine filter cassettes and nine cascade impactors mounted with quick-disconnect fittings. Shielding and sampler placement strategies were used to minimize sampler loss caused by the penetrator impact and the resulting fragments of eroded penetrator and perforated armor. A cyclone train was used to collect larger quantities of DU aerosol for chemical composition and solubility. A moving filter sample was used to obtain semicontinuous samples for depleted uranium concentration determination. Control for the air samplers was provided by five remotely located valve control and pressure monitoring units located inside and around the test vehicle. These units were connected to a computer interface chassis and controlled using a customized LabVIEW engineering computer control program. The aerosol sampling arrays and control systems for the Capstone study provided the needed aerosol samples for physicochemical analysis, and the resultant data were used for risk assessment of exposure to DU aerosol.

Holmes, Thomas D.; Guilmette, Raymond A.; Cheng, Yung-Sung; Parkhurst, MaryAnn; Hoover, Mark D.

2009-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "fully depleted prior" 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

Dynamics of coronal rain and descending plasma blobs in solar prominences: I. Fully ionised case  

E-Print Network (OSTI)

Observations of active regions and limb prominences often show cold, dense blobs descending with an acceleration smaller than that of free fall. The dynamics of these condensations falling in the solar corona is investigated in this paper using a simple fully ionised plasma model. We find that the presence of a heavy condensation gives rise to a dynamical rearrangement of the coronal pressure that results in the formation of a large pressure gradient that opposes gravity. Eventually this pressure gradient becomes so large that the blob acceleration vanishes or even points upwards. Then, the blob descent is characterised by an initial acceleration phase followed by an essentially constant velocity phase. These two stages can be identified in published time-distance diagrams of coronal rain events. Both the duration of the first stage and the velocity attained by the blob increase for larger values of the ratio of blob to coronal density, for larger blob mass, and for smaller coronal temperature. Dense blobs ar...

Oliver, R; Terradas, J; Zaqarashvili, T V; Khodachenko, M L

2013-01-01T23:59:59.000Z

322

Electronic structure of fully epitaxial Co2TiSn thin films  

SciTech Connect

In this article we report on the properties of thin films of the full Heusler compound Co{sub 2}TiSn prepared by DC magnetron co-sputtering. Fully epitaxial, stoichiometric films were obtained by deposition on MgO (001) substrates at substrate temperatures above 600 C. The films are well ordered in the L2{sub 1} structure, and the Curie temperature exceeds slightly the bulk value. They show a significant, isotropic magnetoresistance and the resistivity becomes strongly anomalous in the paramagnetic state. The films are weakly ferrimagnetic, with nearly 1 {mu}{sub B} on the Co atoms, and a small antiparallel Ti moment, in agreement with theoretical expectations. From comparison of x-ray absorption spectra on the Co L{sub 3,2} edges, including circular and linear magnetic dichroism, with ab initio calculations of the x-ray absorption and circular dichroism spectra we infer that the electronic structure of Co{sub 2}TiSn has essentially non-localized character. Spectral features that have not been explained in detail before, are explained here in terms of the final state band structure.

Meinert, Markus; Schmalhorst, Jan; Wulfmeier, Hendrik; Reiss, Gunter; Arenholz, Elke; Graf, Tanja; Felser, Claudia

2010-10-28T23:59:59.000Z

323

A fully covariant mean-field dynamo closure for numerical 3+1 resistive GRMHD  

E-Print Network (OSTI)

The powerful high-energy phenomena typically encountered in astrophysics invariably involve physical engines, like neutron stars and black hole accretion disks, characterized by a combination of highly magnetized plasmas, strong gravitational fields, and relativistic motions. In recent years numerical schemes for General Relativistic MHD (GRMHD) have been developed to model the multidimensional dynamics of such systems, including the possibility of an evolving spacetime. Such schemes have been also extended beyond the ideal limit including the effects of resistivity, in an attempt to model dissipative physical processes acting on small scales (sub-grid effects) over the global dynamics. Along the same lines, magnetic fields could be amplified by the presence of turbulent dynamo processes, as often invoked to explain the high values of magnetization required in accretion disks and neutron stars. Here we present, for the first time, a further extension to include the possibility of a mean-field dynamo action within the framework of numerical 3+1 (resistive) GRMHD. A fully covariant dynamo closure is proposed, in analogy with the classical theory, assuming a simple alpha-effect in the comoving frame. Its implementation into a finite-difference scheme for GRMHD in dynamical spacetimes [the X-ECHO code: (Bucciantini and Del Zanna 2011)] is described, and a set of numerical test is presented and compared with analytical solutions wherever possible.

N. Bucciantini; L. Del Zanna

2012-05-14T23:59:59.000Z

324

SNMSP II: A system to fully automate special nuclear materials accountability reporting for electric utilities  

SciTech Connect

The USNRC requires each licensee who is authorized to possess Special Nuclear Materials (SNM) to prepare and submit reports concerning SNM received, produced, possessed, transferred, consumed, disposed of, or lost. These SNM accountability reports, which need to be submitted twice a year, contain detailed information on the origin, quantity, and type of SNM for several locations. The amount of detail required makes these reports very time consuming and error prone when prepared manually. Yankee Atomic is developing an IBM PC-based computer code that fully automates the process of generating SNM accountability reports. The program, called SNMSP II, prints a number of summaries including facsimiles of the NRC/DOE-741, 742, 742C, and RW-859 reports in a format that can be submitted directly to the NRC/DOE. SNMSP II is menu-driven and is especially designed for people with little or no computer training. Input can be either from a mainframe-based corporate data base or manually through user-friendly screens. In addition, extensive quality assurance features are available to ensure the security and accuracy of the data. This paper discusses the major features of the code and describes its implementation at Yankee.

Pareto, V.; Venegas, R.

1987-07-01T23:59:59.000Z

325

Fully Nonlinear Edge Gyrokinetic Simulations of Kinetic Geodesic-Acoustic Modes and Boundary Flows  

Science Conference Proceedings (OSTI)

We present edge gyrokinetic neoclassical simulations of tokamak plasmas using the fully nonlinear (full-f) continuum code TEMPEST. A nonlinear Boltzmann model is used for the electrons. The electric field is obtained by solving the 2D gyrokinetic Poisson Equation. We demonstrate the following: (1) High harmonic resonances (n > 2) significantly enhance geodesic-acoustic mode (GAM) damping at high-q (tokamak safety factor), and are necessary to explain both the damping observed in our TEMPEST q-scans and experimental measurements of the scaling of the GAM amplitude with edge q{sub 95} in the absence of obvious evidence that there is a strong q dependence of the turbulent drive and damping of the GAM. (2) The kinetic GAM exists in the edge for steep density and temperature gradients in the form of outgoing waves, its radial scale is set by the ion temperature profile, and ion temperature inhomogeneity is necessary for GAM radial propagation. (3) The development of the neoclassical electric field evolves through different phases of relaxation, including GAMs, their radial propagation, and their long-time collisional decay. (4) Natural consequences of orbits in the pedestal and scrape-off layer region in divertor geometry are substantial non-Maxwellian ion distributions and flow characteristics qualitatively like those observed in experiments.

Xu, X Q; Belli, E; Bodi, K; Candy, J; Chang, C S; Cohen, B I; Cohen, R H; Colella, P; Dimits, A M; Dorr, M R; Gao, Z; Hittinger, J A; Ko, S; Krasheninnikov, S; McKee, G R; Nevins, W M; Rognlien, T D; Snyder, P B; Suh, J; Umansky, M V

2008-09-18T23:59:59.000Z

326

FULLY RESOLVED QUIET-SUN MAGNETIC FLUX TUBE OBSERVED WITH THE SUNRISE/IMAX INSTRUMENT  

SciTech Connect

Until today, the small size of magnetic elements in quiet-Sun areas has required the application of indirect methods, such as the line-ratio technique or multi-component inversions, to infer their physical properties. A consistent match to the observed Stokes profiles could only be obtained by introducing a magnetic filling factor that specifies the fraction of the observed pixel filled with magnetic field. Here, we investigate the properties of a small magnetic patch in the quiet Sun observed with the IMaX magnetograph on board the balloon-borne telescope SUNRISE with unprecedented spatial resolution and low instrumental stray light. We apply an inversion technique based on the numerical solution of the radiative transfer equation to retrieve the temperature stratification and the field strength in the magnetic patch. The observations can be well reproduced with a one-component, fully magnetized atmosphere with a field strength exceeding 1 kG and a significantly enhanced temperature in the mid to upper photosphere with respect to its surroundings, consistent with semi-empirical flux tube models for plage regions. We therefore conclude that, within the framework of a simple atmospheric model, the IMaX measurements resolve the observed quiet-Sun flux tube.

Lagg, A.; Solanki, S. K.; Riethmueller, T. L.; Schuessler, M.; Hirzberger, J.; Feller, A.; Borrero, J. M.; Barthol, P.; Gandorfer, A. [Max-Planck-Institut fuer Sonnensystemforschung, Max-Planck-Strasse 2, 37191 Katlenburg-Lindau (Germany); MartInez Pillet, V.; Bonet, J. A. [Instituto de Astrofisica de Canarias, C/Via Lactea s/n, 38200 La Laguna, Tenerife (Spain); Schmidt, W.; Berkefeld, T. [Kiepenheuer-Institut fuer Sonnenphysik, Schoeneckstrasse 6, 79104 Freiburg (Germany); Del Toro Iniesta, J. C. [Instituto de Astrofisica de AndalucIa (CSIC), Apartado de Correos 3004, 18080 Granada (Spain); Domingo, V. [Grupo de AstronomIa y Ciencias del Espacio, Universidad de Valencia, 46980 Paterna, Valencia (Spain); Knoelker, M. [High Altitude Observatory, National Center for Atmospheric Research, P.O. Box 3000, Boulder, CO 80307-3000 (United States); Title, A. M., E-mail: lagg@mps.mpg.d [Lockheed Martin Solar and Astrophysics Laboratory, Bldg. 252, 3251 Hanover Street, Palo Alto, CA 94304 (United States)

2010-11-10T23:59:59.000Z

327

Assessing the risk from the depleted uranium weapons used in Operation Allied Force  

E-Print Network (OSTI)

The conflict in Yugoslavia has been a source of great concern for the neighboring countries, about the radiological and toxic hazard posed by the alleged presence of depleted uranium in NATO weapons. In the present study a worst-case scenario is assumed mainly to assess the risk for Greece and other neighboring countries of Yugoslavia at similar distances . The risk of the weapons currently in use is proved to be negligible at distances greater than 100 Km. For shorter distances classified data of weapons composition are needed to obtain a reliable assessment.

Liolios, T E

1999-01-01T23:59:59.000Z

328

Methods of and apparatus for recording images occurring just prior to a rapid, random event  

DOE Patents (OSTI)

An apparatus and a method are disclosed for recording images of events in a medium wherein the images that are recorded are of conditions existing just prior to and during the occurrence of an event that triggers recording of these images. The apparatus and method use an optical delay path that employs a spherical focusing mirror facing a circular array of flat return mirrors around a central flat mirror. The image is reflected in a symmetric pattern which balances astigmatism which is created by the spherical mirror. Delays on the order of hundreds of nanoseconds are possible.

Kelley, Edward F. (Montpelier, ID)

1994-01-01T23:59:59.000Z

329

Construction of an informative hierarchical prior distribution. Application to electricity load forecasting  

E-Print Network (OSTI)

In this paper, we are interested in the estimation and prediction of a parametric model on a short dataset upon which it is expected to overfit and perform badly. To overcome the lack of data (relatively to the dimension of the model) we propose the construction of a hierarchical informative Bayesian prior based upon another longer dataset which is assumed to share some similarities with the original, short dataset. We apply the methodology to a basic model for the electricity load forecasting on both simulated and real datasets, where it leads to a substantial improvement of the quality of the predictions.

Launay, Tristan; Lamarche, Sophie

2012-01-01T23:59:59.000Z

330

Methods of and apparatus for recording images occurring just prior to a rapid, random event  

DOE Patents (OSTI)

An apparatus and a method are disclosed for recording images of events in a medium wherein the images that are recorded are of conditions existing just prior to and during the occurrence of an event that triggers recording of these images. The apparatus and method use an optical delay path that employs a spherical focusing mirror facing a circular array of flat return mirrors around a central flat mirror. The image is reflected in a symmetric pattern which balances astigmatism which is created by the spherical mirror. Delays on the order of hundreds of nanoseconds are possible.

Kelley, E.F.

1991-12-31T23:59:59.000Z

331

Irrigation Depletions 1928-1989 : 1990 Level of Irrigation, Snake Yakima and Deschutes River Basins.  

DOE Green Energy (OSTI)

The vast amount of irrigation in relation to the available water and extensive system of reservoirs located in the Snake River Basin above Brownlee reservoir precludes this area from using methods such as Blaney-Criddle for estimating irrigation depletions. Also the hydrology, irrigation growth patterns, and water supply problems are unique and complex. Therefore regulation studies were utilized to reflect the net effect on streamflow of the changes in irrigated acreage in terms of corresponding changes in storage regulation and in the amount of water depleted and diverted from and returned to the river system. The regulation study for 1990 conditions was conducted by the Idaho Department of Water Resources. The end product of the basin simulation is 61 years of regulated flows at various points in the river system that are based on 1990 conditions. Data used by the Idaho Department of Water Resources is presented in this section and includes natural gains to the river system and diversions from the river system based on a 1990 level of development and operation criteria. Additional information can be obtained for an Idaho Department of Water Resources Open-File Report ``Stream Flows in the Snake River Basin 1989 Conditions of Use and Management`` dated June 1991. Similar considerations apply to the Yakima and Deschutes river basins.

United States. Bonneville Power Administation; A.G. Crook Company

1993-07-01T23:59:59.000Z

332

Depleted uranium hexafluoride (DUF{sub 6}) management system--a decision tool  

Science Conference Proceedings (OSTI)

The Depleted Uranium Hexafluoride (DUF{sub 6}) Management System (DMS) is being developed as a decision tool to provide cost and risk data for evaluation of short-and long-term management strategies for depleted uranium. It can be used to assist decision makers on a programmatic or site-specific level. Currently, the DMS allows evaluation of near-term cylinder management strategies such as storage yard improvements, cylinder restocking, and reconditioning. The DMS has been designed to provide the user with maximum flexibility for modifying data and impact factors (e.g., unit costs and risk factors). Sensitivity analysis can be performed on all key parameters such as cylinder corrosion rate, inspection frequency, and impact factors. Analysis may be conducted on a system-wide, site, or yard basis. The costs and risks from different scenarios may be compared in graphic or tabular format. Ongoing development of the DMS will allow similar evaluation of long-term management strategies such as conversion to other chemical forms. The DMS is a Microsoft Windows 3.1 based, stand-alone computer application. It can be operated on a 486 or faster computer with VGA, 4 MB of RAM, and 10 MB of disk space.

Gasper, J.R.; Sutter, R.J.; Avci, H.I. [and others

1995-12-31T23:59:59.000Z

333

Econometric Modelling of World Oil Supplies: Terminal Price and the Time to Depletion  

E-Print Network (OSTI)

This paper develops a novel approach by which to identify the price of oil at the time of depletion; the so-called "terminal price " of oil. It is shown that while the terminal price is independent of both GDP growth and the price elasticity of energy demand, it is dependent on the world real interest rate and the total life-time stock of oil resources, as well as on the marginal extraction and scarcity cost parameters. The theoretical predictions of this model are evaluated using data on the cost of extraction, cumulative production, and proven reserves. The predicted terminal prices seem sensible for a range of parameters and variables, as illustrated by the sensitivity analysis. Using the terminal price of oil, we calculate the time to depletion, and determine the extraction and price pro…les over the life-time of the resource. The extraction pro…les generated seem to be in line with the actual production and the predicted prices are generally in line with those currently observed.

Kamiar Mohaddes

2013-01-01T23:59:59.000Z

334

Summary of the cost analysis report for the long-term management of depleted uranium hexafluoride  

SciTech Connect

This report is a summary of the Cost Analysis Report which provides comparative cost data for the management strategy alternatives. The PEIS and the Cost Analysis Report will help DOE select a management strategy. The Record of Decision, expected in 1998, will complete the first part of the Depleted Uranium Hexafluoride Management Program. The second part of the Program will look at specific sites and technologies for carrying out the selected strategy. The Cost Analysis Report estimates the primary capital and operating costs for the different alternatives. It reflects the costs of technology development construction of facilities, operation, and decontamination and decommissioning. It also includes potential revenues from the sale of by-products such as anhydrous hydrogen fluoride (ABF). These estimates are based on early designs. They are intended to help in comparing alternatives, rather than to indicate absolute costs for project budgets or bidding purposes. More detailed estimates and specific funding sources will be considered in part two of the Depleted Uranium Hexafluoride Management Program.

Dubrin, J.W.; Rahm-Crites, L.

1997-09-01T23:59:59.000Z

335

Neutronics studies of uranium-based fully ceramic micro-encapsulated fuel for PWRs  

Science Conference Proceedings (OSTI)

This study evaluates the core neutronics and fuel cycle characteristics using uranium-based fully ceramic micro-encapsulated (FCM) fuel in a pressurized water reactor (PWR). Specific PWR assembly designs with FCM fuel have been developed, which by virtue of their TRISO particle-based elements are expected to achieve higher fuel burnups while also increasing the tolerance to fuel failures. The SCALE 6.1 code package, developed and maintained at ORNL, was the primary software used to model the assembly designs. Analysis was performed using the SCALE double-heterogeneous (DH) fuel modeling capabilities; however, the Reactivity-Equivalent Physical Transformation (RPT) method was used for lattice calculations due to the long run times associated with the SCALE DH capability. In order to understand the impact on reactivity and reactor operating cycle length, a parametric study was performed by varying TRISO particle design features, such as kernel diameter, coating layer thicknesses, and packing fraction. Also, other features such as the selection of matrix material (SiC, zirconium) and fuel rod dimensions were studied. After evaluating different uranium-based fuels, the higher compound density of uranium mononitride (UN) proved to be favorable, as the parametric studies showed that the FCM particle fuel design will need roughly 12% additional fissile material in comparison to that of a standard UO{sub 2} rod in order to match the lifetime of an 18-month PWR cycle. Neutronically, the FCM fuel designs evaluated maintain acceptable design features in the areas of fuel lifetime and temperature coefficients of reactivity, as well as pin cell and assembly peaking factors. (authors)

George, N. M.; Maldonado, I. [Dept. of Nuclear Engineering, Univ. of Tennessee Knoxville, Knoxville, TN 37996-2300 (United States); Terrani, K.; Godfrey, A.; Gehin, J. [Oak Ridge National Laboratory, Oak Ridge, TN 37831 (United States)

2012-07-01T23:59:59.000Z

336

Fully kinetic simulations of magnetic reconnction in semi-collisional plasmas  

SciTech Connect

The influence of Coulomb collisions on the dynamics of magnetic reconnection is examined using fully kinetic simulations with a Monte-Carlo treatment of the Fokker-Planck collision operator. This powerful first-principles approach offers a bridge between kinetic and fluid regimes, which may prove useful for understanding the applicability of various fluid models. In order to lay the necessary groundwork, the collision algorithm is first carefully bench marked for a homogeneous plasma against theoretical predictions for beam-plasma interactions and electrical resistivity. Next, the collisional decay of a current layer is examined as a function of guide field, allowing direct comparisons with transport theory for the parallel and perpendicular resistivity as well as the thermoelectric force. Finally, the transition between collisional and collision less reconnection is examined in neutral sheet geometry. For modest Lundquist numbers S {approx}< 1000, a distinct transition is observed when the thickness of the Sweet-Parker layers falls below the ion inertia length {delta}{sub sp} {approx}< d,. At higher Lundquist number, deviations from the Sweet-Parker scaling are observed due to the growth of plasmoids (secondary-islands) within the elongated resistive layer. In certain cases, this instability leads to the onset of fast reconnection sooner than expected from {delta}{sub sp} {approx} d, condition. After the transition to fast reconnection, elongated electron current layers are formed which are unstable to the formation of new plasmoids. The structure and time-dependence of the electron diffusion region in these semi-collisional regimes is profoundly different than reported in two-fluid simulations.

Daughton, William S [Los Alamos National Laboratory; Roytershteyn, Vadim S [Los Alamos National Laboratory; Albright, Brian J [Los Alamos National Laboratory; Yin, Lin [Los Alamos National Laboratory; Bowers, Kevin J [Los Alamos National Laboratory; Karimabadi, Homa [UCSD

2009-01-01T23:59:59.000Z

337

Hydrocarbon characterization experiments in fully turbulent fires : results and data analysis.  

SciTech Connect

As the capabilities of numerical simulations increase, decision makers are increasingly relying upon simulations rather than experiments to assess risks across a wide variety of accident scenarios including fires. There are still, however, many aspects of fires that are either not well understood or are difficult to treat from first principles due to the computational expense. For a simulation to be truly predictive and to provide decision makers with information which can be reliably used for risk assessment the remaining physical processes must be studied and suitable models developed for the effects of the physics. The model for the fuel evaporation rate in a liquid fuel pool fire is significant because in well-ventilated fires the evaporation rate largely controls the total heat release rate from the fire. This report describes a set of fuel regression rates experiments to provide data for the development and validation of models. The experiments were performed with fires in the fully turbulent scale range (> 1 m diameter) and with a number of hydrocarbon fuels ranging from lightly sooting to heavily sooting. The importance of spectral absorption in the liquid fuels and the vapor dome above the pool was investigated and the total heat flux to the pool surface was measured. The importance of convection within the liquid fuel was assessed by restricting large scale liquid motion in some tests. These data sets provide a sound, experimentally proven basis for assessing how much of the liquid fuel needs to be modeled to enable a predictive simulation of a fuel fire given the couplings between evaporation of fuel from the pool and the heat release from the fire which drives the evaporation.

Suo-Anttila, Jill Marie; Blanchat, Thomas K.

2011-03-01T23:59:59.000Z

338

Testing and Modeling of a 3-MW Wind Turbine Using Fully Coupled Simulation Codes (Poster)  

DOE Green Energy (OSTI)

This poster describes the NREL/Alstom Wind testing and model verification of the Alstom 3-MW wind turbine located at NREL's National Wind Technology Center. NREL,in collaboration with ALSTOM Wind, is studying a 3-MW wind turbine installed at the National Wind Technology Center(NWTC). The project analyzes the turbine design using a state-of-the-art simulation code validated with detailed test data. This poster describes the testing and the model validation effort, and provides conclusions about the performance of the unique drive train configuration used in this wind turbine. The 3-MW machine has been operating at the NWTC since March 2011, and drive train measurements will be collected through the spring of 2012. The NWTC testing site has particularly turbulent wind patterns that allow for the measurement of large transient loads and the resulting turbine response. This poster describes the 3-MW turbine test project, the instrumentation installed, and the load cases captured. The design of a reliable wind turbine drive train increasingly relies on the use of advanced simulation to predict structural responses in a varying wind field. This poster presents a fully coupled, aero-elastic and dynamic model of the wind turbine. It also shows the methodology used to validate the model, including the use of measured tower modes, model-to-model comparisons of the power curve, and mainshaft bending predictions for various load cases. The drivetrain is designed to only transmit torque to the gearbox, eliminating non-torque moments that are known to cause gear misalignment. Preliminary results show that the drivetrain is able to divert bending loads in extreme loading cases, and that a significantly smaller bending moment is induced on the mainshaft compared to a three-point mounting design.

LaCava, W.; Guo, Y.; Van Dam, J.; Bergua, R.; Casanovas, C.; Cugat, C.

2012-06-01T23:59:59.000Z

339

Use of depleted uranium metal as cask shielding in high-level waste storage, transport, and disposal systems  

SciTech Connect

The US DOE has amassed over 555,000 metric tons of depleted uranium from its uranium enrichment operations. Rather than dispose of this depleted uranium as waste, this study explores a beneficial use of depleted uranium as metal shielding in casks designed to contain canisters of vitrified high-level waste. Two high-level waste storage, transport, and disposal shielded cask systems are analyzed. The first system employs a shielded storage and disposal cask having a separate reusable transportation overpack. The second system employs a shielded combined storage, transport, and disposal cask. Conceptual cask designs that hold 1, 3, 4 and 7 high-level waste canisters are described for both systems. In all cases, cask design feasibility was established and analyses indicate that these casks meet applicable thermal, structural, shielding, and contact-handled requirements. Depleted uranium metal casting, fabrication, environmental, and radiation compatibility considerations are discussed and found to pose no serious implementation problems. About one-fourth of the depleted uranium inventory would be used to produce the casks required to store and dispose of the nearly 15,400 high-level waste canisters that would be produced. This study estimates the total-system cost for the preferred 7-canister storage and disposal configuration having a separate transportation overpack would be $6.3 billion. When credits are taken for depleted uranium disposal cost, a cost that would be avoided if depleted uranium were used as cask shielding material rather than disposed of as waste, total system net costs are between $3.8 billion and $5.5 billion.

Yoshimura, H.R.; Ludwigsen, J.S.; McAllaster, M.E. [and others

1996-09-01T23:59:59.000Z

340

Detection of an outburst one year prior to the explosion of SN 2011ht  

E-Print Network (OSTI)

Using imaging from the Pan-STARRS1 survey, we identify a precursor outburst at epochs 287 and 170 days prior to the reported explosion of the purported Type IIn supernova (SN) 2011ht. In the Pan-STARRS data, a source coincident with SN 2011ht is detected exclusively in the \\zps\\ and \\yps-bands. An absolute magnitude of M$_z\\simeq$-11.8 suggests that this was an outburst of the progenitor star. Unfiltered, archival Catalina Real Time Transient survey images also reveal a coincident source from at least 258 to 138 days before the main event. We suggest that the outburst is likely to be an intrinsically red eruption, although we cannot conclusively exclude a series of erratic outbursts which were observed only in the redder bands by chance. This is only the fourth detection of an outburst prior to a claimed SN, and lends credence to the possibility that many more interacting transients have pre-explosion outbursts, which have been missed by current surveys.

Fraser, M; Kotak, R; Smartt, S J; Smith, K W; Polshaw, J; Drake, A J; Boles, T; Lee, C -H; Burgett, W S; Chambers, K C; Draper, P W; Flewelling, H; Hodapp, K W; Kaiser, N; Kudritzki, R -P; Magnier, E A; Price, P A; Tonry, J L; Wainscoat, R J; Waters, C

2013-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "fully depleted prior" 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

D0 Decomissioning : Storage of Depleted Uranium Modules Inside D0 Calorimeters after the Termination of D0 Experiment  

Science Conference Proceedings (OSTI)

Dzero liquid Argon calorimeters contain hadronic modules made of depleted uranium plates. After the termination of DO detector's operation, liquid Argon will be transferred back to Argon storage Dewar, and all three calorimeters will be warmed up. At this point, there is no intention to disassemble the calorimeters. The depleted uranium modules will stay inside the cryostats. Depleted uranium is a by-product of the uranium enrichment process. It is slightly radioactive, emits alpha, beta and gamma radiation. External radiation hazards are minimal. Alpha radiation has no external exposure hazards, as dead layers of skin stop it; beta radiation might have effects only when there is a direct contact with skin; and gamma rays are negligible - levels are extremely low. Depleted uranium is a pyrophoric material. Small particles (such as shavings, powder etc.) may ignite with presence of Oxygen (air). Also, in presence of air and moisture it can oxidize. Depleted uranium can absorb moisture and keep oxidizing later, even after air and moisture are excluded. Uranium oxide can powder and flake off. This powder is also pyrographic. Uranium oxide may create health problems if inhaled. Since uranium oxide is water soluble, it may enter the bloodstream and cause toxic effects.

Sarychev, Michael; /Fermilab

2011-09-21T23:59:59.000Z

342

NEUTRONICS STUDIES OF URANIUM-BASED FULLY CERAMIC MICRO-ENCAPSULATED FUEL FOR PWRs  

Science Conference Proceedings (OSTI)

This study evaluates the core neutronics and fuel cycle characteristics that result from employing uranium-based fully ceramic micro-encapsulated (FCM) fuel in a pressurized water reactor (PWR). Specific PWR bundle designs with FCM fuel have been developed, which by virtue of their TRISO particle based elements, are expected to safely reach higher fuel burnups while also increasing the tolerance to fuel failures. The SCALE 6.1 code package, developed and maintained at ORNL, was the primary software employed to model these designs. Analysis was performed using the SCALE double-heterogeneous (DH) fuel modeling capabilities. For cases evaluated with the NESTLE full-core three-dimensional nodal simulator, because the feature to perform DH lattice physics branches with the SCALE/TRITON sequence is not yet available, the Reactivity-Equivalent Physical Transformation (RPT) method was used as workaround to support the full core analyses. As part of the fuel assembly design evaluations, fresh feed lattices were modeled to analyze the within-assembly pin power peaking. Also, a color-set array of assemblies was constructed to evaluate power peaking and power sharing between a once-burned and a fresh feed assembly. In addition, a parametric study was performed by varying the various TRISO particle design features; such as kernel diameter, coating layer thicknesses, and packing fractions. Also, other features such as the selection of matrix material (SiC, Zirconium) and fuel rod dimensions were perturbed. After evaluating different uranium-based fuels, the higher physical density of uranium mononitride (UN) proved to be favorable, as the parametric studies showed that the FCM particle fuel design will need roughly 12% additional fissile material in comparison to that of a standard UO2 rod in order to match the lifetime of an 18-month PWR cycle. Neutronically, the FCM fuel designs evaluated maintain acceptable design features in the areas of fuel lifetime, temperature coefficients of reactivity, as well as pin cell and assembly peaking factors. Key Words: FCM, TRISO, Uranium Mononitride, PWR

George, Nathan M [ORNL; Maldonado, G Ivan [ORNL; Terrani, Kurt A [ORNL; Gehin, Jess C [ORNL; Godfrey, Andrew T [ORNL

2012-01-01T23:59:59.000Z

343

FAQ 32-What are the potential health risks from conversion of depleted  

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

conversion of depleted uranium hexafluoride to other forms? conversion of depleted uranium hexafluoride to other forms? What are the potential health risks from conversion of depleted uranium hexafluoride to other forms? Accidental release of UF6 during processing activities could result in injuries. The most immediate hazard from a release would be lung injury or death from inhalation of hydrogen fluoride (HF), a highly corrosive gas formed when UF6 reacts with moisture in air. Uranyl fluoride is also formed. Uranyl fluoride is a particulate that can be dispersed in air and inhaled. Once inhaled, uranyl fluoride is easily absorbed into the bloodstream because it is soluble. If large quantities are inhaled, kidney toxicity will result. Conversion of uranium hexafluoride to oxide or metal may involve hazardous chemicals in addition to UF6; specifically, ammonia (NH3) may be used in the process, and HF may be produced from the process. In the PEIS, the conversion accidents estimated to have the largest potential consequences were accidents involving the rupture of tanks containing either anhydrous HF or ammonia. Such an accident could be caused by a large earthquake. The probability of large earthquakes depends on the location of the facility, and the probability of damage depends on the structural characteristics of the buildings. In the PEIS, the estimated frequency of this type of accident was less than once in one million years. However, if such an extremely unlikely accident did occur, it was estimated that up to 41,000 members of the general public around the conversion facility might experience adverse effects from chemical exposures (mostly mild and temporary effects, such as respiratory irritation or temporary decrease in kidney function). Of these, up to 1,700 individuals might experience irreversible adverse effects (such as lung damage or kidney damage), with the potential for about 30 fatalities. In addition, irreversible or fatal effects among workers very near the accident scene would be possible. (Note: The actual numbers of injuries among the general public would depend on the size and proximity of the population around the conversion facility).

344

This paper describes the energy consideration of fully wireless and mobile-wired sensor system and presented the prototype of  

E-Print Network (OSTI)

-minimization, ease of usage and ease of further development. Finally we have described the energy optimized clusterABSTRACT This paper describes the energy consideration of fully wireless and mobile-wired sensor will not deteriorate even a few sensors do not function. The typical example of a wireless sensor system is to have

Halgamuge, Malka N.

345

A second-order accurate immersed boundary method for fully resolved simulations of particle-laden flows  

Science Conference Proceedings (OSTI)

An immersed boundary method (IBM) with second-order spatial accuracy is presented for fully resolved simulations of incompressible viscous flows laden with rigid particles. The method is based on the computationally efficient direct-forcing method of ... Keywords: Finite-volume method, Grid locking, Immersed boundary method, Multidirect forcing scheme, Order of grid convergence, Particle-laden flow, Retraction distance

Wim-Paul Breugem

2012-05-01T23:59:59.000Z

346

A Low-Power Multimedia SoC with Fully Programmable 3D Graphics for Mobile Devices  

Science Conference Proceedings (OSTI)

A low-power multimedia SoC integrates a fully programmable 3D graphics for mobile devices with an MPEG4/JPEG codec and H.264 decoder for mobile devices. A mobile unified shader achieves programmable vertex shading and pixel shading in a single die, reducing ... Keywords: Mobile multimedia SoC, programmable, 3D graphics, mobile unified shader, low-power design

Jeong-Ho Woo; Ju-Ho Sohn; Hyejung Kim; Hoi-Jun Yoo

2009-09-01T23:59:59.000Z

347

An accurate performance model of fully adaptive routing in wormhole-switched two-dimensional mesh multicomputers  

Science Conference Proceedings (OSTI)

Numerous analytical performance models have been proposed for deterministic wormhole-routed mesh networks while only a single model, to our best knowledge, has been suggested for fully adaptive wormhole routing in mesh interconnection networks. This ... Keywords: Adaptive wormhole routing, Analytical modeling, Interconnection network, Meshes, Multicomputer, Performance evaluation

H. Hashemi-Najafabadi; H. Sarbazi-Azad; P. Rajabzadeh

2007-11-01T23:59:59.000Z

348

Development of a fully-consistent reduced order model to study instabilities in boiling water reactors  

SciTech Connect

A simple nonlinear Reduced Order Model to study global, regional and local instabilities in Boiling Water Reactors is described. The ROM consists of three submodels: neutron-kinetic, thermal-hydraulic and heat-transfer models. The neutron-kinetic model allows representing the time evolution of the three first neutron kinetic modes: the fundamental, the first and the second azimuthal modes. The thermal-hydraulic model describes four heated channels in order to correctly simulate out-of-phase behavior. The coupling between the different submodels is performed via both void and Doppler feedback mechanisms. After proper spatial homogenization, the governing equations are discretized in the time-domain. Several modifications, compared to other existing ROMs, have been implemented, and are reported in this paper. One novelty of the ROM is the inclusion of both azimuthal modes, which allows to study combined instabilities (in-phase and out-of-phase), as well as to investigate the corresponding interference effects between them. The second modification concerns the precise estimation of so-called reactivity coefficients or C{sub mn}{sup *V,D} - coefficients by using direct cross-section data from SIMULATE-3 combined with the CORE SIM core simulator in order to calculate Eigenmodes. Furthermore, a non-uniform two-step axial power profile is introduced to simulate the separate heat production in the single and two-phase regions, respectively. An iterative procedure was developed to calculate the solution to the coupled neutron-kinetic/thermal-hydraulic static problem prior to solving the time-dependent problem. Besides, the possibility of taking into account the effect of local instabilities is demonstrated in a simplified manner. The present ROM is applied to the investigation of an actual instability that occurred at the Swedish Forsmark-1 BWR in 1996/1997. The results generated by the ROM are compared with real power plant measurements performed during stability tests and show a good qualitative agreement. The present study provides some insight in a deeper understanding of the physical principles which drive both core-wide and local instabilities. (authors)

Dykin, V.; Demaziere, C. [Chalmers Univ. of Technology, Div. of Nuclear Engineering, Dept. of Applied Physics, SE-412 96 Gothenburg (Sweden)

2012-07-01T23:59:59.000Z

349

Undetected Sources Allow Transmission of the Lyman-alpha Line From Galaxies Prior to Reionization  

E-Print Network (OSTI)

The discovery of Lyman-alpha emission from galaxies at redshifts beyond z~6.5 should not be naively interpreted as implying that the intergalactic medium (IGM) had been reionized at higher redsifts. We show that a cluster of faint undetected sources around each observed galaxy generates an HII region sufficiently large to allow transmission of the galaxy's Lyman-alpha line prior to reionization. We also show that quasars may contribute a significant fraction of the ionizing photons to HII regions around galaxies with a velocity dispersion larger than ~100km/s. These contributing quasars are not usually seen due to the small fraction of time they spend in a luminous phase.

Stuart Wyithe; Abraham Loeb

2004-07-08T23:59:59.000Z

350

Depleted Uranium Hexafluoride Management Program: Data Compilation for the Paducah Site  

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

9 9 Depleted Uranium Hexafluoride Management Program: Data Compilation for the Paducah Site in Support of Site-Specific NEPA Requirements for Continued Cylinder Storage, Cylinder Preparation, Conversion, and Long-Term Storage Activities Environmental Assessment Division Argonne National Laboratory Operated by The University of Chicago, under Contract W-31-109-Eng-38, for the United States Department of Energy Argonne National Laboratory Argonne National Laboratory, with facilities in the states of Illinois and Idaho, is owned by the United States Government and operated by The University of Chicago under the provisions of a contract with the Department of Energy. This technical memorandum is a product of Argonne's Environmental Assessment Division (EAD). For information on the division's scientific and engineering

351

RUNNING OUT OF AND INTO OIL: ANALYZING GLOBAL OIL DEPLETION AND TRANSITION THROUGH 2050  

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

9 9 RUNNING OUT OF AND INTO OIL: ANALYZING GLOBAL OIL DEPLETION AND TRANSITION THROUGH 2050 October 2003 David L. Greene Corporate Fellow Janet L. Hopson Research Assistant Jia Li Senior Research Technician DOCUMENT AVAILABILITY Reports produced after January 1, 1996, are generally available free via the U.S. Department of Energy (DOE) Information Bridge: Web site: http://www.osti.gov/bridge Reports produced before January 1, 1996, may be purchased by members of the public from the following source: National Technical Information Service 5285 Port Royal Road Springfield, VA 22161 Telephone: 703-605-6000 (1-800-553-6847) TDD: 703-487-4639 Fax: 703-605-6900 E-mail: info@ntis.fedworld.gov Web site: http://www.ntis.gov/support/ordernowabout.htm

352

Conclusions of the Capstone Depleted Uranium Aerosol Characterization and Risk Assessment Study  

Science Conference Proceedings (OSTI)

The rationale for the Capstone Depleted Uranium (DU) Aerosol Characterization and Risk Assessment Program and its results and applications have been examined in the previous 13 articles of this special issue. This paper summarizes the results and discusses its successes and lessons learned. The robust data from the Capstone DU Aerosol Study have provided a sound basis for assessing the inhalation exposure to DU aerosols and the dose and risk to personnel in combat vehicles at the time of perforation and to those entering immediately after perforation. The Human Health Risk Assessment provided a technically sound process for evaluating chemical and radiological doses and risks from DU aerosol exposure using well-accepted biokinetic and dosimetric models innovatively applied. An independent review of the study process and results is summarized, and recommendations for possible avenues of future study by the authors and by other major reviews of DU health hazards are provided.

Parkhurst, MaryAnn; Guilmette, Raymond A.

2009-02-26T23:59:59.000Z

353

Assessing the risk from the depleted Uranium weapons used in Operation Allied Force.  

E-Print Network (OSTI)

The conflict in Yugoslavia has been a source of great concern due to the radiological and toxic hazard posed by the alleged presence of depleted uranium in NATO weapons. In the present study some worst-case scenaria are assumed in order to assess the risk for Yugoslavia and its neighboring countries. The risk is proved to be negligible for the neighboring countries while for Yugoslavia itself evidence is given that any increase in total long-term cancer mortality will be so low that it will remain undetected. Local radioactive hotspots such as DU weapons fragments and abandoned battle tanks, fortified or contaminated with DU, constitute a post-war hazard which is not studied in this article.

unknown authors

1999-01-01T23:59:59.000Z

354

Revenue ruling 73-538: the service's assault on percentage depletion for ''D'' miners  

SciTech Connect

In this article, the author examines the Internal Revenue Service's ruling that storage and loading for shipment at the mine site are nonmining processes for ores and minerals described in section 613(c)(4)(D) of the Internal Revenue Code. He explains the tax consequences of the ruling and discusses the correctness of the position taken by the Internal Revenue Service in light of the relevant case law and the language and legislative history of the statute. The effect of the ruling is to reduce the percentage depletion deduction available to many miners of ores and minerals described in section 613(c)(4)(D), including miners of lead, zinc, copper, gold, silver, uranium, fluorspar, potash, soda ash, garnet and tungsten. (JMT)

Barnes, D.A.

1983-01-01T23:59:59.000Z

355

A Process for Reducing the Licensing Burden for New Products Containing Depleted Uranium  

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

3-01 3-01 A Process for Reducing the Licensing Burden for New Products Containing Depleted Uranium Environmental Assessment Division Argonne National Laboratory Operated by The University of Chicago, under Contract W-31-109-Eng-38, for the United States Department of Energy Argonne National Laboratory, a U.S. Department of Energy Office of Science laboratory, is operated by The University of Chicago under contract W-31-109-Eng-38. DISCLAIMER 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 The University of Chicago, nor any of their employees or officers, makes any warranty, express or implied, or assumes

356

Running Out of and Into Oil: Analyzing Global Oil Depletion and Transition Through 2050  

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

L. Greene, Janet L. Hopson, and Jia Li L. Greene, Janet L. Hopson, and Jia Li A risk analysis is presented of the peaking of world conventional oil pro- duction and the likely transition to unconventional oil resources such as oil sands, heavy oil, and shale oil. Estimates of world oil resources by the U.S. Geological Survey (USGS) and C. J. Campbell provide alternative views of ultimate world oil resources. A global energy scenario created by the International Institute of Applied Systems Analysis and the World Energy Council provides the context for the risk analysis. A model of oil resource depletion and expansion for 12 world regions is combined with a market equilibrium model of conventional and unconventional oil sup- ply and demand. The model does not use Hubbert curves. Key variables

357

SR/OIAF/2000-04 Accelerated Depletion: Assessing Its Impacts  

Gasoline and Diesel Fuel Update (EIA)

4 4 Accelerated Depletion: Assessing Its Impacts on Domestic Oil and Natural Gas Prices and Production July 2000 Energy Information Administration Office of Integrated Analysis and Forecasting U.S. Department of Energy Washington, DC 20585 This report was prepared by the Energy Information Administration, the independent statistical and analytical agency within the Department of Energy. The information contained herein should be attributed to the Energy Information Administration and should not be construed as advocating or reflecting any policy position of the Department of Energy or of any other organization. Service Reports are prepared by the Energy Information Administration upon special request and are based on assumptions specified by the requester. Contacts This report was prepared by the staff of the Office of Integrated Analysis and Forecasting of the Energy

358

Grid orientation effects in the simulation of cold water injection into depleted vapor zones  

DOE Green Energy (OSTI)

A considerable body of field experience with injection has been accumulated at Larderello, Italy and The Geysers, California; the results have been mixed. There are well documented cases where injection has increased flow rates of nearby wells. Return of injected fluid as steam from production wells has been observed directly through chemical and isotopic changes of produced fluids (Giovannoni et al., 1981; Nuti et al., 1981). In other cases injection has caused thermal interference and has degraded the temperature and pressure of production wells. Water injection into depleted vapor zones gives rise to complex two-phase fluid flow and heat transfer processes with phase change. These are further complicated by the fractured-porous nature of the reservoir rocks. An optimization of injection design and operating practice is desirable; this requires realistic and robust mathematical modeling capabilities.

Pruess, K.

1991-01-01T23:59:59.000Z

359

Oxidation of depleted uranium penetrators and aerosol dispersal at high temperatures  

SciTech Connect

Aerosols dispersed from depleted uranium penetrators exposed to air and air-CO/sub 2/ mixtures at temperatures ranging from 500 to 1000/sup 0/C for 2- or 4-h periods were characterized. These experiments indicated dispersal of low concentrations of aerosols in the respirable size range (typically <10/sup -3/% of penetrator mass at 223 cm/s (5 mph) windspeed). Oxidation was maximum at 700/sup 0/C in air and 800/sup 0/C in 50% air-50% CO/sub 2/, indicating some self-protection developed at higher temperatures. No evidence of self-sustained burning was observed, although complete oxidation can be expected in fires significantly exceeding 4 h, the longest exposure of this series. An outdoor burning experiment using 10 batches of pine wood and paper packing material as fuel caused the highest oxidation rate, probably accelerated by disruption of the oxide layer accompanying broad temperature fluctuation as each fuel batch was added.

Elder, J.C.; Tinkle, M.C.

1980-12-01T23:59:59.000Z

360

?Just-in-Time? Battery Charge Depletion Control for PHEVs and E-REVs for Maximum Battery Life  

SciTech Connect

Conventional methods of vehicle operation for Plug-in Hybrid Vehicles first discharge the battery to a minimum State of Charge (SOC) before switching to charge sustaining operation. This is very demanding on the battery, maximizing the number of trips ending with a depleted battery and maximizing the distance driven on a depleted battery over the vehicle s life. Several methods have been proposed to reduce the number of trips ending with a deeply discharged battery and also eliminate the need for extended driving on a depleted battery. An optimum SOC can be maintained for long battery life before discharging the battery so that the vehicle reaches an electric plug-in destination just as the battery reaches the minimum operating SOC. These Just-in-Time methods provide maximum effective battery life while getting virtually the same electricity from the grid.

DeVault, Robert C [ORNL

2009-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "fully depleted prior" 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

Delayed neutron measurements for Th-232, Np-237, Pu-239, Pu-241 and depleted uranium  

E-Print Network (OSTI)

The neutron emission rates from five very pure actinide samples (Th-232, Np-237, Pu-239, Pu-241 and depleted uranium) were measured following equilibrium irradiation in fast and thermal neutron fluxes. The relative abundances (alphas) for the first four groups were calculated from the delayed neutron emission (counts vs. time) data using Keepin's 6-group decay constants (lambdas) for Th-232, Pu-239 and depleted uranium (both fast and thermal neutron induced fissions). The relative abundances (alphas) for the first five groups were calculated for the fast neutron induced fission of Np-237 using the 7-group lambdas obtained by Charlton (1997). The relative abundances for the first five groups were also calculated using the 7-group lambdas proposed by Loaiza and Haskin (2000), the 8-group lambdas proposed by Campbell and Spriggs (1998) and the 8-group lambdas proposed by Piksaikin (2000) for all of the samples (fast neutron induced fission only for Th-232 and Np-237, fast and thermal neutron induced fission for the remainder). Fission product yield and delayed neutron emission probability data from the ENDF-349 and JEF 2.2 nuclear data libraries were also used to simulate neutron emission data from the samples. The calculated neutron yield curves were used to obtain group relative abundances for each of the five actinide samples (fast neutron induced fission only for Th-232 and Np-237, fast and thermal neutron induced fission for the remainder) based on each set of proposed lambdas. The relative abundances obtained from the experiments and calculations are compared and the differences are noted and discussed.

Stone, Joseph C.

2001-01-01T23:59:59.000Z

362

Physicochemical Characterization of Capstone Depleted Uranium Aerosols II: Particle Size Distributions as a Function of Time  

SciTech Connect

The Capstone Depleted Uranium (DU) Aerosol Study, which generated and characterized aerosols containing depleted uranium from perforation of armored vehicles with large-caliber DU penetrators, incorporated a sampling protocol to evaluated particle size distributions. Aerosol particle size distribution is an important parameter that influences aerosol transport and deposition processes as well as the dosimetry of the inhaled particles. These aerosols were collected on cascade impactor substrates using a pre-established time sequence following the firing event to analyze the uranium concentration and particle size of the aerosols as a function of time. The impactor substrates were analyzed using beta spectrometry, and the derived uranium content of each served as input to the evaluation of particle size distributions. Activity median aerodynamic diameters (AMADs) of the particle size distributions were evaluated using unimodal and bimodal models. The particle size data from the impactor measurements was quite variable. Most size distributions measured in the test based on activity had bimodal size distributions with a small particle size mode in the range of between 0.2 and 1.2 um and a large size mode between 2 and 15 um. In general, the evolution of particle size over time showed an overall decrease of average particle size from AMADs of 5 to 10 um shortly after perforation to around 1 um at the end of the 2-hr sampling period. The AMADs generally decreased over time because of settling. Additionally, the median diameter of the larger size mode decreased with time. These results were used to estimate the dosimetry of inhaled DU particles.

Cheng, Yung-Sung; Kenoyer, Judson L.; Guilmette, Raymond A.; Parkhurst, MaryAnn

2009-03-01T23:59:59.000Z

363

Environmental acceptability of high-performance alternatives for depleted uranium penetrators  

SciTech Connect

The Army`s environmental strategy for investigating material substitution and management is to measure system environmental gains/losses in all phases of the material management life cycle from cradle to grave. This study is the first in a series of new investigations, applying material life cycle concepts, to evaluate whether there are environmental benefits from increasing the use of tungsten as an alternative to depleted uranium (DU) in Kinetic Energy Penetrators (KEPs). Current military armor penetrators use DU and tungsten as base materials. Although DU alloys have provided the highest performance of any high-density alloy deployed against enemy heavy armor, its low-level radioactivity poses a number of environmental risks. These risks include exposures to the military and civilian population from inhalation, ingestion, and injection of particles. Depleted uranium is well known to be chemically toxic (kidney toxicity), and workplace exposure levels are based on its renal toxicity. Waste materials containing DU fragments are classified as low-level radioactive waste and are regulated by the Nuclear Regulatory Commission. These characteristics of DU do not preclude its use in KEPs. However, long-term management challenges associated with KEP deployment and improved public perceptions about environmental risks from military activities might be well served by a serious effort to identify, develop, and substitute alternative materials that meet performance objectives and involve fewer environmental risks. Tungsten, a leading candidate base material for KEPS, is potentially such a material because it is not radioactive. Tungsten is less well studied, however, with respect to health impacts and other environmental risks. The present study is designed to contribute to the understanding of the environmental behavior of tungsten by synthesizing available information that is relevant to its potential use as a penetrator.

Kerley, C.R.; Easterly, C.E.; Eckerman, K.F. [and others] [and others

1996-08-01T23:59:59.000Z

364

Preconceptual design studies and cost data of depleted uranium hexafluoride conversion plants  

SciTech Connect

One of the more important legacies left with the Department of Energy (DOE) after the privatization of the United States Enrichment Corporation is the large inventory of depleted uranium hexafluoride (DUF6). The DOE Office of Nuclear Energy, Science and Technology (NE) is responsible for the long-term management of some 700,000 metric tons of DUF6 stored at the sites of the two gaseous diffusion plants located at Paducah, Kentucky and Portsmouth, Ohio, and at the East Tennessee Technology Park in Oak Ridge, Tennessee. The DUF6 management program resides in NE's Office of Depleted Uranium Hexafluoride Management. The current DUF6 program has largely focused on the ongoing maintenance of the cylinders containing DUF6. However, the long-term management and eventual disposition of DUF6 is the subject of a Programmatic Environmental Impact Statement (PEIS) and Public Law 105-204. The first step for future use or disposition is to convert the material, which requires construction and long-term operation of one or more conversion plants. To help inform the DUF6 program's planning activities, it was necessary to perform design and cost studies of likely DUF6 conversion plants at the preconceptual level, beyond the PEIS considerations but not as detailed as required for conceptual designs of actual plants. This report contains the final results from such a preconceptual design study project. In this fast track, three month effort, Lawrence Livermore National Laboratory and Bechtel National Incorporated developed and evaluated seven different preconceptual design cases for a single plant. The preconceptual design, schedules, costs, and issues associated with specific DUF6 conversion approaches, operating periods, and ownership options were evaluated based on criteria established by DOE. The single-plant conversion options studied were similar to the dry-conversion process alternatives from the PEIS. For each of the seven cases considered, this report contains information on the conversion process, preconceptual plant description, rough capital and operating costs, and preliminary project schedule.

Jones, E

1999-07-26T23:59:59.000Z

365

Cadmium Depletion Impacts on Hardening Neutron6 Spectrum for Advanced Fuel Testing in ATR  

SciTech Connect

For transmuting long-lived isotopes contained in spent nuclear fuel into shorter-lived fission products effectively is in a fast neutron spectrum reactor. In the absence of a fast spectrum test reactor in the United States of America (USA), initial irradiation testing of candidate fuels can be performed in a thermal test reactor that has been modified to produce a test region with a hardened neutron spectrum. A test region is achieved with a Cadmium (Cd) filter which can harden the neutron spectrum to a spectrum similar (although still somewhat softer) to that of the liquid metal fast breeder reactor (LMFBR). A fuel test loop with a Cd-filter has been installed within the East Flux Trap (EFT) of the Advanced Test Reactor (ATR) at the Idaho National Laboratory (INL). A detailed comparison analyses between the cadmium (Cd) filter hardened neutron spectrum in the ATR and the LMFBR fast neutron spectrum have been performed using MCWO. MCWO is a set of scripting tools that are used to couple the Monte Carlo transport code MCNP with the isotope depletion and buildup code ORIGEN-2.2. The MCWO-calculated results indicate that the Cd-filter can effectively flatten the Rim-Effect and reduce the linear heat rate (LHGR) to meet the advanced fuel testing project requirements at the beginning of irradiation (BOI). However, the filtering characteristics of Cd as a strong absorber quickly depletes over time, and the Cd-filter must be replaced for every two typical operating cycles within the EFT of the ATR. The designed Cd-filter can effectively depress the LHGR in experimental fuels and harden the neutron spectrum enough to adequately flatten the Rim Effect in the test region.

Gray S. Chang

2011-05-01T23:59:59.000Z

366

MODULAR AND FULL SIZE SIMPLIFIED BOILING WATER REACTOR DESIGN WITH FULLY PASSIVE SAFETY SYSTEMS  

SciTech Connect

OAK B204 The overall goal of this three-year research project was to develop a new scientific design of a compact modular 200 MWe and a full size 1200 MWe simplified boiling water reactors (SBWR). Specific objectives of this research were: (1) to perform scientific designs of the core neutronics and core thermal-hydraulics for a small capacity and full size simplified boiling water reactor, (2) to develop a passive safety system design, (3) improve and validate safety analysis code, (4) demonstrate experimentally and analytically all design functions of the safety systems for the design basis accidents (DBA) and (5) to develop the final scientific design of both SBWR systems, 200 MWe (SBWR-200) and 1200 MWe (SBWR-1200). The SBWR combines the advantages of design simplicity and completely passive safety systems. These advantages fit well within the objectives of NERI and the Department of Energy's focus on the development of Generation III and IV nuclear power. The 3-year research program was structured around seven tasks. Task 1 was to perform the preliminary thermal-hydraulic design. Task 2 was to perform the core neutronic design analysis. Task 3 was to perform a detailed scaling study and obtain corresponding PUMA conditions from an integral test. Task 4 was to perform integral tests and code evaluation for the DBA. Task 5 was to perform a safety analysis for the DBA. Task 6 was to perform a BWR stability analysis. Task 7 was to perform a final scientific design of the compact modular SBWR-200 and the full size SBWR-1200. A no cost extension for the third year was requested and the request was granted and all the project tasks were completed by April 2003. The design activities in tasks 1, 2, and 3 were completed as planned. The existing thermal-hydraulic information, core physics, and fuel lattice information was collected on the existing design of the simplified boiling water reactor. The thermal-hydraulic design were developed. Based on a detailed integral system scaling analysis, design parameters were obtained and designs of the compact modular 200 MWe SBWR and the full size 1200 MWe SBWR were developed. These reactors are provided with passive safety systems. A new passive vacuum breaker check valve was designed to replace the mechanical vacuum beaker check valve. The new vacuum breaker check valve was based on a hydrostatic head, and was fail safe. The performance of this new valve was evaluated both by the thermal-hydraulic code RELAP5 and by the experiments in a scaled SBWR facility, PUMA. In the core neutronic design a core depletion model was implemented to PARCS code. A lattice design for the SBWR fuel assemblies was performed. Design improvements were made to the neutronics/thermal-hydraulics models of SBWR-200 and SBWR-1200, and design analyses of these reactors were performed. The design base accident analysis and evaluation of all the passive safety systems were completed as scheduled in tasks 4 and 5. Initial conditions for the small break loss of coolant accidents (LOCA) and large break LOCA using REALP5 code were obtained. Small and large break LOCA tests were performed and the data was analyzed. An anticipated transient with scram was simulated using the RELAP5 code for SBWR-200. The transient considered was an accidental closure of the main steam isolation valve (MSIV), which was considered to be the most significant transient. The evaluation of the RELAP5 code against experimental data for SBWR-1200 was completed. In task 6, the instability analysis for the three SBWR designs (SBWR-1200, SBWR-600 and SBWR-200) were simulated for start-up transients and the results were similar. Neither the geysering instability, nor the loop type instability was predicted by RAMONA-4B in the startup simulation following the recommended procedure by GE. The density wave oscillation was not observed at all because the power level used in the simulation was not high enough. A study was made of the potential instabilities by imposing an unrealistically high power ramp in a short time period, as suggested by GE. RAMON

M. Ishii; S. T. Revankar; T. Downar; Y. Xu, H. J. Yoon; D. Tinkler; U. S. Rohatgi

2003-06-16T23:59:59.000Z

367

Advanced Fuels for LWRs: Fully-Ceramic Microencapsulated and Related Concepts FY 2012 Interim Report  

Science Conference Proceedings (OSTI)

This report summarizes the progress in the Deep Burn project at Idaho National Laboratory during the first half of fiscal year 2012 (FY2012). The current focus of this work is on Fully-Ceramic Microencapsulated (FCM) fuel containing low-enriched uranium (LEU) uranium nitride (UN) fuel kernels. UO2 fuel kernels have not been ruled out, and will be examined as later work in FY2012. Reactor physics calculations confirmed that the FCM fuel containing 500 mm diameter kernels of UN fuel has positive MTC with a conventional fuel pellet radius of 4.1 mm. The methodology was put into place and validated against MCNP to perform whole-core calculations using DONJON, which can interpolate cross sections from a library generated using DRAGON. Comparisons to MCNP were performed on the whole core to confirm the accuracy of the DRAGON/DONJON schemes. A thermal fluid coupling scheme was also developed and implemented with DONJON. This is currently able to iterate between diffusion calculations and thermal fluid calculations in order to update fuel temperatures and cross sections in whole-core calculations. Now that the DRAGON/DONJON calculation capability is in place and has been validated against MCNP results, and a thermal-hydraulic capability has been implemented in the DONJON methodology, the work will proceed to more realistic reactor calculations. MTC calculations at the lattice level without the correct burnable poison are inadequate to guarantee zero or negative values in a realistic mode of operation. Using the DONJON calculation methodology described in this report, a startup core with enrichment zoning and burnable poisons will be designed. Larger fuel pins will be evaluated for their ability to (1) alleviate the problem of positive MTC and (2) increase reactivity-limited burnup. Once the critical boron concentration of the startup core is determined, MTC will be calculated to verify a non-positive value. If the value is positive, the design will be changed to require less soluble boron by, for example, increasing the reactivity hold-down by burnable poisons. Then, the whole core analysis will be repeated until an acceptable design is found. Calculations of departure from nucleate boiling ratio (DNBR) will be included in the safety evaluation as well. Once a startup core is shown to be viable, subsequent reloads will be simulated by shuffling fuel and introducing fresh fuel. The PASTA code has been updated with material properties of UN fuel from literature and a model for the diffusion and release of volatile fission products from the SiC matrix material . Preliminary simulations have been performed for both normal conditions and elevated temperatures. These results indicated that the fuel performs well and that the SiC matrix has a good retention of the fission products. The path forward for fuel performance work includes improvement of metallic fission product release from the kernel. Results should be considered preliminary and further validation is required.

R. Sonat Sen; Brian Boer; John D. Bess; Michael A. Pope; Abderrafi M. Ougouag

2012-03-01T23:59:59.000Z

368

Portsmouth DUF6 Conversion Final EIS - Appendix D: Environmental Synopsis for the Depleted UF6 Conversion Project  

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

Portsmouth DUF Portsmouth DUF 6 Conversion Final EIS APPENDIX D: ENVIRONMENTAL SYNOPSIS FOR THE DEPLETED UF 6 CONVERSION PROJECT Environmental Synopsis D-2 Portsmouth DUF 6 Conversion Final EIS ENVIRONMENTAL SYNOPSIS FOR THE DEPLETED UF 6 CONVERSION PROJECT (Solicitation No. DE-RP05-01OR22717) October 2002 Environmental Assessment Division Argonne National Laboratory Argonne, Illinois Prepared for Office of Site Closure - Oak Ridge Office (EM-32) Office of Environmental Management U.S. Department of Energy Washington, D.C. October 2002 iii CONTENTS 1 INTRODUCTION........................................................................................................... 1 2 BACKGROUND.............................................................................................................

369

Paducah DUF6 Conversion Final EIS - Appendix D: Environmental Synopsis for the Depleted UF6 Conversion Project  

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

Paducah DUF Paducah DUF 6 Conversion Final EIS APPENDIX D: ENVIRONMENTAL SYNOPSIS FOR THE DEPLETED UF 6 CONVERSION PROJECT Environmental Synopsis D-2 Paducah DUF 6 Conversion Final EIS ENVIRONMENTAL SYNOPSIS FOR THE DEPLETED UF 6 CONVERSION PROJECT (Solicitation No. DE-RP05-01OR22717) October 2002 Environmental Assessment Division Argonne National Laboratory Argonne, Illinois Prepared for Office of Site Closure - Oak Ridge Office (EM-32) Office of Environmental Management U.S. Department of Energy Washington, D.C. October 2002 iii CONTENTS 1 INTRODUCTION........................................................................................................... 1 2 BACKGROUND............................................................................................................. 3 3

370

Copyright! 2010!No!part!of!this!presentation!may!be! reproduced!in!any!form!without!prior!authorization.  

E-Print Network (OSTI)

!Power!Research!Institute!(EPRI),!and!support!from!EPRI,!NSF,! and!ORNL!for!my!graduate!students' doctoral!research!is!gratefully!acknowledged. Canada"U.S.!Workshop!on!Smart!Grid!prior!authorization. Smart!Grid:!Tsunami!of!Data!Developing New!devices!in!the!home enabled!by!the!smart!meter You!prior!authorization. "Smart!Grid" Components!&!Devices Google!Power!Meter Smart!Meters Source:!IBM!Smart!Grid! Secure!Smart!Grids

Amin, S. Massoud

371

62369Federal Register / Vol. 75, No. 195 / Friday, October 8, 2010 / Notices with otter trawls that are fully  

E-Print Network (OSTI)

­6, a Categorical Exclusion or other appropriate NEPA document would be completed prior to the issuance of the EFP national policies as set forth by the President and the Congress. The agenda will include a TIP update) improve the accuracy, timing, and quality of fisheries data. VerDate Mar2010 15:29 Oct 07, 2010 Jkt

Magee, Joseph W.

372

Proposal for the award of a contract for the supply of 5 mm depleted-uranium plates for the UA1 calorimeter upgrading  

E-Print Network (OSTI)

Proposal for the award of a contract for the supply of 5 mm depleted-uranium plates for the UA1 calorimeter upgrading

1986-01-01T23:59:59.000Z

373

Proposal for the award of a contract for the supply of 5 mm depleted-uranium plates for the UA1 experiment  

E-Print Network (OSTI)

Proposal for the award of a contract for the supply of 5 mm depleted-uranium plates for the UA1 experiment

1986-01-01T23:59:59.000Z

374

A fully integrated switched-capacitor DC-DC converter with dual output for low power application  

Science Conference Proceedings (OSTI)

This paper presents a fully integrated on-chip switched-capacitor (SC) DC-DC converter that supports two regulated power supply voltages of 2.2V and 3.2V from 5V input supply and delivers the maximum load currents up to 8mA at both of the outputs. The ... Keywords: dc-dc converter, dual output, switched-capacitor

Heungjun Jeon; Yong-Bin Kim

2012-05-01T23:59:59.000Z

375

Chloride removal from plutonium-aluminum alloy dissolver solution prior to purex solvent extraction  

Science Conference Proceedings (OSTI)

The Savannah River Plant (SRP), operated by E. I. du Pont de Nemours Co. for the United States Department of Energy, has successfully recovered plutonium from plutonium-aluminum alloy processed through the F-Canyon Separations facility. The alloy, produced at the Rocky Flats Plant, results from recovery of plutonium residues from spent chloride salts from pyrochemical processing. The alloy, termed scrub alloy'' or Rocky Flats scrub alloy'' (RFSA), contains up to 15 weight percent chloride impurity prior to mercuric ion catalyzed dissolution with fluoride-containing nitric acid. Solutions containing 850 to 3000 {mu}g/mL (parts per million) of chloride result. During subsequent Purex solvent extraction of this solution with 30% tri-n-butyl phosphate in normal paraffin diluent, chloride is rejected to the aqueous waste stream. This stream is eventually evaporated for waste treatment and acid recovery. Chloride concentrations in the product streams, subject to further processing, must be less than 100 {mu}g/mL to prevent excessive corrosion of equipment. This paper describes scrub alloy production at RFP, its dissolution and head end treatment to remove chloride, chloride values in subsequent processing streams including environmental discharges, and the turbidimetric analysis technique. 2 tabs.

Holcomb, H.P.

1990-01-01T23:59:59.000Z

376

CO2-Driven Enhanced Gas Recovery and Storage in Depleted Shale Reservoir-A Numerical Simulation Study  

E-Print Network (OSTI)

1 CO2-Driven Enhanced Gas Recovery and Storage in Depleted Shale Reservoir- A Numerical Simulation for storage and enhanced gas recovery may be organic-rich shales, which CO2 is preferentially adsorbed comprehensive simulation studies to better understand CO2 injection process in shale gas reservoir. This paper

Mohaghegh, Shahab

377

Experimental and simulation studies of sequestration of supercritical carbon dioxide in depleted gas reservoirs  

E-Print Network (OSTI)

he feasibility of sequestering supercritical CO2 in depleted gas reservoirs. The experimental runs involved the following steps. First, the 1 ft long by 1 in. diameter carbonate core is inserted into a viton Hassler sleeve and placed inside an aluminum coreholder that is then evacuated. Second, with or without connate water, the carbonate core is saturated with methane. Third, supercritical CO2 is injected into the core with 300 psi overburden pressure. From the volume and composition of the produced gas measured by a wet test meter and a gas chromatograph, the recovery of methane at CO2 breakthrough is determined. The core is scanned three times during an experimental run to determine core porosity and fluid saturation profile: at start of the run, at CO2 breakthrough, and at the end of the run. Runs were made with various temperatures, 20°C (68°F) to 80°C (176°F), while the cell pressure is varied, from 500 psig (3.55 MPa) to 3000 psig (20.79 MPa) for each temperature. An analytical study of the experimental results has been also conducted to determine the dispersion coefficient of CO2 using the convection-dispersion equation. The dispersion coefficient of CO2 in methane is found to be relatively low, 0.01-0.3 cm2/min.. Based on experimental and analytical results, a 3D simulation model of one eighth of a 5-spot pattern was constructed to evaluate injection of supercritical CO2 under typical field conditions. The depleted gas reservoir is repressurized by CO2 injection from 500 psi to its initial pressure 3,045 psi. Simulation results for 400 bbl/d CO2 injection may be summarized as follows. First, a large amount of CO2 is sequestered: (i) about 1.2 million tons in 29 years (0 % initial water saturation) to 0.78 million tons in 19 years (35 % initial water saturation) for 40-acre pattern, (ii) about 4.8 million tons in 112 years (0 % initial water saturation) to 3.1 million tons in 73 years (35 % initial water saturation) for 80-acre pattern. Second, a significant amount of natural gas is also produced: (i) about 1.2 BSCF or 74 % remaining GIP (0 % initial water saturation) to 0.78 BSCF or 66 % remaining GIP (35 % initial water saturation) for 40-acre pattern, (ii) about 4.5 BSCF or 64 % remaining GIP (0 % initial water saturation) to 2.97 BSCF or 62 % remaining GIP (35 % initial water saturation) for 80-acre pattern. This produced gas revenue could help defray the cost of CO2 sequestration. In short, CO2 sequestration in depleted gas reservoirs appears to be a win-win technology.

Seo, Jeong Gyu

2003-05-01T23:59:59.000Z

378

Effects of capillarity and vapor adsorption in the depletion of vapor-dominated geothermal reservoirs  

DOE Green Energy (OSTI)

Vapor-dominated geothermal reservoirs in natural (undisturbed) conditions contain water as both vapor and liquid phases. The most compelling evidence for the presence of distributed liquid water is the observation that vapor pressures in these systems are close to saturated vapor pressure for measured reservoir temperatures (White et al., 1971; Truesdell and White, 1973). Analysis of natural heat flow conditions provides additional, indirect evidence for the ubiquitous presence of liquid. From an analysis of the heat pipe process (vapor-liquid counterflow) Preuss (1985) inferred that effective vertical permeability to liquid phase in vapor-dominated reservoirs is approximately 10{sup 17} m{sup 2}, for a heat flux of 1 W/m{sup 2}. This value appears to be at the high end of matrix permeabilities of unfractured rocks at The Geysers, suggesting that at least the smaller fractures contribute to liquid permeability. For liquid to be mobile in fractures, the rock matrix must be essentially completely liquid-saturated, because otherwise liquid phase would be sucked from the fractures into the matrix by capillary force. Large water saturation in the matrix, well above the irreducible saturation of perhaps 30%, has been shown to be compatible with production of superheated steam (Pruess and Narasimhan, 1982). In response to fluid production the liquid phase will boil, with heat of vaporization supplied by the reservoir rocks. As reservoir temperatures decline reservoir pressures will decline also. For depletion of ''bulk'' liquid, the pressure would decline along the saturated vapor pressure curve, while for liquid held by capillary and adsorptive forces inside porous media, an additional decline will arise from ''vapor pressure lowering''. Capillary pressure and vapor adsorption effects, and associated vapor pressure lowering phenomena, have received considerable attention in the geothermal literature, and also in studies related to geologic disposal of heat generating nuclear wastes, and in the drying of porous materials. Geothermally oriented studies were presented by Chicoine et al. (1977), Hsieh and Ramey (1978, 1981), Herkelrath et al. (1983), and Nghiem and Ramey (1991). Nuclear waste-related work includes papers by Herkelrath and O'Neal (1985), Pollock (1986), Eaton and Bixler (1987), Pruess et al. (1990), Nitao (1990), and Doughty and E'ruess (1991). Applications to industrial drying of porous materials have been discussed by Hamiathy (1969) arid Whitaker (1977). This paper is primarily concerned with evaluating the impact of vapor pressure lowering (VPL) effects on the depletion behavior of vapor-dominated reservoirs. We have examined experimental data on vapor adsorption and capillary pressures in an effort to identify constitutive relationships that would be applicable to the tight matrix rocks of vapor-dominated systems. Numerical simulations have been performed to evaluate the impact of these effects on the depletion of vapor-dominated reservoirs.

Pruess, Karsten; O'Sullivan, Michael

1992-01-01T23:59:59.000Z

379

Depletion of FKBP does not affect the interaction between isolated ryanodine receptors  

SciTech Connect

The ryanodine receptors/calcium release channels (RyRs) usually form two dimensional regular lattices in the endoplasmic/sarcoplasmic reticulum membranes. The native RyR is associated with many auxiliary proteins, including FKBP. It has been indicated that FKBP may play a role in the intermolecular interaction and coupled gating of neighboring RyRs. However, a more recent study shows that FKBP12 is not involved in the physical linkage between neighboring RyR1s. In the present work, the effect of FKBP12 on the interaction between RyR1s isolated from rabbit skeletal muscle was investigated in an aqueous medium with photon correlation spectroscopy. We found that the depletion of FKBP12 did not affect the oligomerization of RyR1s in the medium containing different [KCl] or under different channel functional states. No evidence is obtained for the involvement of FKBP12 in the intermolecular interaction between RyR1s.

Hu Xiaofang [Bio-X Life Science Research Center, College of Life Science and Biotechnology, Shanghai Jiao Tong University, 1954 Hua-Shan Road, Shanghai 200030 (China); Liang Xin [Bio-X Life Science Research Center, College of Life Science and Biotechnology, Shanghai Jiao Tong University, 1954 Hua-Shan Road, Shanghai 200030 (China); Chen Keying [Bio-X Life Science Research Center, College of Life Science and Biotechnology, Shanghai Jiao Tong University, 1954 Hua-Shan Road, Shanghai 200030 (China); Zhu Peihong [Key Laboratory of Neuroscience, Shanghai Institutes for Biological Sciences, Chinese Academy of Sciences, 320 Yue-Yang Road, Shanghai 200031 (China); Hu Jun [Bio-X Life Science Research Center, College of Life Science and Biotechnology, Shanghai Jiao Tong University, 1954 Hua-Shan Road, Shanghai 200030 (China); Shanghai Institute of Applied Physics, Chinese Academy of Sciences, P.O. Box 800-204, Shanghai 201800 (China); E-mail: jhu@sjtu.edu.cn

2005-10-14T23:59:59.000Z

380

Proceedings of a workshop on uses of depleted uranium in storage, transportation and repository facilities  

SciTech Connect

A workshop on the potential uses of depleted uranium (DU) in the repository was organized to coordinate the planning of future activities. The attendees, the original workshop objective and the agenda are provided in Appendices A, B and C. After some opening remarks and discussions, the objectives of the workshop were revised to: (1) exchange information and views on the status of the Department of Energy (DOE) activities related to repository design and planning; (2) exchange information on DU management and planning; (3) identify potential uses of DU in the storage, transportation, and disposal of high-level waste and spent fuel; and (4) define the future activities that would be needed if potential uses were to be further evaluated and developed. This summary of the workshop is intended to be an integrated resource for planning of any future work related to DU use in the repository. The synopsis of the first day`s presentations is provided in Appendix D. Copies of slides from each presenter are presented in Appendix E.

NONE

1997-12-31T23:59:59.000Z

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381

REVIEW ARTICLE Depletion of atrial natriuretic peptide during longstanding atrial fibrillation  

E-Print Network (OSTI)

atrial fibrillation; heart failure; depletion; cardioversion; maze procedure Abstract This review focuses on the relation between atrial fibrillation (AF) and atrial natriuretic peptide (ANP). ANP is produced by the atria secondary to atrial stretch. By causing atrial stretch, acute AF leads to an increase in plasma ANP concentration, which serves to normalize haemodynamics through natriuresis and vasodilation. However, data have been reported suggesting that prolonged AF, by inflicting structural atrial damage, is associated with a reduced capacity by the atria to produce ANP. An inverse relation was thus demonstrated between the duration of AF and plasma ANP concentration. In addition, a reduced ANP response to exercise has been shown to be predictive of unsuccessful cardioversion of AF to sinus rhythm. Finally, ANP has also been shown to predict outcome after a maze operation. Outcome was poor when preoperative plasma ANP concentration was low. Moreover, a high atrial collagen content, as a measure of atrial degeneration, correlated with low ANP. These data indicate that ANP may serve as a marker of atrial integrity, which may help in selecting AF patients for therapeutic interventions. ª 2004 The European Society of Cardiology. Published by Elsevier Ltd. All rights reserved. Downloaded from

Maarten P. Van Den Berg; Isabelle C. Van Gelder; Dirk J. Van Veldhuisen

2004-01-01T23:59:59.000Z

382

Underground hydrogen storage. Final report. [Salt caverns, excavated caverns, aquifers and depleted fields  

DOE Green Energy (OSTI)

The technical and economic feasibility of storing hydrogen in underground storage reservoirs is evaluated. The past and present technology of storing gases, primarily natural gas is reviewed. Four types of reservoirs are examined: salt caverns, excavated caverns, aquifers, and depleted fields. A technical investigation of hydrogen properties reveals that only hydrogen embrittlement places a limit on the underground storage by hydrogen. This constraint will limit reservoir pressures to 1200 psi or less. A model was developed to determine economic feasibility. After making reasonable assumptions that a utility might make in determining whether to proceed with a new storage operation, the model was tested and verified on natural gas storage. A parameteric analysis was made on some of the input parameters of the model to determine the sensitivity of the cost of service to them. Once the model was verified it was used to compute the cost of service of storing hydrogen in the four reservoir types. The costs of service for hydrogen storage ranged from 26 to 150% of the cost of the gas stored. The study concludes that it is now both safe and economic to store hydrogen in underground reservoirs.

Foh, S.; Novil, M.; Rockar, E.; Randolph, P.

1979-12-01T23:59:59.000Z

383

Equilibrium cycle pin by pin transport depletion calculations with DeCART  

SciTech Connect

As the Advanced Fuel Cycle Initiative (AFCI) program has matured it has become more important to utilize more advanced simulation methods. The work reported here was performed as part of the AFCI fellowship program to develop and demonstrate the capability of performing high fidelity equilibrium cycle calculations. As part of the work here, a new multi-cycle analysis capability was implemented in the DeCART code which included modifying the depletion modules to perform nuclide decay calculations, implementing an assembly shuffling pattern description, and modifying iteration schemes. During the work, stability issues were uncovered with respect to converging simultaneously the neutron flux, isotopics, and fluid density and temperature distributions in 3-D. Relaxation factors were implemented which considerably improved the stability of the convergence. To demonstrate the capability two core designs were utilized, a reference UOX core and a CORAIL core. Full core equilibrium cycle calculations were performed on both cores and the discharge isotopics were compared. From this comparison it was noted that the improved modeling capability was not drastically different in its prediction of the discharge isotopics when compared to 2-D single assembly or 2-D core models. For fissile isotopes such as U-235, Pu-239, and Pu-241 the relative differences were 1.91%, 1.88%, and 0.59%), respectively. While this difference may not seem large it translates to mass differences on the order of tens of grams per assembly, which may be significant for the purposes of accounting of special nuclear material. (authors)

Kochunas, B.; Downar, T. [Dept. of Nuclear Engineering and Radiological Sciences, Univ. of Michigan, 2200 Bonisteel Blvd, Ann Arbor, MI 48109 (United States); Taiwo, T. [Argonne National Laboratory, 9700 S. Cass Ave, Argonne, IL 60439 (United States)

2012-07-01T23:59:59.000Z

384

Impacts of Deacetylation Prior to Dilute Acid Pretreatment on the Bioethanol Process  

Science Conference Proceedings (OSTI)

Dilute acid pretreatment is a promising pretreatment technology for the biochemical production of ethanol from lignocellulosic biomass. During dilute acid pretreatment, xylan depolymerizes to form soluble xylose monomers and oligomers. Because the xylan found in nature is highly acetylated, the formation of xylose monomers requires two steps: (1) cleavage of the xylosidic bonds, and (2) cleavage of covalently bonded acetyl ester groups. Results: In this study, we show that the latter may be the rate limiting step for xylose monomer formation. Furthermore, acetyl groups are also found to be a cause of biomass recalcitrance and hydrolyzate toxicity. While the removal of acetyl groups from native corn stover by alkaline de-esterification prior to pretreatment improves overall process yields, the exact impact is highly dependent on the corn stover variety in use. Xylose monomer yields in pretreatment generally increases by greater than 10%. Compared to pretreated corn stover controls, the deacetylated corn stover feedstock is approximately 20% more digestible after pretreatment. Finally, by lowering hydrolyzate toxicity, xylose utilization and ethanol yields are further improved during fermentation by roughly 10% and 7%, respectively. In this study, several varieties of corn stover lots were investigated to test the robustness of the deacetylation-pretreatment-saccharification-fermentation process. Conclusions: Deacetylation shows significant improvement on glucose and xylose yields during pretreatment and enzymatic hydrolysis, but it also reduces hydrolyzate toxicity during fermentation, thereby improving ethanol yields and titer. The magnitude of effect is dependent on the selected corn stover variety, with several varieties achieving improvements of greater than 10% xylose yield in pretreatment, 20% glucose yield in low solids enzymatic hydrolysis and 7% overall ethanol yield.

Chen, X.; Shekiro, J.; Franden, M. A.; Wang, W.; Johnson, D. K.; Zhang, M.; Kuhn, E.; Tucker, M. P.

2011-12-01T23:59:59.000Z

385

Bayesian inference through encompassing priors and importance sampling for a class of marginal models for categorical data  

E-Print Network (OSTI)

We develop a Bayesian approach for selecting the model which is the most supported by the data within a class of marginal models for categorical variables formulated through equality and/or inequality constraints on generalised logits (local, global, continuation or reverse continuation), generalised log-odds ratios and similar higher-order interactions. For each constrained model, the prior distribution of the model parameters is formulated following the encompassing prior approach. Then, model selection is performed by using Bayes factors which are estimated by an importance sampling method. The approach is illustrated through three applications involving some datasets, which also include explanatory variables. In connection with one of these examples, a sensitivity analysis to the prior specification is also considered.

Bartolucci, Francesco; Farcomeni, Alessio

2012-01-01T23:59:59.000Z

386

On using the WMAP distance priors in constraining the time evolving equation of state of dark energy  

E-Print Network (OSTI)

Recently, the WMAP group has published their five-year data and considered the constraints on the time evolving equation of state of dark energy for the first time from the "WMAP distance priors". In this paper, we study the effectiveness of the usage of these distance priors and find that these compressed CMB information can give similar constraints on dark energy parameters compared with the full CMB power spectrum if dark energy perturbation is included, however, once incorrectly neglecting the dark energy perturbation, the difference of the results is sizable.

Li, Hong; Zhao, Gong-Bo; Fan, Zu-Hui; Zhang, Xinmin

2008-01-01T23:59:59.000Z

387

An applied paleoecology case study: Bahia Grande, Texas prior to construction of the Brownsville Ship Channel  

E-Print Network (OSTI)

Bahia Grande is a large lagoon located within Laguna Atascosa National Wildlife Refuge in Cameron County, Texas. When the Brownsville Ship Channel was built along the southern end of the lagoon in 1936, Bahia Grande was cut off from the marine water of Laguna Madre. Since that time, Bahia Grande has been primarily dry with only ephemeral fresh water coming from heavy rainfall events, resulting in a severe decline in biological productivity. A restoration project led by the U.S. Fish and Wildlife Service has proposed to cut new channels between Bahia Grande and the Ship Channel to restore the connection with Laguna Madre. This is a large-scale project with major implications for the water quality, surrounding ecology, and associated biota in the region. Unfortunately, because very little is known about Bahia Grande prior to isolation, it is difficult to predict whether the results of the restoration will be comparable to the pre-Ship Channel environment. Paleoecological data provide the best opportunity to understand what Bahia Grande was like in the past. This study uses statistical analyses of the molluscan death assemblages from Bahia Grande to gain a better understanding of the environmental conditions in the lagoon before it was isolated. The first question addressed is how does Bahia Grande relate to other water bodies on the Texas coast? This may provide a modern analog to the past conditions in Bahia Grande. The second question inquires whether there are any local patterns or variations within Bahia Grande and several smaller surrounding lagoons. These results provide an important baseline for comparison with the restored lagoon. The results of this investigation show that, in a regional context, Bahia Grande was most similar to Alazan Bay and Baffin Bay, which are mostly enclosed shallow bays with high salinities due to the arid climate and limited freshwater inflow. Within Bahia Grande, there are several distinct molluscan assemblages. Salinity and water coverage are the most likely environmental factors responsible for the differences within Bahia Grande. Additionally, data from surrounding lagoons strongly indicate that some connections with Bahia Grande existed in the past.

Lichlyter, Stephen Alvah

2003-05-01T23:59:59.000Z

388

Developing fuel management capabilities based on coupled Monte Carlo depletion in support of the MIT Research Reactor (MITR) conversion  

E-Print Network (OSTI)

Pursuant to a 1986 NRC ruling, the MIT Reactor (MITR) is planning on converting from the use of highly enriched uranium (HEU) to low enriched uranium (LEU) for fuel. Prior studies have shown that the MITR will be able to ...

Romano, Paul K. (Paul Kollath)

2009-01-01T23:59:59.000Z

389

CORRELATION OF CRITICAL MASS DATA ON LIGHT WATER MODERATED, FULLY ENRICHED URANIUM, STAINLESS STEEL REACTORS. PART I  

SciTech Connect

Experimental data were collected on over 70 light water moderated, fully enriched uranium, stainless steel, critical cores. An equation for the critical mass of cores with a buckling of 0.007 cm/sup -2/ that is lineally dependent on stainless steel volume fraction and grams of B/sup 10/ was compared with available critical experiments and found to yield reasonable results. A correlation method, relating buckling to ( xi SIGMA /sub s// SIGMA /sub a/) was found to fit the available experiments. (auth)

Lee, D.H.

1962-07-17T23:59:59.000Z

390

Development of fully automated and integrated (''Instamatic'') welding systems for marine applications  

SciTech Connect

A two-year research program was conducted at M.I.T. to develop fully automated and integrated welding systems. These systems package many actions involved in welding so that certain prescribed welding jobs can be performed by a person with no welding skill. They have been nicknamed ''instamatic'' welding systems, since they are similar to the easy-to-operate cameras. Following a general discussion on the development of the concept of the ''instamatic'' welding system, discussions are given on two types of systems which have been built and tested: underwater stud welding systems, and those using arc welding processes.

Masubuchi, K.; Gustin, H.L.; Schloerb, D.W.

1983-05-01T23:59:59.000Z

391

Running Out of and Into Oil: Analyzing Global Oil Depletion and Transition Through 2050  

DOE Green Energy (OSTI)

This report presents a risk analysis of world conventional oil resource production, depletion, expansion, and a possible transition to unconventional oil resources such as oil sands, heavy oil and shale oil over the period 2000 to 2050. Risk analysis uses Monte Carlo simulation methods to produce a probability distribution of outcomes rather than a single value. Probability distributions are produced for the year in which conventional oil production peaks for the world as a whole and the year of peak production from regions outside the Middle East. Recent estimates of world oil resources by the United States Geological Survey (USGS), the International Institute of Applied Systems Analysis (IIASA), the World Energy Council (WEC) and Dr. C. Campbell provide alternative views of the extent of ultimate world oil resources. A model of oil resource depletion and expansion for twelve world regions is combined with a market equilibrium model of conventional and unconventional oil supply and demand to create a World Energy Scenarios Model (WESM). The model does not make use of Hubbert curves but instead relies on target reserve-to-production ratios to determine when regional output will begin to decline. The authors believe that their analysis has a bias toward optimism about oil resource availability because it does not attempt to incorporate political or environmental constraints on production, nor does it explicitly include geologic constraints on production rates. Global energy scenarios created by IIASA and WEC provide the context for the risk analysis. Key variables such as the quantity of undiscovered oil and rates of technological progress are treated as probability distributions, rather than constants. Analyses based on the USGS and IIASA resource assessments indicate that conventional oil production outside the Middle East is likely to peak sometime between 2010 and 2030. The most important determinants of the date are the quantity of undiscovered oil, the rate at which unconventional oil production can be expanded, and the rate of growth of reserves and enhanced recovery. Analysis based on data produced by Campbell indicates that the peak of non-Middle East production will occur before 2010. For total world conventional oil production, the results indicate a peak somewhere between 2020 and 2050. Key determinants of the peak in world oil production are the rate at which the Middle East region expands its output and the minimum reserves-to-production ratios producers will tolerate. Once world conventional oil production peaks, first oil sands and heavy oil from Canada, Venezuela and Russia, and later some other source such as shale oil from the United States must expand if total world oil consumption is to continue to increase. Alternative sources of liquid hydrocarbon fuels, such as coal or natural gas are also possible resources but not considered in this analysis nor is the possibility of transition to a hydrogen economy. These limitations were adopted to simplify the transition analysis. Inspection of the paths of conventional oil production indicates that even if world oil production does not peak before 2020, output of conventional oil is likely to increase at a substantially slower rate after that date. The implication is that there will have to be increased production of unconventional oil after that date if world petroleum consumption is to grow.

Greene, D.L.

2003-11-14T23:59:59.000Z

392

Physicochemical Characterization of Capstone Depleted Uranium Aerosols III: Morphologic and Chemical Oxide Analyses  

Science Conference Proceedings (OSTI)

The impact of depleted uranium (DU) penetrators against an armored target causes erosion and fragmentation of the penetrators, the extent of which is dependent on the thickness and material composition of the target. Vigorous oxidation of the DU particles and fragments creates an aerosol of DU oxide particles and DU particle agglomerations combined with target materials. Aerosols from the Capstone DU aerosol study, in which vehicles were perforated by DU penetrators, were evaluated for their oxidation states using X-ray diffraction (XRD) and particle morphologies using scanning electron microscopy/energy dispersive spectrometry (SEM/EDS). The oxidation state of a DU aerosol is important as it offers a clue to its solubility in lung fluids. The XRD analysis showed that the aerosols evaluated were a combination primarily of U3O8 (insoluble) and UO3 (relatively more soluble) phases, though intermediate phases resembling U4O9 and other oxides were prominent in some samples. Analysis of particle residues in the micrometer-size range by SEM/EDS provided microstructural information such as phase composition and distribution, fracture morphology, size distribution, and material homogeneity. Observations from SEM analysis show a wide variability in the shapes of the DU particles. Some of the larger particles appear to have been fractured (perhaps as a result of abrasion and comminution); others were spherical, occasionally with dendritic or lobed surface structures. Amorphous conglomerates containing metals other than uranium were also common, especially with the smallest particle sizes. A few samples seemed to contain small chunks of nearly pure uranium metal, which were verified by EDS to have a higher uranium content exceeding that expected for uranium oxides. Results of the XRD and SEM/EDS analyses were used in other studies described in this issue of The Journal of Health Physics to interpret the results of lung solubility studies and in selecting input parameters for dose assessments.

Krupka, Kenneth M.; Parkhurst, MaryAnn; Gold, Kenneth; Arey, Bruce W.; Jenson, Evan D.; Guilmette, Raymond A.

2009-03-01T23:59:59.000Z

393

Barriers and Issues Related to Achieving Final Disposition of Depleted Uranium  

Science Conference Proceedings (OSTI)

Approximately 750,000 metric tons (MT) of surplus depleted uranium (DU) in various chemical forms are stored at several Department of Energy (DOE) sites throughout the United States. Most of the DU is in the form of DU hexafluoride (DUF6) that resulted from uranium enrichment operations over the last several decades. DOE plans to convert the DUF6 to ''a more stable form'' that could be any one or combination of DU tetrafluoride (DUF4 or green salt), DU oxide (DUO3, DUO2, or DU3O8), or metal depending on the final disposition chosen for any given quantity. Barriers to final disposition of this material have existed historically and some continue today. Currently, the barriers are more related to finding uses for this material versus disposing as waste. Even though actions are beginning to convert the DUF6, ''final'' disposition of the converted material has yet to be decided. Unless beneficial uses can be implemented, DOE plans to dispose of this material as waste. This expresses the main barrier to DU disposition; DOE's strategy is to dispose unless uses can be found while the strategy should be only dispose as a last resort and make every effort to find uses. To date, only minimal research programs are underway to attempt to develop non-fuel uses for this material. Other issues requiring resolution before these inventories can reach final disposition (uses or disposal) include characterization, disposal of large quantities, storage (current and future), and treatment options. Until final disposition is accomplished, these inventories must be managed in a safe and environmentally sound manner; however, this is becoming more difficult as materials and facilities age. The most noteworthy final disposition technical issues include the development of reuse and treatment options.

Gillas, D. L.; Chambers, B. K.

2002-02-26T23:59:59.000Z

394

Isotopic dilution of {sup 233}U with depleted uranium for criticality safety in processing and disposal  

SciTech Connect

The disposal of excess {sup 233}U as waste is being considered. Because {sup 233}U is a fissile material, a key requirement for processing {sup 233}U to a final waste form and disposing of it is the avoidance of nuclear criticality. For many processing and disposal options, isotopic dilution is the most feasible and preferred option to avoid nuclear criticality. Isotopic dilution is dilution of fissile {sup 233}U with nonfissile {sup 238}U. The use of isotopic dilution removes any need to control nuclear criticality in process or disposal facilities through geometry or chemical composition. Isotopic dilution allows the use of existing waste management facilities that are not designed for significant quantities of fissile materials to be used for processing and disposing of {sup 233}U. The amount of isotopic dilution required to reduce criticality concerns to reasonable levels was determined in this study to be approximately 0.53 wt % {sup 233}U. The numerical calculations used to define this limit consisted of a homogeneous system of silicon dioxide (SiO{sub 2}), water (H{sub 2}O), {sup 233}U and depleted uranium (DU) in which the ratio of each component was varied to learn the conditions of maximum nuclear reactivity. About 188 parts of DU (0.2 wt % {sup 235}U) are required to dilute 1 part of {sup 233}U to this limit in a water-moderated system with no SiO{sub 2} present. Thus for the U.S. inventory of {sup 233}U, several hundred metric tons of DU would be required for isotopic dilution.

Hopper, C.M.; Wright, R.Q.; Elam, K.R.; Forsberg, C.W.

1997-07-01T23:59:59.000Z

395

Draft Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Paducah, Kentucky, Site  

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

DRAFT ENVIRONMENTAL IMPACT DRAFT ENVIRONMENTAL IMPACT STATEMENT FOR CONSTRUCTION AND OPERATION OF A DEPLETED URANIUM HEXAFLUORIDE CONVERSION FACILITY AT THE PADUCAH, KENTUCKY, SITE DECEMBER 2003 U.S. Department of Energy-Oak Ridge Operations Office of Environmental Management Cover Sheet Paducah DUF 6 DEIS: December 2003 iii COVER SHEET RESPONSIBLE FEDERAL AGENCY: U.S. Department of Energy (DOE) TITLE: Draft Environmental Impact Statement (DEIS) for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Paducah, Kentucky, Site (DOE/EIS-0359) CONTACT: For further information on this environmental impact statement (EIS), contact: Gary S. Hartman DOE-ORO Cultural Resources Management Coordinator U.S. Department of Energy-Oak Ridge Operations P.O. Box 2001 Oak Ridge, TN 37831

396

Draft Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at Portsmouth, Ohio, Site  

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

DRAFT ENVIRONMENTAL IMPACT DRAFT ENVIRONMENTAL IMPACT STATEMENT FOR CONSTRUCTION AND OPERATION OF A DEPLETED URANIUM HEXAFLUORIDE CONVERSION FACILITY AT THE PORTSMOUTH, OHIO, SITE DECEMBER 2003 U.S. Department of Energy-Oak Ridge Operations Office of Environmental Management Cover Sheet Portsmouth DUF 6 DEIS: December 2003 iii COVER SHEET RESPONSIBLE FEDERAL AGENCY: U.S. Department of Energy (DOE) TITLE: Draft Environmental Impact Statement (DEIS) for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Portsmouth, Ohio, Site (DOE/EIS-0360) CONTACT: For further information on this environmental impact statement (EIS), contact: Gary S. Hartman DOE-ORO Cultural Resources Management Coordinator U.S. Department of Energy-Oak Ridge Operations P.O. Box 2001 Oak Ridge, TN 37831

397

Review of the Portsmouth Gaseous Diffusion Plant Work Planning and Control Activities Prior to Work Execution, January 2013  

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

Review of the Review of the Portsmouth Gaseous Diffusion Plant Work Planning and Control Activities Prior to Work Execution January 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Scope.................................................................................................................................................... 1 3.0 Background........................................................................................................................................... 1

398

Copyright! 2010!No!part!of!this!presentation!may!be! reproduced!in!any!form!without!prior!authorization.  

E-Print Network (OSTI)

electrical energy infrastructure ­ Transform!the!Network!into!a!Smart!Grid ­ Develop!an!Expanded!Transmission!ENERGY!&!GREEN!DESIGN!" Smart!Grid!Cities Material!from!the!Electric!part!of!this!presentation!may!be!reproduced!in!any!form without!prior!authorization. Energy map adapted

Amin, S. Massoud

399

Floodplain/wetland assessment of the effects of construction and operation ofa depleted uranium hexafluoride conversion facility at the Paducah, Kentucky,site.  

SciTech Connect

The U.S. Department of Energy (DOE) Depleted Uranium Hexafluoride (DUF{sub 6}) Management Program evaluated alternatives for managing its inventory of DUF{sub 6} and issued the ''Programmatic Environmental Impact Statement for Alternative Strategies for the Long-Term Management and Use of Depleted Uranium Hexafluoride'' (DUF{sub 6} PEIS) in April 1999 (DOE 1999). The DUF{sub 6} inventory is stored in cylinders at three DOE sites: Paducah, Kentucky; Portsmouth, Ohio; and East Tennessee Technology Park (ETTP), near Oak Ridge, Tennessee. In the Record of Decision for the DUF{sub 6} PEIS, DOE stated its decision to promptly convert the DUF{sub 6} inventory to a more stable chemical form. Subsequently, the U.S. Congress passed, and the President signed, the ''2002 Supplemental Appropriations Act for Further Recovery from and Response to Terrorist Attacks on the United States'' (Public Law No. 107-206). This law stipulated in part that, within 30 days of enactment, DOE must award a contract for the design, construction, and operation of a DUF{sub 6} conversion plant at the Department's Paducah, Kentucky, and Portsmouth, Ohio, sites, and for the shipment of DUF{sub 6} cylinders stored at ETTP to the Portsmouth site for conversion. This floodplain/wetland assessment has been prepared by DOE, pursuant to Executive Order 11988 (''Floodplain Management''), Executive Order 11990 (Protection of Wetlands), and DOE regulations for implementing these Executive Orders as set forth in Title 10, Part 1022, of the ''Code of Federal Regulations'' (10 CFR Part 1022 [''Compliance with Floodplain and Wetland Environmental Review Requirements'']), to evaluate potential impacts to floodplains and wetlands from the construction and operation of a conversion facility at the DOE Paducah site. Reconstruction of the bridge crossing Bayou Creek would occur within the Bayou Creek 100-year floodplain. Replacement of bridge components, including the bridge supports, however, would not be expected to result in measurable long-term changes to the floodplain. Approximately 0.16 acre (0.064 ha) of palustrine emergent wetlands would likely be eliminated by direct placement of fill material within Location A. Some wetlands that are not filled may be indirectly affected by an altered hydrologic regime, due to the proximity of construction, possibly resulting in a decreased frequency or duration of inundation or soil saturation and potential loss of hydrology necessary to sustain wetland conditions. Indirect impacts could be minimized by maintaining a buffer near adjacent wetlands. Wetlands would likely be impacted by construction at Location B; however, placement of a facility in the northern portion of this location would minimize wetland impacts. Construction at Location C could potentially result in impacts to wetlands, however placement of a facility in the southeastern portion of this location may best avoid direct impacts to wetlands. The hydrologic characteristics of nearby wetlands could be indirectly affected by adjacent construction. Executive Order 11990, ''Protection of Wetlands'', requires federal agencies to minimize the destruction, loss, or degradation of wetlands, and to preserve and enhance the natural and beneficial uses of wetlands. DOE regulations for implementing Executive Order 11990 as well as Executive Order 11988, ''Floodplain Management'', are set forth in 10 CFR Part 1022. Mitigation for unavoidable impacts may be developed in coordination with the appropriate regulatory agencies. Unavoidable impacts to wetlands that are within the jurisdiction of the USACE may require a CWA Section 404 Permit, which would trigger the requirement for a CWA Section 401 Water Quality Certification from the Commonwealth of Kentucky. A mitigation plan may be required prior to the initiation of construction. Cumulative impacts to floodplains and wetlands are anticipated to be negligible to minor under the proposed action, in conjunction with the effects of existing conditions and other activities. Habitat disturbance would involve settings commonly found i

Van Lonkhuyzen, R.

2005-09-09T23:59:59.000Z

400

Numerical modeling of self-limiting and self-enhancing caprock alteration induced by CO2 storage in a depleted gas reservoir  

Science Conference Proceedings (OSTI)

This paper presents numerical simulations of reactive transport which may be induced in the caprock of an on-shore depleted gas reservoir by the geological sequestration of carbon dioxide. The objective is to verify that CO{sub 2} geological disposal activities currently being planned for the study area are safe and do not induce any undesired environmental impact. In our model, fluid flow and mineral alteration are induced in the caprock by penetration of high CO{sub 2} concentrations from the underlying reservoir, where it was assumed that large amounts of CO{sub 2} have already been injected at depth. The main focus is on the potential effect of precipitation and dissolution processes on the sealing efficiency of caprock formations. Concerns that some leakage may occur in the investigated system arise because the seal is made up of potentially highly-reactive rocks, consisting of carbonate-rich shales (calcite+dolomite averaging up to more than 30% of solid volume fraction). Batch simulations and multi-dimensional 1D and 2D modeling have been used to investigate multicomponent geochemical processes. Numerical simulations account for fracture-matrix interactions, gas phase participation in multiphase fluid flow and geochemical reactions, and kinetics of fluid-rock interactions. The geochemical processes and parameters to which the occurrence of high CO{sub 2} concentrations are most sensitive are investigated by conceptualizing different mass transport mechanisms (i.e. diffusion and mixed advection+diffusion). The most relevant mineralogical transformations occurring in the caprock are described, and the feedback of these geochemical processes on physical properties such as porosity is examined to evaluate how the sealing capacity of the caprock could evolve in time. The simulations demonstrate that the occurrence of some gas leakage from the reservoir may have a strong influence on the geochemical evolution of the caprock. In fact, when a free CO{sub 2}-dominated phase migrates into the caprock through fractures, or through zones with high initial porosity possibly acting as preferential flow paths for reservoir fluids, low pH values are predicted, accompanied by significant calcite dissolution and porosity enhancement. In contrast, when fluid-rock interactions occur under fully liquid-saturated conditions and a diffusion-controlled regime, pH will be buffered at higher values, and some calcite precipitation is predicted which leads to further sealing of the storage reservoir.

Xu, Tianfu; Gherardi, Fabrizio; Xu, Tianfu; Pruess, Karsten

2007-09-07T23:59:59.000Z

Note: This page contains sample records for the topic "fully depleted prior" from the National Library of EnergyBeta (NLEBeta).
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We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


401

Potential influence of iodine-containing compounds on the chemistry of the troposphere in the polar spring. I. Ozone depletion  

Science Conference Proceedings (OSTI)

Iodine in the atmosphere, identified largely by the presence of IO, is a ubiquitous component of the troposphere in coastal and oceanic areas. The role, if any, that iodine chemistry plays in the polar ozone depletion episodes is not known. These events are rationalized today largely in terms of Br2- and BrCl-initiated reactions. The potential for enhancement of ozone depletions through the presence of iodine-containing molecules (I{sub 2}, IBr, ICl, CH{sub 2}I{sub 2}, CH{sub 2}IBr, CH{sub 2}ICl, and CH{sub 3}I) is investigated in this study. Computer simulations of the homogeneous chemistry are made using a reasonably complete reaction mechanism for Br-, Cl- and I-containing species together with representative chemistry of trace gases in the clean troposphere. The extent of uncertain alternative pathways and efficiencies for OIO and I{sub 2}O{sub 2} photolyses are varied over a range of possible values to establish the sensitivity of the depletion events to these variables. The study shows that significant enhancements of the polar ozone depletion are expected when small amounts of iodine-containing compounds such as CH{sub 2}I{sub 2}, IBr, or ICl are present in a polar air mass containing representative Br{sub 2}-BrCl-trace gas mixtures. The synergistic effect of the iodine compounds results from additional halogen-atom formation from IO-IO, IO-BrO, and IO-ClO reactions. Measurements of IO and precursor iodine-containing compounds are encouraged for future polar spring studies, as well as currently acknowledged important trace species (O{sub 3}, CH{sub 2}O, BrO, Br{sub 2}, and BrCl).

Calvert, Jack G [ORNL; Lindberg, Steven Eric [ORNL

2004-05-01T23:59:59.000Z

402

REACTIVE TRANSPORT MODELING USING A PARALLEL FULLY-COUPLED SIMULATOR BASED ON PRECONDITIONED JACOBIAN-FREE NEWTON-KRYLOV  

SciTech Connect

Systems of multicomponent reactive transport in porous media that are large, highly nonlinear, and tightly coupled due to complex nonlinear reactions and strong solution-media interactions are often described by a system of coupled nonlinear partial differential algebraic equations (PDAEs). A preconditioned Jacobian-Free Newton-Krylov (JFNK) solution approach is applied to solve the PDAEs in a fully coupled, fully implicit manner. The advantage of the JFNK method is that it avoids explicitly computing and storing the Jacobian matrix during Newton nonlinear iterations for computational efficiency considerations. This solution approach is also enhanced by physics-based blocking preconditioning and multigrid algorithm for efficient inversion of preconditioners. Based on the solution approach, we have developed a reactive transport simulator named RAT. Numerical results are presented to demonstrate the efficiency and massive scalability of the simulator for reactive transport problems involving strong solution-mineral interactions and fast kinetics. It has been applied to study the highly nonlinearly coupled reactive transport system of a promising in situ environmental remediation that involves urea hydrolysis and calcium carbonate precipitation.

Luanjing Guo; Chuan Lu; Hai Huang; Derek R. Gaston

2012-06-01T23:59:59.000Z

403

Toward fully self-consistent simulation of the interaction of E-Clouds and beams with WARP-POSINST  

SciTech Connect

To predict the evolution of electron clouds and their effect on the beam, the high energy physics community has relied so far on the complementary use of 'buildup' and 'single/multi-bunch instability' reduced descriptions. The former describes the evolution of electron clouds at a given location in the ring, or 'station', under the influence of prescribed beams and external fields [1], while the latter (sometimes also referred as the 'quasi-static' approximation [2]) follows the interaction between the beams and the electron clouds around the accelerator with prescribed initial distributions of electrons, assumed to be concentrated at a number of discrete 'stations' around the ring. Examples of single bunch instability codes include HEADTAIL [3], QuickPIC [4, 5], and PEHTS [6]. By contrast, a fully self-consistent approach, in which both the electron cloud and beam distributions evolve simultaneously under their mutual influence without any restriction on their relative motion, is required for modeling the interaction of high-intensity beams with electron clouds for heavy-ion beam-driven fusion and warm-dense matter science. This community has relied on the use of Particle-In-Cell (PIC) methods through the development and use of the WARP-POSINST code suite [1, 7, 8]. The development of novel numerical techniques (including adaptive mesh refinement, and a new 'drift-Lorentz' particle mover for tracking charged particles in magnetic fields using large time steps) has enabled the first application of WARP-POSINST to the fully self-consistent modeling of beams and electron clouds in high energy accelerators [9], albeit for only a few betatron oscillations. It was recently observed [10] that there exists a preferred frame of reference which minimizes the number of computer operations needed to simulate the interaction of relativistic objects. This opens the possibility of reducing the cost of fully self-consistent simulations for the interaction of ultrarelativistic beams with electron cloud by orders of magnitude. The computational cost of the fully self-consistent mode is then predicted to be comparable to that of the quasi-static mode, assuming that several stations per betatron period are needed. During the workshop, there was some debate about the number of stations per betatron period that are needed when using the quasi-static mode. The argument was made that if there is less than one station per betatron period, then artificial resonances can be triggered and the resulting emittance growth provides an upper bound. The emittance growth thus obtained will fall either above or below the operational requirements of the machine. In the latter case, one can conclude that the electron effect that has been simulated is of no concern. However, if the emittance growth that was obtained is above the threshold, then the results become inconclusive, and simulations which resolve the betatron motion are then needed. In this case, according to [10], the fully self-consistent approach becomes an option. The aim of this paper is to investigate whether this option is indeed practical.

LLNL; Furman, M.A.; Furman, M.A.; Celata, C.M.; Sonnad, K.; Venturini, M.; Cohen, R.H.; Friedman, A.; Grote, D.P.; Vay, J.-L.

2012-04-09T23:59:59.000Z

404

Modeling studies of cold water injection into fluid-depleted, vapor-dominated geothermal reservoirs  

DOE Green Energy (OSTI)

The physical processes involved in cold water injection into a ''superheated'' fractured reservoir are not yet fully understood, and this insufficient knowledge of the fundamental mechanisms limits the possibility of forecasting future resevoir behavior and optimizing the heat extraction process. Numerical simulation can be a very effective tool in the study of the complex phenomena involved, allowing a rapid examination of different situations and conditions, a systematic investigation of the effects of various parameters on reservoir performance, and some insight into long term behavior. We have performed simulation experiments on simple one-dimensional, porous and fractured reservoir models in order to study the migration of injected water, thermodynamic conditions in the boiling zone, heat extraction, and vapor generation. A two-dimensional radial porous medium model, with some characteristics typical of the high productivity zones of Larderello, has also been applied for studying the evolution of the shape and the thermodynamic conditions of the injection plume in the presence of gravity, reservoir heterogeneities and anisotropy.

Calore, C.; Pruess, K.; Celati, R.

1986-01-01T23:59:59.000Z

405

Does the fully parabolic quasilinear 1D Keller-Segel system enjoy long-time asymptotics analogous to its parabolic-elliptic simplification?  

E-Print Network (OSTI)

We show that the one-dimensional fully parabolic Keller-Segel system with nonlinear diffusion possesses global-in-time solutions, provided the nonlinear diffusion is equal to (1+u)^{-\\alpha}, for \\alpha parabolic-elliptic case to the fully parabolic one. However, in the parabolic-elliptic case the above mentioned integrability condition on nonlinear diffusion sharply distinguishes between global existence and blowup cases. We are unable to recover the entire global existence counterpart of this result in a fully parabolic case.

Jan Burczak; Tomasz Cie?lak; Cristian Morales-Rodrigo

2011-11-07T23:59:59.000Z

406

Fully Dense Ferrous Parts  

Science Conference Proceedings (OSTI)

Table 5   Typical mechanical properties of P/M forged low-alloy steels...Elongation in 25 mm (1 in.), % Reduction in area, % Charpy V-notch impact energy Hardness Fracture toughness ( K Ic ) Density, % of theoretical Ref MPa ksi MPa ksi J ft · lbf MPa ksi Fe-2MCM-0.67C (a) (b) � 960 139.3 590 86 � 12 � � 98 HRB � � � 3 Fe-2MCM-0.67C (a) � 1900 275.6 1500 218 � 4.5 � �...

407

Search for Bbar to Lambda_c+ X l- nu Decays in Events with a Fully Reconstructed B Meson  

SciTech Connect

We present a search for semileptonic B decays to the charmed baryon {Lambda}{sub c}{sup +} based on 420 fb{sup -1} of data collected at the {Upsilon}(4S) resonance with the BABAR detector at the PEP-II e{sup +}e{sup -} storage rings. By fully reconstructing the recoiling B in a hadronic decay mode, we reduce non-B backgrounds and determine the flavor of the signal B. We statistically correct the flavor for the effect of the B{sup 0} mixing. We obtain a 90% confidence level upper limit of {Beta}({bar B} {yields} {Lambda}{sub c}{sup +} X{ell}{sup -} {bar {nu}}{sub {ell}})/{Beta}({bar B} {yields} {Lambda}{sub c}{sup +} X) < 3.5%.

Lees, J.P.; Poireau, V.; Tisserand, V.; /Annecy, LAPP; Garra Tico, J.; Grauges, E.; /Barcelona U., ECM; Martinelli, M.; /INFN, Bari /Bari U.; Milanes, D.A.; /INFN, Bari; Palano, A.; Pappagallo, M.; /INFN, Bari /Bari U.; Eigen, G.; Stugu, B.; Sun, L.; /Bergen U.; Brown, D.N.; Kerth, L.T.; Kolomensky, Yu.G.; Lynch, G.; Tanabe, T.; /UC, Berkeley; Koch, H.; Schroeder, T.; /Ruhr U., Bochum; Asgeirsson, D.J.; Hearty, C.; /British Columbia U. /Brunel U. /Novosibirsk, IYF /UC, Irvine /UC, Riverside /UC, Santa Barbara /UC, Santa Cruz /Caltech /Cincinnati U. /Colorado U. /Colorado State U. /Dortmund U. /Dresden, Tech. U. /Ecole Polytechnique /Edinburgh U. /INFN, Ferrara /INFN, Ferrara /Ferrara U. /INFN, Ferrara /Frascati /INFN, Genoa /Genoa U. /INFN, Genoa /INFN, Genoa /Genoa U. /INFN, Genoa /Indian Inst. Tech., Guwahati /Harvard U. /Harvey Mudd Coll. /Heidelberg U. /Humboldt U., Berlin /Imperial Coll., London /Iowa State U. /Iowa State U. /Johns Hopkins U. /Paris U., VI-VII /LLNL, Livermore /Liverpool U. /Queen Mary, U. of London /Royal Holloway, U. of London /Royal Holloway, U. of London /Louisville U. /Mainz U., Inst. Kernphys. /Manchester U. /Maryland U. /Massachusetts U., Amherst /MIT /McGill U. /INFN, Milan /Milan U. /INFN, Milan /INFN, Milan /Milan U. /Mississippi U. /Montreal U. /INFN, Naples /Naples U. /NIKHEF, Amsterdam /NIKHEF, Amsterdam /Notre Dame U. /Ohio State U. /Oregon U. /INFN, Padua /Padua U. /INFN, Padua /INFN, Padua /Padua U. /Paris U., VI-VII /INFN, Perugia /Perugia U. /INFN, Pisa /Pisa U. /INFN, Pisa /Pisa, Scuola Normale Superiore /INFN, Pisa /Pisa U. /INFN, Pisa /INFN, Pisa /Pisa U. /INFN, Pisa /Princeton U. /INFN, Rome /INFN, Rome /Rome U. /INFN, Rome /INFN, Rome /Rome U. /INFN, Rome /Rostock U. /Rutherford /DAPNIA, Saclay /SLAC /South Carolina U. /Southern Methodist U. /Stanford U., Phys. Dept. /SUNY, Albany /Tel Aviv U. /Tennessee U. /Texas Nuclear Corp., Austin /Texas U., Dallas /INFN, Turin /Turin U. /INFN, Trieste /Trieste U. /Valencia U. /Victoria U. /Warwick U. /Wisconsin U., Madison

2012-04-19T23:59:59.000Z

408

Existence and conditional energetic stability of three-dimensional fully localised solitary gravity-capillary water waves  

E-Print Network (OSTI)

In this paper we show that the hydrodynamic problem for three-dimensional water waves with strong surface-tension effects admits a fully localised solitary wave which decays to the undisturbed state of the water in every horizontal direction. The proof is based upon the classical variational principle that a solitary wave of this type is a critical point of the energy subject to the constraint that the momentum is fixed. We prove the existence of a minimiser of the energy subject to the constraint that the momentum is fixed and small. The existence of a small-amplitude solitary wave is thus assured, and since the energy and momentum are both conserved quantities a standard argument may be used to establish the stability of the set of minimisers as a whole. `Stability' is however understood in a qualified sense due to the lack of a global well-posedness theory for three-dimensional water waves.

Buffoni, Boris; Sun, Shu-Ming; Wahlén, Erik

2011-01-01T23:59:59.000Z

409

Existence and conditional energetic stability of three-dimensional fully localised solitary gravity-capillary water waves  

E-Print Network (OSTI)

In this paper we show that the hydrodynamic problem for three-dimensional water waves with strong surface-tension effects admits a fully localised solitary wave which decays to the undisturbed state of the water in every horizontal direction. The proof is based upon the classical variational principle that a solitary wave of this type is a critical point of the energy subject to the constraint that the momentum is fixed. We prove the existence of a minimiser of the energy subject to the constraint that the momentum is fixed and small. The existence of a small-amplitude solitary wave is thus assured, and since the energy and momentum are both conserved quantities a standard argument may be used to establish the stability of the set of minimisers as a whole. `Stability' is however understood in a qualified sense due to the lack of a global well-posedness theory for three-dimensional water waves.

Boris Buffoni; Mark D. Groves; Shu-Ming Sun; Erik Wahlén

2011-08-09T23:59:59.000Z

410

A fully second order implicit/explicit time integration technique for hydrodynamics plus nonlinear heat conduction problems  

SciTech Connect

We present a fully second order implicit/explicit time integration technique for solving hydrodynamics coupled with nonlinear heat conduction problems. The idea is to hybridize an implicit and an explicit discretization in such a way to achieve second order time convergent calculations. In this scope, the hydrodynamics equations are discretized explicitly making use of the capability of well-understood explicit schemes. On the other hand, the nonlinear heat conduction is solved implicitly. Such methods are often referred to as IMEX methods. The Jacobian-Free Newton Krylov (JFNK) method (e.g. ) is applied to the problem in such a way as to render a nonlinearly iterated IMEX method. We solve three test problems in order to validate the numerical order of the scheme. For each test, we established second order time convergence. We support these numerical results with a modified equation analysis (MEA). The set of equations studied here constitute a base model for radiation hydrodynamics.

Kadioglu, Samet Y. [Multiphysics Methods Group, Reactor Physics Analysis and Design, Idaho National Laboratory, P.O. Box 1625, MS 3840, Idaho Falls, ID 83415 (United States)], E-mail: Samet.Kadioglu@inl.gov; Knoll, Dana A. [Multiphysics Methods Group, Reactor Physics Analysis and Design, Idaho National Laboratory, P.O. Box 1625, MS 3840, Idaho Falls, ID 83415 (United States)], E-mail: dana.knoll@inl.gov

2010-05-01T23:59:59.000Z

411

Fast MCMC sampling for sparse Bayesian inference in high-dimensional inverse problems using L1-type priors  

E-Print Network (OSTI)

Sparsity has become a key concept for solving of high-dimensional inverse problems using variational regularization techniques. Recently, using similar sparsity-constraints in the Bayesian framework for inverse problems by encoding them in the prior distribution has attracted attention. Important questions about the relation between regularization theory and Bayesian inference still need to be addressed when using sparsity promoting inversion. A practical obstacle for these examinations is the lack of fast posterior sampling algorithms for sparse, high-dimensional Bayesian inversion: Accessing the full range of Bayesian inference methods requires being able to draw samples from the posterior probability distribution in a fast and efficient way. The most commonly applied Markov chain Monte Carlo (MCMC) sampling algorithms for this purpose are Metropolis-Hastings (MH) schemes. However, we demonstrate in this article that for sparse priors relying on L1-norms, their efficiency dramatically decreases when the lev...

Lucka, Felix

2012-01-01T23:59:59.000Z

412

Review of the Portsmouth Gaseous Diffusion Plant Work Planning and Control Activities Prior to Work Execution, January 2013  

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

Independent Oversight Review of the Independent Oversight Review of the Portsmouth Gaseous Diffusion Plant Work Planning and Control Activities Prior to Work Execution January 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Scope.................................................................................................................................................... 1 3.0 Background........................................................................................................................................... 1

413

Copyright! 2010!No!part!of!this!presentation!may!be! reproduced!in!any!form!without!prior!authorization.  

E-Print Network (OSTI)

!our!addiction!to!oil!by!transforming! transportation ­ Electrify!Transportation:!Plug"In!Hybrid!Electric!Vehicles ­ Develop!and!Use!Alternative!Transportation!prior!authorization. Enable the Future Integrate microgrids, diverse generation and storage resources into a smart self!our!addiction!to!oil!by!transforming! transportation ­ Electrify!Transportation:!Plug"In!Hybrid! Electric!Vehicles ­ Develop!and!Use!Alternative!Transportation

Amin, S. Massoud

414

Relative Contribution of Greenhouse Gases and Ozone-Depleting Substances to Temperature Trends in the Stratosphere: A Chemistry–Climate Model Study  

Science Conference Proceedings (OSTI)

The temperature of the stratosphere has decreased over the past several decades. Two causes contribute to that decrease: well-mixed greenhouse gases (GHGs) and ozone-depleting substances (ODSs). This paper addresses the attribution of temperature ...

Richard S. Stolarski; Anne R. Douglass; Paul A. Newman; Steven Pawson; Mark R. Schoeberl

2010-01-01T23:59:59.000Z

415

Carotenoids & Retinoids; Molecular Aspects and Health IssuesChapter 13 Effect of Feeding and Then Depleteing a High Fruit and Vegetable Diet on Oxidizability in Human Serum  

Science Conference Proceedings (OSTI)

Carotenoids & Retinoids; Molecular Aspects and Health Issues Chapter 13 Effect of Feeding and Then Depleteing a High Fruit and Vegetable Diet on Oxidizability in Human Serum Health Nutrition Biochemistry eChapters Health - Nutrition - B

416

Global Vegetation and Climate Change due to Future Increases in CO2 as Projected by a Fully Coupled Model with Dynamic Vegetation  

Science Conference Proceedings (OSTI)

Transient simulations are presented of future climate and vegetation associated with continued rising levels of CO2. The model is a fully coupled atmosphere–ocean–land–ice model with dynamic vegetation. The impacts of the radiative and ...

Michael Notaro; Steve Vavrus; Zhengyu Liu

2007-01-01T23:59:59.000Z

417

Efforts towards the synthesis of fully N-differentiated heparin-like glycosaminoglycans; and, Investigations into the mechanism of inactivation of RTPR by gemcitabine triphosphate  

E-Print Network (OSTI)

Efforts towards the Synthesis of Fully N-Differentiated Heparin-like Glycosaminoglycans. Heparin-like glycosaminoglycans (HLGAGs) are complex information-carrying biopolymers and are an important component of the coagulation ...

Lohman, Gregory J. S

2007-01-01T23:59:59.000Z

418

Review of corrosion in 10- and 14-ton mild steel depleted UF{sub 6} storage cylinders  

Science Conference Proceedings (OSTI)

A literature review was conducted to determine the type, extent and severity of corrosion found in the 10- and 14-ton mild steel depleted UF{sub 6} storage cylinders. Also discussed in this review is corrosion found in the valves and plugs used in the cylinders. Corrosion of the cylinders is a gradual process which occurs slowly over time. Understanding corrosion of the cylinders is an important concern for long term storage of the UF{sub 6} in the cylinder yards, as well as the final disposition of the depleted UF{sub 6} tails inventory in the future. The following conclusions are made from the literature review: (1) The general external corrosion rate of the cylinders is about 1 to 2 mils per year (1 mil = 0.001{double_prime}). The highest general external corrosion rate was over 5 mpy on the 48G type cylinders. (2) General internal corrosion from the depleted UF{sub 6} is negligible under normal storage conditions. Crevice corrosion can occur at the cylinder/saddle interface from the retention of water in this area. Crevice corrosion can occur at the cylinder/skirt interface on the older skirted cylinders due to the lack of water drainage in this area. Crevice corrosion can occur on cylinders that have been in ground contact. Crevice corrosion and galvanic corrosion can occur where the stainless steel I.D. nameplates are attached to the cylinder. The packing nuts on the bronze one-inch valves used in the cylinders are susceptible to stress corrosion cracking (SCC). Mechanical damage from routine handling can lead to a breach in a cylinder with subsequent accelerated corrosion of the mild steel due to attack from HF and other UF{sub 6} hydrolysis by-products.

Lykins, M.L.

1995-08-01T23:59:59.000Z

419

The water ice rich surface of (145453) 2005 RR43: a case for a carbon-depleted population of TNOs?  

E-Print Network (OSTI)

Recent results suggest that there is a group of TNOs (2003 EL61 being the biggest member), with surfaces composed of almost pure water ice and with very similar orbital elements. We study the surface composition of another TNO that moves in a similar orbit, 2005 RR43, and compare it with the surface composition of the other members of this group. We report visible and near-infrared spectra, obtained with the 4.2m William Herschel Telescope and the 3.58m Telescopio Nazionale Galileo at the "Roque de los Muchachos" Observatory (La Palma, Spain). The spectrum of 2005 RR43 is neutral in color in the visible and dominated by very deep water ice absorption bands in the near infrared (D= 70.3 +/- 2.1 % and 82.8 +/- 4.9 % at 1.5 \\mu and 2.0 \\mu respectively). It is very similar to the spectrum of the group of TNOs already mentioned. All of them present much deeper water ice absorption bands (D>40 %) than any other TNO except Charon. Scattering models show that its surface is covered by water ice, a significant fraction in crytalline state with no trace (5 % upper limit) of complex organics. Possible scenarios to explain the existence of this population of TNOs are discussed: a giant collision, an originally carbon depleted composition, or a common process of continuous resurfacing. We conclude that TNO 2005 RR43 is member of a group, may be a population, of TNOs clustered in the space of orbital parameters that show abundant water ice and no signs of complex organics. The lack of complex organics in their surfaces suggests a significant smaller fraction of carbonaceous volatiles like CH4 in this population than in "normal" TNOs. A carbon depleted population of TNOs could be the origin of the population of carbon depleted Jupiter family comets already noticed by A'Hearn et al. (1995).

N. Pinilla-Alonso; J. Licandro; R. Gil-Hutton; R. Brunetto

2007-03-06T23:59:59.000Z

420

Issues in Three-Dimensional Depletion Analysis of Measured Data Near the End of a Fuel Rod  

Science Conference Proceedings (OSTI)

The dynamics of reactor operation result in nonuniform axial-burnup profiles in fuel with any significant burnup. At the beginning of life in a pressurized water reactor (PWR), a near-cosine axial-shaped flux will begin depleting fuel near the axial center of a fuel assembly at a greater rate than at the ends. As the reactor continues to operate, the cosine flux shape will flatten because of the fuel depletion and fission-product buildup that occur near the center. However, because of the high leakage near the end of the fuel assembly, burnup will drop off rapidly near the ends. Partial-length absorbers or nonuniform axial fuel loadings can further complicate the burnup profile. In a boiling water reactor, the same phenomena come into play, but the burnup profile is complicated by the significant variation of axial moderator density and by nonuniform axial loadings of burnable poison rods. Numerous studies of axial burnup effects have been published. However, most analyses performed in estimation of isotopic distributions due to axial burnup have been based on a set of two-dimensional (2-D) calculations performed for burnups that represent the axial burnup distribution in a fuel assembly. In general, this approach works quite well because the in-core axial gradient of the neutron flux is small over most of the length of the fuel rod, and the 2-D approximation is appropriate. Conversely, because the axial gradient becomes significant as one approaches either end of the fuel assembly, the 2-D approximation begins to break down at that point. It has been theorized that axial leakage will lead to a reduced fast flux relative to the thermal flux, softening the spectrum near the ends of the fuel, and that a 2-D approximation is conservative in that it provides more plutonium production. This has not been put the test, however, for two reasons--a lack of good three-dimensional (3-D) analysis methods acceptable for away-from-reactor applications and, more importantly, a scarcity of experimental measurements for fuel taken from the end regions of a fuel rod. A number of 3-D depletion approaches based on Monte Carlo methods have been introduced in the past decade including, but not limited to, those listed in Refs. 5-7. A full listing would be quite extensive. Recent fuel-sample measurements from two discharged assemblies of the Takahama Unit 3 PWR provide data for fuel samples taken very close to the top of the active region of the fuel rod. This paper discusses results of TRITON-based 3-D depletion calculations completed in the analysis of the Takahama fuel samples.

DeHart, Mark D [ORNL; Gauld, Ian C [ORNL; Suyama, Kenya [Japan Atomic Energy Agency (JAEA)

2008-01-01T23:59:59.000Z

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421

Experimental results of hydrogen distillation at the low power cryogenic column for the production of deuterium depleted hydrogen  

Science Conference Proceedings (OSTI)

The Deuterium Removal Unit (DRU) has been designed and built at the Petersburg Nuclear Physics Inst. (PNPI) to produce isotopically pure hydrogen with deuterium content less than 1 ppm. The cryogenic distillation column of 2.2 cm inner diameter and 155 cm packing height is the main element of the DRU. Column performances at different hydrogen distillation operating modes have been measured. The height equivalent to theoretical plate (HETP) for the column is 2.2 cm and almost constant over a wide range of vapour flow rates. Deuterium depleted hydrogen with a deuterium content of less than 0.1 ppm was produced in required quantity. (authors)

Alekseev, I.; Fedorchenko, O.; Kravtsov, P.; Vasilyev, A.; Vznuzdaev, M. [Petersburg Nuclear Physics Inst., Leningrad district, Gatchina, 188300 (Russian Federation)

2008-07-15T23:59:59.000Z

422

Ca{sub 2}Pd{sub 3}Ge, a new fully ordered ternary Laves phase structure  

SciTech Connect

The title compound, Ca{sub 2}Pd{sub 3}Ge, was prepared as a part of a systematic investigation of the Ca-Pd-Ge ternary phase diagram. The structure was determined and refined from single-crystal X-ray diffraction data. It is a new fully ordered ternary Laves phase with the space group R-3m, Z=3, a=5.6191 (5) A, c=12.1674 (7) A, wR{sub 2}=0.054 (all data) and is isostructural to Mg{sub 2}Ni{sub 3}Si (Noreus et al., 1985 [17]) but due to the larger size of all elements in Ca{sub 2}Pd{sub 3}Ge, the cell axes are approximately 10% longer. The compound may formally be considered as a Zintl compound, with [Pd{sub 3}Ge]{sup 4-} forming a poly-anionic network and divalent Ca cations located in truncated tetrahedral interstices. The electronic structure and chemical bonding of Ca{sub 2}Pd{sub 3}Ge is discussed in terms of LMTO band structure calculations and compared with CaPd{sub 2} (MgCu{sub 2}-type). - Graphical abstract: The title compound, Ca{sub 2}Pd{sub 3}Ge is a new fully ordered ternary Laves phase which may formally be considered as a Zintl compound, with [Pd{sub 3}Ge]{sup 4-} forming a poly-anionic network and divalent Ca cations located in truncated tetrahedral interstices. The structure is composed of Kagome net layers, consisting of Pd atoms only, which are stacked in an ABC sequence. Band structure calculations show that the Fermi level is located at a local minimum of the DOS (pseudo-gap) indicating that the charge is roughly optimized in the structure. Highlights: Black-Right-Pointing-Pointer Site specific segregation in a Laves phase that is also a Zintl phase. Black-Right-Pointing-Pointer Pseudo-gap at the Fermi level in a Laves phase. Black-Right-Pointing-Pointer Distorted Frank-Kasper polyhedron.

Doverbratt, Isa, E-mail: isa.doverbratt@polymat.lth.se [Centre for Analysis and Synthesis, Lund University, P.O. Box 124, 22100 Lund (Sweden); Ponou, Simeon; Lidin, Sven [Centre for Analysis and Synthesis, Lund University, P.O. Box 124, 22100 Lund (Sweden)

2013-01-15T23:59:59.000Z

423

Transmission grid extensions during the build-up of a fully renewable pan-European electricity supply  

E-Print Network (OSTI)

Spatio-temporal generation patterns for wind and solar photovoltaic power in Europe are used to investigate the future rise in transmission needs with an increasing penetration of these variable renewable energy sources (VRES) on the pan-European electricity system. VRES growth predictions according to the official National Renewable Energy Action Plans of the EU countries are used and extrapolated logistically up to a fully VRES-supplied power system. We find that keeping today's international net transfer capacities (NTCs) fixed over the next forty years reduces the final need for backup energy by 13% when compared to the situation with no NTCs. An overall doubling of today's NTCs will lead to a 26% reduction, and an overall quadrupling to a 33% reduction. The remaining need for backup energy is due to correlations in the generation patterns, and cannot be further reduced by transmission. The main investments in transmission lines are due during the ramp-up of VRES from 15% (as planned for 2020) to 80%. Add...

Becker, Sarah; Andresen, Gorm B; Schramm, Stefan; Greiner, Martin

2013-01-01T23:59:59.000Z

424

Fully relativistic calculation of nuclear magnetic shieldings and indirect nuclear spin-spin couplings in group-15 and -16 hydrides  

Science Conference Proceedings (OSTI)

Fully relativistic calculations of the isotropic and anisotropic parts of both indirect nuclear spin–spin couplings 1 J(X- H ) and 2 J( H-H ) and nuclear magnetic shieldings ?(X) and ?(H) for the group-15 and -16 hydrides are presented. Relativistic calculations were performed with Dirac–Fock wave functions and the random phase approximation method. Results are compared to its nonrelativistic counterpart. Paramagnetic and diamagnetic contributions to the nuclear magnetic shielding constants are also reported. We found very large relativistic corrections to both properties in the sixth-row hydrides ( BiH 3 and PoH 2 ). Our calculations of the relativistic corrections to the isotropic part of ? at the heavy nucleus X show that it is roughly proportional to Z 3.2 in both series of molecules. Paramagnetic term ? p is more sensitive to the effects of relativity than the diamagnetic one ? d even though both have a behavior proportional to third power of the nuclear charge Z.

Sergio S. Gomez; Rodolfo H. Romero; Gustavo A. Aucar

2002-01-01T23:59:59.000Z

425

Clonal evolution following chemotherapy-induced stem cell depletion in cats heterozygous for glucose-6-phosphate dehydrogenase  

SciTech Connect

The number of hematopoietic stem cells necessary to support normal hematopoiesis is not known but may be small. If so, the depletion or damage of such cells could result in apparent clonal dominance. To test this hypothesis, dimethylbusulfan (2 to 4 mg/kg intravenously (IV) x 3) was given to cats heterozygous for the X-linked enzyme glucose-6-phosphate dehydrogenase (G-6-PD). These cats were the daughters of domestic X Geoffroy parents. After the initial drug-induced cytopenias (2 to 4 weeks), peripheral blood counts and the numbers of marrow progenitors detected in culture remained normal, although the percentages of erythroid burst-forming cells (BFU-E) and granulocyte/macrophage colony-forming cells (CFU-GM) in DNA synthesis increased, as determined by the tritiated thymidine suicide technique. In three of six cats treated, a dominance of Geoffroy-type G-6-PD emerged among the progenitor cells, granulocytes, and RBCs. These skewed ratios of domestic to Geoffroy-type G-6-PD have persisted greater than 3 years. No changes in cell cycle kinetics or G-6-PD phenotypes were noted in similar studies in six control cats. These data suggest that clonal evolution may reflect the depletion or damage of normal stem cells and not only the preferential growth and dominance of neoplastic cells.

Abkowitz, J.L.; Ott, R.M.; Holly, R.D.; Adamson, J.W.

1988-06-01T23:59:59.000Z

426

Analytical Estimation of CO2 Storage Capacity in Depleted Oil and Gas Reservoirs Based on Thermodynamic State Functions  

E-Print Network (OSTI)

Numerical simulation has been used, as common practice, to estimate the CO2 storage capacity of depleted reservoirs. However, this method is time consuming, expensive and requires detailed input data. This investigation proposes an analytical method to estimate the ultimate CO2 storage in depleted oil and gas reservoirs by implementing a volume constrained thermodynamic equation of state (EOS) using the reservoir?s average pressure and fluid composition. This method was implemented in an algorithm which allows fast and accurate estimations of final storage, which can be used to select target storage reservoirs, and design the injection scheme and surface facilities. Impurities such as nitrogen and carbon monoxide, usually contained in power plant flue gases, are considered in the injection stream and can be handled correctly in the proposed algorithm by using their thermodynamic properties into the EOS. Results from analytical method presented excellent agreement with those from reservoir simulation. Ultimate CO2 storage capacity was predicted with an average difference of 1.3%, molar basis, between analytical and numerical methods; average oil, gas, and water saturations were also matched. Additionally, the analytical algorithm performed several orders of magnitude faster than numerical simulation, with an average of 5 seconds per run.

Valbuena Olivares, Ernesto

2011-12-01T23:59:59.000Z

427

End-of-life destructive examinations of Zircaloy maximum depletion blanket fuel plates from the Shippingport PWR Core 2  

DOE Green Energy (OSTI)

Destructive examinations were performed on four Shippingport PWR Core 2 maximum fluence and depletion blanket plates for surface integrity, corrosion oxide thickness, and hydrogen absorption of the Zircaloy-4 cladding. The Shippingport PWR Core 2 operated for 23,360 effective full power hours (EFPH) (62,235 hot hours) at an average coolant temperature of 536{degrees}F (280{degrees}C) and a peak neutron flux of 0.6{times}10{sup 14}n/cm{sup 2}/s. The end-of-life examination program included measurements on three PWR-2 beta-quenched blanket fuel plates and one alpha-annealed blanket end plate. The examinations consisted of optical and scanning electron microscopy (SEM) inspections, direct metallographic oxide thickness measurements, and hydrogen extraction analyses on a joined element pair from the peak fluence (132{times}10{sup 20} n/cm{sup 2}), maximum depletion (13.5{times}10{sup 20} fissions/cc)PWR-2 blanket cluster.

Clayton, J.C.; Kammenzind, B.F.; Senio, P.; Sherman, J.

1993-10-01T23:59:59.000Z

428

Integral Test and Engineering Analysis of Coolant Depletion During a Large-Break Loss-of-Coolant Accident  

Science Conference Proceedings (OSTI)

This study concerns the development of an integrated calculation methodology with which to continually and consistently analyze the progression of an accident from the design-basis accident phase via core uncovery to the severe accident phase. The depletion rate of reactor coolant inventory was experimentally investigated after the safety injection failure during a large-break loss-of-coolant accident utilizing the Seoul National University Integral Test Facility (SNUF), which is scaled down to 1/6.4 in length and 1/178 in area from the APR1400 [Advanced Power Reactor 1400 MW(electric)]. The experimental results showed that the core coolant inventory decreased five times faster before than after the extinction of sweepout in the reactor downcomer, which is induced by the incoming steam from the intact cold legs. The sweepout occurred on top of the spillover from the downcomer region and expedited depletion of the core coolant inventory. The test result was simulated with the MAAP4 severe accident analysis code. The calculation results of the original MAAP4 deviated from the test data in terms of coolant inventory distribution in the test vessel. After the calculation algorithm of coolant level distribution was improved by including the subroutine of pseudo pressure buildup, which accounts for the differential pressure between the core and downcomer in MAAP4, the core melt progression was delayed by hundreds of seconds, and the code prediction was in reasonable agreement with the overall behavior of the SNUF experiment.

Kim, Yong Soo; Park, Chang Hwan; Bae, Byoung Uhn; Park, Goon Cherl; Suh, Kune Yull; Lee, Un Chul [Seoul National University (Korea, Republic of)

2005-02-15T23:59:59.000Z

429

Characterization of options and their analysis requirements for the long-term management of depleted uranium hexafluoride  

Science Conference Proceedings (OSTI)

The Department of Energy (DOE) is examining alternative strategies for the long-term management of depleted uranium hexafluoride (UF{sub 6}) currently stored at the gaseous diffusion plants at Portsmouth, Ohio, and Paducah, Kentucky, and on the Oak Ridge Reservation in Oak Ridge, Tennessee. This paper describes the methodology for the comprehensive and ongoing technical analysis of the options being considered. An overview of these options, along with several of the suboptions being considered, is presented. The long-term management strategy alternatives fall into three broad categories: use, storage, or disposal. Conversion of the depleted UF6 to another form such as oxide or metal is needed to implement most of these alternatives. Likewise, transportation of materials is an integral part of constructing the complete pathway between the current storage condition and ultimate disposition. The analysis of options includes development of pre-conceptual designs; estimates of effluents, wastes, and emissions; specification of resource requirements; and preliminary hazards assessments. The results of this analysis will assist DOE in selecting a strategy by providing the engineering information necessary to evaluate the environmental impacts and costs of implementing the management strategy alternatives.

Dubrin, J.W.; Rosen, R.S.; Zoller, J.N.; Harri, J.W.; Schwertz, N.L.

1995-12-01T23:59:59.000Z

430

Burnup calculation by the method of first-flight collision probabilities using average chords prior to the first collision  

Science Conference Proceedings (OSTI)

A technique to calculate the burnup of materials of cells and fuel assemblies using the matrices of first-flight neutron collision probabilities rebuilt at a given burnup step is presented. A method to rebuild and correct first collision probability matrices using average chords prior to the first neutron collision, which are calculated with the help of geometric modules of constructed stochastic neutron trajectories, is described. Results of calculation of the infinite multiplication factor for elementary cells with a modified material composition compared to the reference one as well as calculation of material burnup in the cells and fuel assemblies of a VVER-1000 are presented.

Karpushkin, T. Yu., E-mail: timka83@yandex.ru [Russian Research Centre Kurchatov Institute (Russian Federation)

2012-12-15T23:59:59.000Z

431

ZPR-3 Assembly 11 : A cylindrical sssembly of highly enriched uranium and depleted uranium with an average {sup 235}U enrichment of 12 atom % and a depleted uranium reflector.  

Science Conference Proceedings (OSTI)

Over a period of 30 years, more than a hundred Zero Power Reactor (ZPR) critical assemblies were constructed at Argonne National Laboratory. The ZPR facilities, ZPR-3, ZPR-6, ZPR-9 and ZPPR, were all fast critical assembly facilities. The ZPR critical assemblies were constructed to support fast reactor development, but data from some of these assemblies are also well suited for nuclear data validation and to form the basis for criticality safety benchmarks. A number of the Argonne ZPR/ZPPR critical assemblies have been evaluated as ICSBEP and IRPhEP benchmarks. Of the three classes of ZPR assemblies, engineering mockups, engineering benchmarks and physics benchmarks, the last group tends to be most useful for criticality safety. Because physics benchmarks were designed to test fast reactor physics data and methods, they were as simple as possible in geometry and composition. The principal fissile species was {sup 235}U or {sup 239}Pu. Fuel enrichments ranged from 9% to 95%. Often there were only one or two main core diluent materials, such as aluminum, graphite, iron, sodium or stainless steel. The cores were reflected (and insulated from room return effects) by one or two layers of materials such as depleted uranium, lead or stainless steel. Despite their more complex nature, a small number of assemblies from the other two classes would make useful criticality safety benchmarks because they have features related to criticality safety issues, such as reflection by soil-like material. ZPR-3 Assembly 11 (ZPR-3/11) was designed as a fast reactor physics benchmark experiment with an average core {sup 235}U enrichment of approximately 12 at.% and a depleted uranium reflector. Approximately 79.7% of the total fissions in this assembly occur above 100 keV, approximately 20.3% occur below 100 keV, and essentially none below 0.625 eV - thus the classification as a 'fast' assembly. This assembly is Fast Reactor Benchmark No. 8 in the Cross Section Evaluation Working Group (CSEWG) Benchmark Specificationsa and has historically been used as a data validation benchmark assembly. Loading of ZPR-3 Assembly 11 began in early January 1958, and the Assembly 11 program ended in late January 1958. The core consisted of highly enriched uranium (HEU) plates and depleted uranium plates loaded into stainless steel drawers, which were inserted into the central square stainless steel tubes of a 31 x 31 matrix on a split table machine. The core unit cell consisted of two columns of 0.125 in.-wide (3.175 mm) HEU plates, six columns of 0.125 in.-wide (3.175 mm) depleted uranium plates and one column of 1.0 in.-wide (25.4 mm) depleted uranium plates. The length of each column was 10 in. (254.0 mm) in each half of the core. The axial blanket consisted of 12 in. (304.8 mm) of depleted uranium behind the core. The thickness of the depleted uranium radial blanket was approximately 14 in. (355.6 mm), and the length of the radial blanket in each half of the matrix was 22 in. (558.8 mm). The assembly geometry approximated a right circular cylinder as closely as the square matrix tubes allowed. According to the logbook and loading records for ZPR-3/11, the reference critical configuration was loading 10 which was critical on January 21, 1958. Subsequent loadings were very similar but less clean for criticality because there were modifications made to accommodate reactor physics measurements other than criticality. Accordingly, ZPR-3/11 loading 10 was selected as the only configuration for this benchmark. As documented below, it was determined to be acceptable as a criticality safety benchmark experiment. A very accurate transformation to a simplified model is needed to make any ZPR assembly a practical criticality-safety benchmark. There is simply too much geometric detail in an exact (as-built) model of a ZPR assembly, even a clean core such as ZPR-3/11 loading 10. The transformation must reduce the detail to a practical level without masking any of the important features of the critical experiment. And it must do this without increasing the total uncertain

Lell, R. M.; McKnight, R. D.; Tsiboulia, A.; Rozhikhin, Y.; National Security; Inst. of Physics and Power Engineering

2010-09-30T23:59:59.000Z

432

NatPriorLst  

Office of Legacy Management (LM)

February 1999 February 1999 United States Department of Energy Grand Junction Office The U.S. Department of Energy has prepared this Fact Sheet to explain why supplemental standards are proposed for certain properties in the Monticello Vicinity Properties (MVP) Site and Monticello Mill Tailings Site (MMTS). The supplemental standards establish cleanup standards for soil contaminated with uranium mill tailings and uranium ore based on an evaluation of risk for specific exposure scenarios. The supplemental standards associated with the MVP Site will be applied to city of Monticello streets and utility rights-of-way, along state highway rights-of-way within the Monticello city limits, and on a privately owned property with dense piñon and juniper stands. Supple- mental standards associated with MMTS (Operable Unit II) will be applied to densely vegetated hillsides south of

433

Prior User Rights  

E-Print Network (OSTI)

two firms are conducting R&D directed at the invention inare making socially excessive R&D expenditures in the marketcertainty. In their model, all R&D expenditures by multiple

Shapiro, Carl

2005-01-01T23:59:59.000Z

434

Draft Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Paducah, Kentucky, Site  

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

1 1 Paducah DUF 6 DEIS: December 2003 SUMMARY S.1 INTRODUCTION This document is a site-specific environmental impact statement (EIS) for construction and operation of a proposed depleted uranium hexafluoride (DUF 6 ) conversion facility at the U.S. Department of Energy (DOE) Paducah site in northwestern Kentucky (Figure S-1). The proposed facility would convert the DUF 6 stored at Paducah to a more stable chemical form suitable for use or disposal. In a Notice of Intent (NOI) published in the Federal Register (FR) on September 18, 2001 (Federal Register, Volume 66, page 48123 [66 FR 48123]), DOE announced its intention to prepare a single EIS for a proposal to construct, operate, maintain, and decontaminate and decommission two DUF 6 conversion facilities at Portsmouth,

435

A comparison of delayed radiobiological effects of depleted-uranium munitions versus fourth-generation nuclear weapons  

E-Print Network (OSTI)

It is shown that the radiological burden due to the battle-field use of circa 400 tons of depleted-uranium munitions in Iraq (and of about 40 tons in Yugoslavia) is comparable to that arising from the hypothetical battle-field use of more than 600 kt (respectively 60 kt) of high-explosive equivalent pure-fusion fourth-generation nuclear weapons. Despite the limited knowledge openly available on existing and future nuclear weapons, there is sufficient published information on their physical principles and radiological effects to make such a comparison. In fact, it is shown that this comparison can be made with very simple and convincing arguments so that the main technical conclusions of the paper are undisputable -- although it would be worthwhile to supplement the hand calculations presented in the paper by more detailed computer simulations in order to consolidate the conclusions and refute any possible objections.

Gsponer, A; Vitale, B; Gsponer, Andre; Hurni, Jean-Pierre; Vitale, Bruno

2002-01-01T23:59:59.000Z

436

Final Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at Portsmouth, Ohio, Site  

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

2: Comment and Response Document 2: Comment and Response Document June 2004 U.S. Department of Energy Office of Environmental Management Comment & Response Document Portsmouth DUF 6 Conversion Final EIS iii COVER SHEET RESPONSIBLE FEDERAL AGENCY: U.S. Department of Energy (DOE) TITLE: Final Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Portsmouth, Ohio, Site (DOE/EIS-0360) CONTACT: For further information on this environmental impact statement (EIS), contact: Gary S. Hartman DOE-ORO Cultural Resources Management Coordinator U.S. Department of Energy-Oak Ridge Operations P.O. Box 2001 Oak Ridge, TN 37831 e-mail: Ports_DUF6@anl.gov phone: 1-866-530-0944 fax: 1-866-530-0943 For general information on the DOE National Environmental Policy Act (NEPA) process, contact:

437

Final Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Paducah, Kentucky, Site  

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

2: Comment and Response Document 2: Comment and Response Document June 2004 U.S. Department of Energy Office of Environmental Management Comment & Response Document Paducah DUF 6 Conversion Final EIS iii COVER SHEET RESPONSIBLE FEDERAL AGENCY: U.S. Department of Energy (DOE) TITLE: Final Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Paducah, Kentucky, Site (DOE/EIS-0359) CONTACT: For further information on this environmental impact statement (EIS), contact: Gary S. Hartman DOE-ORO Cultural Resources Management Coordinator U.S. Department of Energy-Oak Ridge Operations P.O. Box 2001 Oak Ridge, TN 37831 e-mail: Pad_DUF6@anl.gov phone: 1-866-530-0944 fax: 1-866-530-0943 For general information on the DOE National Environmental Policy Act (NEPA) process,

438

Final Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Paducah, Kentucky, Site  

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

1: Main Text and Appendixes A-H 1: Main Text and Appendixes A-H June 2004 U.S. Department of Energy Office of Environmental Management Cover Sheet Paducah DUF 6 Conversion Final EIS iii COVER SHEET * RESPONSIBLE FEDERAL AGENCY: U.S. Department of Energy (DOE) TITLE: Final Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Paducah, Kentucky, Site (DOE/EIS-0359) CONTACT: For further information on this environmental impact statement (EIS), contact: Gary S. Hartman DOE-ORO Cultural Resources Management Coordinator U.S. Department of Energy-Oak Ridge Operations P.O. Box 2001 Oak Ridge, TN 37831 e-mail: Pad_DUF6@anl.gov phone: 1-866-530-0944 fax: 1-866-530-0943 For general information on the DOE National Environmental Policy Act (NEPA) process, contact:

439

Final Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at Portsmouth, Ohio, Site  

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

1: Main Text and Appendixes A-H 1: Main Text and Appendixes A-H June 2004 U.S. Department of Energy Office of Environmental Management Cover Sheet Portsmouth DUF 6 Conversion Final EIS iii COVER SHEET * RESPONSIBLE FEDERAL AGENCY: U.S. Department of Energy (DOE) TITLE: Final Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Portsmouth, Ohio, Site (DOE/EIS-0360) CONTACT: For further information on this environmental impact statement (EIS), contact: Gary S. Hartman DOE-ORO Cultural Resources Management Coordinator U.S. Department of Energy-Oak Ridge Operations P.O. Box 2001 Oak Ridge, TN 37831 e-mail: Ports_DUF6@anl.gov phone: 1-866-530-0944 fax: 1-866-530-0943 For general information on the DOE National Environmental Policy Act (NEPA) process, contact:

440

Physicochemical Characterization of Capstone Depleted Uranium Aerosols I: Uranium Concentration in Aerosols as a Function of Time and Particle Size  

SciTech Connect

During the Capstone Depleted Uranium (DU) Aerosol Study, aerosols containing depleted uranium were produced inside unventilated armored vehicles (i.e., Abrams tanks and Bradley Fighting Vehicles) by perforation with large-caliber DU penetrators. These aerosols were collected and characterized, and the data were subsequently used to assess human health risks to personnel exposed to DU aerosols. The DU content of each aerosol sample was first quantified by radioanalytical methods, and selected samples, primarily those from the cyclone separator grit chambers, were analyzed radiochemically. Deposition occurred inside the vehicles as particles settled on interior surfaces. Settling rates of uranium from the aerosols were evaluated using filter cassette samples that collected aerosol as total mass over eight sequential time intervals. A moving filter was used to collect aerosol samples over time particularly within the first minute after the shot. The results demonstrate that the peak uranium concentration in the aerosol occurred in the first 10 s, and the concentration decreased in the Abrams tank shots to about 50% within 1 min and to less than 2% 30 min after perforation. In the Bradley vehicle, the initial (and maximum) uranium concentration was lower than those observed in the Abrams tank and decreased more slowly. Uranium mass concentrations in the aerosols as a function of particle size were evaluated using samples collected in the cyclone samplers, which collected aerosol continuously for 2 h post perforation. The percentages of uranium mass in the cyclone separator stages from the Abrams tank tests ranged from 38% to 72% and, in most cases, varied with particle size, typically with less uranium associated with the smaller particle sizes. Results with the Bradley vehicle ranged from 18% to 29% and were not specifically correlated with particle size.

Parkhurst, MaryAnn; Cheng, Yung-Sung; Kenoyer, Judson L.; Traub, Richard J.

2009-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "fully depleted prior" 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

The mean climate of the Community Atmosphere Model (CAM4) in forced SST and fully coupled experiments  

SciTech Connect

The Community Atmosphere Model, version 4 (CAM4) was released as the atmosphere component of the Community Climate System Model, version 4 (CCSM4) and is described. The finite volume dynamical core available in CAM3 is now the default due to its superior transport and conservation properties. Deep convection parameterization changes include a dilute plume calculation of convective available potential energy (CAPE) and the introduction of a formulation for Convective Momentum Transport (CMT). For the cloud fraction an additional calculation is performed following macrophysical state updates that provides improved thermodynamic condistancy. A freeze-drying modification is further made to the cloud fraction calculation in very dry environments, such as arctic Winter, where cloud fractionand cloud water estimates were often inconsistant in CAM3. In CAM4 the finite volume dynamical core leads to a degradation in the excessive trade-wind simulation, but with an accompanying reduction in zonal stresses at higher latitudes. Plume dilution leads to a moister deep tropics alleviating much of the mid-tropospheric dry biases and reduces the persistant precipitation biases over the Arabian peninsular and the southern Indian ocean during the Indian Monsoon. CMT reduces much of the excessive trade-wind biases in eastern ocean basins. The freeze drying modification alleviates much of the high latitude, winter-time excessive cloud bias and improves the associated surface cloud-related energy budget, but the updated cloud macrophysical calculation generally leads to reduced cloud fraction and cloud forcing away from high latitudes. Although there are marginal improvements in time-averaged, large-scale hydrology there are signficant improvements in regional climate features such as the generation of tropical and propagation of stationary waves from the Pacific into mid-latitudes and in the seasonal frequency of Northern Hemisphere blocking events. A 1? versus 2? horizontal resolution of the finite volume 24 dynamical core exhibits signficiant improvements in model climate. Improvements in the fully coupled mean climate between CAM3 and CAM4 are also much more signficant than in forced Sea Surface Temperature (SST) simulations. Furthermore, improvements in the transient characteristics ofthe model climate, documented elsewhere, are substantial.

Neale, Richard; Richter, Jadwiga; Park, Sungsu; Lauritzen, P. H.; Vavrus, Steven J.; Rasch, Philip J.; Zhang, Minghua

2013-07-15T23:59:59.000Z

442

Numerical Investigation of Fractured Reservoir Response to Injection/Extraction Using a Fully Coupled Displacement Discontinuity Method  

E-Print Network (OSTI)

In geothermal reservoirs and unconventional gas reservoirs with very low matrix permeability, fractures are the main routes of fluid flow and heat transport, so the fracture permeability change is important. In fact, reservoir development under this circumstance relies on generation and stimulation of a fracture network. This thesis presents numerical simulation of the response of a fractured rock to injection and extraction considering the role of poro-thermoelasticity and joint deformation. Fluid flow and heat transport in the fracture are treated using a finite difference method while the fracture and rock matrix deformation are determined using the displacement discontinuity method (DDM). The fractures response to fluid injection and extraction is affected both by the induced stresses as well as by the initial far-field stress. The latter is accounted for using the non-equilibrium condition, i.e., relaxing the assumption that the rock joints are in equilibrium with the in-situ stress state. The fully coupled DDM simulation has been used to carry out several case studies to model the fracture response under different injection/extractions, in-situ stresses, joint geometries and properties, for both equilibrium and non-equilibrium conditions. The following observations are made: i) Fluid injection increases the pressure causing the joint to open. For non-isothermal injection, cooling increases the fracture aperture drastically by inducing tensile stresses. Higher fracture aperture means higher conductivity. ii) In a single fracture under constant anisotropic in-situ stress (non-equilibrium condition), permanent shear slip is encountered on all fracture segments when the shear strength is overcome by shear stress in response to fluid injection. With cooling operation, the fracture segments in the vicinity of the injection point are opened due to cooling-induced tensile stress and injection pressure, and all the fracture segments experience slip. iii) Fluid pressure in fractures increases in response to compression. The fluid compressibility and joint stiffness play a role. iv) When there are injection and extraction in fractured reservoirs, the cooler fluid flows through the fracture channels from the injection point to extraction well extracting heat from the warmer reservoir matrix. As the matrix cools, the resulting thermal stress increases the fracture apertures and thus increases the fracture conductivity. v) Injection decreases the amount of effective stress due to pressure increase in fracture and matrix near a well. In contrast, extraction increases the amount of effective stress due to pressure drop in fracture and matrix.

Lee, Byungtark

2011-08-01T23:59:59.000Z

443

Assessment of Possible Cycle Lengths for Fully-Ceramic Micro-Encapsulated Fuel-Based Light Water Reactor Concepts  

Science Conference Proceedings (OSTI)

The tri-isotropic (TRISO) fuel developed for High Temperature reactors is known for its extraordinary fission product retention capabilities [1]. Recently, the possibility of extending the use of TRISO particle fuel to Light Water Reactor (LWR) technology, and perhaps other reactor concepts, has received significant attention [2]. The Deep Burn project [3] currently focuses on once-through burning of transuranic fissile and fissionable isotopes (TRU) in LWRs. The fuel form for this purpose is called Fully-Ceramic Micro-encapsulated (FCM) fuel, a concept that borrows the TRISO fuel particle design from high temperature reactor technology, but uses SiC as a matrix material rather than graphite. In addition, FCM fuel may also use a cladding made of a variety of possible material, again including SiC as an admissible choice. The FCM fuel used in the Deep Burn (DB) project showed promising results in terms of fission product retention at high burnup values and during high-temperature transients. In the case of DB applications, the fuel loading within a TRISO particle is constituted entirely of fissile or fissionable isotopes. Consequently, the fuel was shown to be capable of achieving reasonable burnup levels and cycle lengths, especially in the case of mixed cores (with coexisting DB and regular LWR UO2 fuels). In contrast, as shown below, the use of UO2-only FCM fuel in a LWR results in considerably shorter cycle length when compared to current-generation ordinary LWR designs. Indeed, the constraint of limited space availability for heavy metal loading within the TRISO particles of FCM fuel and the constraint of low (i.e., below 20 w/0) 235U enrichment combine to result in shorter cycle lengths compared to ordinary LWRs if typical LWR power densities are also assumed and if typical TRISO particle dimensions and UO2 kernels are specified. The primary focus of this summary is on using TRISO particles with up to 20 w/0 enriched uranium kernels loaded in Pressurized Water Reactor (PWR) assemblies. In addition to consideration of this 'naive' use of TRISO fuel in LWRs, several refined options are briefly examined and others are identified for further consideration including the use of advanced, high density fuel forms and larger kernel diameters and TRISO packing fractions. The combination of 800 {micro}m diameter kernels of 20% enriched UN and 50% TRISO packing fraction yielded reactivity sufficient to achieve comparable burnup to present-day PWR fuel.

R. Sonat Sen; Michael A. Pope; Abderrafi M. Ougouag; Kemal O. Pasamehmetoglu

2012-04-01T23:59:59.000Z

444

Effect of Aging on the NOx Storage and Regeneration Characteristics of Fully Formulated Lean NOx Trap Catalysts  

Science Conference Proceedings (OSTI)

In order to elucidate the effect of washcoat composition on lean NO{sub x} trap (LNT) aging characteristics, fully formulated monolithic LNT catalysts containing varying amounts of Pt, Rh and BaO were subjected to accelerated aging on a bench reactor. Subsequent catalyst evaluation revealed that in all cases aging resulted in deterioration of the NO{sub x} conversion as a consequence of impaired NO{sub x} storage and NO{sub x} reduction functions, while increased selectivity to NH{sub 3} was observed in the temperature range 250--450 C. Elemental analysis, H{sub 2} chemisorption and TEM data revealed two main changes which account for the degradation in LNT performance. First, residual sulfur in the catalysts, associated with the Ba phase, decreased catalyst NO{sub x} storage capacity. Second, sintering of the precious metals in the washcoat occurred, resulting in decreased contact between the Pt and Ba, and hence in less efficient NO{sub x} spillover from Pt to Ba during NO{sub x} adsorption, as well as decreased rates of reductant spillover from Pt to Ba and reverse NO{sub x} spillover during catalyst regeneration. For the aged catalysts, halving the Pt loading from 100 to 50 g/ft{sup 3} was found to result in a significant decrease in overall NO{sub x} conversion, while for catalysts with the same 100 g/ft{sup 3} Pt loading, increasing the relative amount of Pt on the NO{sub x} storage components (BaO and La-stabilized CeO{sub 2}), as opposed to an Al{sub 2}O{sub 3} support material (where it was co-located with Rh), was found to be beneficial. The effect of Rh loading on aged catalyst performance was found to be marginal within the range studied (10--20 g/ft{sup 3}), as was the effect of BaO loading in the range 30--45 g/L.

Ji, Yaying [University of Kentucky; Easterling, Vencon [University of Kentucky; Graham, Uschi [University of Kentucky; Fisk, Courtney [University of Kentucky; Crocker, Mark [University of Kentucky; Choi, Jae-Soon [ORNL

2011-01-01T23:59:59.000Z

445

Integration of Advanced Emissions Controls to Produce Next-Generation Circulating Fluid Bed Coal Generating Unit (withdrawn prior to award)  

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

contacts contacts Brad tomer Director Office of Major Demonstrations National Energy Technology Laboratory 3610 Collins Ferry Road P.O. Box 880 Morgantown, WV 26507-0880 304-285-4692 brad.tomer@netl.doe.gov PaRtIcIPant Colorado Springs Utilities Colorado Springs, CO aDDItIonaL tEaM MEMBERs Foster Wheeler Power Group, Inc. Clinton, NJ IntegratIon of advanced emIssIons controls to Produce next-generatIon cIrculatIng fluId Bed coal generatIng unIt (wIthdrawn PrIor to award) Project Description Colorado Springs Utilities (Springs Utilities) and Foster Wheeler are planning a joint demonstration of an advanced coal-fired electric power plant using advanced, low-cost emission control systems to produce exceedingly low emissions. Multi- layered emission controls will be

446

Medical History Questionnaire This form is voluntary. You may ignore it, complete parts of it, or fill it out fully. It is intended solely for  

E-Print Network (OSTI)

Medical History Questionnaire This form is voluntary. You may ignore it, complete parts of it, or fill it out fully. It is intended solely for your self-protection at sea, by making your medical history available for reference at Medical Advisory Systems/ MedAire, 80 E. Salado Parkway, Suite 610

Russell, Lynn

447

Obtain a master's degree in social work from the fully-accredited School of Social Work at Colorado State University. The school is dedicated to  

E-Print Network (OSTI)

range of social work applications. The program's faculty represents a wide range of talents, expertise of this three-year program consists of foundation courses that follow the core areas of social work practiceOverview Obtain a master's degree in social work from the fully-accredited School of Social Work

448

Adaptive fully implicit multi-scale finite-volume method for multi-phase flow and transport in heterogeneous porous media  

Science Conference Proceedings (OSTI)

We describe a sequential fully implicit (SFI) multi-scale finite volume (MSFV) algorithm for nonlinear multi-phase flow and transport in heterogeneous porous media. The method extends the recently developed multiscale approach, which is based on an IMPES ... Keywords: coupled flow and transport, finite-volume, heterogeneous porous media, immiscible multi-phase flow, multiscale methods, numerical simulation

P. Jenny; S. H. Lee; H. A. Tchelepi

2006-09-01T23:59:59.000Z

449

Free, Prior and Informed Consent (FPIC) : does it give indigenous peoples more control over development of their lands in the Philippines?  

E-Print Network (OSTI)

The 1998 Indigenous Peoples Rights Act (IPRA) grants indigenous peoples (IPs) in the Philippines the right to Free, Prior, and Informed Consent (FPIC) with regard to development projects undertaken on their ancestral lands. ...

Co, Ronilda R. (Ronilda Rosario)

2008-01-01T23:59:59.000Z

450

Technology-Based Handling of Science Misconceptions: The GeoDist Tool on the Distinction of Greenhouse Effect and Ozone Depletion  

Science Conference Proceedings (OSTI)

The didactic utilization of the conceptual obstacles constitutes an alternative approach for the design of learning situations in science education, in order to produce a conceptual change and overcome them. Adopting this positive perspective, a relative ... Keywords: conceptual obstacles, GeoDist (Greenhouse Effect and Ozone Depletion Dis-tinction), Science Misconceptions

Sofia J. Hadjileontiadou; Theoxaris Vasilakoglou

2008-07-01T23:59:59.000Z

451